offsite F auxiliary · offsite F auxiliary ... regulatop

98
REGULATOP INFORMATION DISTRIBUTION STEM (RIDS) I~ 'ACCESSION NBR:8511050161 DOC ~ DATE: 85/11/04 NOTARIZED: NO DOCKET '~ FACIL;STN-50-528 Pal o Verde Nuclear .Stationi Unit 1i Ar) zona Publ i 05000528 STN 50 529 Palo Verde- Nuclear Station~ Unit 2~ Arizona Publi 05000529 STN 50-530 Palo Verde Nuclear Station~ Unit 3i Arizona Publi 05000530 AUTH, NAME AUTHOR AFFILIATION VAN BRUNT'~E".E Ar izona Nuclear Power Project (formerly Arizona Public Serv RECIP ~ NAME." RECIPIENT AFFILIATION KNIGHTONiG~ N ~ Office of Nuclear Reactor Regulationr Dir ector SUBJECT; Forwards results of steam generator tube rupture w/loss of offsite power F 851015'chedule for implementation of modsi per 851029 telcon re auxiliary pressurizer spray sys;'ISTRIBUTION CODE: A001D COPIES RECEIVED:LTR "ENCL - SIZE', TITLE: OR Submittal: General Distribution NOTES:Standardized plant. OL o 12/31/80 Standardized plant, Standardized plant. 05000528 05000529 05000530 RECIPIENT ID CODE/NAME NRR LB3 BC 01 COPIES LTTR ENCL 7 7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNALS ACRS ELD/HDS3« NRR/DL DIR NRR/DL/TSRG NgR/DS'I/RAB RGN5 (XTERNAL: 2~X LPDR NSIC 09 03< 05~ 6 6 1 0 1 1 1 1 1 1 1 1 1 1 1- 1 ADM/LFMB NRR/DE/MTEB NRR/DL/ORAB NR 'ETB G FILE 0g EG&G BRUSKEgS NRC'DR 02 1 0 1 1 1 0 1 1 ~ 1 1- TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25

Transcript of offsite F auxiliary · offsite F auxiliary ... regulatop

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REGULATOP INFORMATION DISTRIBUTION STEM (RIDS)I~

'ACCESSION NBR:8511050161 DOC ~ DATE: 85/11/04 NOTARIZED: NO DOCKET'~ FACIL;STN-50-528 Pal o Verde Nuclear .Stationi Unit 1i Ar) zona Publ i 05000528

STN 50 529 Palo Verde- Nuclear Station~ Unit 2~ Arizona Publi 05000529STN 50-530 Palo Verde Nuclear Station~ Unit 3i Arizona Publi 05000530

AUTH,NAME AUTHOR AFFILIATIONVAN BRUNT'~E".E Ar izona Nuclear Power Project (formerly Arizona Public Serv

RECIP ~ NAME." RECIPIENT AFFILIATIONKNIGHTONiG~ N ~ Office of Nuclear Reactor Regulationr Dir ector

SUBJECT; Forwards results of steam generator tube rupture w/loss ofoffsite power F 851015'chedule for implementation of modsiper 851029 telcon re auxiliary pressurizer spray

sys;'ISTRIBUTION

CODE: A001D COPIES RECEIVED:LTR "ENCL - SIZE',TITLE: OR Submittal: General DistributionNOTES:Standardized plant.

OL o 12/31/80Standardized plant,Standardized plant.

05000528

0500052905000530

RECIPIENTID CODE/NAME

NRR LB3 BC 01

COPIESLTTR ENCL

7 7

RECIPIENTID CODE/NAME

COPIESLTTR ENCL

INTERNALS ACRSELD/HDS3«NRR/DL DIRNRR/DL/TSRGNgR/DS'I/RABRGN5

(XTERNAL: 2~XLPDRNSIC

09

03<05~

6 61 01 1

1 1

1 1

1 1

1 1

1- 1

ADM/LFMBNRR/DE/MTEBNRR/DL/ORABNR 'ETB

G FILE 0g

EG&G BRUSKEgSNRC'DR 02

1 0

1 1

1 01 1 ~

1 1-

TOTAL NUMBER OF COPIES REQUIRED: LTTR 28 ENCL 25

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Arizona Nuclear Power ProjectP.o. BOX 52034 ~ PHOENIX. ARIZONA85072-2034

