Rev 0 to HNP-I/INST-1045, 'Steam Generator Narrow Range ... · Carolina Power 4 Light Company...

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CAROLINA POWER & LIGHT COMPANY

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REASON FOR CHANGE:

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List of-Effective PagesCalculation No. HNP-I/INST-1045

Page No. iRev. 0

PAGE REV PAGE REV PAGE3.ii123456789

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ATTACHMENTSA1A2A3A4

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Table W ContentsCalculation No. HNP-I/INST-1045

Page No. iiRev. 0

1. 0 OBJECTIVE

PacaPeo

2.0 LOOP FUNCTIONAL DESCRIPTION ~ 1

3.0 REFERENCES

4.0 INPUTS AND ASSUMPTIONS

5.0 DETERMINATION OF UNCERTAINTIES

6.0 CALCULATION OF UNCERTAINTIES

7-0 DISCUSSION OF RESULTS

8.0 FIGURES

~ 7

9

10

22

26

'IHIP\ *

z+ ',C ~

Computed by: DatesJohn P. Boska 6/1/94

Checked by: DatesChris Geor eson 6/1/94TAR/PZD No.

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CALCULATION SHEET

Calculation IDcHNP-I/INST-1045

Pg. 1 Rev. 0

Files

Pro)ect Titles Reactor Trip Setpoint Calculation

Calculation Titles Steam Generator Narrow Range I.evel:Low, Low-Low, and High-High

Status c Prelim. Q Final QX Void

1 0 OBJEC~~1.1 The ob)ective of this calculation is to establish the design basis for

the steam generator (SG) narrow range (NR) level setpoints found in theTechnical Specifications. These setpoints are found by taking thesafety analysis limit (usually from the FSAR) and applying an amount inthe conservative direction to account for the instrument channelinaccuracies (the total loop uncertainty) and then allowing for someadditional margin. This calculation is being prepared to comply withCPQL commitments to Reg. Guide 1.105 as outlined in FSAR Section 1.8.In addition, this calculation has been prepared to be consistent withthe methodology outlined in ISA S.67-04.

2 ' LOOP FUNCTIONAL DESCRIPTION

2 ~ 1 Instrumentation is provided to indicate the narrow range level of thesteam generators. The level transmitters are differential pressuretransmitters, which measure the pressure difference between an externalinsulated reference leg. and the column of water in the downcomer region.The reference leg is not sealed and is kept full of water by acondensate pot on the upper tap. The SG Low and Low-Low level tripsprotect the reactor from loss of heat sink. The SG High-High level tripprotects the turbine and the steam lines from water impact damage.

3 ~ 0 ~RE

3 ~ 1 SHMPP Drawings

3 ~ 1.1 CAR-2166»8-401 Sh.993 "Steam Generator Znstrumentation-CWD" ~

F 1.2 CAR-2166-8-401 Sh.994 "Steam Generator Znstrumentation-CWD".

3 ~ 1 ~ 3

3.1.4

F 1 5

3 ' '

CAR-2166-B-431 Sh.L-18 "Level Instrument Typical ImpulsePiping Hook-Up To Local Instrument Rack".

CAR-2166-8-432 "Znstrument List"CAR-2166-G-450 "Containment Building E1.236'nstrumentArrangement".

CAR-2166M-451 "Containment Building E1.236'nstrumentArrangement".

3 ~ 1.7

3 ~ 1 ~ 8

3 ~ i+9

CAR-2166-S-LFW0473 "Steam Generator Level Loop Diagram".



Computed bye DatesJohn P. Boska 6/1/94

IChecked bye Dates'Chris Georgeson 6/1/94TAR/PID Noi

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Calculation ID:HNP-I /INST-1045

Pg. 2 Rev. 0

Pile:

Pro)ect Title: Reactor Trip Setpoint Calculation

'alculation Title: Steam Generator Narrow Range LevelsLow, Low-Low, and High-High

i Status: Prelim. Final X Void

3.1+10

3.1 ll3 ~ 1 ~ 12

3 '.133 ' ~ 14

3+ 1 ~ 15

3.1 ~ 16

3.1 17

3 ~ 1 ~ 18

3 ~ 1 ~ 19

CAR-2166-S«LFW0476 "Steam Generator Level Loop Diagram".









CAR-2166-S-2500 Section 90.1 "EQDP Instrument Loop AccuracyCalculations".

3 '.20

3+1.21

3 '+223+ 1+23

3+1.24

3 ~ 1.25

3.1 ~ 26

3 ' 27

3 ~ 1 ~ 28

3. 1+29

3 '.303 1 ~ 31

3 '.323.1.33

Emdracs

Emdracs

1364-46575

1364-46575

Sh.9 "Steam Generator Loop L-475 - IWD".

Sh.10 "Steam Generator Loop L-485 - IWD".

Emdracs 1364-46575 Sh.ll "Steam Generator Loop L-495 — IWD".

Emdracs 1364-46576 Sh.9 "Steam Generator Loop L-476 — IWD".


Emdracs 1364-46576 Sh.ll "Steam Generator Loop L-496 - IWD".

Emdracs 1364-46577 Sh.25 "Steam Generator Loop L-473 - IWD".



CAR-2166-S-2500 Section 8.18, 8.19 "Barton 764, Tobar32DP1". Environmental Qualification Data Packages

CAR-2165-S-0544, "SFD-Feedwater System".



Emdracs 1364-46574 Sh.ll "Steam Generator Loop L-494 - IWD".

Computed by: DatesJohn P. Boska 6/1/94

!Checked by: Dates1 Chris Georgeson 6/1/94TAR/PID No

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Calculation ID s

HNP I/INST-1045

Pg. 3 Rev. 0

Files


,Calculation Titles steam Generator Narrow Range LevelsLow, Low-Low, and High-High

I

Statues Prelim. Final X Void

3 ~ 1 ~ 34

3 1.35

Emdracs 1364-96736, "Model D4 Steam Generator, Thermal andHydraulic Design Report, Revision 2, 12/1/93"

Emdracs 1364-53067, Rev 1, Westinghouse Setpoint Methodologyfor Protection Systems, Shearon Harris (Revision 1), July1985"

3 '.363 ' ~ 37

3 ~ 1.38

3 ' ~ 39

3 ' '03+1+41

3 ~ 1 ~ 42

3+1 ~ 43

F 1 44

3 145

3 ' ~ 46

3 ~ 1+47

IS/1-FW-286 "Isometric for LT-01-FW-474-IW".

ZS/1-FW-287 "Isometric for LT-01-FW-475".

S/1-FW-288 "Isometric for LT-01-FW-476".

ZS/1-FW-290 "Isometric for LT-Ol-FW-484-IW".

ZS/1-FW-291 "Isometric for LT-01-FW-485" ~

ZS/1-FW-292 "Isometric for LT-Ol-FW-486".

