ES -301 Administrative Topics Outline Form ES-301-1 · 2013. 9. 26. · Method of Performance:...

ES-301 Administrative Topics Outline Form ES-301-1

Facility: __Callaway_______________________ Date of Examination: _8/27/13______ Examination Level: RO SRO Operating Test Number: 2013 Re-Exam

Administrative Topic (see Note)

Type Code*

Describe activity to be performed

RSA-1

Conduct of Operations

R

M

Review SDM Calculation

2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (3.8)

RSA-2

Conduct of Operations

R

D

Determine the volume and RMCS control settings for raising RWST level

2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)

RSA-3

Equipment Control

R

N

Review CCP Surveillance for Operability

2.2.12 Knowledge of surveillance procedures. (4.1)

RSA-4

Radiation Control

R

M

Determine Maximum Allowable Stay Time

2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.7)

RSA-5

Emergency Procedures/Plan

R

D

Classify Emergency Events Requiring Emergency Plan Implementation

2.4.41 Knowledge of the emergency action level thresholds and classifications. (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (≤ 3 for ROs; ≤ 4 for SROs & RO retakes) (N)ew or (M)odified from bank (≥ 1) (P)revious 2 exams (≤ 1; randomly selected)

Administrative Topic Outline Task Summary RSA-1: Review SDM Calculation The Applicant will review a SDM calculation performed in accordance with OSP-SF-00001, “Shutdown Margin Calculations”. The critical steps include identifying the error of using the wrong data from a table, performing the calculation with the correct data, and identifying that boration is needed. This JPM is modified from the 2013 RO Exam. RSA-2: Determine the volume and RMCS control settings for raising RWST level The Applicant will determine the potentiometer settings for Boric Acid and Blended flow using RWST level/volume curves and OTN-BG-00002, “Reactor Makeup Control and Boron Thermal Regeneration System”. The critical steps include determining the volume to be added to the RWST, interpolating curves to determine Boric Acid and Makeup Water flows, and determining the potentiometer settings for Boric Acid and Blended flow. This JPM is from the bank and was used on the 2005 ILT SRO Exam. RSA-3: Review CCP Surveillance for Operability The Applicant will review Attachment 2 of OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B” and identify the pump D/P was calculated incorrectly. The critical steps include identifying the calculation error, declaring the pump inoperable and entering the correct Technical Specification. This is a new JPM. RSA-4: Determine Maximum Allowable Stay Time The Applicant will determine the allowable stay time using a RWP and Survey Map. The critical steps include determining the correct RWP, dosimeter setting, dose rate from survey map, and calculate stay time. This JPM is modified from a bank JPM that was used on the 2005 ILT SRO Exam. RSA-5: Classify Emergency Events Requiring Emergency Plan Implementation The Applicant will be given a set of plant conditions and will implement the Radiological Emergency Response Plan (RERP) to classify the event within 15 minutes (Time Critical) This JPM is from the bank and has not been used on an ILT exam since 2004.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

JPM No: RSA-1 KSA No: GEN 2.1.18 Revision: July 2013 KSA Rating: 3.8 Job Title: SRO Task Title: Review SDM Calculation. Validation Time: 30 minutes Learning Objective: T61.0110, LP SS-08, Obj D, Perform shutdown margin calculation while at power The performance of this task was evaluated against the standards contained in this JPM and determined to be: [ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY: Evaluators Signature: Date: Task Performer: Location of Performance: Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___ Student Handouts: OSP-SF-00001, Shutdown Margin Calculations, Rev 40

Core Operating Limits Report (COLR), Rev 1, Pages 1-5 Curve Book Table 1-8 WINPCNDR Handouts

Calculator References: OSP-SF-00001, Shutdown Margin Calculations, Rev 40 Core Operating Limits Report (COLR), Rev 1 Plant Curve Book

JPM NO: RSA-1, Rev 1

PAGE 1 of 3

Initial Conditions: The plant is at 3565 MWt, as indicated on REU1118, with Control Rods D @ 215

steps and RCS Boron Concentration at 750 ppm. It is near the end of Cycle 19 Effective Full Power Days (EFPD) is at 465 (20000 MWD/MTU). During performance of SR 3.1.4.2 it was discovered that 1 control rod would not

move. Initiating Cues: Due to the stuck control rod, the Reactor Operator has completed a Shutdown

Margin Calculation for the current plant conditions IAW OSP-SF-00001, Shutdown Margin Calculations.

You are to review this calculation The PC program OSPSF1 is currently being revised by reactor engineering and is

not available. When completed, inform the Shift Manager the Shutdown Margin (SDM)

calculation has been reviewed. Task Standard: Upon completion of this JPM, the Applicant will have determined that the

Shutdown Margin calculation was performed incorrectly and a boration is needed. START TIME: STOP TIME:

JPM NO: RSA1, Rev 1 JPM TASK STEP ELEMENT

PERFORMANCE STANDARD

SCORE

PAGE 2 of 3

1. Obtain a verified working copy of OSP-SF-00001

Applicant obtained working copy of OSP-SF-00001

S U

Comments:

2. Review completed copy of Attachment 4 of OSP-SF-00001.

Applicant reviewed completed copy of Attachment 4 of OSP-SF-00001.

S U

Comments:

3. *Identifies the data in step 6.11.5 (Total Power Defect) was copied incorrectly from Curve Book Table 1-8

Applicant identified that the number for Total Power Defect should be 2607 pcm instead of 1974 pcm

S U

Comments:

4. *Identifies the data in step 6.11.7 (Corrected Total Power Defect) was calculated incorrectly.

Applicant identified that the number for Corrected Total Power Defect should be 2877 pcm instead of 2244 pcm

S U

Comments:

JPM NO: RSA1, Rev 1 JPM TASK STEP ELEMENT


SCORE

PAGE 3 of 3

5. *Identifies the data in step 6.11.11 (Total corrected Reactivity) was calculated incorrectly.

Applicant identified that the number for Total corrected Reactivity should be (-)893 pcm instead of (-)1526 pcm

S U

Comments:

6. *Informs Shift Manager that Corrected Reactivity is NOT more negative than the limits provided in the COLR, and indicate that a boration is needed.

Applicant informed SM that SDM is not acceptable at a value of (-)893 pcm when the COLR states it must be more negative than 1.3Δk/k and a boration is required.

S U

Comments:

7. The JPM is complete

Record stop time on Page 1 S U

Comments:

∗ Denotes Critical Step

Initial Conditions: The plant is at 3565 MWt, as indicated on REU1118, with Control Rods D @ 215

steps and RCS Boron Concentration at 750 ppm. It is near the end of Cycle 19 Effective Full Power Days (EFPD) is at 465 (20000 MWD/MTU). During performance of SR 3.1.4.2 it was discovered that 1 control rod would not

move. Initiating Cues: Due to the stuck control rod, the Reactor Operator has completed a Shutdown

Margin Calculation for the current plant conditions IAW OSP-SF-00001, Shutdown Margin Calculations.

You are to review this calculation The PC program OSPSF1 is currently being revised by reactor engineering and is

not available. When completed, inform the Shift Manager the Shutdown Margin (SDM)

calculation has been reviewed.

of 45 CONTINUOUS USE

OSP-SF-00001

SHUTDOWN MARGIN CALCULATIONS

ADMINISTRATIVE CORRECTION Revision 040

OSP-SF-00001

Rev. 040


TABLE OF CONTENTS

Section Page Number

Page 2 of 45 CONTINUOUS USE

1.0 PURPOSE ...................................................................................................................................... 4

2.0 SCOPE ........................................................................................................................................... 4

3.0 ACCEPTANCE/FUNCTIONAL CRITERIA .............................................................................. 4

4.0 PRECAUTIONS AND LIMITATIONS ....................................................................................... 5

5.0 PREREQUISITES ......................................................................................................................... 6

6.0 PROCEDURE INSTRUCTIONS ................................................................................................. 7

6.1. General ................................................................................................................................ 7

6.2. SDM Calculation While Subcritical, Method 1..................................................................... 8

6.3. SDM Calculation While Subcritical, Method 2................................................................... 10

6.4. Xenon Correction To SDM ................................................................................................ 12

6.5. Rods Correction To SDM .................................................................................................. 13

6.6. Temperature Correction To SDM ....................................................................................... 15

6.7. Boron Correction To SDM ................................................................................................. 16

6.8. Corrected SDM Determination ........................................................................................... 18

6.9. COLR Comparison ............................................................................................................ 19

6.10. Boron Concentration Required To Maintain Keff< 0.99 With Shutdown Banks

Withdrawn ......................................................................................................................... 21

6.11. At Power SDM Calculation ................................................................................................ 23

6.12. SDM Determination Prior To Mode 6 Entry And During Mode 6 Prior To Core

Reload 27

6.13. SDM While Subcritical After Refueling But Prior To Initial Startup .................................. 28

7.0 RESTORATION ......................................................................................................................... 30

8.0 REFERENCES ............................................................................................................................ 30

8.1. Implementing ..................................................................................................................... 30

8.2. Developmental ................................................................................................................... 31

9.0 RECORDS ................................................................................................................................... 32

10.0 SUMMARY OF CHANGES ....................................................................................................... 32

ATTACHMENT 1, SDM Calculations While Subcritical, Method 1 ....................................................... 33

ATTACHMENT 2, SDM Calculations While Subcritical, Method 2 ....................................................... 35

ATTACHMENT 3, Boron Concentration Required To Maintain Keff Less Than 0.99 With

Shutdown Banks Withdrawn ......................................................................................................... 40

OSP-SF-00001

Rev. 040


TABLE OF CONTENTS

Section Page Number


ATTACHMENT 4, At Power SDM Calculation ...................................................................................... 41

ATTACHMENT 5, SDM Determination Prior To Mode 6 Entry And During Mode 6 Prior To Core

Reload ........................................................................................................................................... 42

ATTACHMENT 6, SDM While Subcritical After Refueling, But Prior To Initial Startup........................ 43

ATTACHMENT 7, Input Guidelines For Shutdown Margins .................................................................. 44

ATTACHMENT 8, Correction For Pzr Boron Concentration .................................................................. 45

OSP-SF-00001

Rev. 040



1.0 PURPOSE

1.1. To provide instructions for performing SHUTDOWN MARGIN (SDM) calculations.

1.2. To satisfy the following Tech Spec surveillances:

• T/S SR 3.1.1.1

• T/S SR 3.9.1.1

2.0 SCOPE

This procedure is applicable for MODES 1 through 6.

3.0 ACCEPTANCE/FUNCTIONAL CRITERIA

3.1. In MODES 1 and 2, SDM shall be within the limits provided in the Core Operating Limits

Report (COLR).

• T/S ACT 3.1.4.A.1.1

• T/S ACT 3.1.4.B.2.1.1

• T/S ACT 3.1.4.B.2.3

• T/S ACT 3.1.4.D.1.1

3.2. In MODE 1 and MODE 2 with Keff greater than or equal to 1.0, the SDM shall be within the

limits provided in the COLR.

• T/S ACT 3.1.6.A.1.1

• T/S ACT 3.1.6.B.1.1

3.3. In MODE 1 and MODE 2 with any control bank not fully inserted, the SDM shall be within

the limits provided in the COLR.

• T/S ACT 3.1.5.A.1.1

OSP-SF-00001

Rev. 040


3.4. In MODE 2 with Keff less than 1.0, and MODES 3, 4, and 5, the SDM shall be within the

limits provided in the COLR.

• T/S LCO 3.1.1

• T/S SR 3.1.1.1

• T/S BSR 3.1.1.1

• T/S APP 3.1.1 NOTE

3.5. In MODE 6, the boron concentrations of all filled portions of the Reactor Coolant System and

the refueling pool that have direct access to the reactor vessel, shall be maintained within the

limit.

• T/S LCO 3.9.1

• T/S SR 3.9.1.1

• T/S ACT 3.9.2.A.3

4.0 PRECAUTIONS AND LIMITATIONS

4.1. During startup and/or power operations, the control bank insertion limits of COLR, Figure 2

of Curve Book, Figure 13-1 (COLR Figure 2), shall be maintained.

4.2. Many figures in the Curve Book are provided for BOL, MOL, and EOL conditions. BOL

curves are generated for a burnup of 150 MWD/MTU (after xenon has reached equilibrium)

and MOL curves are generated at 10000 MWD/MTU burnup. EOL curves are generated for

design end of life, which varies from cycle to cycle. Design end of life may be obtained from

Curve Book, Figure 5-4. Generally, better results will be obtained by interpolating between

the two curves which bound the current burnup. However, it is also permissible to use the

curve for the burnup nearest to the current burnup.

In addition, some data is provided as a function of power level. If power is not at a power

level for which the data is provided, best results are obtained by interpolating between the two

power levels which bound the current power. However, it is permissible to use data from the

power level nearest the current power.

4.3. The PC Nuclear Design Report (PCNDR) may be used to obtain reactivity data instead of the

Curve Book. Many Curve Book values at exact burnups are available using the PCNDR. The

WINPCDNR is also available to obtain reactivity data.

4.4. When obtaining reactivity data from the Curve Book to manually perform a SDM calculation,

the sign convention (+ or -) specified in the Curve Book should be neglected and the absolute

value of the reactivity data should be recorded on Attachment 2, 3, or 4. The required sign

convention is already provided on Attachments 2, 3, and 4 in parentheses by the recorded

value.

OSP-SF-00001

Rev. 040


4.5. SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or

would be subcritical from its current condition assuming all rod cluster control assemblies

(RCCA's) are fully inserted except for the single RCCA of highest reactivity which is

assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the

reactivity of the RCCA must be accounted for in the determination of SDM. In MODES 1

and 2, the fuel and moderator temperatures are changed to the hot zero power temperatures.

5.0 PREREQUISITES

None

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.0 PROCEDURE INSTRUCTIONS

6.1. General

6.1.1. IF calculating a SDM while subcritical with all rods fully inserted AND no credit

for Xenon, PERFORM Section 6.2.

6.1.2. To determine required boron concentration for blocking SI below P-11, PERFORM

Step 6.2.9.

6.1.3. IF calculating a SDM while subcritical with any rods NOT fully inserted, OR IF

taking credit for Xenon, PERFORM Sections 6.3 through 6.10.

6.1.4. IF calculating a SDM to determine required Boron concentration to maintain

Keff < 0.99 with Shutdown Banks withdrawn, PERFORM Section 6.10.

6.1.5. IF calculating a SDM while in MODES 1 or 2, PERFORM Section 6.11.

6.1.6. IF calculating a SDM in preparation for core reload OR while in MODE 6,

PERFORM Section 6.12.

6.1.7. IF calculating a SDM after refueling, but prior to initial startup, PERFORM

Section 6.13.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.2. SDM Calculation While Subcritical, Method 1

6.2.1. CHECK all rods fully inserted.

6.2.2. IF all rods are NOT fully inserted, Go To Section 6.3 to calculate the SDM.

6.2.3. INITIATE Attachment 1 and RECORD all data in this section on Attachment 1.

6.2.4. RECORD plant MODE.

6.2.5. RECORD fuel burnup in EFPD for the current cycle.

6.2.6. RECORD current boron concentration.

6.2.7. CALCULATE required boron concentration:

a. RECORD required boron concentration for current fuel burnup from the Curve

Book, Table 1-8, Section I.

b. IF PZR concentration is less than RCS concentration, RECORD amount from

Attachment 8.

c. ADD Step 6.2.7.a and Step 6.2.7.b to obtain required boron concentration.

NOTE

If current boron concentration is greater than or equal to required boron concentration, sufficient

core SDM exists to meet the requirements of COLR Sections 2.1.1 / 2.1.3.

6.2.8. IF current boron concentration is less than the required boron concentration,

PERFORM one of the following:

• Section 6.3.

• Within 15 minutes INITIATE and CONTINUE boration in accordance with

OTO-ZZ-00003, Loss of SDM, until the required boron concentration of

Step 6.2.7 is obtained.

OSP-SF-00001

Rev. 040


NOTE

Step 6.2.9 can be used to determine the required boron concentration prior to blocking SI below

P-11 if desired.

Step 6.2.9 ensures boron concentration is adequate to meet the assumptions of a Steamline Break

Design Basis Accident (DBA) without automatically initiated SI available to add borated water.

[Ref: 8.2.11 and 8.2.12]

6.2.9. IF in MODE 3 or 4, and below P-11, and SI is blocked, PERFORM the following:

a. RECORD required boron concentration for current fuel burnup from the Curve

Book, Figure 13-2.


Attachment 8.

c. ADD Steps 6.2.9.a and 6.2.9.b to obtain required boron concentration.

d. RECORD the current boron concentration.

6.2.10. IF current boron concentration is less than the boron concentration determined in

Step 6.2.9.a, immediately INITIATE and CONTINUE boration in accordance with

OTO-ZZ-00003, Loss of SDM, until the boron concentration recorded in Step 6.2.7

is obtained.

6.2.11. IF current boron concentration is greater than or equal to the boron concentration

determined in Step 6.2.9.a, NO ACTION is required (sufficient core SDM exists to

meet the requirements of COLR Section 2.1.2).

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.3. SDM Calculation While Subcritical, Method 2

NOTE

PC program OSPSF1 may be used to calculate SDM in lieu of completing Sections 6.3 through

6.10. Attachment 7 contains input data to use with OSPSF1.

If any information is taken from a URO Logbook entry for any rod heights, critical boron

concentrations, or power level, then the logbook entry should be used obtaining for all three.

6.3.1. IF desired, PERFORM SDM using OSPSF1.

a. IF necessary, REPEAT Step 6.3.1.

b. IF no other SDM calculations are needed, EXIT this procedure.

6.3.2. INITIATE Attachment 2 and RECORD all data in Sections 6.3 through 6.9 on

Attachment 2.

6.3.3. RECORD shutdown date and time.

6.3.4. RECORD burnup in EFPD.

NOTE

Power level may be obtained from SE-NR45 Recorder after a Rx trip, the Computer Log or the

URO log entry at the beginning of the shift when the plant was at power.

6.3.5. RECORD power level for the last time Keff equaled one.

6.3.6. RECORD critical boron concentration.

6.3.7. RECORD total power defect for the associated power level and burnup from Curve

Book Table 1-8, Section II.

6.3.8. RECORD the redistribution allowance and voids reactivity from Curve Book

Table 1-8, Section II.

6.3.9. RECORD the corrected total power defect obtained by adding the redistribution

allowance and voids reactivity in Step 6.3.8 and the total power defect in

Step 6.3.7.

6.3.10. RECORD the available rod worth from Curve Book Table 1-8, Section II.

OSP-SF-00001

Rev. 040


6.3.11. RECORD rod worth of the worst case stuck rod from Curve Book Table 1-8,

Section II.

NOTE

A rod is considered trippable if it was demonstrated OPERABLE during the last performance of

T/S SR 3.1.4.2 and met the rod drop time criteria during the last performance of T/S SR 3.1.4.3

(T/S BACT 3.1.4.A.1.1).

If any rod is misaligned below the other rods in its bank, its full worth from the bank position is not

available for insertion; therefore, the rod is INOPERABLE.

6.3.12. IF any rods are INOPERABLE:

a. RECORD the number of INOPERABLE rods.

b. MULTIPLY the number INOPERABLE rods by the rod worth of the worst

case stuck rod from Step 6.3.11.

6.3.13. SUM Steps 6.3.9, 6.3.10, and 6.3.12.b to obtain the uncorrected SDM.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.4. Xenon Correction To SDM

NOTE

T/S BSR 3.1.1.1 requires the consideration of samarium concentration when determining SDM. In

the interest of providing a conservative SDM calculation, samarium worth is considered to be zero.

6.4.1. RECORD the time interval since shutdown.

6.4.2. RECORD the current xenon worth from one of the following:

• XENON_PREDICTION on the PC

• XEPRED on the PC

• The PCNDR (WINPCNDR)

• Computer point REU1504

6.4.3. RECORD xenon worth prior to the shutdown from one of the following:

• XEPRED on the PC

• The PCNDR (WINPCNDR)

• Computer point REU1504

CAUTION

Subtracting negative numbers may result in either a positive or negative change in xenon worth.

6.4.4. SUBTRACT xenon worth in Step 6.4.3 from Step 6.4.2 to obtain net xenon worth.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.5. Rods Correction To SDM

6.5.1. RECORD the Rod Insertion Limit (RIL) for the power level which existed prior to

the shutdown by using COLR, Figure 2 of Curve Book, Figure 13-1.

NOTE

The rod worth is based on the power level and burnup which existed prior to the shutdown.

6.5.2. RECORD the integral rod worth obtained from PCNDR (WINPCNDR) for the

associated RIL in Step 6.5.1.

NOTE

All values for the rod banks and individual rod worths are located in the PCNDR (WINPCNDR).

6.5.3. RECORD the controlling control rod bank AND its height prior to the shutdown

from one of the following:

• The step counters

• The URO Logbook entry at the beginning of the shift the last time the unit was

at steady state power

• The plant computer (see Attachment 7)

NOTE

The remaining amount of negative rod worth is based on the recorded bank height, power level, and

burnup which existed prior to the shutdown.

6.5.4. RECORD the integral rod worth obtained from PCNDR (WINPCNDR) for the

associated rod height in step 6.5.3.

OSP-SF-00001

Rev. 040


NOTE

This calculation allows for a 10% rod worth uncertainty.

6.5.5. RECORD the rod worth correction from the following calculation:

a. Subtract the critical rod worth in Step 6.5.4 from the rod worth at RIL in

Step 6.5.2.

b. Multiply the results in Step 6.5.5.a by 0.90.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.6. Temperature Correction To SDM

6.6.1. ENTER the minimum anticipated temperature during the shutdown.

6.6.2. RECORD the isothermal temperature defect obtained from PCNDR (WINPCNDR)

for the critical boron concentration from Step 6.3.6 and the minimum anticipated

temperature.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.7. Boron Correction To SDM

NOTE

Boron integral worth values are positive values as supplied by Westinghouse. The intent of this

Section is to determine the integral boron worth for a change in boron concentration.

6.7.1. CALCULATE adjusted current boron concentration:

a. RECORD the current boron concentration.


Attachment 8.

c. SUBTRACT Step 6.7.1.b from Step 6.7.1.a to obtain adjusted current boron

concentration.