ANPP-33905-EEVB/KLM

November 4, 1985

Director of Nuclear Reactor RegulationAttention: Mr. George W. Knighton, Project Director

PWR Project Directorate 87Division of Pressurized Water Reactor Licensing — B

U.S. Nuclear Regulatory CommissionWashington, D.C. 20555

Subject: Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3Docket Nos. STN-50-528 (License No. NPF-41)/529/530Information Concerning the PVNGS AuxiliaryPressurizer Spray SystemFile: 85-056-026; G.1.01.10

References: (1) Letter to G. W. Knighton, NRC, from E. E. Van Brunt, Jr.,ANPP, dated October 15, 1985 (ANPP-33713);Subject: Auxiliary Pressurizer Spray Design

(2) Letter to G. W. Knighton, NRC, from E. E. Van Brunt, Jr.,ANPP, dated October 22, 1985 (ANPP-33771);Subject: Additional Information Concerning the September 12;1985 Event at Palo Verde Unit 1

Dear Mr. Knighton:

As a result of a telephone conversation on October 29, 1985, with members ofthe NRC staff, ANPP is providing information in addition to that previouslyprovided in References 1 and 2. The requested information, provided inAttachments to this letter, is as follows:

Attachment 1: Results of Steam Generator Tube Rupture with a Lossof Offsite Power and a fully stuck open ADV using thePressurizer Gas Vent System (Auxiliary PressurizerSpray System inoperable).

Attachment 2: Schedule for Implementation of Modificationsdescribed in ANPP-33713, dated October 15, 1985(Reference 1).

I- 85iiosoihi 85 e)5281,PDR ADOCK 0

PDRP o~

1

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Mr. George W. KnightonInformation Concerning the PVNGS AuxiliaryPressurizer Spray SystemANPP-33905-EEVB-KLHPage Two

Attachment 3: Additional Considerations to ANPP-33713, datedOctober 15, 1985 (Reference 1).

If you should have any questions concerning this matter, contact Mr. W.F. Quinn,of my staff.

Very truly yours,

~+v~8E. E. Van Brunt, Jr.Executive Vice PresidentProject Director

EEVB/KLM/dimAttachments

cc: E. A. LicitraR. P. ZimmermanM. C. LeyA. C. Gehr

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ATTACHMENT 1

STEAM GENERATOR TUBE RUPTURE WITH A LOSS

OF OFFSITE POWER AND A FULLY STUCK OPEN

ATMOSPHERIC DUMP VALVE (ADV)

The Steam Generator Tube Rupture (SGTR) analysis currently contained in thePVNGS FSAR Appendix 15A, was performed in response to a NRC staff concern thatoperator actions may affect the assumption of a worst single failure. As a

result, the Appendix 15A analysis was submitted, (Appendix to Reference 1 and

subsequent information in References 2 and 3) considering the operator actionsthat are outlined in the plant procedures.

These procedures provide guidance to the operator in the event of a SGTR witha loss of offsite power to lower RCS pressure through the use of the AuxiliaryPressurizer Spray System (APSS). Thus, the current Appendix 15A analysisassumes an operator action at 1015 seconds to initiate the APSS.

In response to a staff concern that this action was required to achieve

acceptable consequences, the event was reanalyzed without operator action toinitiate the APSS until two hours after the event initiation. The results

of'his

analysis were transmitted in Reference 4.

A two-hour time delay was chosen for two reasons. First, this delay willmaximize the two-hour Exclusion Area Boundary dose for this event. Second,

the two-hour delay provides adequate time to manually establish auxiliarypressurizer spray, even in the event failures in the system occur, per BTP RSB

5-1.

In response to a staff concern that the APSS may remain inoperable longer than

two hours, the event was reanalyzed with the APSS assumed inoperable

throughout the entire event and with the pressurizer gas vent system (withflow restricted by a 7/32" orifice) assumed activiated by the operator at 2

hours.

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JL ~~~1 f>l C'*, ( Jd=-" a f%~ 1 l yV ~ l~ 4 a ) 5= <'V4 > <II J lrl ail

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IDENTIFICATION OF EVENT AND CAUSES

This transient analysis is similar to that described in the PVNGS FSAR

Appendix 15A except that auxiliary pressurizer spray is never initiated and

the pressurizer gas vent is opened at two hours. It assumes that the plant ischallenged by a steam generator tube rupture including the conservative

assumptions of the Standard Review Plan Section 15.6.3 (loss of offsite power,

accident meterology, iodine spiking, etc.). In addition, the analysis

postulates that 1) the operators open an ADV on the affected steam generator

and 2) it runs to the full open position and 3) it sticks open for the

duration of the transient.