IS/1-FW-294,'Isometric for LT-01-FW-494-IW"~

ZS/1-FW»295 "Isometric for LT-Ol-FW-495".

IS/1-FW-296 "Isometric for LT-01-FW-496".

ZS/1-FW-412 "Isometric for LT-Ol-FW-473".

IS/1-FW-414 "Isometric for LT-01-FW-483".

ZS/1-FW-416 "Isometric for LT-01-FW-493".

3.2 SHNPP Updated FSAR

3+2 ~ 1

3 ~ 2 02

3 ~ 2 ~ 3

3.2.4

Section 6.2.2.2.1.2.2 c) "Lowest. Containment Temperature".

section 9 ~ 4 0 "Air Conditioning, Heating, cooling, andgVentilation System" .

Figure 3.11B-1 "Containment Building E1.221'El.236'nvironmentalParameters During Normal & Post-Accident

Environments".

Figure 3.11B-20 "Containment Building El.221'El-236'ntegratedRadiation Doses To Equip. During Normal & Post-

Accident Environments".

3 ~ 2 ~ 5

3.2 ~ 6

3 ~ 2 ~ 7

Figure 3.11.4-3 "DBA Temperature profile Inside containment(MSLB)".

Table 15.0.6-1, Trip Points and Time Delays to Trip Assumedin Accident Analysis

Section 15, Accident Analysis

< 1

''AJa

Computed bys DatesJohn P. Boska 6/1/94

Checked bys DatesChris Geor eson 6/1/94TAR/PID No.

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CALCULATION SHEET

Calculation IDsHNP-I/INST-1045

Pg. 4 Rev. 0

File s

Project Titles Reactor Trip Setpoint Calculation

Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High

Statuss Prelim. Final X Void@

3.3 SHNPP System Descriptions3 ~ 3 ~ 1 SD-126.2 "Steam Generators, Steam Generator Water Level

Control System".

3 ' ' SD-103 "Reactor Protection"3.4 CP6L Design Guides

3 ~ 4+i

3 ~ Q ~ 2

DG-VIII.50 "Instrument Setpoints" .

Design Basis Document 300, nstrument Set Points

3.5 Vendor Literature3.5.1

3 ~ 5 2

3 ~ 5 ~ 3

3 ~ 5 ~ 4

3 ~ 5 ~ 5

3 ' '

VM-ONY " TT Barton Technical Manual".

VMMSF "Westinghouse Analog Controls".

VM-MWV "Indicators and Instruments".

VM-PYC "NSSS Process Instrumentation and Control System".

Westinghouse WCAP-8687 Supp.2-813 Rev.2 "EquipmentQualification Test Report 'Process Protection System".

VM-BFL "Tobar Technical Manual".

3.6 SHNPP Procedures and Scaling Docssaents

3.6 ' MST-Z0034 "Steam Generator A Narrow Range Level Loop L-473Calibration" .

3 ~ 6 ~ 2 MST-Z0023 "Steam Generator A Narrow Range Level Loop L-474Calibration".

3 ~ 6o3 MST-Z0024 "Steam Generator A Narrow Range Level Loop L-475Calibration".

3o6 ~ 4 MST-I0025 "Steam Generator A Narrow Range Level Loop L-476Calibration" .

3 ~ 6 ~ 5 MST-I0035 "Steam Generator B Narrow Range Level Loop L-483Calibration" .

3.6.6 MST-Z0026 "Steam Generator B Narrow Range Level Loop L-484Calibration".

3 ' ' MST-Z0027 "Steam Generator B Narrow Range Level Loop L-485Calibration".

3.6.8 MST-Z0028 "Steam Generator B Narrow Range Level Loop L-486Calibration" .

'omputed by: Data:John P. Boska 6/1/94

Checked by: Date:Chris Geor eson 6/1/94TAR/PID No.

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CALCULATION SHEET

Calculation ID a

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~

Calculation Title: Steam Generator Naxrow Range Level:Low, Low-Low, and High-High

I Status'relim. Final X Void

3 ~ 6 ~ 9 MST-Z0036 "Steam Generator C Nax'row Range Level Loop L-493Calibration".

3.6 '0 MST-I0029 "Steam Generator C Narrow Range Level Loop L-494Calibration".

3.F 11 MST»I0030 "Steam Generator C Narrow Range Level Loop L-495Calibration".

3.F 12 MST-I0031 "Steam Generator C Narrow Range Level Loop L-496Calibration" .

3.6 13

3.6.14

3 ' 15

3 6 ~ 16

3 ~ 6 ~ 17

3.6+18

3.6 '93 ' 20

3.6.21

3.6 '23 ' 23

3.6 '4

SCN-175 "Steam Generatox' Narrow Range Level L-473".4

SCN-040 "Steam Generator A Narrow Range Level L-474".



SCN-176 "Steam Generator B Narrow Range Level L-483".


SCN-044 "Steam Generator B'Narrow Range Level L-485".


SCN-177 "Steam Genexator C Narrow Range Level L-493".

SCN-042 "Steam Generator C Narrow Range Level L-494".



3.7 Industry Standards and Reference

3.7 ~ 1

3.7 ~ 2

ZSA Standard S67.04-1988 "Setpoints For Nuclear SafetyRelated Instrumentation Used Zn Nuclear Power Plants".

ISA Standard RP67.04 "Methodologiee For The Determination OfSetpoints For Nuclear Safety Related Instrumentation", Draft9.

3.7.3

3.7.4

USNRC Reg. Guide 1.105 "Instrument Satpoints For SafetyRelated Systems".

ASME Steam Tables, Fifth Edition

~ ~

jl

. Computed by: DatesJohn P. Boska 6/1/94

Checked bys DatesChris Geor eson 6/1/94TAR/PZD No.

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Calculation ZDsHNP-I/INST-1045

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'ro)ect Titles Reactor Trip Setpoint Calculation

:Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High

, Status: Prelim. Final X Void

3.8 Other References

3.8 ~ 1

3.8 '

3 ' '

3.8.4

3i8 ~ 5

3.8.6

3.8 '

3 ~ 8 ~ 8

3 ' '3 ~ 8 ~ 10

3.Soll3e8 ~ 12

3e8el3

3 ~ &~ 14

3 ' '5

Equipment, Data Base System tEDBS)

Mechanical Calculation EQS-42, Rev 2, 9/22/86, SG ReferenceLeg Heat;Up.

Mechanical Calculation FW-022, Rev 0, 1/11/93, Evaluation ofSteam Generator Level Setpoints"

Westinghouse Letter CQL-92-031, 6/18/92, "SG Water Level PMATerm Inaccuracies"

Proceedings of the 34th Power Instrumentation Symposium,June 1991, ZSA paper 91-722, "Delta»P Level MeasurementSystems" by Glenn E. Lang and James P. Cunningham.

Westinghouse Letter CQL-88-568, 5/23/88, "Veritrak/TobarTransmitter Closeout"FCR-P-4126, 6/3/85, "Reroute of FW Lines for Instrumentationof SGs"

Technical Specifications for Shearon Harris Unit 1, throughAmendment 46, 3/3/94.