6.7.2. RECORD the boron concentration from Step 6.3.6.

6.7.3. CALCULATE the boron depletion correction as follows:

a. IF Step 6.7.1.c is less than or equal to Step 6.3.6, USE zero (0) for boron

depletion correction.

b. IF Step 6.7.1.c is greater than Step 6.3.6, USE the following: Boron depletion

correction equals (Step 6.7.1.c minus Step 6.3.6) times (-0.025).

6.7.4. RECORD the boron depletion correction.

6.7.5. CALCULATE the corrected boron concentration by adding Step 6.7.1.c and

Step 6.7.4.

6.7.6. RECORD the integral boron worth obtained from PCNDR (WINPCNDR) for the

critical boron concentration obtained in Step 6.3.6, and the minimum anticipated

temperature from Step 6.6.1.

6.7.7. RECORD the integral boron worth obtained from PCNDR (WINPCNDR) for the

corrected boron concentration from Step 6.7.5 and minimum anticipated

temperature from Step 6.6.1.

6.7.8. SUBTRACT the integral boron worth for the corrected boron concentration in

Step 6.7.7 from the integral boron worth for the critical boron concentration in

Step 6.7.6.

OSP-SF-00001

Rev. 040


NOTE

A +300 pcm correction factor accounts for xenon-boron competition.

6.7.9. ADD the change in boron worth from Step 6.7.8 and the 300 pcm boron correction

factor to determine the corrected change in boron worth.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.8. Corrected SDM Determination

6.8.1. SUM the reactivities from Steps 6.3.13, 6.4.4, 6.5.5, 6.6.2, and 6.7.9 to obtain

corrected SDM.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.9. COLR Comparison

6.9.1. RECORD the reactivity required to meet shutdown limits for the current MODE.

• IF in MODES 1 – 4, USE COLR Section 2.1.1.

• IF in MODE 5, USE COLR Section 2.1.3.

6.9.2. RECORD the corrected Shutdown Reactivity from Step 6.8.1.

NOTE

If Total Shutdown Reactivity is more negative than the reactivity recorded in Step 6.9.1, then

sufficient core SDM exists to meet the requirements of COLR Sections 2.1.1 / 2.1.3.

6.9.3. IF corrected Shutdown Reactivity is NOT more negative than the reactivity

recorded in Step 6.9.1, immediately INITIATE and CONTINUE boration using

OTO-ZZ-00003, Loss of SDM, until the boron concentration meets the SDM

requirements of COLR Sections 2.1.1 / 2.1.3.

OSP-SF-00001

Rev. 040


NOTE

Step 6.9.4 ensures the boron concentration is adequate to meet the assumptions of a Steamline

Break Design Basis Accident (DBA) without automatically initiated Safety Injection (SI) available

to add borated water. [Ref: 8.2.11 and 8.2.12]

6.9.4. IF in MODE 3 or 4, and Below P-11, and SI is Blocked, PERFORM the

following:

a. RECORD the required boron concentration from Curve Book Figure 13-2

using the burnup recorded in Step 6.3.4 for either zero or one

untrippable/misaligned rods.

b. RECORD the corrected boron concentration from Step 6.7.5.

NOTE

If the current boron concentration is greater than or equal to the boron concentration determined in

Step 6.9.4.a, CIRCLE Yes to indicate that sufficient core SDM exists to meet the requirements of

COLR Section 2.1.2.

c. If current boron concentration is less than the boron concentration determined

in Step 6.9.4.a, immediately INITIATE and CONTINUE boration in

accordance with OTO-ZZ-00003, Loss of SDM, until the required boron

concentration recorded in Step 6.9.4.b is obtained.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.10. Boron Concentration Required To Maintain Keff< 0.99 With Shutdown Banks Withdrawn

NOTE

When calculating SDM just prior to shutdown bank withdrawal per OTG-ZZ-0001A, this Section

will determine the minimum boron concentration to keep the reactor from entering MODE 2.

These Steps should be used to calculate the required boron concentration to maintain Keff < 0.99

with the shutdown banks withdrawn.

6.10.1. INITIATE Attachment 3 and RECORD all data for this section on Attachment 3.

6.10.2. RECORD the total shutdown reactivity from Step 6.8.1.

6.10.3. RECORD the worth of the shutdown banks obtained from Curve Book Table 2-2

using ARI Bank Worth for the appropriate core life and xenon conditions.

6.10.4. RECORD the most reactive rod worth from Curve Book Table 1-8, Section II.

NOTE

The safety margin of 1500 pcm consists of 1000 pcm to reduce Keff from 1.0 to 0.99, and 500 pcm,

which can reasonably be expected to bound any reactivity errors.

6.10.5. RECORD the reactivity in excess of that required to ensure Keff less than 0.99 with

shutdown banks withdrawn by summing the reactivities in Steps 6.10.2, 6.10.3,

6.10.4, and the 1500 pcm safety margin.

6.10.6. RECORD the integral boron worth at the current boron concentration from

Step 6.7.7.

6.10.7. RECORD the integral boron worth for the minimum allowable boron concentration

to ensure Keff less than 0.99 with shutdown banks withdrawn by summing the

values in Steps 6.10.5 and 6.10.6.

6.10.8. RECORD the minimum boron concentration obtained from WINPCNDR for

reactivity in Step 6.10.7 and the temperature recorded in Step 6.6.1, to ensure Keff

less than 0.99 with shutdown banks withdrawn.

6.10.9. IF PZR concentration is less than RCS concentration, RECORD amount from

Attachment 8.

6.10.10. ADD Steps 6.10.8 and 6.10.9 to obtain required boron concentration.

OSP-SF-00001

Rev. 040


NOTE

When preparing for a reactor startup, the Estimated Critical Position Calculation may dictate a

lower boron concentration than that calculated in this Section. Since the ECP is a more accurate

reactivity balance, a lower boron concentration is permitted. As long as the control rods are

predicted to be above the Rod Insertion Limit and the ECP is current, a mode change will not occur

during the dilution to the critical boron concentration.

6.10.11. IF current boron concentration is NOT greater than or equal to one of the following

AND a reactor startup is NOT anticipated within the next hour:

• Boron concentration recorded in Step 6.10.8

• Boron concentration calculated in the Estimated Critical Position Calculation

(Refer To above note)

PRIOR to withdrawing shutdown banks, BORATE until the required concentration

is obtained.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.11. At Power SDM Calculation

NOTE

At power SDM is normally maintained by ensuring rods are above the rod insertion limits. At

power SDM calculation is normally performed only when one or more rods are INOPERABLE,

misaligned, or NOT within the insertion, sequence or overlap limits.

6.11.1. IF desired, USE PC program OSPSF1 to calculate SDM in lieu of completing this

Section.


6.11.3. RECORD the indicated power level as follows:

a. IF power is greater than 20%, OBTAIN power level from one of the following:

• Computer point REU1118 (i.e., REU1118 x 100% / 3565 MW)

• The highest power range meter:

• SE NI-41B

• SE NI-42B

• SE NI-43B

• SE NI-44B

b. IF power if less than or equal to 20% power, OBTAIN power from the highest

delta T indication:

• BB TI-411A

• BB TI-421A

• BB TI-431A

• BB TI-441A

NOTE

This calculation assumes that PZR boron concentration is equal to or greater than RCS boron

concentration.

6.11.4. RECORD the current critical boron concentration.

OSP-SF-00001

Rev. 040


6.11.5. RECORD the total power defect for the associated power level and burnup from

Curve Book Table 1-8, Section II.

6.11.6. RECORD the redistribution allowance and voids reactivity from Curve Book Table

1-8, Section II.

6.11.7. RECORD the corrected power defect by summing the redistribution allowance and

voids reactivity in Step 6.11.6 and the total power defect in Step 6.11.5.

6.11.8. RECORD the available rod worth from Curve Book Table 1-8, Section II.

6.11.9. DETERMINE the Rods Correction for INOPERABLE Rods:

a. RECORD the most reactive rod's worth from Curve Book Table 1-8,

Section II.

NOTE

A rod is considered trippable if it was demonstrated OPERABLE during the last performance of

T/S SR 3.1.4.2 and met the rod drop time criteria during the last performance of T/S SR 3.1.4.3

(T/S BACT 3.1.4.A.1.1).

The available rod worth of Step 6.11.8 accounts for rods being inserted as deep as the RIL. If a

misaligned rod is below the RIL, its full worth from the RIL position is not available for insertion.

Therefore such rods should be accounted for in Step 6.11.9.b.

IF an entire rod bank is below the RIL (i.e., with no misaligned rods), its full bank worth from the

RIL position is NOT available for insertion. Therefore such banks should be accounted for in Step

6.11.10 rather than in Step 6.11.9.b.

b. RECORD the number of INOPERABLE rods.

c. RECORD the total rod worth by multiplying the number of INOPERABLE

rods from Step 6.11.9.b by the worth of the most reactive rod from Step

6.11.9.a.

OSP-SF-00001

Rev. 040


6.11.10. DETERMINE the Rods Correction for Rod Banks below the Rod Insertion Limit

(RIL) as follows: [Ref: 8.2.8]

a. RECORD the RIL for the power level recorded in Step 6.11.3.

b. RECORD the current critical controlling control rod bank AND its height from

one of the following:

• The step counters

• The plant computer

c. IF the current controlling control rod bank position from Step 6.11.10.b is

above the RIL from Step 6.11.10.a, PERFORM the following (i.e., no

correction is necessary for rod banks above the RIL):

1. Mark Steps 6.11.10.d through 6.11.10.g NA

2. Go To Step 6.11.10.h

NOTE

The integral rod worths are based on the bank height (either RIL or critical position) and the power

level and burnup which exist for the current critical condition.

d. RECORD the integral rod worth obtained from PCNDR (WINPCNDR) for the

associated RIL in Step 6.11.10.a.

e. RECORD the integral rod worth obtained from PCNDR (WINPCNDR) for the

associated critical rod height in Step 6.11.10.b.

f. Subtract the critical rod worth in Step 6.11.10.e from the rod worth at RIL in

Step 6.11.10.d.

NOTE

This calculation allows for 10% rod worth uncertainty.

g. Multiply the results in Step 6.11.10.f by 1.10 to DETERMINE the rod worth

correction for rod banks below the RIL.

h. RECORD the rod worth correction for rod banks per one of the following:

• IF rod banks are below the RIL, RECORD the rod worth correction from

Step 6.11.10.g.

• IF rod banks are above the RIL, RECORD a rod worth correction of 0 pcm.

OSP-SF-00001

Rev. 040


6.11.11. RECORD the total corrected reactivity summing the reactivity from Steps 6.11.7,

6.11.8, 6.11.9.c and 6.11.10.h.

NOTE

If total corrected reactivity from Step 6.11.11 is more negative than the limits provided in the

COLR, SDM is sufficient to meet the Tech. Spec.

6.11.12. IF the total Corrected Reactivity from Step 6.11.11 is NOT more negative than the

limits provided in the COLR, INITIATE and CONTINUE boration in accordance

with OTO-ZZ-00003, Loss of SDM until SDM is achieved.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.12. SDM Determination Prior To Mode 6 Entry And During Mode 6 Prior To Core Reload


6.12.2. RECORD the limit for the Mode 6 RCS or Refueling Pool boron concentration, as

applicable obtained from CDP-ZZ-00200 Appendix B, Primary Plant Systems

Tables, Table 2.3 and Table 2.5.

6.12.3. RECORD the Refueling Boron Concentration value specified in T/S LCO 3.9.1.

6.12.4. RECORD the higher boron concentration from Steps 6.12.2 and 6.12.3.

6.12.5. IF PZR is NOT drained AND PZR concentration is less than RCS concentration,

RECORD amount from Attachment 8.

6.12.6. ADD Steps 6.12.4 and 6.12.5 to obtain required boron concentration.

6.12.7. RECORD the current boron concentration.

NOTE

IF the current boron concentration from Step 6.12.7 is greater than or equal to the most restrictive

boron concentration from Step 6.12.4, SDM is adequate.

6.12.8. IF the current boron concentration from Step 6.12.7 is less than the boron

concentration from Step 6.12.4, immediately SUSPEND all operations involving

CORE ALTERATIONS or positive reactivity changes and INITIATE action to

restore boron concentration to within limits.

-END OF SECTION-

OSP-SF-00001

Rev. 040


6.13. SDM While Subcritical After Refueling But Prior To Initial Startup

NOTE

The following data is to be recorded on Attachment 6.


6.13.2. RECORD the current plant MODE.

6.13.3. RECORD the current boron concentration.

6.13.4. DETERMINE the required shutdown boron concentration value from the

following:

a. IF in MODE 6, RECORD the most restrictive value from either:

1. CDP-ZZ-00200 Appendix B, Primary Plant Systems Tables, Tables 2.3

and 2.5

2. T/S LCO 3.9.1

b. IF in MODE 2 with Keff less than 1.0, OR in MODES 3, 4 or 5, RECORD the

value from Curve Book Table 1-8 for required SDM at xenon-free Conditions.

c. IF PZR concentration is less than RCS concentration, RECORD amount from

Attachment 8.

d. ADD Steps 6.13.4.a/6.13.4.b and 6.13.4.c to obtain required boron

concentration.

6.13.5. IF in Mode 3 just prior to pulling the shutdown banks, USE the * value from Curve

Book Figure 1-8, Section I, “Shutdown (Mode 3) with ARO, HZP (K=0.987),

BOL” to prevent inadvertent entry into Mode 2 during the shutdown bank pull.

OSP-SF-00001

Rev. 040


NOTE

If the current boron concentration from Step 6.13.3 is greater than or equal to the required shutdown

boron concentration from Step 6.13.4.d, SDM is adequate.

6.13.6. IF the current boron concentration is less than the required shutdown boron

concentration, PERFORM the following:

a. IF in Mode 6, immediately SUSPEND all operations involving CORE

ALTERATIONS or positive reactivity changes and INITIATE action to restore

boron concentration to within limits.

b. IF in MODE 2 with Keff less than 1.0, or MODES 3, 4, or 5, within 15

minutes INITIATE and CONTINUE boration an accordance with

OTO-ZZ-00003, Loss of SDM until SDM is achieved.

-END OF SECTION-

OSP-SF-00001

Rev. 040


7.0 RESTORATION

None

8.0 REFERENCES

8.1. Implementing

8.1.1. T/S LCO 3.1.1

8.1.2. T/S SR 3.1.1.1

8.1.3. T/S BSR 3.1.1.1

8.1.4. T/S APP 3.1.1 NOTE

8.1.5. T/S ACT 3.1.4.A.1.1

8.1.6. T/S BACT 3.1.4.A.1.1

8.1.7. T/S ACT 3.1.4.B.2.1.1

8.1.8. T/S ACT 3.1.4.B.2.3

8.1.9. T/S ACT 3.1.4.D.1.1

8.1.10. T/S ACT 3.1.5.A.1.1

8.1.11. T/S ACT 3.1.6.A.1.1

8.1.12. T/S ACT 3.1.6.B.1.1

8.1.13. T/S LCO 3.9.1

8.1.14. T/S SR 3.9.1.1

8.1.15. T/S ACT 3.9.2.A.3

8.1.16. OTO-ZZ-00003, Loss of SDM

8.1.17. OTG-ZZ-0001A, Shutdown Bank Withdrawal

8.1.18. CDP-ZZ-00200 Appendix B, Primary Plant Systems Tables

8.1.19. ODP-ZZ-00016, Reactor Operator Watchstation Practices And Logs

8.1.20. Curve Book, Table 1-8, Section I

OSP-SF-00001

Rev. 040


8.1.21. Curve Book Table 1-8, Section II

8.1.22. Curve Book, Figure 5-4

8.1.23. COLR, Figure 2 of Curve Book, Figure 13-1

8.1.24. Curve Book, Figure 13-2

8.2. Developmental

8.2.1. CDP-ZZ-00200, Chemistry Schedule and Water Specs

8.2.2. ETP-ZZ-00015, Preparation, Review, Approval, and Control of the Curve Book

8.2.3. COMN 5602

8.2.4. CARS 199501204

8.2.5. CARS 199501985

8.2.6. CARS 19960751

8.2.7. CARS 19990040

8.2.8. CARS 200508310

8.2.9. T/S SR 3.1.4.2

8.2.10. T/S SR 3.1.4.3

8.2.11. NSAL-02-14

8.2.12. TS Bases 3.1.1, SDM

OSP-SF-00001

Rev. 040


9.0 RECORDS

Records generated by this procedure are filed with the Work Authorizing Document.

9.1. Attachment 1 - SDM Calculation While Subcritical, Method 1

9.2. Attachment 2 - SDM Calculation While Subcritical, Method 2

9.3. Attachment 3 - Boron Concentration Required to Maintain Keff Less Than 0.99 With

Shutdown Banks Withdrawn

9.4. Attachment 4 - At Power SDM Calculation

9.5. Attachment 5 – SDM Determination Prior to MODE 6 Entry and During MODE 6 Prior to

Core Reload

9.6. Attachment 6 - SDM While Subcritical After Refueling, But Prior to Initial Startup

10.0 SUMMARY OF CHANGES

Page(s) Section or Step

Number Description

7 and 9 6.1.2 and 6.2.9

note Reworded the term blocking P-11 to blocking SI below P-11.

OSP-SF-00001

Rev. 040


Attachment 1

SDM Calculations While Subcritical, Method 1 Sheet 1 of 2

Person Performing (Print) Initials Date / Time

____________________________PIN # _______ _____ Started: ________ / _____

____________________________PIN # _______ _____ Completed: ________ / _____

6.2.4 Plant MODE: _______

6.2.5 Fuel burnup: _______ EFPD

6.2.6 Current boron concentration: _______ ppm

6.2.7.a Required boron concentration for current fuel burnup: _______ ppm

6.2.7.b Add PZR concentration correction: _______ ppm

6.2.7.c Required Boron Concentration: _______ ppm

6.2.8 IF current boron concentration is less than the required boron

concentration, PERFORM one of the following:

• Section 6.3.

• Within 15 minutes INITIATE and CONTINUE boration

in accordance with OTO-ZZ-00003, Loss of SDM, until the

required boron concentration of Step 6.2.7 is obtained.

OSP-SF-00001

Rev. 040


Attachment 1 (Cont'd.)

Sheet 2 of 2

Steam Line Break Consideration

NOTE: This section is only required if in MODE 3 or 4, and Below P-11, and SI is Blocked

6.2.9.a Required boron concentration from curve book: _______ ppm

6.2.9.b Add PZR concentration correction: _______ ppm

6.2.9.c Required Boron Concentration: _______ ppm

6.2.9.d Current boron concentration: _______ ppm

6.2.10 IF current boron concentration is less than required boron

concentration, immediately INITIATE and CONTINUE boration

in accordance with OTO-ZZ-00003, Loss of SDM, until the boron

concentration recorded in Step 6.2.7 is obtained.

6.2.11 IF current boron concentration is greater than or equal to the boron

concentration determined in Step 6.2.9.a, NO ACTION is required.

OSP-SF-00001

Rev. 040


Attachment 2

SDM Calculations While Subcritical, Method 2 Sheet 1 of 5


__________________________PIN # _________ _____ Started: ________ / _____

__________________________PIN # _________ _____ Completed: ________ / _____

6.3.3 Shutdown Date/Time: ________ / _____

6.3.4 Fuel Burnup: _______ EFPD

6.3.5 Reactor Power when Keff last equaled one (1): _______ %

6.3.6 Critical Boron Concentration: _______ ppm

6.3.7 Total Power Defect from curve book: (+)_______ pcm

6.3.8 Redistribution Allowance And Voids Reactivity from curve book: (+)_______ pcm

____________________

6.3.9 Corrected Total Power Defect: (+)_______ pcm

(Sum Steps 6.3.7 and 6.3.8)

6.3.10 Available Rod Worth from curve book: (–)_______ pcm

6.3.11 Rod worth of worst case stuck rod from curve book: (+)_______ pcm

6.3.12.a Number of inoperable rods: ________

6.3.12.b INOPERABLE rod worth: ______ x ________ = (+)_______ pcm.

6.3.11 6.3.12.a

6.3.9 (+)_______ pcm

+ 6.3.10 (–)_______ pcm

+ 6.3.12.b (+)_______ pcm

____________________

6.3.13 Uncorrected SDM: = ( )_______ pcm *

OSP-SF-00001

Rev. 040



Sheet 2 of 5

Xenon Correction

6.4.1 Time since shutdown: _______ hours

6.4.2 Current xenon worth: (–)_______pcm

6.4.3 Xenon worth prior to shutdown: – (–)_______pcm

____________________

6.4.4 Net xenon worth: = ( )_______pcm *

Rods Correction

6.5.1 Critical RIL: Bank _______ Steps _______

6.5.2 Rod worth at RIL from WINPCNDR: (–)_______ pcm

6.5.3 Critical rod height: Bank _______ Steps _______

6.5.4 Critical rod worth from WINPCNDR: – (–)_______ pcm

____________________

6.5.5.a Rod worth correction: = (–)_______ pcm

6.5.5.b Rod worth correction: ________ X 0.90: (–)_______ pcm *

6.5.5.a

Temperature Correction

6.6.1 Minimum anticipated temperature: _______ Deg F

6.6.2 Isothermal temperature defect: (+)_______ pcm *

OSP-SF-00001

Rev. 040



Sheet 3 of 5

Boron Correction

6.7.1.a Current boron concentration: _______ ppm

6.7.1.b Subtract PZR concentration correction: _______ ppm

6.7.1.c Adjusted current Boron Concentration: _______ ppm

6.7.2 Record the boron concentration from Step 6.3.6: _______ ppm

6.7.3.a IF Step 6.7.1.c is less than or equal to Step 6.7.2, RECORD zero (0) in 6.7.4.

6.7.3.b IF Step 6.7.1.c is greater than Step 6.7.2, RECORD the following result in 6.7.4.

(_______ – _______ ) x (-0.025) = (–)_______ ppm

6.7.1.c 6.7.2

6.7.4 Boron depletion correction: + (–)_______ ppm

____________________

6.7.5 Corrected boron concentration: SUM 6.7.1.c and 6.7.4: =_______ ppm

6.7.6 Integral boron worth for critical boron concentration: (+)_______ pcm

6.7.7 Integral worth for corrected boron concentration: – (+)_______ pcm

____________________

6.7.8 Change in boron worth: SUBTRACT 6.7.7 from 6.7.6: = ( )______ pcm

Boron correction factor: + (+) 300 pcm

____________________

6.7.9 Corrected change in boron worth: SUM +300 pcm and 6.7.8: = ( )_______ pcm *

OSP-SF-00001

Rev. 040



Sheet 4 of 5

Total Shutdown Margin

Step Condition Data

NOTE: The following values come from previous Steps

that have an asterisk after the pcm value.