SE UENCES OF EVENTS AND SYSTEMS OPERATION

Refer to the PVNGS FSAR Appendix 15A for a description of the event

assumptions. In addition, Table 1 of this Attachment 1 provides the sequence

of events and setpoint values used for the revised steam generator tube

rupture analysis. The sequence of events and setpoint values are identical to

those described in the PVNGS FSAR Appendix 15A, through 1015 seconds, at which

time it was assumed the operator initiated auxiliary pressurizer spray. This

reanalysis conservatively assumes no initiation of auxiliary pressurizer spray

and opening of the pressurizer gas vent two hours into the event. By delaying

opening of the pressurizer gas vent to this time, the primary to secondary

tube leak is maximized and therefore, the 0-2 hour exclusion area boundary

(EAB) radiological consequences are maximized. Most of the radioactive

releases contributing to the dose at the low population zone (LPZ) occur inthe first two hours. At 8 hours, plant conditions are such that the operator

initiates shutdown cooling system operation and the radioactive releases from

the plant are terminated. The opening of the pressurizer gas vent at 2 hours

permits gradual venting of the pressurizer steam bubble causing slow recovery

of the pressurizer level.'hen the level is sufficiently high, the operator

is permitted to throttle the high pressure safety injection (HPSI) pumps which

results in a RCS depressurization.

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Due to the delay in operator intervention from 1015 seconds to 7200 seconds,

resulting in an increased primary to secondary leak rate, the steam generator

tubes are covered at 1347 seconds which is slightly earlier than the PVNGS

FSAR Appendix 15A analysis. Approximately 25 minutes after the pressurizer

gas vent is opened, pressurizer level is regained. The operator then controls

the HPSI flow to allow RCS depressurization and reduce the primary to

secondary leak flow rate. At 22,106 seconds, the operator closes the

pressurizer gas vent and uses the backup pressurizer heaters to maintain the

20'F subcooling criteria. 't 28,800 seconds, the operator activates the

shutdown cooling system. The dynamic behavior'f important NSSS parameters

following this revised steam generator tube rupture analysis are provided inFigure 1-14 of this Attachment l.

ANALYSIS OF EVENTS AND CONSE UENCES

The mathematical model used for this analysis is described in CESSAR Section

15D.3.1.A.

RADIOLOGICAL CONSE UENCES

The physical model is the same as that discussed in CESSAR Section 15D.3.2

except that the ADV of the affected steam generator opens fully. In order to

reduce the radiological releases, the operator takes appropriate actions to

cover the U-tubes of the affected steam generator. Actions assumed in thisanalysis included overriding the automatic isolation of Auxiliary Feed Water

(AFW) flow to the affected steam generator and diverting the flow of both AFW

pumps to the affected steam generator.

The mathematical dose model is as described in CESSAR Section 15D.3.2.C.

The assumptions and conditions employed for the evaluation of radiologicalreleases are the same as those discussed in CESSAR Section 15D.3.2.B with the

exceptions of assumptions 7, 9, and 10. The assumptions used in this analysis

are:

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7. During the period when the water level in the affected steam generator isabove the top of the U-tubes, the portion of the leaking primary fluidwhich flashes to steam upon entering the steam generator is assumed to be

released to the atmosphere with a decontamination factor (DF) of 1.0.The portion'f the leaked fluid that does not flash, mixes with the

liquid in the steam generator and is released to the atmosphere with a DF

of 100. During that period when the water level is below the top of the

U-tubes, it is assumed that all the activity associated with the leakingprimary fluid escapes to the atmosphere with a DF of 1.0, which is more

conservative than the CESSAR assumptions. No credit is taken for the

presence of steam separators and dryers which would retain a part of the

escaping primary liquid in the steam generator.

9. The 0-2 hour and 2-8 hour primary-to-secondary leakage through the

rupture are 447,600 ibm and 814,100 ibm, respectively.