I

FCR-P-3637, Rev 2, 9/25/86, SG Reference Leg InsulationWestinghouse Letter CQL-88-530, 3/7/88, "EquipmentQualification"PCR-6464, SG Water Level Inaccuracies

PCR-6986, T-Hot Reduction-

Westinghouse Field Change Notice CQLM-10561

EMF-93-033(P), March, 1994, "Plant Parameters for ShearonHarris Nuclear Power Plant"

EMF-93-163, March, 1994, "Shearon Harris Cycle 6sDisposition of FSAR Chapter 15 Events and Analysis of PlantTransients"

Ccxnputod bye DatogJohn P. Boska 6/1/94

IChecked bye Dates:Chris Georgeson 6/1/94TAR/PID No

PCR-6464

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CALCULATION SHEET

Calculation ZDcHNP I/INST-1045

Pg. 7 Rev. 0

Files


Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High

Status! Prelim. Q Final QX Void@

4+0 I UTS AS ONS

4.1 Based on the scaling documents (eg. Ref. 3.6.18), the transmitters arescaled using the fallowing parameterse a reference leg temperature of120'F and a SG process pressure of 983 psia. The typical range is 64inwc to 230 inwc, so the span is 166 inwc. This varies slightly amongtransmitters. The high side of the transmitter is connected to thereference leg, and the output is 4'a at 0% level (maximum d/p) and 20ma at 100t level (minimum d/p).

4.2 Unless specifically linked to a temperature, all references to pressurein inches of water column (inwc) will be far inwc at 684F.

4.3 Any uncertainty determined to be 10 times less than the magnitude of thegreatest uncertainty will be considered insignificant and may be leftout of this calculation.4 ' When referring to a loop, the calculation is actually referring to thepart of the loop that goes from the process being measured to thecamparator (bistable) which provides input to the reactor protection

systemo

4.5 The differential pressuro transmitters aro located on the E1.236'evelof the Containment Building. This is an inside area which is exposed totemperature extremes from 804F to 1204F during normal operation and upto 380 F during an accident (Ref. 3.2.1, 3.2.3, 3.2.5]. Thetransmitters are Safety Class A. Only the SG low-low level setpoint isassumed to function during high energy line break (HELB) conditions(Ref. 3.2.7].

4.6 The PZC roam is designed to maintain a temperature between 65 t and 80~tfor all operating conditions (Ref. 3.2.2]. The uncertainties associatedwith temperature and radiation in the PZC room are considered negligibleper Ref. 3.5.4, and Assumption 4.3. The seismic effects on Westinghouse7300 series cards in the PZC room are considered negligible per Ref.3.5.5.

4.7 The Steam Generator narrow range level loops are classified as nuclearsafety related. The loop components are expected to withstand bothaccident and seismic events. The HNP FSAR does not consider a designbasis accident (DBA) occurring concurrently with a seismic eventfconsequently, the uncertainties associated with a DBA will not beconsidered together with the uncertainties associated with a seismicevent. Only those which represent a worst case condition will beconsidered.

4.8 The Steam Generator level differential pressure transmitters are ZTTBarton Model 764 and Tobar Model 32 3,483,493 only) with atypical maximum and calibrated span 166 inw Ref. 3.1.4, 3.6.13-3.6.24]. Uncertainties will be grou er for these transmittersgconsidering the most conservative in each case

I

I I

I4'

Computed by< DatesJohn P. Boska 6/1/94

Checked by<'atesChris Geor eson 6/1/94TAR/PID No

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Pg. 8 Rev. 0

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4+9

4.10

4 ~ 11

4o12

Tolerance values given in percent maximum span will be converted topercent span by applying a factor of a turndown ratio (Max Span/Cal.Span) or (166/166), which gives a value of 1.0 for all loops.

As an additional measure of conservatism, a margin will be includedbetween the analytical limit and the trip setpoint.There is no error associated with measuring the pressure of a liquid atthe level of the transmitter, as opposed to measuring the pressure atthe level of the lower tap since differential pressure is being measuredand the sensing lines run together to the transmitter (which is lowerthan the lower tap) (Ref. 3.1.3).The uncertainty associated with a change in the density of water in. thereference leg will be considered.

4 ~ 13 The uncertainties presented in this calculation represent. the deviationof the instrument reading from the actual parameter. For example, anegative error means that the instrumentation would read less than theactual SG level.

eComputed bys Dates

John P. Boska 6/1/94:Checked by: DatesjChris Geor eson 6/1/94TAR/PID No

PCR-6464

Carolina Power 4 Light Coapassy

CALCULATION SHEET

Calculation IDsHNP-I / INST-1045

Pg. 9 Rev. 0

Files


Calculation Title: Steam Generator Narrow Range LevelsLow, Low-Low, and High-High


5 . 0 DETERMINA 0 OF UN T INTIES

F 1

F 2

The following uncertainties will be determineds

Process Measurement Effect (pME) — This will account for errors such asreference leg heating, process pressure and temperature change, downcomersubcooling and fluid velocity effects.Primary Element Accuracy (PEA) - Since there are no venturis, elbow taps,orifice, etc. in these loops this term will be zero.

5 ~ 3 Sensor Calibration Accuracy (SCA) - The transmitter calibration accuracy, alsoknown as the Reference Accuracy, the Sensor Measurement and Test EquipmentAccuracy (SMTE) and Sensor Calibration Tolerance are all included in thisterm.

5 ' Static Pressure Effects (SPE) — The change in the transmitter output as aresult of the difference between static head pressures at operating andcalibration conditions.

5.5

5.6

5 ~ 7

Sensor Temperature Effects (STE) — The change in the transmitter output as aresult of normal variation i.n the local temperature.

Sensor Drift (SD) - The change in transmitter output over the period betweencalibrations (typically 18 months +/-25%).

Rack Calibration Accuracy. (RCA) - The process instrumentation calibrationaccuracy, including the calibration of all modules up to and i.ncluding thebistable. The Rack Measurement and Test Equipment Accuracy (RMTE) and bistablecalibration tolerance is included in this term.

5 ~ 8

5.9

5 ~ 10

Rack Drift (RD) - The change in process instrumentation output over the periodbetween calibrations (typically 3 months).

Rack Temperature Effects (RTE) - The change in process instrumentati.on outputas a result of normal variation in the local temperature.

Harsh Environment Effects (HEE) - The change in transmitter output due to aharsh environment (e.g. after a HELB). It is applied only to instrumentchannels which must survive a harsh environment.

5 11 combination of terms - All terms will be combined into a total loopuncertainty (TLU). Random uncertainties will be combined as described in Ref.3.4.1, -using the method known as "square root, of the sum of the squares"- Biaserrors will be given an'arithmetic sign (+ or -) and will be combinedseparately. A negative sign means that the bias is such that the indicatedlevel will be less than the actual level.