From Step 6.3.13 ( )_______ pcm *

From Step 6.4.4 ( )_______ pcm *

From Step 6.5.5.b (–)_______ pcm *

From Step 6.6.2 (+)_______ pcm *

From Step 6.7.9 ( )_______ pcm *

6.8.1 Total Corrected SDM

= 6.3.13 + 6.4.4 + 6.5.5.b + 6.6.2 + 6.7.9: ( )_______ pcm

COLR Comparison

6.9.1 Reactivity required to meet shutdown limits for the current MODE: (–)______ pcm

6.9.2 Corrected SDM from Step 6.8.1: ( )______ pcm

6.9.3 IF corrected Shutdown Reactivity is NOT more negative than the

reactivity recorded in Step 6.9.1, immediately INITIATE and

CONTINUE boration using OTO-ZZ-00003, Loss of SDM,

until the proper SDM is achieved.

OSP-SF-00001

Rev. 040



Sheet 5 of 5

Steam Line Break Consideration

NOTE: This section is only required if In MODE 3 or 4, and

Below P-11, and SI is Blocked.

6.9.4.a Required boron concentration from Curve Book

Figure 13-2: _______ ppm

6.9.4.b Corrected boron concentration (from Step 6.7.5): _______ ppm

6.9.4.c If current boron concentration is less than the boron

concentration determined in Step 6.9.4.a, immediately

INITIATE and CONTINUE boration in accordance with

OTO-ZZ-00003, Loss of SDM, until the required boron

concentration recorded in Step 6.9.4.a is obtained.

OSP-SF-00001

Rev. 040


Attachment 3

Boron Concentration Required To Maintain Keff less than 0.99

With Shutdown Banks Withdrawn Sheet 1 of 1


_____________________________PIN #_______ _____ Started: ________ / _____

_____________________________PIN # _______ _____ Completed: ________ / _____

6.10.2 Total SDM from 6.8.1: ( )______ pcm

6.10.3 Shutdown bank worth: + (+)______ pcm

6.10.4 Most reactive rod worth: + (–)______ pcm

Safety margin: + (+) 1500 pcm

______________

6.10.5 Excess reactivity. SUM Steps 6.10.2, 6.10.3, 6.10.4, and Safety margin: = ( )______ pcm

6.10.6 Integral boron worth at current boron concentration: + (+)______ pcm

____________________

6.10.7 Integral boron worth for minimum required boron: = ( )______ pcm

SUM Steps 6.10.5 and 6.10.6.

6.10.8 Minimum boron concentration with shutdown banks

fully withdrawn: _______ ppm

6.10.9 Add PZR concentration correction: _______ ppm

6.10.10 Required Boron Concentration: _______ ppm

OSP-SF-00001

Rev. 040


Attachment 4

At Power SDM Calculation Sheet 1 of 1


_______________________________PIN #_______ _____ Started: ________ / _____

_______________________________PIN #_______ _____ Completed: ________ / _____

6.11.3 Reactor power: _______ %

6.11.4 Critical Boron Concentration: _______ ppm

6.11.5 Total Power Defect: (+)_______ pcm

6.11.6 Redistribution Allowance And Voids Reactivity: + (+)_______ pcm

____________________

6.11.7 Corrected Total Power Defect (Sum Steps 6.11.5 and 6.11.6): = (+)_______ pcm

6.11.8 Available Rod Worth: + (–)_______ pcm

6.11.9.a Rod worth of worst case stuck rod: (+)_______ pcm

6.11.9.b Number of INOPERABLE rods: ________

6.11.9.c Untrippable/Misaligned Rod Worth: 6.11.9.a x 6.11.9.b: + (+)_______ pcm

6.11.10.a Critical RIL: Bank ________ Step ________

6.11.10.b Critical Controlling Bank: Bank ________ Step ________

6.11.10.d Rod worth all RIL from WINPCNDR: (-) _________pcm

6.11.10.e Critical rod worth from WINPCNDR: - (-) _________pcm

_________________

6.11.10.f Rod worth correction: = (+) _________pcm

6.11.10.g Rod worth correction: ______ X 1.10 = (+) _________pcm 6.11.10.f

6.11.10.h Rod worth correction for rod banks below RIL + (+)_______ pcm

6.11.11 Total corrected Reactivity (SUM Steps 6.11.7, 6.11.8, 6.11.9.c and 6.11.10.h): = ( )_______ pcm

6.11.12 IF the total Corrected Reactivity from Step 6.11.11 is NOT more negative than the limits provided

in the COLR, INITIATE and CONTINUE boration in accordance with OTO-ZZ-00003, Loss of

SDM until SDM is achieved.

OSP-SF-00001

Rev. 040


Attachment 5

SDM Determination Prior To MODE 6 Entry

And During MODE 6 Prior To Core Reload Sheet 1 of 1


_____________________________ PIN #_______ _____ Started: ________ / _____

_____________________________ PIN #_______ _____ Completed: ________ / _____

6.12.2 Boron concentration from

CDP-ZZ-00200 Appendix B, Primary Plant Systems Tables: _______ ppm

6.12.3 Boron concentration from T/S LCO 3.9.1: _______ ppm

6.12.4 Largest boron concentration from 6.12.2 and 6.12.3: _______ ppm

6.12.5 Add PZR concentration correction: _______ ppm

6.12.6 Required Boron Concentration: _______ ppm

6.12.7 Current boron concentration: _______ ppm

6.12.8 IF the current boron concentration from Step 6.12.7 is less than

the boron concentration in Step 6.12.4, immediately SUSPEND

all operations involving CORE ALTERATIONS or positive

reactivity changes and INITIATE action to restore boron

concentration to within limits.

OSP-SF-00001

Rev. 040


Attachment 6

SDM While Subcritical After Refueling, But Prior To Initial Startup Sheet 1 of 1


____________________________ PIN #_______ _____ Started: ________ / _____

____________________________ PIN #_______ _____ Completed: ________ / _____

Step Condition Data

6.13.2 Current MODE: _______

6.13.3 Current concentration: _______ ppm

6.13.4.a MODE 6 required concentration: _______ ppm

OR

6.13.4.b MODE 2 – 5 required concentration: _______ ppm

6.13.4.c Add PZR concentration correction: _______ ppm

6.13.4.d Required boron concentration: _______ ppm

6.13.6 IF the current boron concentration is less than the required

shutdown boron concentration, PERFORM the following:

a. IF in Mode 6, immediately SUSPEND all operations

involving CORE ALTERATIONS or positive reactivity

changes and INITIATE action to restore boron

concentration to within limits.

b. IF in MODE 2 with Keff less than 1.0, or MODES 3, 4,

or 5, within 15 minutes INITIATE and CONTINUE

boration an accordance with OTO-ZZ-00003, Loss of SDM

until SDM is achieved.

OSP-SF-00001

Rev. 040


Attachment 7

Input Guidelines For Shutdown Margins Sheet 1 of 1

DATA POINT TYPE OF REACTOR SHUTDOWN

Controlled Shutdown Reactor Trip/Rapid Shutdown

Time of Shutdown Time when 10-8

data was

taken. Note 1

Time of trip or commencement

of shutdown.

Critical Boron Conc.

Critical Rod Height

Controlling Bank

From 10-8

data. Note 1

From most recent RO turnover

entry or midnight entry,

whichever is most recent.

Power Level Prior to Shutdown Use 0%. Note 1

Enter power at time of trip or

commencement of shutdown.

Xenon

Iodine

Use poison concentrations

at “Time of Shutdown”

from XEPRED run or

from curve book. Will

need to account for power

descension causing xenon

buildup.

Use poison concentrations from

midnight

ODP-ZZ-00016Control Room

Computer Log printout if power

was constant from midnight

until trip. Otherwise do

XEPRED run.

Burnup From midnight Control

Room Computer Log

printout.

From midnight Control Room

Computer Log printout.

Note 1: If available, reference reactivity data should be taken from equilibrium conditions prior

to 10-8

data. In this case, input data will be from the equilibrium conditions.

OSP-SF-00001

Rev. 040


Attachment 8

Correction for PZR Boron Concentration Sheet 1 of 1

NOTE

When sample values are between table values, the higher boron concentration shall be used.

Initial Boron �

(RCS Boron) – (PZR Boron)

� RCS Boron after

Mixing Boron

Correction (ppm)

Initial Boron �

(RCS Boron) – (PZR Boron)

� RCS Boron after

Mixing Boron

Correction (ppm)

10 1.4 450 62.1

20 2.8 500 69.0

30 4.1 550 75.9

40 5.5 600 82.8

50 6.9 650 89.7

60 8.3 700 96.6

70 9.6 750 103.5

80 11 800 110.4

90 12.4 850 117.3

100 13.8 900 124.2

120 16.5 950 131.1

140 19.3 1000 138.0

160 22.1 1050 144.9

180 24.8 1100 151.8

200 27.6 1150 158.7

220 30.3 1200 165.6

240 33.1 1250 172.5

260 35.8 1300 179.4

280 38.6 1350 186.3

300 41.3 1400 193.2

320 44.1 1450 200.1

340 46.9 1500 207.0

360 49.6

380 52.4

400 55.1


JPM No: RSA-2 KSA No: GEN 2.1.25 Revision: July 2013 KSA Rating: 4.2 Job Title: SRO Task Title: Determine the volume and RMCS control settings for raising RWST level Validation Time: 16 minutes Learning Objective: T61.0110.6, LP 11, Obj P, IDENTIFY the BTRS MCB controls, alarms and indications and DESCRIBE how each is used to predict, monitor or control changes in the BTRS System. The performance of this task was evaluated against the standards contained in this JPM and determined to be: [ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY: Evaluators Signature: Date: Task Performer: Location of Performance: Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: __ ____ Time Critical: ___ ___ Student Handouts: OTN-BG-0002 RWST Level/Volume Curve Tank Book Curve Book Straight Edge Calculator References: OTN-BG-00002, “Reactor Makeup Control and Boron Thermal Regeneration System”


PAGE 1 of 3

Initial Conditions: The unit is coming out of a refueling outage.

A significant leak occurred during the refuel pool draindown process. RWST level is 92%. RWST Boron Concentration is 2375 PPM. BAST concentration is 7000 ppm

Initiating Cues: You have been directed to determine the volume addition required to establish

the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at it’s current value with a makeup flow rate of 90 GPM

Task Standard: Upon completion of this JPM, the Applicant will have determined the Volume

addition and controls settings within the specified range. START TIME: STOP TIME:

JPM NO: RSA-2, Rev 1 JPM TASK STEP ELEMENT


SCORE

PAGE 2 of 3

1. Obtain a verified working copy of OTN-BG-00002 and determines that Section 5.5 – MANUAL MODE OF RMCS OPERATION applies.

Applicant obtained working copy of OTN-BG-00002

S U

Comments:

2. *Determine the volume to be added.

Refers to RWST Level/Volume Curve and determines ≥ 23,500 gallons but ≤ 25,500 must be added.

S U

Comments:

3. *Determines RMCS settings based upon required blended flow rates

Refers to Figure 7-2 and determines: • Boric Acid flow BG-FK-111 potentiometer setting 5.63 ±.1

• Blended flow BG-FK-110 potentiometer setting 7.63 ±.1

S U

Comments:



Comments:


Initial Conditions: The unit is coming out of a refueling outage.

A significant leak occurred during the refuel pool draindown process. RWST level is 92%. RWST Boron Concentration is 2375 PPM.

BAST concentration is 7000 ppm Initiating Cues: You have been directed to determine the volume addition required to establish the

RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at it’s current value with a makeup flow rate of 90 GPM

Provide to Examiner when complete:

Volume to be added ___________

Reactor Makeup Control System settings: ___________________________


OTN-BG-00002

REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION

SYSTEM

MINOR Revision 041

OTN-BG-00002

Rev. 041


SYSTEM

TABLE OF CONTENTS

Section Page Number


1.0 PURPOSE ...................................................................................................................................... 4

2.0 SCOPE ........................................................................................................................................... 4


3.1. Precautions .......................................................................................................................... 4

3.2. Limitations........................................................................................................................... 5

3.3. General Notes ...................................................................................................................... 5

4.0 PREREQUISITES ......................................................................................................................... 7


5.1. Automatic Mode Of RMCS Operation ................................................................................. 8

5.2. Dilute Mode Of RMCS Operation ........................................................................................ 9

5.3. Alternate Dilute Mode Of RMCS Operation ...................................................................... 11

5.4. Borate Mode Of RMCS Operation ..................................................................................... 13

5.5. Manual Mode Of RMCS Operation To CCP Suction (VCT) .............................................. 15

5.6. Manual Mode Of RMCS Operation (RWST-RHUT-BTRS) ............................................... 17

5.7. BTRS Operation - Boration ................................................................................................ 20

5.8. BTRS Operation - Dilution ................................................................................................ 24

5.9. BTRS Operation - Borate To Dilute Mode Change ............................................................ 28

5.10. BTRS Operation - Dilute To Borate Mode Change ............................................................ 31

5.11. Flushing BTRS Demineralizers Using RCS Letdown Flow ................................................ 34

5.12. Flushing BTRS Demineralizers Using Reactor Makeup Water ........................................... 36

5.13. Pressure Testing BTRS With Reactor Makeup Water ......................................................... 41

5.14. Immediate Boration To Support Plant Shutdown ................................................................ 44

5.15. Restoration Of The SW Side Of CVCS Chiller Unit From Dry Layup Condition ............... 46

5.16. Placing The SW Side Of CVCS Chiller Unit In Dry Layup Condition ................................ 48

5.17. Restoration Of Chilled Water Side Of CVCS Chiller Unit From Dry Layup Condition ...... 50

5.18. Placing The Chilled Water Side Of CVCS Chiller Unit In Dry Layup Condition ................ 53

5.19. Removing BTRS From Service For Maintenance ............................................................... 55

5.20. Filling And Venting BTRS Following Maintenance Using Letdown Or Rx M/U Water ..... 56

6.0 REFERENCES ............................................................................................................................ 61

6.1. Implementing ..................................................................................................................... 61

6.2. Developmental ................................................................................................................... 61

OTN-BG-00002

Rev. 041


SYSTEM

TABLE OF CONTENTS

Section Page Number


7.0 RECORDS ................................................................................................................................... 62

7.1. QA Records ....................................................................................................................... 62

7.2. Commercial Records .......................................................................................................... 62


ATTACHMENT 1, BTRS Performance Data/Status Log......................................................................... 64

ATTACHMENT 2, RCS Letdown Flow - BTRS Demineralizer Flushing Data ....................................... 65

ATTACHMENT 3, Reactor Makeup Water - BTRS Demineralizer Flushing Data .................................. 66

ATTACHMENT 4, Volume Control Tank Level Control System ............................................................ 67

ATTACHMENT 5, BTRS Controls For BG HIS-27 Indication ............................................................... 68

ATTACHMENT 6, Dilute Mode Of RMCS Operation ............................................................................ 69

ATTACHMENT 7, Alternate Dilute Mode Of RMCS Operation ............................................................. 70

ATTACHMENT 8, Borate Mode Of RMCS Operation ........................................................................... 71

Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up

Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up

Checklist 3, Locked Valve Restoration

Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side

OTN-BG-00002

Rev. 041



SYSTEM

1.0 PURPOSE

To provide instructions for the operation of the Reactor Makeup Control System (RMCS) and the

Boron Thermal Regeneration System (BTRS).

2.0 SCOPE

This procedure addresses all modes of RCS boration and dilution and also includes:

• Flushing BTRS Demineralizers

• Pressure testing BTRS Demineralizers

• Immediate Boration

• Establishing & Securing From Dry Layup in the CVCS Chiller Unit

• Removing BTRS from Service for Maintenance

• Restoring BTRS to Service


3.1. Precautions

3.1.1. The boric acid storage tank level should not be reduced below the minimum

required by FSAR 16.1.2.6, if in MODES 1 through 4 or FSAR 16.1.2.5, if in

MODES 5 and 6.

Plant

MODE

Contained

Volume (gal)

% Level in

One Tank

1, 2, 3, or 4 17,658 70

5 or 6 2,968 10

3.1.2. Whenever a difference of 50 ppm exists, the pressurizer spray should be operated

by placing the backup heaters on to equalize the boron concentration in the RCS

and pressurizer.

3.1.3. Prior to make up being added to the refueling canal, RCS or Spent Fuel Pool, with

all four RCPs secured, recirculation flow should be checked through the RCS

(RHR flow greater than or equal to 1000 gpm) or the concentration of the make up

should be greater than or equal to 2000 ppm.

3.1.4. At all times when boration/dilution via BTRS is initiated or in progress, the Reactor

Coolant Filter must be in service with BGV8421, CVCS RX CLNT FLTR BYP ISO,

CLOSED, to prevent possible resin leakage from entering the RCS.

OTN-BG-00002

Rev. 041


3.1.5. When placing a BTRS bed into service after an extended period of time or when

the bed boron concentration is suspect, letdown flow should be diverted to the

RHUT until the desired trend in boron concentration is observed by the Boron

Concentration Monitoring System, (BCMS), or chemistry sample.

3.1.6. The recirculation return line to the RWST is non-seismic. To ensure the RWST

remains OPERABLE in MODES 1 through 4, no other systems, with the exception

of the SI pumps in standby, are aligned to the RWST return header when

performing Section 5.6 aligned to the RWST. [Ref: 6.2.13]

3.1.7. Prior to establishing M/U flow for flushing a BTRS Demineralizer bed,

BG FY-111B, COMBINED M/U & BA COUNTER, must be reset and the counter set to

the maximum amount of water that Radwaste can receive. It is important to stop

letdown flow through the letdown reheat heat exchanger prior to stopping M/U

flow. This will allow cooling of the letdown reheat heat exchanger.

3.1.8. During Reactor Makeup Control System operation, it is permissible to place one of

the Boric Acid Transfer Pumps in Pull To Lock. This will allow for maintenance

of level in one of the Boric Acid Storage Tanks to prevent Annunciator 37B, BA

TKS LEV LO.

3.1.9. When setting BG FY-111B, COMBINED M/U & BA COUNTER, and BG FY-110B, BA

COUNTER, allowances should be made in the setpoint to compensate for instrument

inaccuracies and isolation valve closure times on total flow delivered. For instance,

the accuracy of both the boric acid integrator BG FY-110B and the total makeup

flow integrator BG FY-111B is +/- one count. This equates to +/- 0.1 gal for

BG FY-110B and +/- 1.0 gal for BG FY-111B. Differences in setpoint and total

flow delivered are also dependent on the amount of time it takes for valves to close

and isolate flow once the integrator setpoint has been reached.

3.2. Limitations

Under normal conditions, the RMCS should operate in the AUTOMATIC mode. When used

in modes other than AUTOMATIC, the system should be returned to AUTOMATIC upon

completion of the evolution.

3.3. General Notes

3.3.1. BG HC-387, BTRS DEMIN BYPASS CTRL, should be adjusted to maintain a constant

flow through the BTRS Demineralizer beds. This will allow more accurate results

to be obtained for operator aid development.

3.3.2. Demineralizer flushing may be stopped or interrupted as required by plant

conditions. However, to minimize the frequency of flushing operations, the

Demineralizer should be flushed for the duration determined by the BG System

Engineer.

OTN-BG-00002

Rev. 041


3.3.3. A new BTRS Demineralizer bed should be flushed in accordance with

OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System, prior to

placing the bed into service for the first time.

3.3.4. The BTRS Chiller Unit and Pumps are normally NOT in service.

a. The Service Water Inlet and Outlet Headers are in a dry lay-up condition until

the Chiller Unit is required for service. This requires a fill and vent of service

water headers prior to the Chiller Unit being placed in service. A dry lay-up

condition requires the inlet and outlet service water isolation valves to be

LOCKED CLOSED with various vents and drains OPENED.

b. The Chill Water side of the BTRS Chiller is also placed in dry lay-up condition

until the Chiller Unit is required for service. Power is removed from the

pumps and chiller unit. Some drains and vents are left OPEN with FME

screens installed.

3.3.5. During Startup testing of the BTRS system, the following noted items were

documented:

a. Operation of BTRS in the Borate mode following an extended period of time

in the Dilute mode can initially produce BTRS effluent of approximately

200 ppm greater than the RCS boron concentration.

b. If the Demineralizers are saturated when boration begins, or if the

Demineralizers have been recently flushed before starting a dilution, the

maximum anticipated change in RCS boron concentration via BTRS is

approximately 100 ppm. Under either condition, the maximum change will

require 8-10 hours for the Demineralizers to become saturated.

c. Demineralizer inlet temperature as indicated on BG TI-381, LTDN RH HX TUBE

SIDE OUTLET TEMP CTRL TEMP IND, should go to between 40°F to 60°F within

approximately 1 hour after BTRS has been placed in the Dilute mode, when

BTRS is originally at ambient conditions (80°F). This is due to the time

required to cool down the associated heat exchangers and piping.

d. Demineralizer inlet temperature, as indicated on BG TI-381, should go to

between 135°F and 145°F within approximately 15 minutes after BTRS has

been placed in the Borate mode, when BTRS is originally at ambient

conditions (80°F).

e. When BTRS is in the Borate mode for more than 30 minutes at a time,

Demineralizer inlet temperature, as indicated on BG TI-381, may begin to

oscillate +8 to –10°F from the setpoint value.

OTN-BG-00002

Rev. 041


Step 3.3.5 Cont'd

f. During Borate mode of operation, to prevent the Demineralizer inlet

temperature from reaching the BTRS TEMP HI DIVERT alarm setpoint of

156°F or the BTRS TEMP HI alarm setpoint of 150°F, it may be necessary to

lower the setpoint on BG TK-381A, LTDN DIVERT FLOW CTRL, to prevent the

oscillations.

3.3.6. Attachment 4, Volume Control Tank Level Control System, provides information

on the setpoints and controls of the VCT level.