10. The PVNGS site specific atmospheric dispersion factors employed in the-4 3

analyses are: 3.1 x 10 sec/m for the exclusion area boundary and-5 35.1 x 10 sec/m for the low population zone.

The two-hour exclusion area boundary (EAB) and the eight-hour low population

zone (LPZ) boundary inhalation doses for both the Generated Iodine Spike (GIS)

and the Preaccident Iodine Spike (PIS) are presented in Table 2 of thisAttachment 1. The calculated EAB and LPZ doses are well within the acceptance

criteria of 10CFR Part 100. The dose results from the PVNGS FSAR Appendix 15A

are also provided in Table 2 for reference.

CONCLUSIONS

Assuming the APSS is not actuated throughout the entire event, and that the

pressurizer gas vent is opened at two hours after the event, the radiologicalreleases calculated for the SGTR event with a loss of offsite power and a

fully stuck open ADV are well within the acceptance criteria of 10CFR100. The

secondary system pressures are well below 110X of the design pressure limitsensuring the integrity of these systems.

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REFERENCES

(1) Letter from E. E. Van Brunt, Jr., ANPP, to G. W. Knighton, NRC, dated

September 19, 1984, ANPP-30572. Subject: Steam Generator Tube Rupture

Analysis.

(2) Letter from E. E. Van Brunt, Jr., ANPP, to G.'. Knighton, NRC, dated

October 5, 1984, ANPP-30746. Subject: , Steam Generator Tube Rupture

Analysis.

(3) Letter from E. E. Van Brunt, Jr., ANPP, to, G. W. Knighton, NRC, dated!

October 24, 1984, ANPP-30938. Subject: Steam Generator, Tube Rupture

Analysis.

(4) Letter from E. E. Van Brunt, Jr., ANPP, to G. W. Knighton, NRC, dated

October 15, 1985, ANPP-33713. Subject: Auxiliary Pressurizer Spray

Design.

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TABLE 1

SE UENCE OF EVENTS FOR A STEAM GENERATOR TUBE

RUPTURE WITH A LOSS OF OFFSITE POWER

AND FULLY STUCK OPEN ADV

(Auxiliary Spray System Inoperable)(Sheet 1 of 3)

(8ec) EventSetpoint*or Value Success'Path or Comment

0.0

40

40

47

47.15

48

51

Tube Rupture Occurs ~

Third Charging Pump Started,feet below program level

-0.75

CPC Hot Leg Saturation TripSignal Generated

Trip Breakers Open

Turbine/Generator Trip

Loss of Offsite Power

Letdown Control Valve ', -0.75Throttled Back to Minimum Flow,feet below program level

Primary System IntegrityI

t\

Primary System"Integrity

Reactivity Control

Reactivity Control

Secondary System Integrity

52

52

LH Main Steam Safety ValvesOpen, psia

RH Main Steam Safety ValvesOpen, psia

1265

1265

Secondary System Integrity

Secondary System Integrity

56

121

Maximum SteamGenerator PressuresBoth Steam Generators, psia

Steam Generator Water LevelReaches Auxiliary FeedwaterActuation Signal (AFAS)Analysis Setpoint in UnaffectedGenerator, percent wide rangelevel

1330

25 Secondary System Integrity

122 AFAS Generated

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TABLE 1

SE UENCE OF EVENTS FOR A STEAM GENERATOR TUBERUPTURE WITH A LOSS OF OFFSITE POWER

AND FULLY STUCK OPEN ADV(Auxiliary Spray System Inoperable)

(Sheet 2 of 3)

(Sec) EventSetpoint*or Value Success Path or Comment

131

132

Steam Generator Water LevelReaches AFAS Analysis Setpointin the Affected Generator,percent wide range level

AFAS Generated

25 Secondary System Integrity

167.0 Auxiliary Feedwater Initiatedto Unaffected Steam Generator

Secondary System Integrity

177.0 Auxiliary Feedwater Initiatedto Affected Steam Generator

Secondary System Integrity

460 Operator Initiates PlantCooldown by Opening One ADVon Each SG —ADV of theAffected SG InstantaneouslyOpens Fully

Reactor Heat Removal

484 Pressurizer Empties

513 MSIS Actuation, SecondaryPressure, psia

919 Secondary System Integrity

535 Automated Isolation of AFW toAffected SG, hP SGs, psi

581 Pressurizer Pressure ReachesSafety Injection ActuationSignal (SIAS) AnalysisSetpoint, psia

581 Safety Injection ActuationSignal Generated

185

1578(1837)