Checked bye DatesChris Georgeson 6/1/94TAR/PID No

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Calculation ID!HNP-I/INST-1045

Pg. 10 Rev. 0

Files

Project Titlet Reactor Trip Setpoint Calculation

Calculation Titlet Steam Generator Narrow Range Level:Low, Low-Low, and High-High

Status a Prelim. Final X Void

6 ~ 0 CALCULAT ONS 0 UNCER I IES

6.1 Symbols used

H

LH„=

PU

Pt.Pr

PrpPwr =

g

W

ACR+ aCRdpo ~

vertical distance between the SG NR upper and lower taps at normaloperating conditions ~ 19.55 ft (234.6 in) (Ref. 3.6.18).actual water level in the SG above the lower tap (in ft)vertical distance between the lower tap to the water level in thecondensate pot (at the upper tap) at normal operating conditions20 06 ft (240 73 in) (Ref. 3 6 18).vertical distance between the water level in the condensate potand the upper tap ~ 0.51 ft (6.125 in) (Ref. 3.6.18) (B~H„-H)water density in the reference leg used for calibration scaling ~

61.88 ibm/ft~ (120'F, 983 psia) (Ref. 3.6.18).water density in the reference leg.saturated water density used for calibration scaling = 46.45ibm/ft~ (983 psia).saturated steam density used for calibration scaling 2.20ibm/ft~ (983 psia).saturated water density at the process pressure.saturated steam density at the process pressure.water density in the vicinity of the lower tap.gravitational constant for the English Engineering units ~ 32.174ft-ibm/lbf-sec-.steam flow from one SG at 100'ower ~ 1129.6 ibm/sec (4.07 MPPH)

(Ref 3.8.3).fluid flow rate normal to the lo~er tap (ibm/sec)flow area at the lower tap 5.74 ft~ (Ref. 3.8.3)circulation ratio at 100% power ~ 2.13 (Ref. 3.1.34)circulation ratio at this power levelfluid flow losses in the downcomer above the lower tap ~ .1 psi(Ref. 3.8.3)friction and form loss factor (unitless)

~~

+1%

~ II

It=ws

Computed by> DateaJohn P. Boska 6/1/94

Checked by! DatesChris Georgeson 6/1/94TAR/PID No

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CALClKATIOM SHEET

Calculation IDeHNP I/INST 1045

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Files

Pro)ect Titles Reactor Trip Setpoint calculation

Calculation Title! Steam Generator Narrow Range Level!Low, Low-Low, and High-High

Status< Prelim. Final X Void

6.2 PME Term

6 ',a. Reference Leg Temperature Changes - The transmitter is calibrated for areference leg temperature of 120'F. During normal operations thereference leg temperature may vary from 100'F to 130'F. Since the SG low-low level trip is used in the analysis of a Feedline Break (FLB)accident, an additional error is required for those conditions. Ref.3.8.2 reports that the average temperature reached in the insulatedreference legs (initially at 120'F) at 5 minutes after a main steamlinebreak accident (MSLB) is about 160.6'F (density ~ 61.1726 ibm/cubicft.). This is conservative since containment heats up less on a FLB, andFSAR section 15.2.8 shows the reactor trip on SG low-low level at lessthan 1 minute after the FLB. This is a bias error term, not a randomerror term. The error term- is calculated as followers

The transmitter is calibrated by setting the d/p at 0% level to be 4maand the d/p at 100% level to be 20ma. The maximum d/p is at 0% level(the transmitter high side is connected to the reference leg).Calibrated dP (at 0% level) ~ pressure in the reference leg — pressure

in the steam generator.

<cpcc ~ - <cp~ ~~c Fc

Since g/g, is numerically equal to 1 for this application, it will be dropped fromthese equations but it is still needed to derive the correct units.

Calibrated hP (at 0\ level) - H„(pcc - p~)

Calibrated hP (at 100% level) Hc pcs - (Hpa + Bp~)

Calibrated span ~ hP (at Ol level) - dP (at 100% level)~ H„pic - H„p~ - H„pcc + (Hp„+ Bp~)

~ Hpa Hv Py + Bpge (B~Hc,-H)

Hp> - Hc p~ + H<p~ - Hp~

H(pr " p„)

dP(at level L) ~ pressure in the reference leg - pressure in the steam generator

Hcpcc - [Lp> + (H< - L) pi ]

Computed byt DatesJohn P. Boska 6/1 94

Checked byt Date tChris Gear eson 6/1/94TAR/PID No.

PCR-6464

Carolina Penner 4 Light. Company

CALCULKTIOH SHEET

Calculation IDtHNP-I/INST-1045

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Project Titlet Reactor Trip Setpoint calculation

Calculation Titlet Steam Generator Narrow Range Level:Low, Low-Low, and High-High

Status: Prelim. Final X Void

fractional level hP(at 0% level) -hP(at level L)

Hcpcc — H p — «cpcc - Lptc H'P + LP ] LH(pt - pc,) H

Assume the temperature of the reference leg changes (pic goes to pi).Error due to the reference leg temperature change ~ ez (in 0 level)e~ ~ (new fractional level - previous fractional level) x 100

new fractional level ~ calibrated hP (at 0%) - new hP (at L)calibrated span

HcPcc H P (Hcpc Lptc HtP + LP

H(ptc Pge)

Hc(Pcc Pt) + L(ptc P

H(Ptc Pgc)

ee Ht(pcc Pt) + L(pt P ) L(pt P ) (100]«Ptc Pyc)

c(Pcc " Pt.)

H(ptc Pcc)

e~ only depends on the density of water in the reference leg.

At 130 F, 983 psia, p„~ 61.73 ibm/ft~

ee (20.06) (61.88 - 61.73) (100] +35'9

~ 55 (46 ~ 45 - 2 ~ 20)

At 100'F, 983 psia, p„62.19 ibm/ft~

(20.06) (61.88 - 62.19) (100]72'9

~ 55 (46e45 - 2+20)

At 160.6F, p„ ~ 61.17 (MSLB analysis, Ref. 3.8.2)

(20.06) (61.88 - 61.17) (10p] +1 6519.55 (46o45 —2.20)

4%

F

E

Computed by: DaterJohn P. Boska 6/1/94

Checked by: DatesChris Georgeson 6/1/94TAR/PID No

PCR-6464

Carolina Power r'ight, CoIspany

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Calculation IDsHNP-I / INST-1045

Pg. 13 Rev. 0

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Calculation Titles Steam Generator Narrow Range LevelrLow, Low-Low, and High-High

Statues Prelim Final X VoidQ6.2.b. Process Pressure Variations - The transmitter is calibrated for a

saturated steam/water condition of 983 psia. However, the SG pressurevaries with power, reaching a high of about 1106 psia (557'F) at 0\power and a low of about 869 psia (528'F) at 100% power. This introducesan error at the other operating conditions. This is a bias error term,and is calculated as follower

Calibrated AP at 0% level ~ Hq (p~ - ps,)Calibrated span ~ H (pq — p~)

Fractional level at the calibration point =

Fractional level at the new condition ~

(calibzaced hp ac 0%level) - (ALP ac new level)cali braced span

IH

Hept.e H P ) - (H Pcc (~pr + (Hc L) p ])(Prc Pgc)

r(pH(P rc Pre)

fractional level at)e~ ~ the new condition I

fractional level atthe calibration pointl (100]

Hs(p P + L(pr P ) [100]H(pre -

Pg ) H

This error varies with SG pressure and SG level. It will be zero when the SG is at983 psia ( the calibration point ) .