3.3.7. Attachments 6 through 8 are provided to assist in normal shiftly dilutions/borations

of the RCS. It is the intent that the cover page of this procedure and applicable

Attachments 6, 7, or 8 be copied for the intended shiftly dilutions/borations

discussed at the beginning of shift brief. Copies should be made of the quantity

discussed for the incremental dilutions/borations during the shift.

4.0 PREREQUISITES

4.1. WHEN required, ENSURE the following:

• Reactor Makeup Water System is available to supply the RMCS.

• Sufficient boric acid of proper concentration is available to supply the RMCS.

• The Service Water System is available to supply the CVCS Chiller Unit during

BTRS operation.

• The CVCS Chiller Surge Tank is within the normal operating range.

4.2. Prior to make up being added to the refueling canal, RCS or Spent Fuel Pool, with all four

RCPs secured, MAKE a URO Log entry documenting that either recirculation flow through

the RCS (RHR flow) is greater than or equal to 1000 gpm, or that the boron concentration of

the make up is greater than or equal to 2000 ppm.

4.3. IF making up to the RWST per Section 5.6 in MODES 1 through 4, ENSURE no other

systems, with the exception of the SI pumps in standby, are aligned to the RWST return

header.

-END OF SECTION-

OTN-BG-00002

Rev. 041



NOTE

All control switches are on Panel RL001 or RL002 unless otherwise noted.

BG FK-111, REACTOR M/U WTR FLOW CTRL, defaults to 120 gpm when the Reactor Mode Selector

Switch is in AUTO.

BGHCV0387, BTRS DEMINS BYP HV, is interlocked such that BGHCV0387 can NOT be taken out

of the bypass position unless one of the BTRS Demineralizer Inlet valves is open. This section is

sequenced such that this interlock is NOT challenged.

5.1. Automatic Mode Of RMCS Operation

NOTE

Automatic mode of RMCS controls VCT level between 30% and 50%

5.1.1. DETERMINE the desired boric acid flow rate for blended flow required using

Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs – Blended

Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates, or equivalent.

5.1.2. PLACE BG HS-26, RCS M/U CTRL, in STOP.

5.1.3. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO.

5.1.4. SET BG FK-110, BA FLOW CTRL, at the desired flow rate and PLACE the

controller in AUTO.

5.1.5. PLACE BG FK-111, REACTOR M/U WTR FLOW CTRL, in AUTO.

5.1.6. PLACE BG HS-26, RCS M/U CTRL, in RUN.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.2. Dilute Mode Of RMCS Operation

NOTE

A "Nominal 120 gpm Dilution" should be performed per Attachment 6 instead of this section.

5.2.1. DETERMINE the desired dilution volume and flow rate using the following (as

applicable):

• Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs –

Boron Dilution


Boron Dilution Rate


Boron Dilution and Boron Addition

• The shiftly Reactivity brief

• Using OpsReactivityCalc software


5.2.3. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL.

5.2.4. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired dilution flow rate

and PLACE the controller in AUTO.

NOTE

When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument

inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more

information, if required.)

5.2.5. SET BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to deliver the desired

amount of makeup water.


5.2.7. IF desired, using BG FK-111, ADJUST the flow rate as required by plant

conditions.

5.2.8. IF desired to stop the dilution flow before BG FY-111B automatically stops it,

PLACE BG HS-26, RCS M/U CTRL, in STOP.

OTN-BG-00002

Rev. 041


5.2.9. WHEN dilution is complete, RESTORE from the Dilute Mode as follows:

a. PLACE BG HS-26, RCS M/U CTRL, in STOP.

b. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO.

c. ENSURE BG FK-110, BA FLOW CTRL, is set to the desired concentration for

the current RCS boron concentration.

d. PLACE BG HS-26, RCS M/U CTRL, in RUN.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.3. Alternate Dilute Mode Of RMCS Operation

NOTE

A "Nominal 120 gpm Alternate Dilution" should be performed per Attachment 7 instead of this

section.


applicable):


Boron Dilution


Boron Dilution Rate






5.3.3. PLACE BG HS-25, RCS M/U CTRL SEL, in ALT DIL.

5.3.4. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired dilution flow rate

and PLACE the controller in AUTO.

NOTE



information if required.)

5.3.5. SET BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to deliver the desired

amount of makeup water.

OTN-BG-00002

Rev. 041


NOTE

In the Alternate Dilute Mode, a portion of the dilution flow goes directly to the charging pump

suction; therefore, the effects on reactivity will be seen sooner and occur more rapidly.



conditions.

5.3.8. IF desired to stop the dilution flow before BG FY-111B automatically stops it,


5.3.9. WHEN dilution is complete, RESTORE from the Alternate Dilute Mode as

follows:






-END OF SECTION-

OTN-BG-00002

Rev. 041


5.4. Borate Mode Of RMCS Operation

NOTE

A "Normal Frequently Performed Boration" should be performed per Attachment 8 instead of this

section.


applicable):


Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates


Boron Addition


Boron Addition Rate


Boron Dilution Rate






5.4.3. PLACE BG HS-25, RCS M/U CTRL SEL, in BOR.

5.4.4. SET BG FK-110, BA FLOW CTRL, at the desired boron flow rate and PLACE the

controller in AUTO.

NOTE




5.4.5. SET BG FY-110B, BA FLOW COUNTER, to deliver the desired amount of boron.


OTN-BG-00002

Rev. 041



conditions.

5.4.8. IF desired to stop the boration flow before BG FY-110B automatically stops it,


5.4.9. WHEN boration is complete, RESTORE from the Boration Mode as follows:






-END OF SECTION-

OTN-BG-00002

Rev. 041


5.5. Manual Mode Of RMCS Operation To CCP Suction (VCT)

5.5.1. DETERMINE the desired boric acid and makeup water flow rates for blended flow

using Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs –

Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates.


5.5.3. PLACE BG HS-25, RCS M/U CTRL SEL, in MAN.


controller in AUTO.

5.5.5. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired flow rate and

PLACE the controller in AUTO.

NOTE




5.5.6. SET BG FY-111B, COMBINED M/U & BA COUNTER, to deliver the desired amount

of makeup water.

5.5.7. SET BG FY-110B, BA COUNTER, sufficiently high to ensure boric acid flow

continues throughout manual makeup.

5.5.8. PLACE BG HIS-111B, MAKEUP TO VCT INLET, in CLOSE.

5.5.9. OPEN BG HIS-110B, MAKEUP TO VCT OUTLET.

OTN-BG-00002

Rev. 041


CAUTION

BG FK-110, BA FLOW CTRL, is normally in AUTO in the Full Open position. During manual

makeup to the VCT with low RCS boron concentrations, boric acid will inject at 40 gpm until

BG FK-110 throttles back flow, resulting in adding more boron than required.

5.5.10. IF operating near end of cycle with low RCS boron concentration, PERFORM the

following

a. PLACE BG FK-110, BA FLOW CTRL, in MANUAL

b. REDUCE output to the approximate boric acid addition rate in gpm. (Late in

the core cycle this may be close to zero demand.)

NOTE

Steps 5.5.10.c and 5.5.11 should be performed concurrently.

c. PLACE BG-FK-110, BA FLOW CTRL, in AUTO.


5.5.12. WHEN the makeup addition is complete, PLACE BG HS-26, RCS M/U CTRL, in

STOP.

5.5.13. PLACE the following in AUTO:

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET

5.5.14. RESTORE the RMCS to AUTO per Section 5.1.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.6. Manual Mode Of RMCS Operation (RWST-RHUT-BTRS)

5.6.1. ENSURE VCT level is sufficient for expected plant operating conditions for the

duration of the makeup.

5.6.2. IF makeup is required to the Spent Fuel Pool, Refer To OTN-EC-00001, Fuel Pool

Cooling And Cleanup System.

5.6.3. DETERMINE the desired boric acid and makeup water flow rates for blended flow

using Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs –

Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates.




controller in AUTO.

5.6.7. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired flow rate and

PLACE the controller in AUTO.

NOTE




5.6.8. SET BG FY-111B, COMBINED M.U & BA COUNTER, to deliver the desired amount

of makeup water.

5.6.9. SET BG-FY-110B, BA COUNTER, sufficiently high to ensure boric acid flow

continues throughout manual makeup.

5.6.10. PLACE the following in CLOSE:



OTN-BG-00002

Rev. 041


5.6.11. OPEN the appropriate valve(s) below to align the Boric Acid Blender Outlet to the

desired location:

NOTE

BGV0192, M/U TO BA BLENDING TEES HDR ISO, and BGV0034, RX M/U WTR TO BTRS ISO, should

be entered in the Locked Component Deviation List if performance of this procedure is terminated

or postponed prior to restoration of these valves to the LOCKED CLOSED position.

• Makeup to RWST

• BGV0192, M/U TO BA BLENDING TEES HDR ISO (AB-2000 Rm 1318)

• BGV0195, M/U TO RWST HDR ISO (AB-2000 Rm 1318)

• Makeup to RHUT


• HEV0027, BA BLEND TEE TO RECYC EVAP FEED DEMIN IN (AB-2000

Rm1318)

• Makeup to BTRS


• BGV0034, RX M/U WTR TO BTRS ISO (AB-1974 Rm 1105)

5.6.12. IF adding water to the RWST, NOTIFY Chemistry that sampling is required.


OTN-BG-00002

Rev. 041


5.6.14. WHEN the makeup addition is complete:


b. RESTORE any components that were manipulated in Step 5.6.11 as follows:

• CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO.

• CLOSE BGV0195, M/U TO RWST HDR ISO.

• CLOSE HEV0027, BA BLEND TEE TO RECYC EVAP FEED DEMIN IN.

• CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO.

c. RESTORE the RMCS to AUTO per Section 5.1.

d. PLACE the following in AUTO:



e. PERFORM Checklist 3, Locked Valve Restoration.

f. IF makeup was added to the RWST, PERFORM the following:

NOTE

RWST recirc time requirements are determined by Chemistry per CSP-ZZ-07620, Borated Water

Sources (BAST-A, BAST-B and RWST).

1. IF makeup was added to the RWST, NOTIFY Chemistry to sample within

24 hours of the recirc time being met.

2. PLACE the RWST in a recirculation lineup in accordance with

OTN-EC-00001, Fuel Pool Cooling And Cleanup System.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.7. BTRS Operation - Boration

5.7.1. IF the BTRS bed to be placed into service is a new resin bed, ENSURE it has been

flushed per OTS-BG-00006, Flushing BTRS Demineralizers.

CAUTION

Normal alignment for Chiller Unit is service water inlet and outlet headers and chill water side in

dry lay-up condition with various vents and drains open.

5.7.2. IF the Chiller Unit is in dry lay-up condition, PERFORM the following:

• Section 5.15 (to fill and vent the Chiller Unit service water headers)

• Section 5.17 (to fill and vent the Chiller Unit chilled water side)

5.7.3. ENSURE Service Water is available to the Chiller unit.

5.7.4. Using the Plant Curve Book as needed, DETERMINE the required increase in

boron concentration.

NOTE

It is preferred to use Step 5.7.6 for startup of BTRS, since it allows startup of the Chiller and

establishes the desired Chilled Water Loop temperatures prior to aligning the BTRS valves and

sending CVCS flow through the BTRS piping.

5.7.5. PLACE the BTRS in the Borate Lineup in accordance with either Step 5.7.6 or

5.7.7 below.

5.7.6. IF desired, STARTUP the Chilled Water Loop and PREPARE BTRS for operation

in the Borate Mode by performing the following:

a. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure

BG HCV-387 is fully open).

b. ENSURE either of the following CVCS Chiller Pump control switches is in

RUN, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

c. WHEN BG FI-375, CVCS CHILLER SYS FLOW, has stabilized, PLACE

BG HIS-21, CVCS CHILLER UNIT, in AUTO.

OTN-BG-00002

Rev. 041


Step 5.7.6 Cont'd

d. WHEN BG TI-379, CVCS CHILLER SURGE TANK TEMP is between 40°F and

50°F:

1. Refer To Night Orders or the current BTRS Performance Data/Status Log

(Attachment 1) for guidance and DETERMINE which Demineralizer(s) to

use for the Borate Mode.

2. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE

the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

e. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to

zero.

5.7.7. IF Step 5.7.6 was NOT performed, PREPARE the BTRS for operation in the

Borate Mode as follows:

a. ENSURE demand on BG HC-387, BTRS DEMIN BYPASS CTRL, is set at 100%

(to ensure BG HCV-387 is fully open).

b. ENSURE one of the following CVCS Chiller Pump control switches is in

AUTO, and the other is in STOP:



c. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in AUTO.

d. Refer To Night Orders or the current BTRS Performance Data/Status Log

(Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use

for the Borate Mode.

e. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the

inlet valves for the other Demineralizers:





f. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to

zero.

OTN-BG-00002

Rev. 041


5.7.8. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN.

5.7.9. PLACE BG HIS-27, BTRS CTRL, in BORATE.

NOTE

Attachment 5, BG HIS-27 BTRS Controls, shows the input into the lights for the DILUTE, OFF

and BORATE switch positions. [Ref: 6.2.9]

5.7.10. CHECK the white BORATE light on BG HIS-27 ON.

5.7.11. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245.

5.7.12. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in AUTO, and ENSURE it is set

below 7.0.

5.7.13. IF the boron concentration of the BTRS bed or piping is known (or suspected) to be

different from the current RCS boron concentration:

a. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT.

b. WHEN the desired trend in boron concentration is observed by BCMS or

chemistry sample, PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in

VCT.

5.7.14. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 135°F and 145°F:

a. WITHIN 5 minutes before the start of boration, RECORD the data required in

Block 1 of Attachment 1.

b. ADJUST BG HC-387, BTRS DEMIN BYPASS CTRL, to obtain the desired

boration rate.

c. RECORD the data required in Block 1A of Attachment 1.

5.7.15. WHEN the desired boron concentration has been established:

a. RECORD the data required in Block 2 of Attachment 1 (required within 5

minutes before completion of the boration).

b. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure



OTN-BG-00002

Rev. 041


NOTE

Attachment 1 should be retained at the Reactor Operator’s desk until the data sheet is filled. When

filled, the original copy should be forwarded to the BG System Engineer and a copy retained for

reference for the next boration/dilution.

The normal alignment of BTRS is with flow through BGHCV0387.

5.7.16. IF the BTRS mode is to be changed from Borate to Dilute, Go To Section 5.9.

5.7.17. IF normal alignment with flow through BGHCV0387 is desired, N/A Step 5.7.18.

5.7.18. WHEN no additional boration is desired, as determined by the SM/CRS:

a. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245.

b. PLACE BG HIS-27, BTRS CTRL, in OFF.

c. ADJUST the RMCS as required by plant conditions.

d. IF desired to place the Chiller Unit in a Dry Lay-up condition, PERFORM the

following:

• Section 5.16 (to drain the Chiller Unit service water headers)

• Section 5.18 (to drain the Chiller Unit chilled water side)

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.8. BTRS Operation - Dilution



CAUTION

Normal alignment for Chiller Unit is service water inlet and outlet headers and chill water side in

dry lay-up condition with various vents and drains open.

5.8.2. IF the Chiller Unit is in dry lay-up condition, PERFORM the following:

• Section 5.15 (to fill and vent the Chiller Unit service water headers)

• Section 5.17 (to fill and vent the Chiller Unit chilled water side)

5.8.3. ENSURE Service Water is available to the Chiller Unit.

5.8.4. Using the Plant Curve Book as needed, DETERMINE the required increase in

boron concentration.

NOTE

If the BTRS Demineralizers have been flushed or have had new resin installed, the initial RCS

dilution rate will be more rapid than normally observed.

Step 5.8.6 is the preferred method to use for startup of BTRS, since it allows startup of the Chiller

and establishes desired Chilled Water Loop temperatures prior to aligning the BTRS valves and

sending CVCS flow through the BTRS piping.

5.8.5. PLACE the BTRS in the Dilute lineup in accordance with either Step 5.8.6 or 5.8.7

below.

5.8.6. IF desired, STARTUP the Chilled Water Loop and PREPARE the BTRS for

operation in the Dilute Mode by performing the following:



b. ENSURE either of the following CVCS Chiller Pump control switches is in

RUN, and the other pump control switch is in STOP:



OTN-BG-00002

Rev. 041


Step 5.8.6 Cont'd

c. WHEN BG FI-375, CVCS CHILLER SYS FLOW, has stabilized, PLACE

BG HIS-21, CVCS CHILLER UNIT, in RUN.

d. WHEN BG TI-379, CVCS CHILLER SURGE TANK TEMP is between 40°F and

50°F:

1. Refer To Night Orders or the current BTRS Performance Data/Status Log

(Attachment 1) for guidance and DETERMINE which Demineralizer(s) to

use for the Borate Mode.

2. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE

the inlet valves for the other Demineralizers:





5.8.7. IF Step 5.8.6 was NOT performed, PREPARE the BTRS for operation in the Dilute

Mode as follows:



b. ENSURE ONE of the following CVCS Chiller Pump control switches is in

AUTO, and the other pump control switch is in STOP:



c. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in AUTO.

d. Refer To Night Orders or the current BTRS Performance Data/Status Log

(Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use

for the Dilute Mode.

e. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the

inlet valves for the other Demineralizers:






OTN-BG-00002

Rev. 041


5.8.9. PLACE BG HIS-27, BTRS CTRL, in DILUTE.

NOTE

Attachment 5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF, and

BORATE switch positions. [Ref: 6.2.9]

5.8.10. CHECK the white DILUTE light on BG HIS-27 ON.


5.8.12. IF the boron concentration of the BTRS bed or piping is known (or suspected) to be

different from the current RCS boron concentration:

a. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT.

b. WHEN the desired trend in boron concentration is observed by BCMS or

chemistry sample, PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in

VCT.


a. WITHIN 5 minutes before the start of dilution, RECORD the data required in



dilution rate.




minutes before completion of the dilution).




OTN-BG-00002

Rev. 041


NOTE





5.8.15. IF the BTRS Mode is to be changed from Dilute to Borate, Go To Section 5.10.


5.8.17. WHEN no additional dilution is desired, as determined by the SM/CRS:





following:



-END OF SECTION-

OTN-BG-00002

Rev. 041


5.9. BTRS Operation - Borate To Dilute Mode Change

NOTE

This section should be performed whenever BTRS is used for load follow operations due to

Maintenance or ambient conditions.

5.9.1. ENSURE the BTRS is aligned per Section 5.7



5.9.3. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure


5.9.4. ENSURE either of the following CVCS Chiller Pump control switches is in RUN,

and the other pump control switch is in STOP:



5.9.5. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in RUN.



5.9.8. CHECK the white DILUTE light on BG HIS-27 ON.

NOTE

Attachment 5, BG HIS-27 BTRS Controls, shows the input into the lights for the DILUTE, OFF



5.9.10. Refer To Night Orders or the current BTRS Performance Data/Status Log

(Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for

the Dilute Mode.

OTN-BG-00002

Rev. 041


5.9.11. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet

valves for the other Demineralizers:






a. WITHIN 5 minutes before beginning the dilution, RECORD the data required

in Block 1 of Attachment 1.


dilution rate.




minutes before completion of the dilution).




NOTE






OTN-BG-00002

Rev. 041







following:



-END OF SECTION-

OTN-BG-00002

Rev. 041


5.10. BTRS Operation - Dilute To Borate Mode Change

NOTE

This section should be performed whenever BTRS is used for load-follow operations due to

Maintenance or ambient conditions.

5.10.1. ENSURE the BTRS is aligned per Section 5.8.





5.10.4. ENSURE ONE of the following CVCS Chiller Pump control switches is in RUN,

and the other pump control switch is in STOP:



5.10.5. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in RUN.


5.10.7. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero.


NOTE

Attachment #5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF






the Borate Mode.

OTN-BG-00002

Rev. 041








5.10.13. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in AUTO, and ENSURE it is set

below 7.0.


a. WITHIN 5 minutes before beginning a boration, RECORD the data required in



boration rate.




minutes before completion of the boration).




NOTE






OTN-BG-00002

Rev. 041







following:



-END OF SECTION-

OTN-BG-00002

Rev. 041


5.11. Flushing BTRS Demineralizers Using RCS Letdown Flow

NOTE

When it has been determined that the BTRS Demineralizers are saturated and continued dilution of

the RCS is desired, the Demineralizer may be flushed to the Boron Recycle System.

5.11.1. CONTACT Chemistry to ensure that BTRS effluent samples will be taken on

intervals of 30 to 60 minutes during Demineralizer flushing.



CAUTION

VCT level should be monitored closely during BTRS flushing.



NOTE

Attachment #5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF



NOTE

It is desirable to flush one Demineralizer Bed at a time. The other Demineralizers should be isolated

by closing their respective inlet Isolation valve.



the Borate Mode.

OTN-BG-00002

Rev. 041










a. SET BG HC-387, BTRS DEMIN BYPASS CTRL, at 0% (to close BGHCV387 and

divert total letdown flow to the BTRS Demineralizers).

b. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT.

c. INFORM Chemistry that BTRS flushing has begun.

d. RECORD the data required on Attachment 2, BTRS Flushing Data, now and at

30 to 60 minute intervals during the flush.

e. WHEN the Demineralizers appear to be flushed as indicated by the data

recorded on Attachment 2, (with reference to General Note 3.3.2), FORWARD

the completed copy of Attachment #2 to the BG System Engineer.

f. WHEN the Demineralizers have been rinsed, as indicated by the Boron

Concentration Measurement System or effluent samples, PERFORM the

following:

1. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to fully

open BGHCV0387).

2. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245.

3. PLACE BG HIS-27, BTRS CTRL, in OFF.

4. ADJUST the RMCS as required by plant conditions.

5. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in AUTO.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.12. Flushing BTRS Demineralizers Using Reactor Makeup Water

NOTE

When it has been determined that the BTRS Demineralizers are saturated, the BTRS System may be

isolated to allow flushing boron from the Demineralizers to the Boron Recycle System.

Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to flush the

Demineralizers, no boration via the BA Blending Tee should be performed during Steps 5.12.18

through 5.12.27.

5.12.1. INFORM Chemistry that BTRS effluent samples will be taken on intervals of 30 to

60 minutes during Demineralizer flushing.

5.12.2. ENSURE BG HIS-8245, CVCS DEMIN OUTLET VLV, is in OPEN.

5.12.3. ENSURE BG HIS-27, BTRS CTRL, is in OFF.


5.12.5. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL.