Secondary System Integrity

Reactivity Control

581 Safety Injection FlowInitiated

Reactivity Control

655 Operators Overrides the AFW

Isolation Signal and StartsFeeding the Affected SG withAFW

-7-

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TABLE 1

SE UENCE OF EVENTS FOR A STEAM GENERATOR TUBERUPTURE WITH A LOSS OF OFFSITE POWER

AND FULLY STUCK OPEN ADV(Auxiliary Spray System Inoperable)

(Sheet 3 of 3)

(Sec) EventSetpoint*or Value Success Path or Comment

775

895

Operator Takes Manual Controlof the AFW System, FeedsAffected SG with Both AFW

Pumps

Operators Shuts the ADV ofthe Unaffected Steam Generator

1347

7200

Level in the Affected SG Abovethe Top of U-tubes, percentwide range

Operator Opens PressurizerSteam Vent

71.5

8666

8906

Pressurizer Level, percent

Operator Throttles HPSI PumpFlow to Allow RCS Depressuriza-tion and Reduce the LeakFlow Rate

33

221106

28,800

Pressurizer Heaters Actuated,Pressurizer Gas Vent Closedto Maintain SubcoolingCriteria, 'F

Shutdown Cooling EntryConditions are Reached RCS

psia/'F

20

400/350

28,800 Operator Activates ShutdownCooling System

Where the Technical Specification (TS) Setpoint is different from whatwas used, the TS value is listed in parenthesis for reference.

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TABLE 2

RADIOLOGICAL CONSE UENCES OF THE STEAM GENERATOR

TUBE RUPTURE WITH A LOSS OF OFFSITE POWER

AND FULLY STUCK OPEN ADV(Auxiliary Spray System Inoperable)

Offsite Doses Rems

Location

l. Exclusion Area Boundary0-2 hr. Thyroid

2. Low Population Zone OuterBoundary 0-8 hr. Thyroid

GIS

, 22

PIS

208

44

RADIOLOGICAL CONSE UENCES'OF THE STEAM GENERATOR

TUBE RUPTURE WITH A LOSS OF OFFSITE POWER

AND FULLY STUCK OPEN ADVAPSS OPERATION AT 1015 SECONDS

(PVNGS FSAR APPENDIX 15A)

Offsite Doses Rems

Location GIS PIS

l. Exclusion Area Boundary0-2 hr. Thyroid

2. Low Population Zone OuterBoundary 0-8 hr. Thyroid

40

20

200

41

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FI6IJRE 1

CORE POWER VS. Tlj'1E

(SHEET 1 OF 2)

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

100

80

60

00

20

.0 1200 2400 5600 4800

TINE,'ECONDS

6000 720I

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I'

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 1

CORE POWER VS. TIME

(Sheet 2 of 2)

120

- 100

I—„

I

800

CLI

GG

CL

40

Qi

5000 10000 15000 20000 25000 30000TIME SECONGS

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FIGURE 2

RCS PRESSVRE VS. TINE

.(SHEET 1 OF 2)

STEAM GENERATOR TUBE RUPTUREWITH IOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

2500

2000

li00

oooo

500

03.200 2000 5600

TINE,'ECGNDS

~800 6000 72Ca

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

. Figure 2

RCS PRESSURE VS. TIME

(Sheet 2 of 2)

2SGQOperator'takes control of plant -'pens one ADV in each Sfl

2000 Operator opens pressurizer steam vent

1500Operator throttles HPSI flow toreduce RCS'ressure whils maintainingpressurizer level and 20 F subcoolinq

1000

SGO RCS reaches shutdowncooling entry conditions

0,,

5000 10000 15000 20000 25GOQ 30000,TIME SECONOS

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

FIGURE 3

{:QRP COOLANT TENPERATURES VS, TII'IE

(SHEET 1'OF 2)

650

S75

~HOT LEG

cn 50Q

I'25 AVERAGE

35Q

COLO L

2?5

1200 2400 '600 4800 6000 7"CQ

TtSE, SECONDS

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I

I

II'!