Power

oa

100%100%100%100%25%25%

SGPressure

(psia)110611061106110686986986986910471047

Pr

45.5145 5145 5145 '147.35.47 '547 '547.3545 9545 '5

2.512.512.512.511.92 ~

1~921.921.922 362 36

L(ft)(0 level)

19.'55 (1004) 2.02%16. 11 (82.4%) -0.85%19.55 (100%) -1 ~ 12%

0 (0%) 0 72%7.53 (38.5%) -.37%16.11 (82.4%) -1 61%19.55 (100%) -2 11%

0 (0%) -.65%7 '3 (38 5%) 0 39%

16 11 (82 '%) 1.55%

a —~

~ P

1

A

I~ ~

; Computed by: DatesJohn P. Boska 6/1/94

Checked bys DatesChris Georgeson 6/1/94TAR/PID No

PCR-6464

Carolina power S Light Company

CALCULATION SHEET

'alculation IDsHNP-I /INST-1045

Pg. 14 Rev. 0

File:



'tatus s Prelim. Final X Void

6.2.c. Downcomor Subcooling Variations - the transmitter is calibrated for asaturated steam/water condition of 983 psia. However, because somefeedwater is injected at the auxiliary feedwater nozzle, the density ofthe water in the downcomer is somewhat more than what was assumed forthe calibration. This will produce a positive error (the indicated levelwill be higher than the actual level). This is a bias error tenn, not arandom error term.

Since the auxiliary feedwater nozzle is high in the SG, with a dischargepipe which directs the water upward, it will be assumed that thefeedwater mixes uniformly with the recirculation water from the steamseparators. .his will produce an average density o the water in thedowncomer. The error term is calculated as followss

Fractional level with subcooled downcomer ~

(calibraced hP ae 04 level) - (IP vi th subcooled downcomer)calibraced span

Hs(psc " p ) [Hspm (Lpn + (Hs ] p )

H(p rc Pyc)

Hs,(P P ) + L(per P )

H(pr,- p )

Fractional level at the process pressure ~

Hs(p P ) + L(Pr P

fractional level with) ( fractional level ate, subcooled downcomer I l the process pressure [100]

H (p - p ) + L(p - p )

H(pre -Pg )

H (p - p ) + L(pr - p )

H(pre -Pg )

L ( pn P r) (100](Prc Pgc)

This error varies with power level and with SG level. p~ is calculated as describedin Ref. 3.8.3. The maximum error is at 100% power.

~ 4

~ a

Computed by> DatesJohn P. Boska 6/1/94

Checked bye DatesChris Gear eson 6/1/94TAR/PID No

PCR 6464


CALCULATION SHEET

Calculation ID tHNP-I/ INST-1045

Pg. 15 Rev. 0

Files


Calculation Title: steam Generator Narrow Range Level:Low, Low-Low, and High-High

Status< Prelim. Q Final X Void

Power

100%

SG Pressure(psia)

869

Pr

47.35 48 'L(ft)

(0 level)0 (0%)

BI

100%100%100%25%25%

869869869

10471047

47.3547.3547 3545.9545.95

48 248 248. 246.246 '

19.55 (100%) 1 92%16 11 (82 4%) 0 47%19 55 (100%) 0 '6%

7.53 (38 5%) 0 '4%16 11 (82 '%) 1.58%

6 '.d. Fluid Velocity Effects - The transmitter is calibrated for a static headof water. However, at power there is water flowing dawn the downcceerpast the lower tap (the upper tap is in the steam space). The fluidvelocity creates a reduced pressure at the lower tap. This will producea negative error (the indicated level will be less than the actuallevel). This is a bias error term, not a random error term. The errorterm is approximated as follows (using Bernoulli's equation forfrictionless, noncompressible fluids) s

a'i pZ cr Va Par 2 + + —a r~~ t +gc 2gc pz gc 2gc Pa

Since the static head hp has already been accounted for, only the hpassociated with flow losses will be calculated. Since the flow areaabove the downcomer is much larger than the flow area in the dawnccear,initial velocity vl ~ 0 Also'i p~ Per

2p, v~ p~a +pn 2gc Pn

2Vg

(ug-ui) pn (—)2 g+p

Wp~ V2 Vg

hP ~ (—) ( —)~Pm'

P err 2F~ >8 Par

I i i~

4


Checked by: DatesChris Georgeson 6/1/94TAR/PZD No.

PCR-6464

Carolina Power t Light Company

CALCUZATXQN SHEET

Calculation IDsHNP-E / INST-1045

Pg. 16 Rev. 0

Files


Calculation Titles steam Generator Narrow Range Levels Low, Low-Low, and High-High

Status: Prelim. Q Final X VoidQ

e„ hP [100]calibraeed apaa

(-) '100)gc Parr H(Ps'c Pyc>

Since frictionless flow does not account for flow losses in thedowncomer, it is recommended to increase this error by a friction andform loss factor, 1 + Q. An equation for Q is given in reference 3.8.5.

288 g~ p~ hP>( )V~ CR~

The 288 includes the conversion factor of 144 in/ft, so that hPe is inpsi0

At 100% power, 4PD = .1 psi, p~ = 48.2 ibm/ft (see Ref. 3.8.3), so Ks ~

288(32 174) (48 2) ( 1) ('s ~ 25

(1129 ~ 6) (2 ~ 13)

.25 will be used for all power levels, since p~ and APE are the only termsthat vary and they do not vary much with the power level.

"(-) (1 + Ki)(100)

2gc Pn >(Prc Pyc)

.25

The fluid velocity error varies with power level. W and p~ are calculatedusing the methods of Ref. 3.8.3. W ~ water from the steam separators + waterfrom the AFW nozzle ~ (CR-l)(steam flow) + .2(feedwater flow).

eComputed by: Date:

John P. Boska 6/1/94Checked by: DatesChris Gear eson 6/1/94TAR/PID No

PCR 6464

Carolina Pcnier k Light Company

CALClKATZOM SHEET


Pg. 17 Rev 0

Files


Calculation Titles Steam Generator Narrow Range Level:Low, Low-Low, and High«High

Status'relim. Final X Void

Power e„

(—)ibmsec

CR Feed Temp(P)

0% -0 45 ~ 6 020% 2462.5 46 ' -9.0%251K 2513 4 46.0 -9 '%30% 2507.7 46 ~ 1 -9+3%50% 2372.2 46.5 -8.3%75% 1990 9 47.3 -5. 7%

100% 1502 4 47 ' -3+2%

-045 '56.567 '113 0169. 4225.9

N/A11.79 '8 '5.0

3.152 ~ 13

80280310330370400435

This method assumes uniform downward flow around the downcomer, which isconservative. On the cold leg side of the downcomer, where the level taps arelocated, the preheater section blocks part of the entrance to the tube bundle andmain feedwater is flowing into the preheater section. This means W is smaller in thevicinity of the. level taps. However, this can not, be quantified without detailedcomputer models, so uniform flow will be assumed.