• BG HIS-110A, BA TO BA BLENDING TEE





5.12.8. ENSURE the following are in STOP:



• BG HIS-21, CVCS CHILLER UNIT

OTN-BG-00002

Rev. 041


5.12.9. CLOSE the applicable valves for the Demineralizers which will NOT be flushed

and OPEN the applicable valve for the Demineralizer to be flushed.





NOTE

The following step prevents BGHV7054 from opening when BG HIS-0027 is placed in BORATE.

CAUTION

Performance of Steps 5.12.10 and 5.12.12 isolates BTRS from the CVCS. No RCS

boration/dilution is possible due to BTRS operation in this lineup.

5.12.10. Using BG HIS-7054, BTRS INLET VLV, CLOSE BGHV7054.

NOTE

If performance of this procedure is terminated or postponed prior to restoration of the following

valves to the LOCKED CLOSED position, they should be entered in the Locked Component

Deviation List:

• BGV0192, M/U TO BA BLENDING TEES HDR ISO

• BGV0034, RX M/U WTR TO BTRS ISO

5.12.11. UNLOCK and OPEN BGV0192, M/U TO BA BLENDING TEES HDR ISO (in VCT

Valve Room).

5.12.12. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (SE corner Rm 1105).

5.12.13. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 7.0 (corresponds to 140°F).

5.12.14. NOTIFY Chemistry to ensure BTRS effluent samples are taken during

performance of Steps 5.12.24 through 5.12.27.c to determine when no additional

flushing is required.

OTN-BG-00002

Rev. 041


5.12.15. NOTIFY Radwaste that BTRS Demineralizer Flushing is starting.

5.12.16. UNLOCK and OPEN BGV0034, RX M/U WTR TO BTRS ISO (Rm 1105).

5.12.17. OPEN BGV0060, BTRS TO RECYC EVAP FEED DEMIN IN HDR ISO.

NOTE

Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to flush the

Demineralizers, no boration via the BA Blending Tee should be performed during Steps 5.12.18

through 5.12.27.

5.12.18. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero.


NOTE

The Borate white light will not energize due to BGHV7054 being CLOSED. Valve position per

Attachment 5 is required.

5.12.20. ENSURE position of all valves listed on Attachment 5 (except BGHV7054) in the

Borate position.

5.12.21. ADJUST BG FK-111, REACTOR M/U WTR FLOW CTRL, to 5.0 (corresponds to

80 gpm).

CAUTION

Step 5.12.22 implements P&L Step 3.1.7.

5.12.22. RESET BG FY-111B, COMBINED M/U & BA COUNTER, and SET it to the maximum

amount of water that Radwaste can receive.

NOTE

The following step will commence M/U flow.


OTN-BG-00002

Rev. 041


5.12.24. Slowly RAISE the output of BG TK-381A, LTDN DIVERT FLOW CTRL, to raise the

letdown reheat heat exchanger outlet temperature at BG TI-381, BTRS DEMIN INLET

TEMP, to between 135°F and 145°F.

5.12.25. WHEN the temperature at BG TI-381 is at the desired value and stable:

a. PLACE BG TK-381A in AUTO.

b. RECORD the BG FY-111B totalizer reading on Attachment #3.

c. Using BG HC-387, BTRS DEMIN BYPASS CTRL, slowly CLOSE BGHCV0387

to commence flushing the Demineralizer.

d. INFORM Chemistry that BTRS flushing has begun and to obtain the data

required on Attachment 3 at 30 to 60 minute intervals during the flush.

NOTE

In this lineup, automatic high temperature protection is not available for the Demineralizers.

If BG TI-381 temperature exceeds 156°F, letdown may divert to the VCT.

e. MONITOR BG TI-381, BTRS DEMIN INLET TEMP, periodically to ensure the

reactor makeup flushing water temperature does not exceed 145°F.

5.12.26. WHEN the Demineralizers appear to be flushed as indicated by the data recorded

on Attachment 3 and referencing step 3.3, FORWARD the completed copy of

Attachment 3 to the BG System Engineer.

5.12.27. WHEN the Demineralizer flushing is complete PERFORM the following:

a. PLACE BG TK-381A in MANUAL.

NOTE

The following step will stop LTDN Flow to the LTDN Reheat Hx.

b. Using BG TK-381A, slowly CLOSE BG TCV-381B while monitoring

temperature drop on BG TI-381.

c. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to fully

open BG HCV-387).

d. PLACE BG HIS-27, BTRS CTRL, in OFF.

OTN-BG-00002

Rev. 041


Step 5.12.27 Cont'd

e. CLOSE BGV0060, BTRS TO RECYC EVAP FEED DEMIN IN HDR ISO.

f. PLACE BG HS-26, RCS M/U CTRL, in STOP.

g. ADJUST BG FK-111, REACTOR M/U WTR FLOW CTRL, to 7.5 (corresponds to

120 gpm).

h. CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO.

i. OPEN BG7053, LTDN DIVERT FLOW CTRL.

j. CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO.

k. RESTORE the BTRS Demineralizers to the normal lineup by ensuring the

following valves are open, or in the desired lineup for BTRS operation:





l. PLACE BG HIS-7054, BTRS INLET VLV, in AUTO.

m. ADJUST the RMCS as required by plant conditions.

n. PLACE the following valves handswitches in AUTO:




o. PERFORM Checklist 3, Locked Valve Restoration.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.13. Pressure Testing BTRS With Reactor Makeup Water

NOTE

This section of the procedure should follow major maintenance on BTRS System.

Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to pressurize the

system, no boration via the BA Blending Tee should be performed during performance of this

section.


5.13.2. PLACE BG HIS-27, BTRS CTRL, in OFF.









5.13.7. ENSURE the following are in STOP:



• BG HIS-21, CVCS CHILLER UNIT

5.13.8. IF desired, CLOSE the BTRS Demineralizer Isolation valves using the following:





OTN-BG-00002

Rev. 041


CAUTION

Performance of Steps 5.13.9 and 5.13.11isolates BTRS from the CVCS.


NOTE


valves to their LOCKED CLOSED position, they should be entered in the Locked Component

Deviation List:

• BGV0192, M/U TO BA BLENDING TEES HDR ISO

• BGV0034, RX M/U WTR TO BTRS ISO

5.13.10. UNLOCK and OPEN BGV0192, M/U TO BA BLENDING TEES HDR ISO (in VCT

Valve Room).

5.13.11. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (SE corner Rm 1105).

NOTE

Step 5.13.12 will prevent letdown flow through the letdown reheat heat exchanger. This MUST be

done to prevent boiling of the pressure test fluid.

5.13.12. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 0.

5.13.13. UNLOCK and OPEN BGV0034, RX M/U WTR TO BTRS ISO, (Rm 1105).


5.13.15. IF the BG HIS-27 Borate light is not ON, ENSURE position of valves by other

indications in accordance with Attachment 5.

5.13.16. Using BG HIS-111A, REACTOR M/U WTR TO BA BLENDING TEE, manually OPEN

BGFCV0111A and ESTABLISH flow to the BTRS System.

5.13.17. MONITOR BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to determine the

amount of Reactor Makeup Water added to the system.

OTN-BG-00002

Rev. 041


5.13.18. WHEN an inspection has been made of the BTRS Valve Room (Aux. Bldg, 1974,

Room 1105), PERFORM the following:

a. Using BG HIS-111A, REACTOR M/U WTR TO BA BLENDING TEE, CLOSE

BGFCV0111A.


c. PLACE the following in AUTO:

• BG HIS-7054, BTRS INLET VLV




d. ADJUST the RMCS as required by plant conditions.

e. ENSURE the following valves are OPEN or in the desired lineup for BTRS

Operation:





f. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 6.5 and ENSURE it is in

AUTO.

g. CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO, (Rm 1105).

h. OPEN BG7053, LTDN DIVERT FLOW CTRL, (Rm 1105).

i. CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO

(Rm 1318).

j. PERFORM Checklist 2, Placing the Chiller Unit Service Water Headers in Dry

Lay-up.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.14. Immediate Boration To Support Plant Shutdown

5.14.1. ENSURE the water plan or Chemistry is referenced to determine the source of

boric acid for boration of the RCS.

5.14.2. ENSURE one of the Charging Pumps is in operation in accordance with

OTN-BG-00001, Chemical And Volume Control System.

5.14.3. IF it is desired to borate from the Boric Acid Storage Tanks, PERFORM the

following:

a. START at least one Boric Acid Transfer Pump using the following

handswitch:

• BG HIS-5A, BA TRANSFER PUMP A

• BG HIS-6A, BA TRANSFER PUMP B

b. Using BG HIS-8104, EMERG BORATE TO CHG PUMP SUCT, OPEN BGHV8104.

c. ENSURE greater than 30 gpm flow is indicated on BG FI-183A, EMERG

BORATE FLOW.

d. WHEN boration from the Boric Acid Storage Tanks is complete:

1. STOP any operating Boric Acid Transfer Pump using:

• BG HIS-5A, BA TRANSFER PUMP A

• BG HIS-6A, BA TRANSFER PUMP B

2. Using BG HIS-8104, EMERG BORATE TO CHG PUMP SUCT, CLOSE

BGHV8104.

3. EQUALIZE charging pump suction header and RCS boron concentrations

as follows: [Ref: 6.2.11]

a) ALLOW the running charging pump to continue flowing to the RCS

for at least 30 minutes.

b) IF plant conditions allow, FLUSH the suction header of the non

running charging pumps per OTN-BG-00001, Chemical And Volume

Control System.

c) IF a charging pump can NOT be flushed at this time, ENSURE a

Caution Tag is placed on the affected charging pump hand switch

warning of high boron concentrations and the need to flush the

charging pump suction header per OTN-BG-00001, Chemical And

Volume Control System.

OTN-BG-00002

Rev. 041


5.14.4. IF it is desired to borate from the RWST, PERFORM the following:

a. IF CCP A is in operation, using BN HIS-112D, CCP A SUCT FROM RWST,

OPEN BNLCV112D.

b. IF CCP B is in operation, using BN HIS-112E, CCP B SUCT FROM RWST,

OPEN BNLCV112E.

c. ENSURE the applicable valve indicates OPEN using:

• BN HIS-112D, CCP A SUCT FROM RWST

• BN HIS-112E, CCP B SUCT FROM RWST

d. Using BG HIS-112B, VCT OUTLET VLV, CLOSE BGLCV112B.

e. Using BG HIS-112C, VCT OUTLET VLV, CLOSE BGLCV112C.

f. WHEN Boration from the RWST is complete:

1. Using BG HIS-112C, VCT OUTLET VLV, OPEN BGLCV112C.

2. Using BG HIS-112B, VCT OUTLET VLV, OPEN BGLCV112B.

3. ENSURE both VCT outlet valves are OPEN using:

• BG HIS-112C, VCT OUTLET VLV

• BG HIS-112B, VCT OUTLET VLV

4. CLOSE both RWST suction valves using:

• BN HIS-112D, CCP A SUCT FROM RWST

• BN HIS-112E, CCP B SUCT FROM RWST

5. EQUALIZE charging suction header and RCS boron concentrations as

follows: [Ref: 6.2.11]

a) ALLOW the running charging pump to continue flowing to the RCS

for at least 30 minutes.

b) IF plant conditions allow, FLUSH the suction header of the non

running charging pumps per OTN-BG-00001, Chemical And Volume

Control System.

c) IF a charging pump can NOT be flushed at this time, ENSURE a

Caution Tag is placed on the affected charging pump hand switch

warning of high boron concentrations and the need to flush the

charging pump suction header per OTN-BG-00001, Chemical And


-END OF SECTION-

OTN-BG-00002

Rev. 041


5.15. Restoration Of The SW Side Of CVCS Chiller Unit From Dry Layup Condition

5.15.1. CLOSE the following vents and drains on Checklist 1, Removing the Chiller Unit

Service Water Headers from Dry Lay-up.

• EAV0083, CVCS CHL SERV WTR IN VENT

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN

• EAV0084, CVCS CHL SERV WTR OUT VENT

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN

• BGV0304, CVCS CHL UNIT SERV WTR SPLY TEST CONN

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN

• BGV0305, CVCS CHL UNIT SERV WTR RTN TEST CONN

NOTE

With the Chiller Unit shutdown, BGFC5010, CVCS CHILLER UNIT COND SERV WTR OUT FLOW CTRL

could be opened or closed. Filling and venting the service water inlet and outlet headers will be

performed as though this valve were CLOSED.

5.15.2. UNLOCK and SLOWLY OPEN the EAV0168, CVCS CHL SERV WTR IN ISO and

ALLOW the inlet header to fill up to BGFC5010, CVCS CHILLER UNIT COND SERV

WTR OUT FLOW CTRL.

5.15.3. VENT the header from EAV0083, CVCS CHL SERV WTR IN VENT.

5.15.4. UNLOCK and SLOWLY OPEN EAV0170, CVCS CHL SERV WTR OUT ISO and

ALLOW the inlet header to fill up to BGFC5010, CVCS CHILLER UNIT COND SERV

WTR OUT FLOW CTRL.

OTN-BG-00002

Rev. 041


NOTE


valves to the LOCKED CLOSED position they should be entered in the Locked Component

Deviation List:

• EAV0168, CVCS CHL SERV WTR IN ISO

• EAV0170, CVCS CHL SERV WTR OUT ISO

5.15.5. VENT the header from the following valves:

• EAV0084, CVCS CHL SERV WTR OUT VENT

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT

5.15.6. COMPLETE Checklist 1, Removing the Chiller Unit Service Water Headers from

Dry Lay-up.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.16. Placing The SW Side Of CVCS Chiller Unit In Dry Layup Condition

5.16.1. CLOSE and LOCK the following valves, (CB-1974 Rm-3101 N Center Of Room,

7' Up):

• EAV0168, CVCS CHL SERV WTR IN ISO

• EAV0170, CVCS CHL SERV WTR OUT ISO

5.16.2. PLACE drain rigs on the following drain valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102, NW of

Chl Unit next to N wall)

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102, East of

Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974, Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974, Rm-3101)

5.16.3. OPEN the following drain valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102 NW of


• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102 East of

Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974 Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974 Rm-3101)

5.16.4. OPEN the following vent valves:

• EAV0083, CVCS CHL SERV WTR IN VENT, (AB-1974 Rm-1102 West Of BTRS

Chiller 15ft Up Over Walk Zone)

• EAV0084, CVCS CHL SERV WTR OUT VENT, (AB-1974 Rm 1102 West Of

BTRS Chiller 15 Ft Up Over Walk Zone)

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT, (AB-1974 Rm-1102 NW Of

Chl Unit Near Wall 9' High)

OTN-BG-00002

Rev. 041


5.16.5. WHEN draining is complete, REMOVE the drain rigs from the following valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102 NW of


• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102 East of

Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974 Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974 Rm-3101)

5.16.6. COMPLETE Checklist 2, Placing the Chiller Unit Service Water Headers in Dry

Lay-up.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.17. Restoration Of Chilled Water Side Of CVCS Chiller Unit From Dry Layup Condition

5.17.1. REMOVE tags.

5.17.2. REMOVE the FME screens and CLOSE the following valves:

• BGV0409, CVCS CHL SRG TK OUT DRN

• BGV0414, CVCS LTDN CHL HX CHILLED WTR IN HDR DRN

• BGV0417, CVCS LTDN CHL HX CHILLED WTR OUT DRN

5.17.3. REMOVE the FME screens and INSTALL venting hoses for the following vents:

• BGV0419, CVCS CHL SRG TK IN VENT

• BGV0410, CVCS CHL UNIT IN VENT

5.17.4. Slowly THROTTLE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, to begin filling

the system.

NOTE

When CVCS Chiller Surge Tank level instrumentation has been vented and placed in service by

I&C, vent line monitoring may be replaced by monitoring computer points BGL0380H, BTRS CHL

SRG TK, and BGL0380L, BTRS CHL SRG TK.

5.17.5. Continuously MONITOR the CVCS Chiller Surge Tank vent line 368-HBD-2” and

CLOSE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, if any water is observed.

5.17.6. Continuously MONITOR BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND.,

and maintain level between 55 to 75 % using BGV0070, DI WTR TO CVCS CHL SRG

TK ISO.

5.17.7. REQUEST I&C vent BGLT0380, CVCS CHL SURGE TK LVL XMTR.

5.17.8. MONITOR BGV0410, CVCS CHL UNIT IN VENT, and CLOSE the valve when a

solid stream of water has been observed for at least two (2) minutes.

5.17.9. INSTALL venting hoses for the following vents:

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT

OTN-BG-00002

Rev. 041


5.17.10. WHEN surge tank level has been established, VENT at the following locations

until a solid stream of water has been observed for at least two (2) minutes:



5.17.11. ENSURE the following valves are closed:





5.17.12. RAISE surge tank level on BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL

IND., to 80 to 82 % using BGV0070, DI WTR TO CVCS CHL SRG TK ISO.

5.17.13. ENSURE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, is closed.

5.17.14. CLOSE the following breakers:

• PG19NBF5, FDR BKR TO PBG01A CVCS CHILLER PMP A

• PG20NCF4, FDR BKR TO PBG01B CVCS CHILLER PMP B

• PG2003, FDR BKR TO SBG02 CVCS CHILLER UNIT

5.17.15. Using one of the following, START a chiller pump and run for up to

one (1) minute:



5.17.16. WHEN the chiller pump has been stopped, VENT at the following locations until a

solid stream of water has been observed for at least two (2) minutes:




5.17.17. ENSURE surge tank level on BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL

IND., is 80 to 82 % using BGV0070, DI WTR TO CVCS CHL SRG TK ISO.

OTN-BG-00002

Rev. 041


5.17.18. Using one of the following, START the chiller pump NOT started in Step 5.17.15

and run for up to one (1) minute:



5.17.19. WHEN the second chiller pump has been stopped, VENT at the following locations

until a solid stream of water has been observed for at least two (2) minutes:




5.17.20. WHEN BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND., is

between 55 to 82 %, CLOSE BGV0070, DI WTR TO CVCS CHL SRG TK ISO.

5.17.21. REMOVE venting hoses and INSTALL caps on the following vents:





5.17.22. PERFORM Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill

Water Side.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.18. Placing The Chilled Water Side Of CVCS Chiller Unit In Dry Layup Condition

[Ref: 6.2.10]

NOTE

Chilled Water should NOT be drained to the DRW sumps. Drains should be routed to the SLW

sump in the north east corner of the Aux Building. This will require approximately 300 feet of

hose.

5.18.1. CONTACT Chemistry to determine if any special requirements are needed for dry

layup.

5.18.2. ENSURE the following breakers are OPEN:

• PG19NBF5, FDR BKR TO PBG01A CVCS CHILLER PMP A

• PG20NCF4, FDR BKR TO PBG01B CVCS CHILLER PMP B

• PG2003, FDR BKR TO SBG02 CVCS CHILLER UNIT

5.18.3. ENSURE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, is closed.

5.18.4. ROUTE a drain hose "header" from the Chiller Pumps to the SLW sump.

5.18.5. CONNECT drain hoses from the following drains to the "drain header":


• BGV0500, CVCS CHL PMP A DISCH DRN

• BGV0501, CVCS CHL PMP B DISCH DRN



5.18.6. OPEN BGV0409, CVCS CHL SRG TK OUT DRN.

5.18.7. AFTER the CVCS Chiller Surge Tank has mostly drained, OPEN the following

drains:





OTN-BG-00002

Rev. 041


5.18.8. Slowly OPEN the following vents to ensure the system is drained:



5.18.9. Using a container, DRAIN the residual water from the impellers of the Chiller

Pumps by opening the following:

• BGV0302, CVCS CHL PMP A DRN

• BGV0303, CVCS CHL PMP B DRN

5.18.10. CONNECT an air line for Service Air to vent BGV0410, CVCS CHL UNIT IN VENT.

5.18.11. ENSURE the drain hose going into the SLW Sump is secured to NOT move.

5.18.12. Slowly THROTTLE the air line to no more than two (2) turns open.

5.18.13. ALLOW air to blow through the piping for approximately one (1) hour.

5.18.14. CLOSE the air line and REMOVE the air hose.

5.18.15. ENSURE the following are closed:

• BGV0302, CVCS CHL PMP A DRN

• BGV0303, CVCS CHL PMP B DRN

5.18.16. CLOSE the following valves and REMOVE their drain hoses:



5.18.17. REMOVE the drain hoses and INSTALL FME screens for the following valves:




5.18.18. INSTALL FME screens for the following vents:



5.18.19. HANG Tags

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.19. Removing BTRS From Service For Maintenance

5.19.1. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is open.

5.19.2. ENSURE BG HIS-27, BTRS CTRL, is in OFF.


5.19.4. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (AB-1975 Rm 1105,

SE corner).

5.19.5. CLOSE BG7001, CVCS MOD HX TO LTDN CHL HX HDR UPSTRM ISO (AB-1975

Rm-1105, NW Corner Of Rm Against West Wall)

5.19.6. VENT and DRAIN as required to perform maintenance.

-END OF SECTION-

OTN-BG-00002

Rev. 041


5.20. Filling And Venting BTRS Following Maintenance Using Letdown Or Rx M/U Water

NOTE

It takes approximately 400 to 500 gallons to fill the BTRS system. If BTRS demin Beds are drained

that would add to the total gallons. (A BTRS Bed is approximately 200 gals if it is filled with

resin.)

5.20.1. IF using letdown, ENSURE VCT level is sufficient to support refilling the portion

of BTRS that was drained.


5.20.3. Using BG HIS-7054, BTRS INLET VLV, PLACE BGHV7054 in CLOSE.

5.20.4. ENSURE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, is CLOSED

(SE corner AB 1974 Rm 1105).

5.20.5. OPEN BG7001, CVCS MOD HX TO LTDN CHL HX HDR UPSTRM ISO (AB-1975

Rm-1105, NW Corner Of Rm Against West Wall).

NOTE

BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO, remains closed during fill and vent to

prevent water hammer of the sample system.

5.20.6. ENSURE BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO, is CLOSED.


NOTE

The white DILUTE light will not be lit due to BGHV7054 being closed. Computer points should

be used to verify valves positions. BGUV7022 will have to be verified locally.

5.20.8. CHECK the white DILUTE light on BG HIS-27 is off.

OTN-BG-00002

Rev. 041


5.20.9. CONFIRM valve positions using the following computer points:

• Using BGZ7002A, CHECK BGUV7002A, CVCS MOD HX TO LTDN CHL HX

HDR CTRL VLV, OPEN.