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 3

CORE COOLANT TEMPERATUREVS. TIME

(Sheet 2 of 2)

575

500 HOT LEG

425 AVERAGE

275

COLD LEG

2000 5000 10000 15000 20000 '5000. 30000

TINE. SECONDS

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1'

4

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FIGURE '4

UppER Hgg T@pERATURE YS, TINE

(SHEET 1 OF 2>

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

.' '00

550

500

450

400

5001200 2400 5600

TIi'IE, SECONDS

4800 6000

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,II

t

l

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STEAM GENERATOR TUBE RUPTURE

WITH LOSS OF OFFSITE POWER ANE

A FULLY STUCK OPEN ATMOSPHERIC

DUMP VALVE,(ASSUMING AUXILIARYPZR SPRAY IS INOPERABLE)

Figure 4

UPPER HEAD TEMPERATURE VS. TIME

(Sheet 2 of 2)

650

600

55G

I— ~

5GO

450

400

5000 10000 15000 20000 25000 30000TINE, SECONDS

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!

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE {ASSUMINQ AUXILIARY

PZR SPRAY IS INOPERABLE)FIr.USE 5

PRESSURI2ER MATER VOLUNE VS, TINE

(SHEET' OF 2)

20QQ

1500

1000

SOO

-5001200 2000 3600

TlNE, SECONDS

~SCO 66'4 J 7200

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 5

PRESSURIZER WATER

VOLUME VS. TIME

(Sheet 2 of 2)

2000

1500

OPERATOR THROTTLES HPSI FLOW TO REDUCE RCS

PRESSURE WHILE MAINTAININGPRESSURIZER

LEVEL AND 20 F SUBCOOLING

1000

SQO

0 OPERATOR OPENS''PRESSURIZERSTEAM VENT

-5000 5000 10000 15000 20000 25000 30000

TINE SECONGS

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)FIGURE 6

LAID L~yEL ggyP 7)p OF HOT LEGS

(SHEET 1 OF 2>

ZOOO

TOP OF Rv

- 1600

1200

800

a 000

TOP OF HOT LEG

00 1200 2000 560Q 4800 6000

TIiNE, SECONDS

7)PIO

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,0 0,

If

li

III

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERIC

DUMP VALVE (ASSUMING AUXILIARYPZR SPRAY IS INOPERABLE)

Figure 6

LI(UID LEVEL ABOVE TOPOF HOT LEGS

(Sheet 2 of 2)

2000

1600

Top of Reactor Vessel

I—CD

1200CD

I—UJ 4)

e

C C~

800UJ)CD

400

00 5000 10000 15000

Top of HotLegs

0 0

TIME, SECONDS

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ll

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FIGURE 7

RC$ LIQUID NASS VS, TINE

(SHEET 1 0F 2)I

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

@no

550

5On

1200 2400 5600 4809

TI~E, SECONDS

6000 7200

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 7

RCS LIgUID MASS VS. TIME

(Sheet 2 of 2)

700000

650000

600000

A

55GOOO

5GOOOO

450000

4ooaao0 5000 10000 15000 20000 25000 3000

TINE, SECONDS

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P

i

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMINQ AUXILIARY

PZR SPRAY IS INOPERABLE)

FIGURE 8

STEN GENERATOR PRESSURE VS, TINE

(SHEET 1 OF 2)

1000

1200

IOOO

800

600 IJNFFECTED SS

200

1200 2400 3600 4800TtrlE, SECONDS

7200

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L

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1400

e

Figure 8

'TEAM GENERATOR PRESSURE

VS. TIME(Sheet 2 of 2)

STEAM GENERATOR TUBE RUPTURE

WITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERIC

DUMP VALVE (ASSUMING AUXILIARYPZR SPRAY IS INOPERABLE)

1200

1000

MSIVS CLOSE

800

600

400UNAFFECTED SG

200 ~AFFECTED SG

05000 10000 15000 20000 25000 30000

TIME SECONDS

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)FIGURE 9

I,INTEGRATED ARI Ff OIP| TO AFFECTED SG VS, TIt'IE

.(SHEET 1,0F 2>

800

CD

600

I~<00

200

1200 2~OO 3i00 4800 6000 7,| g

TI~E, SECONDS

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I

0 0

I

!1

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STEAM GENERATOR TUBE RUPTUREPITH LOSS OP OPESITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 9