I P J

4 f

1

'1

I

~ I ~

; Computed by> DatesJohn P. Boska 6/1/94

'Checked by: Date~~Chris Georgeson 6/1/94TAR/PID No.

PCR 6464


CALCULATION SHEET

Calculation IDsHNP I/ INST 1045

Pg. 18 Rev. 0

Files


. Calculation Titles Steam Generator Narrow Range LevelcLow, Low-Low, and High-High


6.3 Sensor Cal ration Accurac SCA

ITT Barton Model 764 or Tobar Model 32DP1, differential pressure transmitter:

As stated in Ref. 3.5.1, the reference accuracy is t 0.5% of calibrated span.This includes the combined effects of linearity, deadband, hysteresis andrepeatability. There are no humidity effectsg these transmitters can operatewithin their reference accuracy for 5-95% humidity. Since these transmitterswill be within their reference accuracy following a seismic event (Ref.3.1.20), there is no seismic allowance.

Sensor Measurement and Test Equipment (SMTE) Inaccuraciess

The calibration of this transmitter depends on a digital Heise pressure gauge(Model 710A) for input and a Fluke multimeter (Model 8600A) to measure theoutput. (See Ref. 3.6.2.). The accuracy of the pressure gauge is 4 0.835 inwc.The span of this transmitter is 166 inwc. The accuracy is a 0.50% span. Theaccuracy of the multimeter is a 0.01 vdc. Converting this to percent span for

a lv to Sv signal (4-20ma)s a0.01v (—) ~ x0.25%10044v

Calibration Tolerancec

As stated in Ref. 3.6.1 - 3.6.12, the allowable range during calibration is~0.02v. Converting this to percent span, for a lv to 5v signal (4-20ma)s

a 0.02v x —= ~ 0.50% span100%4V

Therefore, SCA ~ a0.5 i.56 a0.5 ~ 41.56% span (a random error)

6.4 Static Pressure Efiects (SPE)

As stated in Ref. 3.5.1, static pressure effect is a0.2\ of span per 1000psig. The maximum SG pressure is limited by the SG safety valves. There are 5

safety valves with staggered settings. The highest setting is 1230 psig (TachSpec 3.7.1.1). The sensing line to the transmitter is at most 74 ft. high.

This adds (74 f(:) (62.2 —) (—) 32 psi.2hn 1 fe'g> 144 jn~

The maximum

pressure is 1230 + 32 ~ 1262 psig.

SPE a 0.2%(—) = w 0.25% span12621000

I \t

lh


Checked bye Dateschris Geor eson 6/1/94TAR/PID No

PCR 6464


CALCDLATIOM SHEET

calculation IDa

HNP I/INST 1045

Pg, 19 Rev 0

Files


Calculation Tltlet Steam Generator Narrow Range Levels Low, Low-Low, and High-High


6.5 Sensor Temperature Effects (STE)

The temperature inside containment in the vicinity of this transmitter mayvary from 80'F to 130'F. The temperature coefficient is kl% per 100'F. (Ref.3.5 ~ 1) ~

STE ~ aO 50%

There was some concern in the past with a thermal non-repeatability problem onBarton transmitters, but that was fixed by a factory modification. (Ref.3 ' 13) ~

6.6 Sensor Drift (SD) ~ ~p~.As stated in Ref. 3.5.1, dri.ft is al.00% of the . per year.The normal calibration cycle for this transmitter is 18 months, but may beextended to as long as 22 months. Allowing for a 24 month calibration cycle,1% drift in the first year followed by 1% drift in the second year:

SD ~ (1 + 1 )» ~ 1.41% span

6.7 Rack Calibration Accuracy (RCA)

As stated in Ref. 3.1.35, RCA (except for the bistable) ~ 10.5% span

Rack Measurement and Test Equipment (RMTE) InaccuraciesaA digital voltmeter is used to measure the input voltage. The accuracy isiO 01 vdc so RMTE a iO 25\

Calibration Tolerancee As stated in Ref. 3.6.1-3.6.12, the allowable range toset the bi.stable is -.01v, +.02v for the low-low 'level trip and i.02v for thelow level and high level trip. Converting this to 0 span, for a lv to 5vsignal (4-20ma) a

1

.Olv x —~ .25% span100\4v *.02v x —~ a0.50\ span100\

4V

Total RCA ~ 11.00% span.

6.8 Rack Drift (RD)

As stated in Ref. 3.1.35, RD a i1.00\ span.

6.9 Rack Temperature Effects (RTE)

As stated in Ref. 3.1.35, RTE ~ a0.50% span

I I L J

~4

Computed bys DatesJohn P- Boska 6 1 94

Checked bys DatesChris Geor eson 6/1/94TAR/PID No.

PCR 6464

Carolina power a Light CoaEsany

CALCQLlLTIQS SHEET

calculation ID s

HNP-I/INST-1045

Pg. 20 Rev. 0

Files


Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-Hi.gh

Statues Prelim. FinalQX Void

6.10 Harsh Environment Effects (HEE)

The only safety analysis for high energy line breaks which assumes a reactortrip on SG level is the Feedline Break (FLB) analysis. The reference legheating effects were already calculated in section 6.2.a. The maximum effectis ez ~ +1.65% span. The transmitter may experience a temperature increase.The error has been verified to be less than a10% error. (Ref. 3.1.20)

HEE ~ i10% e~ ~ +1.65t

Cable insulation resistance is affected to some extent, by a FLB. Since theanalysis vas done '"r a MSLB, this error is conservative. Since the leakagecurrent increases the loop current, the error is positives

E~ ~ +0.53%

6.11 Total Loop Uncertainty (TLU)

6 ~ lloa

(SGL) + (SD) + (STE) + (SPE) + (RCA) + (RD) + (RTE)

plus bias terms.