• Using BGZ7002B, CHECK BGUV7002B, LTDN CHL HX TO LTDN REHEAT HX

HDR CTRL VLV, OPEN.

• Using BGZ7040, CHECK BGUV7040, CVCS LTDN CHL HX TO RX CLNT FLTR

HDR CTRL VLV, CLOSED.

• Using BGZ7041, CHECK BGUV7041, CVCS LTDN CHL HX BYP HDR CTRL

VLV, CLOSED.

• Using BGZ7045, CHECK BGUV7045, CVCS BTRS DEMINS OUT CTRL VLV,

NOT CLOSED.

• Using BGZ7046, CHECK BGUV7046, CVCS BTRS DEMINS IN BYP CTRL VLV,

NOT OPEN.

• Using BGZ7056, CHECK BGUV7056, CVCS BTRS DEMINS HDR CTRL VLV,

OPEN.

• Using BGZ7057, CHECK BGUV7057, CVCS BTRS DEMINS OUT BYP CTRL

VLV, CLOSED.

• Using BGZ7054, CHECK BGHV7054, CVCS MOD HX BTRS IN ISO HV,

CLOSED.

• Using BGZ0381A, CHECK BGTCV0381A, CVCS LTDN DIVERT FLOW TCV A,

NOT OPEN.

• Using BGZ0381B, CHECK BGTCV0381B, LTDN DIVERT BYP TCV B, NOT

CLOSED.

5.20.10. Locally CONFIRM BGUV7022, CVCS MOD HX TO RX CLNT FLTR CTRL VLV,

OPEN.

NOTE

Failing open BGUV7057 provides a flowpath to refill the BTRS Demin inlet header while in the

DILUTE mode.

5.20.11. CLOSE BGUV7057V1, AIR SPLY ISO FOR BG-UV-7057, and BLEED air to fail open

BGUV7057.

OTN-BG-00002

Rev. 041


5.20.12. IF using Letdown to refill the BTRS:

a. Slowly THROTTLE OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT

FLTR, (SE corner AB 1974 Rm 1105), until flow is heard.

b. During the BTRS refill, IF the VCT requires filling, PERFORM the following:

1. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR.

2. Manually FILL the VCT using applicable parts of this procedure.

3. Slowly THROTTLE OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT

FLTR, (SE corner AB 1974 Rm 1105), until flow is heard.

NOTE

Step 5.20.13 can be performed in parallel with Steps 5.20.14 and 5.20.15

to complete the BTRS Fill and Vent.

5.20.13. IF using Rx M/U water to refill the BTRS, MAKEUP to BTRS using Section 5.6,

Manual Mode of RMCS Operation (RWST-RHUT-BTRS).

NOTE

In the following step, venting is only required for the portion of the BTRS that was drained.

Suggested vents to use are the first six in the list.

5.20.14. Thoroughly VENT the system using the appropriate valves below:

• BGV0552, CVCS BTRS DEMINS OUT BGUV7045 UPSTRM VENT

• BGV0295, CVCS BTRS DEMIN E PRI SLUICE WTR RTN DRN

• BGV0499, CVCS BTRS DEMINS BYP VENT

• BGV0383, MB DEMINS TO MOD HX VENT

• BGV0425, CVCS LTDN CHL HX BYP HDR VENT

• BGV0395, BTRS DEMINS OUT HDR BGUV7045 DNSTRM VENT

• BGV0294, CVCS BTRS DEMIN D PRI SLUICE WTR RTN DRN

• BGV0292, CVCS BTRS DEMIN B PRI SLUICE WTR RTN DRN

• BGV0393, CVCS BTRS DEMINS BYP HDR VENT

OTN-BG-00002

Rev. 041


Step 5.20.14 Cont'd

• BGV0386, CVCS MOD HX TO LTDN CHL HX HDR VENT

• BGV0401, CVCS LTDN CHL HX TO RX CLNT FLTR HDR VENT

• BGV0389, LTDN CHL HX TO LTDN REHEAT HX HDR VENT

• BGV0391, CVCS LTDN REHEAT HX OUT TO BTRS DEMINS HDR VENT

• BGV0291, CVCS BTRS DEMIN A PRI SLUICE WTR RTN DRN

• BGV0397, CVCS MOD HX TO RX CLNT FLTR OUT VENT

5.20.15. WHEN venting is complete, ENSURE any of the following that were used for

venting are CLOSED and CAPPED:

• BGV0552, CVCS BTRS DEMINS OUT BGUV7045 UPSTRM VENT

• BGV0295, CVCS BTRS DEMIN E PRI SLUICE WTR RTN DRN

• BGV0499, CVCS BTRS DEMINS BYP VENT

• BGV0383, MB DEMINS TO MOD HX VENT

• BGV0425, CVCS LTDN CHL HX BYP HDR VENT

• BGV0395, BTRS DEMINS OUT HDR BGUV7045 DNSTRM VENT

• BGV0294, CVCS BTRS DEMIN D PRI SLUICE WTR RTN DRN

• BGV0292, CVCS BTRS DEMIN B PRI SLUICE WTR RTN DRN

• BGV0393, CVCS BTRS DEMINS BYP HDR VENT

• BGV0386, CVCS MOD HX TO LTDN CHL HX HDR VENT

• BGV0401, CVCS LTDN CHL HX TO RX CLNT FLTR HDR VENT

• BGV0389, LTDN CHL HX TO LTDN REHEAT HX HDR VENT

• BGV0391, CVCS LTDN REHEAT HX OUT TO BTRS DEMINS HDR VENT

• BGV0291, CVCS BTRS DEMIN A PRI SLUICE WTR RTN DRN

• BGV0397, CVCS MOD HX TO RX CLNT FLTR OUT VENT

NOTE

WHEN opening BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, there maybe a small VCT level

drop due to pressurizing the system.

5.20.16. FULLY OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR.

5.20.17. OPEN BGUV7057V1, AIR SPLY ISO FOR BG-UV-7057, and ENSURE BGUV7057,

CVCS BTRS DEMINS OUT BYP CTRL VLV, is closed.

OTN-BG-00002

Rev. 041


5.20.18. OPEN BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO.

5.20.19. PLACE BG HIS-7054, BTRS INLET VLV, in AUTO.

5.20.20. IF Reactor Makeup Water was used to fill the system, ENSURE a proper flush is

performed.

5.20.21. WHEN desired, PLACE the BTRS system in service using

OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System.

-END OF SECTION-

OTN-BG-00002

Rev. 041


6.0 REFERENCES

6.1. Implementing

6.1.1. CSP-ZZ-07620, Borated Water Sources (BAST-A, BAST-B and RWST)

6.1.2. OTN-EC-00001, Fuel Pool Cooling And Cleanup System

6.1.3. OTN-BG-00001, Chemical And Volume Control System

6.1.4. OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System

6.1.5. OTS-BG-00006, Flushing BTRS Demineralizers

6.1.6. ODP-ZZ-00004, Locked Component Control

6.1.7. Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs – Blended

Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates

6.1.8. Curve Book, Figure 7-3, Reactor Makeup Control System Nomographs – Boron

Addition


Addition Rate


Dilution


Dilution Rate


Dilution and Boron Addition

6.1.13. Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up

6.1.14. Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up

6.1.15. Checklist 3, Locked Valve Restoration

6.1.16. Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side

6.2. Developmental

6.2.1. M-22BG01

6.2.2. M-22BG02

OTN-BG-00002

Rev. 041


6.2.3. M-22BG03

6.2.4. M-22BG04

6.2.5. M-22HE01

6.2.6. M-23BG12

6.2.7. FSAR 16.1.2.2

6.2.8. FSAR 16.1.2.5

6.2.9. CAR 199803251, During Performance Of A Retest On BGTCV0381B, An

Unexpected Leak Occurred

6.2.10. CARS 199901416

6.2.11. CARS 200308549, Reactivity Management Near Miss while starting 'B' CCP

6.2.12. CARS 200606374

6.2.13. CARS 201010145

6.2.14. 8809D57 S041

7.0 RECORDS

7.1. QA Records


Dilution


Dilution Rate


Dilution and Boron Addition

7.1.4. Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up

7.1.5. Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up

7.1.6. Checklist 3, Locked Valve Restoration

7.1.7. Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side

7.2. Commercial Records

7.2.1. Data acquired in Attachment 1, 2 or 3 will be filed in the system files as a

commercial record.

OTN-BG-00002

Rev. 041



Page(s) Section or

Step Number Description

5 Old step 3.1.7 Deleted precaution on RWST recirc time. Recirc time is controlled by

CSP-ZZ-07620.

19 5.6.14.f.1 note Reworded note to state that recirc time requirements are determined by

Chemistry per CSP-ZZ-07620.

61 and

62

6.1.1 and old

steps 6.2.7 and

6.2.8

Added CSP-ZZ-07620 as a reference. Deleted RFR 017192A and

UOTCR 96-152 as references.

OTN-BG-00002

Rev. 041


Attachment 1

BTRS Performance Data/Status Log Sheet 1 of 1

Block 1A – Desired flow established through BTRS Demineralizer

Time flow established

through BTRS Demineralizer

BTRS Demin flow BG FI-385 As desired

Block 2 – Data recorded, in the given order, prior to completion of Dilution/Boration

BTRS Demin Inlet Temp BG TI-381 50 ± 10°F / 140 ± 5°F

BTRS Demin Outlet Temp BG TI-389 (Note 1)

BTRS Outlet Temp BG TI-386 95 ± 5 °F / 95 ± 5°F

Block 2A – Flow secured through BTRS Demineralizers

Time BTRS demin bypassed

Latest RCS CB

Demineralizer in Service Circle letter A D E A D E A D E A D E A D E

REMARKS:

NOTE 1: Optimum performance should exist when the outlet temperature reaches 50 ± 10°F for the Dilute mode, or 140 ± 5 °F for the Borate mode. These conditions will NOT be reached unless continuous flow to the Demineralizer has existed for at least 1 hour. However, as long as the outlet temperature raises for dilution and lowers

for boration, the system is functioning properly.

PARAMETER Instrument Desired Temp Range

Dilute / Borate DATA

DATE

Block 1 – Data recorded, in the given order, prior to Dilution/Boration via BTRS

BTRS Demin Inlet Temp BG TI-381 50 ± 10°F / 140 ± 5°F

BTRS Demin Outlet Temp BG TI-389 (Note 1)

BTRS Outlet Temp BG TI-386 95 ± 5 °F / 95 ± 5°F

OTN-BG-00002

Rev. 041


Attachment 2

RCS Letdown Flow - BTRS Demineralizer Flushing Data Sheet 1 of 1

DATE: ____________________________ Demineralizer being flushed ____________

Performed by: ____________________________________________________________

Time of data acquisition

Effluent boron concentration Elapsed time

Time of data acquisition Effluent boron concentration

Elapsed time

BG FI-132, LTDN HX OUTLET FLOW ______________ gpm

OTN-BG-00002

Rev. 041


Attachment 3

Reactor Makeup Water - BTRS Demineralizer Flushing Data Sheet 1 of 1

DATE: ____________________________ Demineralizer being flushed ____________

Performed by: ____________________________________________________________

Time of data acquisition Effluent boron concentration

Elapsed time

Time of data acquisition

Effluent boron concentration

Elapsed time

Final Totalizer reading: __________________

Initial Totalizer reading: __________________ Total water used: ______________________

OTN-BG-00002

Rev. 041


Attachment 4

Volume Control Tank Level Control System Sheet 1 of 1

LCV 112C/E

OPEN LCV 112E

SHUT LCV 112C

OTN-BG-00002

Rev. 041


Attachment 5

BTRS Controls For BG HIS-27 Indication Sheet 1 of 1

COMPONENT

Equipment status required to energize the

BG HIS-27 white light with the switch in the

indicated position:

BG HIS-27, BTRS CTRL DILUTE OFF BORATE

BGUV7002A, CVCS MOD HX TO LTDN CHL HX

HDR CTRL VLV OPEN CLOSED CLOSED

BGUV7002B, LTDN CHL HX TO LTDN REHEAT

HX HDR CTRL VLV OPEN CLOSED CLOSED

*BGUV7022, CVCS MOD HX TO RX CLNT FLTR

CTRL VLV OPEN CLOSED CLOSED

BGUV7040, CVCS LTDN CHL HX TO RX CLNT

FLTR HDR CTRL VLV CLOSED OPEN OPEN

BGUV7041, CVCS LTDN CHL HX BYP HDR CTRL

VLV CLOSED OPEN OPEN

BGUV7045, CVCS BTRS DEMINS OUT CTRL VLV OPEN OPEN CLOSED

BGUV7046, CVCS BTRS DEMINS IN BYP CTRL

VLV CLOSED CLOSED OPEN

BGUV7056, CVCS BTRS DEMINS HDR CTRL VLV OPEN CLOSED CLOSED

BGUV7057, CVCS BTRS DEMINS OUT BYP CTRL

VLV CLOSED OPEN OPEN

BGHV7054, CVCS MOD HX BTRS IN ISO HV OPEN CLOSED OPEN

BGTCV0381A, CVCS LTDN DIVERT FLOW TCV A CLOSED CLOSED Not Required

BGTCV0381B, LTDN DIVERT BYP TCV B OPEN OPEN Not Required

* Valve position for BGUV7022 does NOT input into the plant computer. Local position verification

is required.

OTN-BG-00002

Rev. 041


Attachment 6

Dilute Mode Of RMCS Operation Sheet 1 of 1

NOTE

This attachment provides direction for frequently performed, nominal 120 gpm dilutions.

1. PLACE BG HS-26, RCS M/U CTRL, in STOP.

2. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL.

3. RESET BG FY-111B, COMBINED M/U & BA FLOW TOTALIZER, to 000.

NOTE




4. ENSURE BG FY-111B is set to deliver the desired amount of makeup water.

5. PLACE BG HS-26, RCS M/U CTRL, in RUN.

6. WHEN the desired amount of water has been added, PLACE BG HS-26, RCS M/U CTRL, in

STOP.

7. IF required, PERFORM the following:

a. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO.

b. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002

Rev. 041


Attachment 7

Alternate Dilute Mode Of RMCS Operation Sheet 1 of 1

NOTE

This attachment provides direction for frequently performed, nominal 120 gpm alternate dilutions.


2. PLACE BG HS-25, RCS M/U CTRL SEL, in ALT DIL.

3. RESET BG FY-111B, COMBINED M/U & BA FLOW TOTALIZER, to 000.

NOTE




4. ENSURE BG FY-111B is set to deliver the desired amount of makeup water.


6. WHEN the desired amount of water has been added, PLACE BG HS-26, RCS M/U CTRL, in

STOP.




OTN-BG-00002

Rev. 041


Attachment 8

Borate Mode Of RMCS Operation Sheet 1 of 1

NOTE

This attachment provides direction for frequently performed, nominal borations.


2. PLACE BG HS-25, RCS M/U CTRL SEL, in BOR.

3. RESET BG FY-110B, BA COUNTER, to 000.

NOTE




4. ENSURE BG FY-110B is set to deliver the desired amount of boron.


6. WHEN the desired amount of borated water has been added, PLACE BG HS-26, RCS M/U

CTRL, in STOP.




CALLAWAY PLANT JOB PERFORMANCE MEASURE

JPM No: RSA-3 KSA NO: GEN2.2.12 Revision: KSA RATING: KSA Rating: 4.1 Job Title: SRO Task Title: Review CCP Surveillance for Operability Validation Time: 20 minutes Learning Objective: T61.003A-6, LP A22, Obj A.2.a, PERFORM the following as they pertain to APA-ZZ-00340, Surveillance Program Administration: DESCRIBE: SM responsibilities regarding the Surveillance Program The performance of this task was evaluated against the standards contained in this JPM and determined to be: [ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY: Evaluators Signature: Date: Task Performer: Location of Performance: Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: __ ____ Time Critical: ___ ___ Student Handouts: Copy of OSP-BG-P005B

Completed copy of Attachment 2, System Performance Data Sheet, from OSP-BG-P005B.

References: OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B” TECHNICAL SPECIFICATIONS 3.5.2

JPM NO: RSA-3 Rev 1

Page 1 of 3

Initial Conditions: C allaway is at 100% Power. The Reactor Operator has just completed the Group B operational readiness of CCP B from OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B”.

Initiating Cues: You are an extra SRO on shift. The Shift Manager (SM) has given you

Attachments 2 of OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B” to review. Inform the SM when your review is complete and include any Actions required that need to be taken. Write down required Actions, if any, on your cue sheet and return to the Examiner.

Task Standard: Upon completion of this JPM, the Operator will have determined that CCP B is

INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours.

START TIME: STOP TIME:

JPM NO: RSA-3 Rev 1 TASK NUMBER - ELEMENT

STANDARD

SCORE

Page 2 of 3

1. Obtain a verified working copy of OSP-BG-P005B

Applicant obtained working copy of OSP-BG-P005B

S U

Comments:

2. Review completed copy of Attachment 2 of OSP-BG-P005B.

Applicant reviewed completed copy of Attachment 2 of OSP-BG-P005B.

S U

Comments:

3. *Identifies the data in step 6.1.27 (Pump Differential Pressure) was calculated incorrectly

Applicant identified that the number for Pump Differential Pressure should be 2396 psid instead of 2416 psid

S U

Comments:

4. *Identifies the data in step 6.1.27 (Pump Differential Pressure) is less than the Tech Spec Limit of 2400 psid

Applicant identified that the Pump Differential Pressure is less than the Tech Spec limit of 2400 psid

S U

Comments:

JPM NO: RSA-3 Rev 1 TASK NUMBER - ELEMENT

STANDARD

SCORE

Page 3 of 3

5. *Informs Shift Manager that that CCP B is INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours in arrordance with T/S LCO 3.5.2

Applicant informed SM that CCP B is INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours. Review APA-ZZ-00340 “Surveillance Program Administration”

S U

Comments:

CUE: If the applicant does not state the T/S ask them:

“What T/S needs to be entered and what actions that need to be taken?”


Record stop time on Page 1

S U

Comments:


Initial Conditions: C allaway is at 100% Power. The Reactor Operator has just completed the Group

B operational readiness of CCP B from OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B”.

Initiating Cues: You are an extra SRO on shift. The Shift Manager (SM) has given you

Attachments 2 of OSP-BG-P005B “Centrifugal Charging Pump B Inservice Test – Group B” to review. Inform the SM when your review is complete and include any Actions required that need to be taken. Write down required Actions, if any, on your cue sheet and return to the Examiner.


OSP-BG-P005B

CENTRIFUGAL CHARGING PUMP B INSERVICE TEST - GROUP B

MINOR Revision 048

OSP-BG-P005B

Rev. 048


TABLE OF CONTENTS

Section Page Number


1.0 PURPOSE ...................................................................................................................................... 3

2.0 SCOPE ........................................................................................................................................... 3

3.0 ACCEPTANCE CRITERIA ......................................................................................................... 4

3.1. Pump Test Data.................................................................................................................... 4

3.2. Check Valve Tests ............................................................................................................... 4


5.0 PREREQUISITES ......................................................................................................................... 6

5.1. Initial Conditions ................................................................................................................. 6

5.2. Test Equipment .................................................................................................................... 7


6.1. CCP B Inservice Test Pump Run.......................................................................................... 8

6.2. BGV0605 Open Test And BGV0091 Closure Test ............................................................. 14

6.3. BGV0589 Check Valve Open Test ..................................................................................... 15

7.0 RESTORATION ......................................................................................................................... 18

8.0 REFERENCES ............................................................................................................................ 19

8.1. Implementing ..................................................................................................................... 19

8.2. Developmental ................................................................................................................... 20

9.0 RECORDS ................................................................................................................................... 20


ATTACHMENT 1, CCP PBG05B Test Flow Path .................................................................................. 22

ATTACHMENT 2, System Performance Data Sheet ............................................................................... 23

ATTACHMENT 3, CCP B Suction Pressure Calculations ....................................................................... 24

ATTACHMENT 4, Maintenance Rule Functionality Brief ...................................................................... 25

Checklist 1, CCP PBG05B Restoration

OSP-BG-P005B

Rev. 048



1.0 PURPOSE

1.1. This procedure demonstrates the Group B operational readiness of Centrifugal Charging

Pump B (CCP B) per APA-ZZ-00356, Pump and Valve Inservice Testing Program.

1.2. This procedure performs the open testing of BGV0095, BGV0589, BGV0605 and the close

testing of BGV0091.

1.3. This procedure obtains pump spin up time for use in ITP-ZZ-00004, Response Time Testing

Program, on a 36 month cycle.

2.0 SCOPE

2.1. The Group B operational readiness of CCP B is proved by development of a differential

pressure between 2400 and 2899 psid on a frequency described in APA-ZZ-00356, Pump and

Valve Inservice Testing Program.

2.2. The following check valve tests are performed:

• BGV0095, CCP B DISCH TO SEAL WTR HX CHECK - open safety test

• BGV0589, CCP B DISCH TO SEAL WTR INJ FLTRS HDR CHECK - open safety test

• BGV0605, CCP B DISCH BGFCV0121 UPSTEAM CHECK - open non-safety test

• BGV0091,CCP A DISCH TO SEAL WTR HX CHECK - closed non-safety test

2.3. Pump spin up time is the elapsed time from initiation of the start signal to obtaining a

discharge pressure greater than 2405 psig. This response time test is normally performed

once per 36 months.

2.4. The Centrifugal Charging Pump B room cooler is checked and documented for an automatic

start when the Centrifugal Charging Pump B is started.

OSP-BG-P005B

Rev. 048


3.0 ACCEPTANCE CRITERIA

3.1. Pump Test Data

3.1.1. Differential pressure is within the Normal Range as specified on Attachment 2,

System Performance Data Sheet, per T/S SR 3.5.2.4, T/S SR 3.5.3.1, FSAR

16.1.2.3.1, and FSAR 16.1.2.4.1.

3.1.2. The Centrifugal Charging Pump B Room Cooler automatically starts when the

Centrifugal Charging Pump B is started within the requirements of

ODP-ZZ-00002, Equipment Status Control.

3.1.3. If pump spin up time is measured, the pump obtains the required discharge

pressure from initiation of start signal as specified on Attachment 2. This partially

satisfies T/S SR 3.3.2 1.C#10, T/S SR 3.3.2 1.D#10, T/S SR 3.3.2 1.E#10, FSAR

16.3.2.1.1, and FSAR 16.3-2, Table items 2a, 3a and 4a.