INTEGRATED AFM FLOW TOAFFECTED STEAM GENERATOR VS. TIME

(Sheet 2 of 2)

1 2E+06

1 OE+06

800000

C5

600000

400000

200000

ip5000 10000 15000 20000 25000 3000(

TINE. SECONDS

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j

t

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FIGURE 10

TUBE LEAK RATE VS TIL'lE

(SHEET 1 OF 2)

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

70

w 50

00

3'0

10

1200 2'0 5600

TAHE, SECONDS

~800 6000 72QG

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 10

TUBE LEAK RATE VS. 'TIME

(Sheet 2 of 2)

70

60

PressurizerSteam Vent Opened

40

30OperatorOpens AOV

20

10,5000 10000 15000 200QO 25000 30000

TINE, SECONOS

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II

II

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FIGURE 11

INTEGRATED LEAK FLQH VS. TIPIE

(SHEET 1 OF 2)

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

1200

IQOO

n 800

Q

600

000

200

1200 2400 3600 'SCOTIME, SECONDS

6000 7<".0

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f

~ Y

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1.2E+06

Figure 11

INTEGRATEO LEAK FLOW

VS. TIME

(Sheet 2 of 2)

STEAM GENERATOR TUBE RUPTURE

WITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

1.0E+06

800000

A

C)

~ ~ 600000Cl

400000

200000

05000 10000 15000 20QOO 25000 3000(

TINE SECONDS

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I

l

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0STEAM GENERATOR TUBE RUPTURE

WITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

FIGURE 12

FRACTION OF LEAKED ACTIVITY

RELEASED IMMEDIATELYVS. TIME

(SHEET 1 of 2)

1200 2400 3600

Ttr~f, SKCG'rOS

~HQQ

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1

~ I

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0

Figure 12

FRACTION OF LEAKED ACTIVITY

RELEASED IMMEDIATELYVS. TIME

(Sheer 2 of 2)

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

F 16

F 12

~ 08

~ 04Affected Steam t)eneratorLevel Above Top of

U-Tubes

~ 005000 10000 15000 20000 25000 30000

TINE. SECONOS

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l

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FIGURE 13

STEN GENERATOR NASS YS,. TII1E

,(SHEET 1,0F 2)

STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

AFFECTED SG

UVi AFFECTED SG

1200 2400 5600 6000 7200

TINE, SECONDS

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

Figure 13

STEAM GENERATOR MASS

VS. TIME

(Sheet 2 of 2)

S40000

450000

360000

270000AFFECTEDSTEAM GENERATOR

18GQOO UNAFFECTEDSTEAM GENERATOR

90000 ~ OPERATOR FEEDS AFFECTED STEAN

GENERATOR WITH BOTH AFW PUMPS

00 SGOQ 10000 1SGOO 20000 2SGOQ 3000C

TIME . SECONDS

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II

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER ANDA FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)FI6URE 10

IATE(yTg) g)V FLOW VS.. TINE

(SHEET 1 OF 2)

15CO

1200

900

600

500

0

0 1200 2400 5600 4800

TtHE; SECONDS

6000 7200

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I(

f"

4

t

t

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STEAM GENERATOR TUBE RUPTUREWITH LOSS OF OFFSITE POWER AND

A FULLY STUCK OPEN ATMOSPHERICDUMP VALVE (ASSUMING AUXILIARY

PZR SPRAY IS INOPERABLE)

1 8E+06

Figure 14

INTEGRATED ADV fLOW

VS. TINE

(Sheet 2 of 2)

1.5E+06

o 1..ZE+06)C5

ClI-

900000

600000

'00000

5000 10000 15000 20000 25000 3000TIME SECON'OS

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II

yl

h

t

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ATTACHMENT 2

SCHEDULE FOR IMPLEMENTATION

OF MODIFICATIONS DESCRIBED IN

ANPP 33713 J DATED OCTOBER 15 ~ 1985

Three modifications were discussed in detail in Attachment 3 of Reference l.These modifications can be briefly described as: 1) provide power to Valves

CH-501 and CH-536 from a lE Motor Control Center (MCC), 2) enhanced automatic

realignment to the refueling water tank (RWP) and, -3) enhanced volume control

tank (VCT) level instrumentation.

The schedule for implementation for all of the modifications for each PVNGS

Unit is as follows:

PVNGS Unit 1: Following completion of engineering and procurement,

currently in process, implementation will be during the

first outage of sufficient duration but not later than the

completion of the first refueling outage.