For the FLB analysis (the SG low-low level setpoint),

~ (1.56) + (1 ~ 41) + (0.5) + ( ~ 25) + (1 ~ 0) + (1 ~ 0) + (0 ~ 5)

2 64%+1.65% (e~ at 160.6'F)+0.39% (e~ at 100% power, 38.5% level)+0.74\-(e, at 100% power, 38.5\ level)+0.53% (em for HELB)+10% (HEE for HELB)

TLU ~ + 15.95t (SG low-low setpoint)The SG loss of feedwater accident is most severe at 100% power,especially since the mass of water in the SG is lowest at 100'ower(Ref 3.1.34). Therefore, the worst case bias terms for 100\ power areused. Since a negative error is conservative (it means the indicatedlevel is less than the actual level and the reactor will trip sooner)>the bias for fluid velocity effects is ignored.

0

«4

'1

~~

i Computed by< DatesJohn P. Boska 6/1/94

i Calculation ZDcM~1~ P~r Mght ~~+ HNP-I/INST-1045Checked bys Date:Chris Geor eson 6/1/94

, TAR/PID No.PCR-6464

CALCULATZ0N SHEETPg. 21 Rev. 0

Files

Pro)ect Titles Reactor Trip Setpoint CalculationI

I Calculation Titles Steam Generator Narrow Range LevelsLow, Low-Low, and High-High

Status c Prelim. Final X Void

6 ~ 11.b. For the SG low level setpoint (loss of normal feedwater),

TLU ~ i 2.64% plus bias terms

+2.64m+0.35% (e~ at 130'F)+0.39% (e~ at 100% power, 38.5% level)+0.74% (e, at, 100% power, 38.5% level)

TLU ~ +4.12%

Since the SG low level setpoint is not required for reactor protectionduring a high energy line break (HELB), no harsh environment effects arerequired. To be conservative, the fluid velocity effects are not

'ncluded.

6 ~ 11.ci For the SG high-high level setpoint,TLU ~ k2.64% plus bias terms.

A negative erroractual level, sosetpoint will bepower means that

will cause the indicated level to be less than thethe largest negative errors at levels close to theconsidered. The fluid velocity error of -9.4% at 25125% power will be the limiting case.

TLU ~ -2.64%-0 '2%-0 85%+0 '7%-9.4\

(e~ at 100'F is conservative)(e at 25% power, 82.4% level)(e, at 25% power, 82.4% level)(e, at 25% power)

TLU ~ -13.14%

Since the SG high«high level setpoint is not required for reactorprotection during a HELB, no harsh environment effects are required.

Computed by: Date:John P. Boska 6/1/94

Checked by> DatesChris Geor eson 6/1/94TAR/PID No

PCR-6464


CALCDLATZON SHEET

Calculation ZDsHNP-Z/ZNST-1045

Pg. 22 Rev. 0

File!I

I Pro)ect Title: Reactor Trip Setpoint CalculationI

; Calculation Titles Steam Generator Narrow Range Level:Low, Low-Low, and High-HighI

I Status: Prelim. Final X Void

7.0 Discussion of Results

To determine the Technical specification parameters, the following terms willbe usedc

S = Sensor error term ~ SCA + SD (in 0 span)

A ~ the sum of the squares of all random errors that are not associated withSCA, SD, RCA, or RD.

SAL ~ Safety Analysis LimitTS ~ .rip setpoint in Tech Specs

TA Total Allowance TS-SAL (in 0 span)

Margin ~ TA — TLU

T ~ Rack trigger value ~ .TA - [(A+S')" + all bias errors] or (RD+RCA),whichever is less.

AV ~ Tech Spec Allowable Value TS - T (this allows for rack'rift but hasno allowance for sensor drift).

Z ~ Q + any bias error terms, (in 0 span), the statistical suamation oferrors excluding those associated with sensor drift, rack drift, sensorcalibration accuracy, and rack calibration accuracy.

~I )

I'

Computed bye DatsunJohn P. Boska 6/1/94

Checked by: DatesChris Georgeeon 6/1/94TAR/PID No

PCR-6464


CALCULATION SHEET

Calculation IDtHNP I/INST-1045

Pg. 23 Rev. 0

Files

Project Titles Reactor Trip Setpoint calculation


Status> Prelim. Q FinalQX Void

7 ' SO w- ve

S ~ SCA + SD ~ 1.56 + 1.41 ~ 2.97%

(SPE) + (STE) + (RTE)

(0.25)i + (0.50)~ + (0.50)i

0.56%

TS ~ 38.5% (Ref. 3.8.8)SAL ~ 19. 3% (Ref . 3.8. 14)

TA ~ TS - SAL ~ 19.2%

T = RD + RCA

1.0 + 1.0

2.0% span

2 ~ A" + all bias terms

(0.56)" + 1 ~ 65 + .39 + .74 + .53 + 10

14.06'panAV s TS - T ~ 38.5% — 2.0% a 36.5% span

Margin ~ Th - TLU ~ 19.2% - 15.95' 3.25%

comparison with current Tech Specs (Ref. 3.8.8)s

TSAVS2

TA

N/A36 '%2.97%

14 06%19. 2't

38 5%38.0%1 '%

18 18%19.2%

Since the calculated values show margin to the Tech Spec trip setpoint, there is noneed for a Tech Spec change.


Checked by> DatesChris Geor eson 6/1/94TAR/PID Noi

PCR 6464


CALCULATION SHEET

Calculation IDsHNP-I/INST-1045

Pg. 24 Rev. 0

Pile:



Statuss Prelim. Final X Void

d s

S ~ SCA + SD ~ 1 ~ 56 + 1.41 ~ 2.97%

A ~ (SPE)s + (STE) + (RTE)

(0 '5)s + ( 5)' (5)'.56%

TS ~ 38.5% (Ref. 3.8.8)

SAL ~ 19.3% (Ref. 3.8.14) [Not used in Safety Analysis but use same value asSG Low Low SAL for conservatism)

TA ~ TS - SAL ~ 38.5 — 19.3 ~ 19.2% span

T ~ RD + RCA

1.0 + 1 0

2.0% span

Z ~ A" + all bias terms

0 56)s + 35 + 39 + 74

2.23% span

AV ~ TS - T ~ 38 '% - 2 '% ~ 36 USE span

Margin,~ TA.- TLQ. ~ 19.2\ — 4.12% ~ 15.08%

Comparison with'urrent Tech Specs (Ref. 3.8.8)

C te Cu e t Tec S

TSAV8Z

TA

N/A36 5%2.97%2.23%19 '%

38 '%36 '%1 '%

6.68%19 '%

Since the calculated values show margin to the Tech Spec trip setpoint, there is noneed for a Tech Spec change.

[ ~

y4h

lk

'h


Checked by> DatesChris Geor eson 6/1 94TAR/PID No.

PCR-6464

carolina power a Light Colipany

CALCDLATIOM SHEET

Calculation IDxHNP-I /INST-1045

Pg. 25 Rev. 0

Pile!