3.2. Check Valve Tests

3.2.1. BGV0095, CCP B DISCH TO SEAL WTR HX CHECK, is demonstrated open by pump

differential pressure being in the Normal Range as specified on Attachment 2.

3.2.2. BGHV8111, B CCP DISCH MINIFLOW TO SEAL WTR HX ISO, pipe temperature is in

the Normal Range as specified on Attachment 2.

3.2.3. BGV0605, CCP B DISCH BGFCV0121 UPSTREAM CHECK, is demonstrated open by

initiating flow through the normal charging header as specified on Attachment 2.

3.2.4. BGV0589, CCP B DISCH TO SEAL WTR INJ FLTRS HDR CHECK, is demonstrated

open by passing the required seal injection flow as specified on Attachment 2.

3.2.5. BGV0091, CCP A DISCH TO SEAL WTR HX CHECK, is demonstrated closed by

meeting back leakage criteria specified on Attachment 2.

OSP-BG-P005B

Rev. 048



4.1. If performing in MODE 1, 2, or 3, T/S LCO 3.5.2 and FSAR 16.1.2.4 are applicable.

4.2. If performing in MODE 4, 5 or 6, FSAR 16.1.2.3 is applicable.

4.3. If performing in MODE 4, T/S LCO 3.5.3 is applicable.

4.4. A pretest brief should be held to familiarize the appropriate personnel with the required

testing this procedure dictates and with the Maintenance Rule Functionality requirements in

Attachment 4.

4.5. IF the data falls in the Required Action Range:

4.5.1. The SM/CRS declares the component INOPERABLE and takes the required

actions in accordance with Technical Specifications and APA-ZZ-00340,

Surveillance Program Administration.

4.5.2. The SM/CRS checks the validity of the data (i.e., by immediately rerunning the

test, evaluating test instruments and conditions, conferring with test personnel, or

other methods).

4.6. When measured pump test parameters that fall outside the Normal Range have resulted from

an identified systematic error such as improper system lineup or inaccurate instrumentation,

the test shall be rerun after correcting the error.

4.7. If testing is terminated or temporarily postponed at some point prior to the locked valve

being returned to its normal locked position, the altered valve shall be logged in the Locked

Component Deviation List per ODP-ZZ-00004, Locked Component Control.

4.8. PBG05B, CCP B, should NOT be run at less than 60 gpm.

4.9. PBG05B, CCP B, should NOT be run at less than 130 gpm for more than 30 minutes.

4.10. RCP Seal injection flow must be maintained between 8 and 13 gpm for each RCP.

4.11. Prior to starting a CCP, the associated Auxiliary Lube Oil Pump should be started per

OTN-BG-00001, Chemical And Volume Control System, to ensure proper CCP sleeve

bearing lubrication is present before pump loading occurs. [Ref: 8.2.7]

4.12. After a CCP is secured, the associated Auxiliary Lube Oil Pump should be stopped per

OTN-BG-00001, Chemical And Volume Control System. [Ref: 8.2.7]

4.13. If testing is required during Cold Shutdown, the reactor vessel should be open to atmosphere.

OSP-BG-P005B

Rev. 048


4.14. If testing is required with the vessel head installed during Cold Shutdown, the discharge of

the charging pump must NOT be opened unless transferring charging pumps for normal

charging alignment. FSAR 5.2.2.10.4 [Ref: 8.1.13]

4.15. If CCP B has been made incapable of injection per T/S LCO 3.4.12, then CCP B should be

aligned per OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection

Into RCS.

4.16. If charging is required, then CCP A or the NCP should be in service supplying normal

Charging/Seal Injection per OTN-BG-00001, Chemical And Volume Control System.

4.17. An FPIP (based on Master FPIP MFP-00826) should be implemented any time a CCP is run.

This requires a Fire Watch to implement compensatory measures due to impact on capability

of post fire safe shutdown.

4.18. After pump testing conditions are stable, the pump must be run for at least two (2) minutes

prior to taking pump performance data.

5.0 PREREQUISITES

5.1. Initial Conditions

5.1.1. ENSURE SM/CRS has reviewed Technical Specifications for any LCO Action

Statements that may be entered should any component tested be declared

INOPERABLE.

5.1.2. ENSURE SM/CRS has reviewed the applicable activities and plant conditions

which must exist prior to procedure performance.

5.1.3. ENSURE a job brief has been held and the actions in Attachment 4 were discussed

with the Maintenance Rule Dedicated Operator.

5.1.4. ENSURE CCP B suction is lined up to the Volume Control Tank or the RWST.

5.1.5. ENSURE the method for communications between Control Room and local

operator in pump room has been established.

5.1.6. WHEN plant is in MODE 4 with any RCS cold leg temperature less than or equal

to 275°F, MODE 5 or MODE 6 with the reactor vessel head on, ENSURE Cold

Over Pressure Mitigation System (COMS) is in effect per T/S LCO 3.4.12.

5.1.7. INFORM RP CCP B will be placed into operation.

OSP-BG-P005B

Rev. 048


NOTE

This pump is run on recirc during performance of this procedure, the recirc returns to the suction of

all the charging pumps so if boron concentration in this pump differs from RCS then core reactivity

will be changed. [Ref: 8.2.1 and 8.2.2]

5.1.8. ENSURE the difference in boron concentrations between the RCS and CCP B is

managed per OTN-BG-00001, Chemical And Volume Control System.

5.1.9. ENSURE a flowmeter, supplied by Engineering, is installed on piping upstream of

BGV0091, CCP A DISCH TO SEAL WTR HX CHECK, to record back leakage in

Section 6.2.

5.1.10. ENSURE a FPIP for PBG05B, CCP B, is in effect.

5.2. Test Equipment

5.2.1. ENSURE the following is available:

• Pyrometer

• Stopwatch, required only if pump spin up time is to be measured

• 25 feet of 3/8" tubing to be used for venting

• Poly vent bottle

5.2.2. ENSURE all M&TE is within their calibration due date and RECORD ID number

and calibration due date on Attachment 2.

-END OF SECTION-

OSP-BG-P005B

Rev. 048



NOTE

When pump spin up time measurement is required, a separate PM0903516 specifying measurement

of pump spin up time will be issued, normally once per 36 months.

Steps pertaining to measurement of pump spin up time may be marked N/A at all other times.

6.1. CCP B Inservice Test Pump Run

CAUTION

If COMS is in effect, only one CCP is allowed to be capable of injection to the RCS.

6.1.1. IF COMS is in effect, ENSURE CCP B is aligned in accordance with the

applicable section of OSP-BG-00002, Verify One Centrifugal Charging Pump

Incapable Of Injection Into RCS.

6.1.2. ENSURE Train B of CCW is in service per OTN-EG-00001, Component Cooling

Water System.

6.1.3. RECORD tank to be used on Attachment 2:

• TBG05, CVCS VOL CTRL TK

• TBN01, REFUELING WATER STORAGE TANK

OSP-BG-P005B

Rev. 048


6.1.4. RECORD initial level for tank being used from applicable indicator listed below

on Attachment 2.

a. TBG05, CVCS VOL CTRL TK

• BG LI-185, VCT LVL

• BG LI-112, VCT LEV

b. TBN01, REFUELING WATER STORAGE TANK

• BN LI-930, RWST PROT A LEV IND

• BN LI-931, RWST PROT B LEV IND

• BN LI-932, RWST PROT A LEV IND

• BN LI-933, RWST PROT B LEV IND

6.1.5. IF using the VCT, RECORD pressure indicated on BG PI-115, VCT PRESS, from

TBG05, CVCS VOL CTRL TK, on Attachment 2.

NOTE

The Auxiliary Lube Oil Pump should be allowed to run for at least five (5) minutes prior to starting

associated CCP.

6.1.6. PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, in AUTO to START PBG03B.

6.1.7. CHECK BG HIS-2AX, CCP B AUX L-0 PUMP, RUN light is on.

6.1.8. Using the appropriate handswitch, ENSURE valves listed below are in their

designated position:

• BG HIS-8111, CCP B RECIRC VLV, OPEN

• BG HIS-8357B, CCP B TO RCP SEALS, CLOSED

• EM HIS-8803B, BORON INJ HDR CVCS INLET VLV, CLOSED

6.1.9. Using one of the following, CHECK SGL12B, AUX BLD CCP B RM CLR, status:

• Computer point GLQ0026, CCP RM CLR 12B FAN

• GLHS0192, START/STOP PUSHBUTTON FOR SGL12B

6.1.10. IF SGL12B is running, using GLHS0192, START/STOP PUSHBUTTON FOR SGL12B,

STOP SGL12B, AUX BLD CCP B RM CLR.

OSP-BG-P005B

Rev. 048


6.1.11. IF COMS is in effect, Go To Step 6.1.13.

6.1.12. IF CCP A is supplying charging, PERFORM the following:

a. STATION a Maintenance Rule Dedicated Operator in communication with

the Control Room to OPEN BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO,

to restore system to functional should a valid signal occur.

b. ENSURE BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO, is unlocked and

closed. [Ref: 8.1.13]

6.1.13. IF NCP is supplying normal charging, PLACE BG FK-121, CCP DISCH FLOW

CTRL, in MANUAL and CLOSE BGFCV0121, CVCS CCP A&B DISCH TO REGEN

HX FCV.

CAUTION

Pipe temperature just upstream of BGHV8111, B CCP DISCH MINIFLOW TO SEAL WTR HX ISO,

should be continuously monitored for the first five (5) minutes of pump operation. If pipe remains

cool after 1 to 2 minutes, it is an indication of no recirculation flow and the pump should be shut

off immediately to prevent damage to pump.

6.1.14. Using pyrometer, MEASURE pipe temperature just upstream of BGHV8111, B

CCP DISCH MINIFLOW TO SEAL WTR HX ISO, and RECORD on Attachment 2.

NOTE

Fire Watch is required when CCP is running.

6.1.15. STATION Step 5.1.10 FPIP Fire Watch.

OSP-BG-P005B

Rev. 048


NOTE

Steps 6.1.16 and 6.1.17 may be performed concurrently.

The Control Room Operator should count down (i.e. 3, 2, 1, mark) to the pump start initiation for

the local operator to begin timing.

CAUTION

Starting the CCP could affect core reactivity due to the recirc flow path going back to the suction

of all the pumps.

6.1.16. IF pump spin up time is to be measured using PM0903516, MEASURE the

elapsed time from pump start initiation to greater than or equal to 2405 psig

indicated on BGPI0119, CVCS CCP B DISCH PRESS IND.

6.1.17. PERFORM one of the following to start the pump:

a. IF OSP-SA-0017B, Train B SIS-CSAS Slave Relay Test, (PM0903412) is

being performed concurrently, START CCP B per the instructions in that

procedure.

b. Using BG HIS-2A, CCP B, START CCP B.

6.1.18. IF performed, RECORD pump spin-up time on PM0903516 and Attachment 2.

6.1.19. PERFORM the following:

• IF SGL12B, AUX BLD CCP B RM CLR, is running CIRCLE Yes on

Attachment 2.

• IF SGL12B, AUX BLD CCP B RM CLR, is NOT running, CIRCLE No on

Attachment 2 and NOTIFY the SM/CRS to evaluate using ODP-ZZ-00002,

Equipment Status Control.

6.1.20. ENSURE BG HIS-2AX, CCP B AUX L-0 PUMP, RUN light is off and the STOP

light is on after a reasonable time following start of the CCP. [Ref: 8.2.7]

6.1.21. IF the Aux Lube Oil Pmp remained in service, NOTIFY system engineer.

6.1.22. RECORD BGPI0020, CCP MTR 5B FLTR DISCH L/O PRESS IND, on Attachment 2.

6.1.23. CONTINUE with data collection steps while pipe temperature monitoring is

recorded in the next step.

OSP-BG-P005B

Rev. 048


NOTE

Normally, the pipe temperature should rise to between 100 and 130°F and stabilize. If CCW

temperature is below usual temperature due to cold weather, the pipe temperature may be as much

as five (5) degrees below this normal range and is acceptable. [Ref: 8.2.6]

CAUTION

If pipe remains cool, it is an indication of no recirculation flow and the pump should be stopped

immediately. If pipe gets over 160°F, it is an indication of not enough recirculation flow, the pump

should be stopped and the recirculation flow path investigated.

6.1.24. At approximately five (5) minute intervals for the first 15 minutes of pump

operation, MEASURE pipe temperature just upstream of BGHV8111, CCP B

DISCH MINIFLOW ISO VLV, and RECORD on Attachment 2.

NOTE

Pressure indication may be subject to rapid fluctuations. If this occurs, BGV0093, CCP B SUCT

BGPI0188 ROOT, should be slowly closed until readings stabilize prior to recording pressure.

6.1.25. OBTAIN suction pressure from BGPI0188, CCP PMP B SUCTION PRESS IND, and

RECORD on Attachment 2.

6.1.26. OBTAIN discharge pressure from BGPI0119, CVCS CCP B DISCH PRESS IND, and

RECORD on Attachment 2.

6.1.27. CALCULATE the pump differential pressure by subtracting suction pressure from

the discharge pressure and RECORD on Attachment 2.

6.1.28. IF COMS is in effect, PERFORM the following:

• Using BG HIS-2A, CCP B, STOP CCP B.

• RELEASE the Step 5.1.10 FPIP Fire Watch.

OSP-BG-P005B

Rev. 048


6.1.29. IF CCP A is supplying normal charging, PERFORM the following:

a. PLACE BG FK-121, CCP DISCH FLOW CTRL, in MANUAL.

b. CONTROL charging flow.

c. OPEN and LOCK BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO.

d. RELEASE the Maintenance Rule Dedicated Operator.

6.1.30. IF Section 6.2 and 6.3 will NOT be performed, PERFORM the following:

a. Using BG HIS-2A, CCP B, STOP CCP B.

b. PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, to the STOP position.

c. IF appropriate, TERMINATE the FPIP of Step 5.1.10.

d. Go To Section 7.0 RESTORATION.

-END OF SECTION-

OSP-BG-P005B

Rev. 048


6.2. BGV0605 Open Test And BGV0091 Closure Test

6.2.1. IF COMS is in effect, ENSURE the appropriate section of OSP-BG-00002, Verify

One Centrifugal Charging Pump Incapable Of Injection Into RCS, has been

completed to swap charging pump capable of injection to the RCS PRIOR to

continuation of this procedure.

6.2.2. INITIATE shifting charging supply from pump currently supplying normal

charging to charging supply from CCP B per OTN-BG-00001, Chemical And


6.2.3. WHEN the shift to CCP B is complete, RECORD flow through BGV0605, CCP B

DISCH BGFCV0121 UPSTEAM CHECK, as shown on BG FI-121A, CHG HDR FLOW,

on Attachment 2.

6.2.4. RECORD the back leakage through BGV0091, CCP A DISCH TO SEAL WTR HX

CHECK, as shown on the flow meter upstream of BGV0091, on Attachment 2.

6.2.5. IF NOT performing Section 6.3, RESTORE charging supply alignment as directed

by the SM/CRS per OTN-BG-00001, Chemical And Volume Control System.

-END OF SECTION-

OSP-BG-P005B

Rev. 048


6.3. BGV0589 Check Valve Open Test

6.3.1. ENSURE CCP B is supplying normal charging/seal injection per OTN-BG-00001,

Chemical And Volume Control System.

CAUTION

• IF BGV0100 is allowed to remain closed for more than two (2) minutes, unless Step 6.3.3.a is

performed, the reduced charging flow may cause a decrease in pressurizer level that can reduce

RCS pressure to less than the LCO 3.4.1.a DNB limit.

• Energizing Pressurizer Heaters will cause an outsurge from the Pressurizer that may result in a

reactivity change.

6.3.2. IF a VT2 inspection of BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO, will be

performed while it is closed, ENERGIZE a BU Heater group per OTN-BB-00005,

Pressurizer and Pressurizer Pressure Control.

OSP-BG-P005B

Rev. 048


NOTE

When closing BGV0100, the greatest decrease in RCP seal flow will occur near the end of valve

travel.

While closing BGV0100, if higher flow letdown orifice is in service and BG HC-182 is throttled

closed to maintain seal flow greater than 32 gpm, Pressurizer level may be observed to lower with

BGFCV0121 full open.

While closing BGV0100 and opening BG HIS-8357B, it will be necessary to monitor and maintain

the following parameters using BG HC-182 and BG FK-121 to keep Pressurizer and VCT levels

relatively stable:

• Seal flow between 32 and 52 gpm on BG FI-215A or BG FI-215B

• Combined flow on BG FI-121A and BG FI-215A or BG FI-215B maintained greater than 70

gpm to meet CCP minimum flow requirements. When BGV0100 is closed BG FI-121A will

indicate charging flow only, and BG FI-215A or BG FI-215B, will indicate RCP seal flow only.

• Pressurizer level within 5 % of program

• Pressurizer pressure 2225 to 2250 psig

• Letdown Regen HX outlet temperature less than 385 ºF on BG TI-127

6.3.3. PERFORM the following steps to provide RCP seal flow through the alternate seal

injection line:

a. MONITOR and MAINTAIN parameters listed in the above note.

b. Slowly OPEN BG HIS-8357B, CCP B TO RCP SEALS.

c. UNLOCK and CLOSE BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO.

d. WHEN BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO, is fully closed,

RECORD RCP seal flow using BG FI 215A, CHG PUMP TO RCP SEAL FLOW,

or BG FI 215B, CHG PUMP TO RCP SEAL FLOW, on Attachment 2.

e. Slowly OPEN BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO.

f. Slowly CLOSE BG HIS-8357B, CCP B TO RCP SEALS.

g. WHEN Pressurizer level is restored to program, ADJUST BG HC-182, CHG

HDR BACK PRESS CTRL, to attain 32 gpm RCP seal flow or as desired on

BG FI-215A, CHG PUMP TO RCP SEAL FLOW, or BG FI-215B, CHG PUMP TO

RCP SEAL FLOW.

OSP-BG-P005B

Rev. 048


6.3.4. IF energized per Step 6.3.2, DE-ENERGIZE BU Heaters per OTN-BB-00005,

Pressurizer and Pressurizer Pressure Control.

6.3.5. IF ISF-SB-0A33A, SSPS Train B Slave Relay K624, K626, K604, K711, & K743

Test, is to be performed, REQUEST I&C perform the procedure at this time.

6.3.6. ENSURE all pump related test data has been recorded on Attachment 2 AND

REVIEWED by the Reactor Operator.

6.3.7. RESTORE charging/seal injection alignment as directed by the SM/CRS per

OTN-BG-00001, Chemical And Volume Control System.

6.3.8. IF CCP B is secured, ENSURE the following are performed:

• PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, to the STOP position.

[Ref: 8.2.7]

• IF appropriate, TERMINATE the FPIP of Step 5.1.10.

-END OF SECTION-

OSP-BG-P005B

Rev. 048


7.0 RESTORATION

7.1. INITIATE restoration of equipment per Checklist 1, CCP PBG05B Restoration.

7.2. INITIATE performance of independent verification of equipment status per Checklist 1, CCP

PBG05B Restoration.

NOTE

Steps 7.3 through 7.8 may be performed in any order.

7.3. At NG02ADR1, FDR BKR TO SGL12B B CCP RM COOLER, using GLHS0192, START/STOP

PUSHBUTTON FOR SGL12B, STOP SGL12B.

7.4. IF CCW pumps were started, as directed by the CRS/SM, STOP any CCW pumps that were

started to support pump run.

7.5. ENSURE the Actual Value condition is evaluated against the acceptance/functional criteria

and that the SM/CRS is immediately notified if the Actual Value condition is out of

tolerance.

7.6. IF NCP is supplying normal charging, ENSURE BG FK-121, CCP DISCH FLOW CTRL, is set

at 25 % and in AUTO.

7.7. IF both CCPs are secured, ENSURE the CCPs suction is vented per OTN-BG-00001

ADD02, Shifting from one of the CCPs to the NCP.

7.8. UPDATE Status Board for current boron concentration of the CCP.

-END OF SECTION-

OSP-BG-P005B

Rev. 048


8.0 REFERENCES

8.1. Implementing

8.1.1. APA-ZZ-00340, Surveillance Program Administration

8.1.2. APA-ZZ-00356, Pump and Valve Inservice Testing Program

8.1.3. ISF-SB-0A33A, SSPS Train B Slave Relay K624, K626, K604, K711, & K743

Test

8.1.4. ITP-ZZ-00004, Response Time Testing Program

8.1.5. ODP-ZZ-00002, Equipment Status Control

8.1.6. ODP-ZZ-00004, Locked Component Control

8.1.7. OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection

Into RCS

8.1.8. OSP-SA-0017B, Train B SIS-CSAS Slave Relay Test

8.1.9. OTN-BB-00005, Pressurizer and Pressurizer Pressure Control

8.1.10. OTN-BG-00001 ADD02, Shifting from one of the CCPs to the NCP

8.1.11. OTN-BG-00001, Chemical And Volume Control System

8.1.12. OTN-EG-00001, Component Cooling Water System

8.1.13. COMN 1401

8.1.14. FSAR 5.2.2.10.4

8.1.15. FSAR 16.1.2.3

8.1.16. FSAR 16.1.2.3.1

8.1.17. FSAR 16.1.2.4

8.1.18. FSAR 16.1.2.4.1

8.1.19. FSAR 16.3.2.1.1

8.1.20. FSAR 16.3-2, Table items 2a, 3a and 4a

8.1.21. T/S LCO 3.4.12

OSP-BG-P005B

Rev. 048


8.1.22. T/S LCO 3.5.2

8.1.23. T/S LCO 3.5.3

8.1.24. T/S SR 3.3.2 1.C#10

8.1.25. T/S SR 3.3.2 1.D#10

8.1.26. T/S SR 3.3.2 1.E#10

8.1.27. T/S SR 3.5.2.4

8.1.28. T/S SR 3.5.3.1

8.1.29. Checklist 1, CCP PBG05B Restoration

8.2. Developmental

8.2.1. CARS 199901812

8.2.2. CARS 199903408

8.2.3. CARS 199903524

8.2.4. CARS 200306153

8.2.5. CARS 200402614

8.2.6. CARS 200704247

8.2.7. RFR 016691B

8.2.8. PM0901017

8.2.9. PM0901003

8.2.10. PM0903412

8.2.11. PM0903516

9.0 RECORDS

9.1. Attachment 2, System Performance Data Sheet (Filed with the appropriate Work Authorizing

Document.)