Pro)ect Titles Reactor Trip Setpoint calculation


statusc Prelim. Q Final X VoidQ7 ~ 3 SO

I

S > SCA + SD > 1 56 + 1.41 > 2.97%

A ~ (SPE)~ + (STE)~ + (RTE)~

(0.25)~ + (.5)i + (.5)i0.56%

TS ~ 82.4% (Ref. 3.8.8)SAL = 97.4% (Ref. 3.8.14, p. 2-32)

TA ~ SAL — TS ~ 97.4 - 82.4 ~ 15.0%

T > RD + RCA

1.0 + 1.0

2.0% span

2 ~ A" + all bias terms

(0.56)» + .72 + .85 - .47 + 9.4

11.25% span

AV ~ TS + T ~ 82@4 + 2 ' ~ 84 'Margin ~ TA - TLU ~ 15.0% - 13.14% ~ 1.86%

This calculation shows that margin exists to the Tech Spec trip setpoint based uponthe TA of 15% for the SO high high level provided by the Cycle 6 fuel vendor.Licensing plans to submit a proposed revision to'he HNP Tech Spec. Table 3.3.4based upon this information.

Comparison with the current Tech Specs (Ref. 3.8.8)

TSAVS2TA

~C~t~N/A84.42.9711 2515.0

82 484 21.54.287 ~ 1

S c

ol l ( I a

Computed by> DatesJohn P. Boska 6/1/94

Checked by< DatesChris Geor eson 6/1/94TAR/PID Noi

PCR 6464

carolina power 4 Light Company

CALCULATION SHEET

Calculation IDeHNP-I / INST 1045

Pg. 26 Rev. 0

Filet


Calculation Titles Steam Generator Narrow Range LevelxLow, Lo'w-Low, and High-High

Status t Prelim. Q Final QX VoidQ8.0 ~Pa~~

8. 1 Loop L-484, SG Narrow Range Level

Steam Generator

Differential Pressure TransmitterLT-04844-20 ma

Channel Test CardLS/484

Loop Power Supply (Isolated)LQY-484

0-10 vdc

Lead-Lag CircuitLY-484A0-10 vdc

(Channels 474, 484, 494 only)

Signal ComparatorLS-484A

Set at 38.5% level

Channel Test CardLS/484

SSPS Input Bay

e s

A

~4s7= /ofS gev 8

/~et ~~~+ — +//DISCIPLINE DESICR VIQtZPZChTZOH RECORD

Instructions to Vertffcatfon Perseuwl

! ant

opec

F:."e nc.=ac~ant No.g

C.tJL, 7 OPJ5-~ ~hl 57 0Rev

Q

Level

~ Q (Class Al

( ) Seismsc IClass Sl

I ) FP Q iClass Dl

i l Other

Design ver]I:catton snould be cone tn accorcance rich ANSI N45.2.11. Sect)on 6. as amended by Regulatorye .»se» nev

pec:d. nstruc 'ons:

Discsptine Pro)ect Sngtneer

ver1ffcatioa pocumatatkon

~conan:ca.'VA

Electr:cal:CC

Cs vt I St ruct ura lsessmsc Equip. Qual ~

Civil StressFire Protect lonEnvironmental Qual iiicat ]onHuman FaccorsNatertals » 5

ner

!er:.':cat>on NethodhUsed'p(

Design Rev:er J Alternate Calculat lans Quaiiftcatson Test tng

*»» - »»as 1gn Ver' er Date

Actnorsecgement" ot Verification:c ~4

ItI. Resolution ot Cemeatas

.=ments Reso l At hedl:

Ac 'cn taken aea

=estgn Vert :erc nts Acceptaole:

Date

»'

P C '04 / Rev. 9

OXSCZPLXÃS OSSZCW VERXPXCLTXOS %@CORD

CDNNENT SHEET

?lant

?ro7ect

?ile Ho. us7= oft////P W/Z-AINT-/4 )CAN It d.t

.His sneer is cniy required wnen comments are being made.

Comment

No. mment

gL /Ilc. iia4.l~l <

ResolutionResolved

:nit ial/Date

ot o&

Ul cl W at'l+oY

sk >id ~ s~ ws//, Q ~~0 ftl~ ~ ////

Proc 309 / Rev. 0

+Nf+jz<'57 -4 &'s, ge v, 8~CLuuc w.+ —k

DESIGN RKVIZN CHECK SHEET

~lant nJI Document Type 0 LCC)4+7 Jd NPro jectg ULA7TdAJ5 Document No. -K M+57 Jd.""ile Nophll 2 ~- GI~S qevision

Description:

Mark each item yes, nc, or not applicable and initial each item checked by you.

1. Were the inputs correctly selected and incorporated into design? ~s88-2- Are assumptions used in the design adequately described and reasonable?

NOTE: Review snail 'nclude but 's not limited to applicable'nputs specified in NED procedure 302, paragraph 302.4.

Are the appropr'ate quality and qualit" assurance requirements specified?4 ~ Are applicable codes, standards. and regulatory requirements including

issue and addendum properly dent fied, and are their reauirements fordesign met?

Has appl'cable construction and operat'ng experience been considered?

> ~ Have des 1gn -'" er face equirements been sat isf ied?

?. 'alas an appropr'ate design method used?

8. Is the output reasonable compared to inputs?

Are the specified parts, equipment, and processes suitablefor the application?

10. Are the specified materials compatible with each other and the designenvironmental conditions to which the materials will be exposed?

11. Have adequate maintenance features and requirements beenspecified?

12. Are accessibility and other provisions adequate for performance ofmaintenance, repair, and any expected in-service inspections?

Has the design properly considered radiation exposure to the publicand to plant personnel (ALAN&)?

14 'as the design properly documented changes in radiation affectingpost-accident plant access and/or affecting EQ?

15. Has the new design properly considered all system modes of operation-

A>A W

gems

+ ~A

Proc 309 i Rev. 0

ws7.—r~fS, p v. 4

~p A'/Document Type LK~

Document No. -X

Are acceptance criteria in the design documents sufficient to allowverification that design requirements have been satisfactorilyaccomplished? 5

17. Have adequate preoperational and periodic test requirements dkbeen specified?'S. ate adequate stoning. handling, cleaning, shipping, and identification grequirements specified? N'9. Are reouirements for record preparation,etc .. adequately speci fied2"0. Have all problems with this desian known

been considered and resolved2

review, approval, retention,

from prior application45

.=or each question on the check list not answered yes, explain below. Ef"Not Applicable" aive reason.

Signature(Design Verifier)

Date

+ 7P/5 r 5 3 area ae 3/Sa/4]ue dA4<~44>~~+ 7A~<DOaS ZdV m+~7AZd., +dPZiy, OA ~~~7

A~/'~gUCroAE.SSp'S7~S og do+poAI&VTSN0 r AFF<g-7 gdDIA~rdAI Zmua<S uNb~

4~/'L,A-As'oDFs oF oP&~X/~N ~X gccr8&u7-gc&WA-g.loS .

proc 309 / Rev 0

~ ~'

a<

Rev 0 to HNP-I/INST-1045, 'Steam Generator Narrow Range ... · Carolina Power 4 Light Company...

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