9.2. Checklist 1, CCP PBG05B Restoration

OSP-BG-P005B

Rev. 048



Page(s) Section or

Step Number Description

5 4.5 Combined old Steps 4.5, 4.6, and 4.7 to give clear direction should data

fall in the Required Action Range. Per CARS 201206883

6 4.18 Added step about running stable for two minutes before taking pump

performance data. Per CARS 201206883

OSP-BG-P005B

Rev. 048


Attachment 1

CCP PBG05B Test Flow Path Sheet 1 of 1

OSP-BG-P005B

Rev. 048


Attachment 2

System Performance Data Sheet Sheet 1 of 1

Person Performing (Print) Initials/PIN

Date Started:

Date Completed:

Tank TBG05 TBN01

Steps 6.1.14 and 6.1.24

(normal temp range is 100 to 130°F)

Step 6.1.18

Calculated Pump Spin-up Time: ______ (≤ 5 sec)

Time Pipe Temp °F

Step 6.1.3 - Tank to be used (3) T=00 _______ _________ Step 6.1.19 - CCP B Room Cooling Fan started as

Step 6.1.4 - Initial Level T+05 _______ _________ required:YES / NO (circle one)

Step 6.1.5 - Initial Press T+10 _______ _________ Step 6.1.22

T+15 _______ _________ Lube Oil Inlet Pressure: BGPI0020 ______ (≥ 15 psig)

Suction pressure (psig)

(Step 6.1.25)

Discharge pressure (psig)

(Step 6.1.26)

Pump Differential Pressure (psid)

(Step 6.1.27)

Required Action Range (High) > 2899

Actual Value

Normal Range 14.4 to 82.4 2400 to 2899

Required Action Range (Low) < 2400

Tech Spec Limit ≥ 2400

Baseline 44.5 2680 2635.5

Valve Verification Flowrate

Step 6.2.3 BGV0605 BGFI0121A

Step 6.2.4 BGV0091 Flow meter upstream of BGV0091 < 12 gpm

Step 6.3.3.d BGV0589 BGFI0215A or BGFI0215B ≥ 32 gpm

M&TE Data

ID Numbers

Cal Due Dates

OSP-BG-P005B

Rev. 048


Attachment 3

CCP B Suction Pressure Calculations Sheet 1 of 1

Per J-24BG40 and J-07P16, BG PI-188 is at 1976' 7 1/2". Instruction manual M-721-0093 gives Net Positive Suction

Head (NPSH) required equals 16 feet. M-23BG02 gives pump suction nozzle elevation at 1979' 7". Pump can take suction from the RWST or the VCT. The VCT has the limiting suction pressure characteristics. J-U8000 gives the

following setpoints:

VCT Hi Pressure Alarm (BG-PAHL-115) = 65 psig

VCT Lo Pressure Alarm (BG-PAHL-115) = 5 psig VCT Hi Level Alarm (BG-LAHL-149) = 97%

VCT Lo Level Alarm (BG-LAHL-149) = 22%

Westinghouse Precautions, Limitations, and Setpoints document (PLS) gives BG- 8120, VCT relief valve, setpoint at 75 psig. M-23BG04 gives VCT full at 2013' 8 3/8". The PLS also states that BG LT-149 is calibrated to a 75" span

extending from the lower tap to a point 75" above the lower tap. Per J-24BG12, the lower instrument tap is at 2003' 9

1/2". From this, 97% is calculated to be at 2009' 10 1/4" and 22% to be at 2005' 2". 0-150 psig ± 2% FS pressure

gauges give ± 3 psig accuracy. Add or subtract this as appropriate.

Using the above information:

Low Action Range From NPSH required

1979' 7" + 16' - 1976' 7 1/2" = 8.21 psig

-3.0 psig

5.21 psig

<5.2 psig

Low Alert Range From VCT low alarm for pressure and level

2005' 2" - 1976' 7 1/2" = 27' 2 1/2" =11.78 psig + 5 psig = 17.35 psig

-3.0 psig

14.35 psig

5.2 -14.4 psig

High Action Range From maximum VCT level and pressure

2013' 8 3/8" - 1976' 7 1/2' = 35' 8 7/8" = 15.47 psig + 75 psig = 91.00 psig

+ 3.0 psig

94.00 psig >94.00 psig

High Alert Range From VCT high alarm for pressure and level

2009' 10 1/4" - 1976' 7 1/2' = 31' 10 3/4" = 13.8 psig + 65 psig = 79.4 psig

+ 3.0 psig

82.4 psig

82.4 -94.0 psig

Normal Range From Low Alert Range and High Alert Range 14.4-82.4 psi

OSP-BG-P005B

Rev. 048


Attachment 4

Maintenance Rule Functionality Brief Sheet 1 of 1

While Safety Systems are thought of as those systems designed to mitigate design basis accidents, not all

mitigating systems have the same risk importance. Those systems that have a higher risk importance are

monitored for unavailability time, which is when the system is not functional as related to Maintenance Rule

unavailability indicator.

Actions taken to maintain system functionality such as taking credit for actions by the Reactor Operator in

the Control Room or a stationed Maintenance Rule Dedicated Operator do NOT make the system operable.

Crediting these actions only maintains Maintenance Rule Functionality so the system does not accrue

Unavailability hours.

Actions may be credited if they are simple and may be performed in a short time frame. If actions are being

credited, and if required to be relieved or leave the area, the operator involved must perform a turnover of the

listed functionality actions in event of a valid demand of the system or secure from the test and restore

system functionality.

Functionality Actions for OSP-BG-P005B:

Use of a Maintenance Rule Dedicated Operator:

When BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO, is closed, CCP B is NOT functional unless a

Maintenance Rule Dedicated Operator is stationed in the vicinity of BG8483C to restore system to functional

should a valid signal occur.

During restoration, the Maintenance Rule Dedicated Operator is released when BG8483C is opened and

locked open.


JPM No: RSA-4 KSA No: GEN 2.3.4 Revision: July 2013 KSA Rating: 3.7 Job Title: SRO Task Title: Determine Maximum Allowable Stay Time. Validation Time: 12 minutes Learning Objective: T61.01106.C.2, DESCRIBE the management policy regarding radiation exposure as defined in APA-ZZ-01000, Callaway Plant Radiation Protection Program The performance of this task was evaluated against the standards contained in this JPM and determined to be: [ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY: Evaluators Signature: Date: Task Performer: Location of Performance: Control Room Simulator/Lab Plant Classroom X Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ ___ Student Handouts: RWP 300501 “Routine” Survey CA-M-20130702-3 “1111 RHR Pump Room Title: A & Pump Platform”. References: RWP 300501 “Routine” Survey CA-M-20130702-3 “1111 RHR Pump Room Title: A & Pump Platform”.

APA-ZZ-01000 “CALLAWAY ENERGY CENTER RADIATION PROTECTION PROGRAM”


Page 1 of 2

Initial Conditions: A leak has developed in the RHR Pump “A” room cooler that requires isolating

the room cooler. You have been directed to close RHR Pump “A” room cooler isolation valves EFV0037 and EFV0038.

Initiating Cues: Determine maximum allowable stay time before a dosimeter limit is exceeded. Task Standard: Stay time identified as 2.75 hours based upon exceeding maximum dose . START TIME: STOP TIME:



SCORE

Page 2 of 2

1. Reviews RWP and survey maps required for task

Provide the applicant with a copy of RWP 300501 “Routine”, and Survey CA-M-20130702-3 “1111 RHR Pump Room Title: A & Pump Platform”.

S U

Comments:

2. *Identifies the dose limit per the RWP

Applicant identified the dose limit per RWP 300501 “Routine” is 11 mrem

S U

Comments:

3. *Identifies the dose rate near the valves to be operated.

Applicant identified that the dose rate near isolation valves EFV0037 and EFV0038 is 4 mrem/hr

S U

Comments:

4. *Identifies the maximum stay time

Applicant identified the maximum stay time is 2.75 hr or 165 minutes

11 mrem / (4 mrem/hr) = .2.75hr

.73333 hr x (60 min/ hr) = 165 minutes

S U

Comments:



Comments:

∗ Critical Step

Initial Conditions: Initial Conditions: A leak has developed in the RHR Pump “A” room cooler that

requires isolating the room cooler. You have been directed to close RHR Pump “A” room cooler isolation valves EFV0037 and EFV0038.

Initiating Cues: Determine maximum allowable stay time before a dosimeter limit is exceeded.

Operations and Radwaste Routine Activities Including WPA, Technician Rounds, and Shipping Activities. Includes All Activities Previously Assigned to RWP Numbers 200501OSPPROC and 300501OSPPROC.

NO ACCESS TO SATELLITE RCA'S ON THIS RWP.FOR ACCESS TO SATELLITE RCA'S, USE 300501MISCL.

System Component: VARIOUS Job Location: RCA

Status: Active Begin Date: 03/22/2013 00:00 Expire Date:

General RequirementsRP Coverage Type: Intermittent RWP Type: General Dose Projection (mrem): 775

Level 2 Brief Required: No Authorization Required: No Single Use: No

Electronic Dosimeter Alarm Settings: Dose: 11 mrem Rate: 100 mrem/hr

Radiological ConditionsRadiological Condition Comments Radiological Impact Rating

Dose Rates (mrem/hr)Contact : General Area: See SurveysTravel Path :

Contamination (DPM/100cm2)Internal : External : General Area: See Surveys

Radiological conditions vary by Room/Area.Airborne radioactivity is not anticipated. Areas will be posted as required.

Review current survey data and area postings prior to entry. 3

Page 1 of 3

07/29/2013 07:39

Radiation Work Permit300501ROUTINE Rev 04

Special Instructions for WorkersDosimetry: *OSLD and Electronic Dosimeter.

Protective Clothing/Equipment: *Full set of Protective Clothing in Contaminated Areas. *Partial PC's allowed for tours, inspections, and work allowed by RP. ...No climbing, crawling, or kneeling in Partial PCs. *Lab Coat and Gloves in contaminated Fume Hoods, Sinks, Cabinets, and when handling radioactive samples except discharge system samples.

Contact RP Prior to: *Breach, drain, or vent of a contaminated system. (Discuss Noble Gas Release Potential) *Entry into an area not normally surveyed or accessed. *Accessing areas greater than 8 ft above floor / work platform. *Work requiring a change to radiological postings or boundaries. *Evolutions that will/could change radiological conditions. *Handling contaminated hoses or vent rigs. *Opening drums, containers, or other packages of RAM to assess the need for additional Protective Clothing.

Work Practices: *Check Electronic Dosimeter every 15 minutes, or more often as needed, to prevent receiving a Dose Alarm. *Contain or clean up all liquid leakage. *Handle drain covers/strainers as contaminated materials. *Bag or seal contaminated hose ends as soon a practical to prevent contamination spread. *To access satellite RCA's use RWP 300501MISCL.

Limitations: *No entry to Locked High RadiationAreas or High Contamination Areas. *No entry to Airborne Radioactivity Areas except as follows: *Entry to posted Airborne Radioactivity Areas is permitted if: ...Area is posted due to Noble Gas. ...Total DAC (per CA0387) is < 0.3 DAC Total. *Contact RP to determine DAC information. *No Handling items >5000 mRem/hr. *No access to Satellite RCA'S on this RWP. *Use RWP 391120EMERGENCY for access to RCA during emergencies.

Special Instructions for RP TechnicianWith failed fuel, large amounts of noble gas can be released while venting primary systems. ...Discuss compensatory actions such as running hoses to ventilation, slower vent rates, etc. (CAR200706674)

Page 2 of 3

07/29/2013 07:39


Special MemosLevel 1 ALARA brief required (pre-work discussion of RWP requirements with RP): *Shiftly prior to accessing a High Radiation Area.

Access to East RW Yard from RW NE door to perform work requires RP Supervision approval.Follow requirements of HTP-ZZ-01203 Section 6.3.3 when accessing Radwaste Yard via RW Northeast door.

Stop, place work in safe condition and Notify RP if: *Work area dose rates or contamination levels exceed ranges listed in the RWP (or in referenced survey maps), exceed ranges discussed in RCA entry briefs, or dose rates exceed 800 mRem/hour. *Abnormal conditions become evident. *Scope of work changes. *Accumulated Dose Alarm is received. *Unanticipated Dose Rate Alarm or Continuous Dose Rate Alarm is received.

Revision 04: Changed Rate Alarm set point back to 100 mRem/hr.

Page 3 of 3

07/29/2013 07:39


VSDS Standard Map SurveyH210.0001

Survey CA-M-20130702-3 General Information

1111 RHR Pump Room A & Pump PlatformTitle:

Survey Date/Time: 07/02/2013 16:00

Survey Type: Quarterly

Counted By:

Lindstrom, JonathanLead Surveyor:

Work Order/Task #:

Rx % Pwr: 100%

RWP #: 300101ROUTINE PIN: 100390

Approved by: Hurla, Gerald W, 07/03/2013Status: PIN: 2883

Ready for Review by: Lindstrom, Jonathan, 07/02/2013 PIN: 100390

Dose Rate (DR) Object Prefixes/Suffixes

* = Contact+ = 30cm

Gen AreaGen. Area

HS = Hot Spot

Dose Rates with Prefixes: Dose Rates with No Prefixes: Default Prefixes: Default Suffixes:"n" = Neutron"b" = Beta"c" = Corrected

Postings Legend

CA=Contaminated Area RA=Radiation Area

Location Description#

Map Locations

File Name Image Description Location Code Bldg/Area Name

1 1111 AB 1974 V1111 RESIDUAL HEAT REMOVAL PUMP ROOM A AB

2 1111A AB 1974 V1111A RHR PUMP A PLATFORM AB

Instruments Used

# Model Serial # TypeInstrument Instrument Inst

1 RO-2 ION-4108-HP D

2 Model 177 CRM-4150-HP C

Survey #: CA-M-20130702-3 - PDF Generated On: 07/03/2013 15:51 Page 1 of 5

H210.0001VSDS Standard Map Survey

Map: 1 Date/Time: 07/02/2013 16:00Survey #: CA-M-20130702-3RESIDUAL HEAT REMOVAL PUMP ROOM A

DRR changed from 0-70 mRem/hr to 0-30 mRem/hr due to thecurrent dose rates.

Comments:

QuarterlyType:RWP #: 300101ROUTINEReactor Power = 100%

Symbol Legend (for example only)

Unless otherwise noted, dose rates in mrem/hr.

Air Samples & WipesSmears

Summary of Highest Readings(All available values may not be listed)

4) 6000 dpm/100 cm2 b/g Wipe 3) 4000 cpm/Wipe b/g

Status: Approved by: Hurla, Gerald W, 07/03/2013Lead Surveyor: Lindstrom, Jonathan

Location Code: AB 1974 Bldg/Area Name: 1111

Location Description: AB


Image File: V1111


Data Point Details

# NotesType Inst. Value Units Position

Survey #: CA-M-20130702-3Map: 1 - RESIDUAL HEAT REMOVAL PUMP ROOM A

1 DR g N/A 2 mrem/hr

2 DR g N/A 2.0 mrem/hr









11 DR g N/A * 14 mrem/hr

N/A + 10 mrem/hr








1 Smear N/A b/g <1000 dpm/100 cm2


3 Smear N/A b/g 3000 dpm/100 cm2










1 Wipe b/g 300 cpm/Wipe




Text DRR 0-30 mRem/hr

HS 1111-1Note

Text 60/12

Posting RA

CA


Image File: V1111


Map: 2 Date/Time: 07/02/2013 16:00Survey #: CA-M-20130702-3RHR PUMP A PLATFORM

Comments:

QuarterlyType:RWP #: 300101ROUTINEReactor Power = 100%

Symbol Legend (for example only)

Unless otherwise noted, dose rates in mrem/hr.

Air Samples & WipesSmears

Summary of Highest Readings(All available values may not be listed)

3) <1000 dpm/100 cm2 b/g Wipe 1) <100 cpm/Wipe b/g

Status: Approved by: Hurla, Gerald W, 07/03/2013Lead Surveyor: Lindstrom, Jonathan

Location Code: AB 1974 Bldg/Area Name: 1111A

Location Description: AB


Image File: V1111A


Data Point Details

# NotesType Inst. Value Units Position

Survey #: CA-M-20130702-3Map: 2 - RHR PUMP A PLATFORM






1 Wipe b/g <100 cpm/Wipe


Image File: V1111A


JPM No: RSA5 KSA No: GEN 2.4.41 Revision: July 2013 KSA Rating: 4.6 Job Title: SRO Task Title: Knowledge of the emergency action level thresholds and classifications:

Initiate RERP implementation to include event classification and initial offsite notification.

Validation Time: No greater than 30 minutes (Time Critical) Learning Objective: T61.0110, LP-76, Obj C, Identify initial classifications and potential escalations when plant conditions change and Obj D, For a given Emergency Declaration, demonstrate the use of Sentry computer to make the required notifications The performance of this task was evaluated against the standards contained in this JPM and determined to be: [ ] SATISFACTORY [ ] UNSATISFACTORY Reason, if UNSATISFACTORY: Evaluators Signature: Date: Task Performer: Location of Performance: Control Room Simulator/Lab X Plant Classroom Method of Performance: Simulated Performed X Alternate Path: ___ ___ Time Critical: ___ X___ Student Handouts: EIP-ZZ-00102, Emergency Implementing Actions, Rev 48 References: EIP-ZZ-00101, Classification of Emergencies, Rev 47 EIP-ZZ-00101, ADD 1, EAL Classification Matrix, Rev 3 EIP-ZZ-00102, Emergency Implementing Actions, Rev 48


PAGE 1 of 3

Initial Conditions: Given the following plant conditions:

∗ The Plant has been at 100% for 3 days following a Refueling Outage

∗ Annunciator 76D, SFP LEVEL HILO, alarms

∗ EC LI-39A, SFP LEV, is lowering

∗ Annunciator 62D, AREA RAD HIHI, alarms ◦ SD-RE-37, Fuel Pool Bridge Crane Rad, indicates 660 mr/hr and rising ◦ SD-RE-38, Spent Fuel Pool Area Rad, indicates 630 mr/hr and rising ◦ GG-RE-27 and 28, Fuel/Aux BLDG Normal Exhaust and Emergency Exhaust System, have risen to their HI HI setpoint and actuated a Fuel Building Ventilation Isolation Signal (FBVIS). ◦ GT-RE-21B, Unit Vent Air Exh Radiation, indicates radiation level has risen to 6.3 E+7 µCi/sec, and is stable.

∗ Non-essential personnel are evacuated from the Fuel Building Initiating Cue: You have been provided the combined EAL attachments and directed to determine

the Emergency Event Classification, complete the Sentry Notification Form and then perform the notification of off-site agencies within the required time limits.

This JPM is Time Critical.

(THIS IS A DRILL)

Task Standard: Upon completion of this JPM, the operator will have determined the event

classification to be a Site Area Emergency based on EAL RS 1.1, Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid CDE for the actual or projected duration of the release. The operator will then complete the Sentry Notification Form and send it within 15 minutes of the event classification time. Total time shall not exceed 30 minutes but the second 15 minute clock started at the EAL classification time on Attachment 1.

START TIME: STOP TIME:



SCORE

PAGE 2 of 3

1. Obtain a verified working copy of EIP-ZZ-00101, Classification of Emergencies, ADD1 Wall Chart, and combined EAL attachments

Applicant obtained working copies of procedures

S U

Comments:

*2. Using the given conditions and Addendum 1, determine the appropriate emergency classification: Site Area Emergency

Applicant declared a Site Area Emergency, RS 1.1, Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid CDE for the actual or projected duration of the release., within 15 minutes of start

S U

Comments: Time of Declaration (Start of new 15 min clock)

*3. Notify Facility Personnel Announce the Emergency Classification, the Declaration Time and the Cause

EIP-ZZ-00102, ATT 5, EC Flowchart

Applicant notified facility personnel

S U

Comments:

*4. Notify Onsite Personnel Complete Attachment 1 – Sound the Emergency Alarm


Applicant notified onsite personnel

S U

Comments:



SCORE

PAGE 3 of 3

*5. Is Emergency an Alert or Higher?


Applicant determined emergency was an Site Area emergency

S U

Comments:

*6. Have SAS activate callout per KOA-ZZ-00200 using the appropriate message, if not already activated at a lower classification


Applicant had SAS activate callout per KOA-ZZ-00200.

Examiner Cue: SAS has been notified to activate callout

S U

Comments:

*7. Is Emergency a General Emergency


Applicant determined emergency was not a General Emergency

S U

Comments:

*8. Notify offsite agencies by completing and sending the Sentry notification form


Applicant filled out the Sentry notification form and sent it to the offsite agencies within 15 minutes of completing the EAL classification IAW the key

Examiner CUE

If asked:

A release evaluation is in progress

S U

Comments: Time Notification Sent (Completion time of 2nd 15 min clock)



Comments:

∗ Critical Step

(THIS IS A DRILL) Initial Conditions: Given the following plant conditions:

∗ The Plant has been at 100% for 3 days following a Refueling Outage

∗ Annunciator 76D, SFP LEVEL HILO, alarms

∗ EC LI-39A, SFP LEV, is lowering

∗ Annunciator 62D, AREA RAD HIHI, alarms ◦ SD-RE-37, Fuel Pool Bridge Crane Rad, indicates 660 mr/hr and rising ◦ SD-RE-38, Spent Fuel Pool Area Rad, indicates 630 mr/hr and rising ◦ GG-RE-27 and 28, Fuel/Aux BLDG Normal Exhaust and Emergency Exhaust System, have risen to their HI HI setpoint and actuated a Fuel Building Ventilation Isolation Signal (FBVIS). ◦ GT-RE-21B, Unit Vent Air Exh Radiation, indicates radiation level has risen to 6.3 E+7 µCi/sec, and is stable.

∗ Non-essential personnel are evacuated from the Fuel Building Initiating Cue: You have been provided the combined EAL attachments and directed to determine

the Emergency Event Classification, complete the Sentry Notification Form and then perform the notification of off-site agencies within the required time limits.

This JPM is Time Critical.

(THIS IS A DRILL)

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