PVNGS Unit 2: Prior to exceeding 5% power.

PVNGS Unit 3: Prior to fuel load.

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I

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REFERENCES

(1) Letter to G. V. Knighton, NRC, from E. E. Van Brunt, Jr., ANPP, dated

October 15, 1985 (ANPP-33713); Subject: Auxiliary Pressurizer Spray

Design

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ATTACHMENT 3

ADDITIONALCONSIDERATIONS TO

ANPP 33713@ DATED OCTOBER 15'985

In addition to the items already considered in Reference 1, the NRC staffrequested that ANPP review four additional areas of concern. The descriptionand results of ANPPs evaluation for each of the items are described below.

Item 1: RWZ Level Evaluation

&e NRC concern was with respect to the availability of the auxiliarypressurizer spray system (APSS) for the Steam Generator Tube Rupture (SGTR)

event as described in Reference 1 (APSS actuation at 7200 seconds into theevent). The concern is based on the fact that the charging pumps (which

provide flow for the APSS) draw their suction from the high suction nozzle on

the refueling water tank (RWl').

Assuming that the RWT level is at its low level alarm setpoint, there would

still be 25,000 gallons of water above the high suction nozzle in the RUT when

the operator actuates the shutdown cooling system and the auxiliarypressurizer spray system is no longer needed. Even if the RVZ levelcorresponds to the Technical Specification minimum required volume, the RNT

level would not drop below the high suction nozzle until after approximately5-1/2 hours following event initiation. The referenced analysis indicatesthat the RCS pressure and temperature at this time would be approximately 260

psia and 390- F, respectively. A more aggressive cooldown would allow normal

shutdown cooling entrance conditions to be reached within 5-1/2 hours insteadof the currently assumed value of 8 hours. In addition; 5-1/2 hours is ample

time for the operator to realign the charging pump suction to the lower nozzle

on the RNT. Therefore, the RNT has sufficient inventory to satisfy the amount

of water required for APSS availability.

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$

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Item 2: Verification of ui ent Qualification

The NRC requested that ANPP verify that Valve CH-239 and the heat exchanger

CHE-E01 are qualified.

CH-239 — Fisher pneumatically operated valve has been verified to meet therequirements of the mechanical equipment and seismic qualification

programs'he

ASCO solenoid has been verified to meet the requirements of theenvironmental and seismic qualification programs.

The NAMCO position switches have been verified to meet the

requirements of the environmental and seismic qualification. programs.

CHE-EOl — Regenerative heat exchanger has been verified to meet the'equirementsof the mechanical equipment and seismic qualification

programs.

Item 3: Descri tion of Preventative Maintenance (PM) Pr ram and ASME Section

~XI Testin

lhe NRC has requested that ANPP provide a description of the PM program

performed on the volume control tank (VCT) level instrumentation and the ASME

Section XI testing that is performed on Valves CH-239, CH-240 and CH-501.

These descriptions are provided below.

PM on The VCT Level Instrumentation

'lhe water level in the reference leg is checked daily. This check consists of

connecting a pressurized water source to the reference leg and monitoring the

VCT level transmitter output (via a trace from the plant computer) for any

change in the VCT indicated level. If the data obtained justifies a less

frequent monitoring interval, ANPP will propose a different interval to the

NRC staff.

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t

r

I

p

]

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ASME Section XI Testin Pro ram on Valves CH-239 CH-240 and CH-501

These valves will be tested as part of the Section XI valve testing program.

These valves will be full stroke tested during cold shutdowns per ASNE SectionXI Article IWV-3412.

Item 4: Valves CH-532 and CH-524

To ensure a flow path to the APSS, ANPP will lock open Valves CH-524 and

CH-532. In addition to locking open CH-524, MPP will also remove power fromthe valve. Implementation of these modifications, for each PVNGS Unit, willbe performed consistent with the schedule provided in Attachment 2 of thisletter.

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0 I4

I

II

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REFERENCES

(1) Letter to G. W. Knighton, NRC, from E. E. Van Brunt, Jr., ANPP, dated

October 15, 1985 (ANPP-33713); Subject: Auxiliary Pressurizer Spray

Design

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~

~a

P

4

1

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~ AR s I)$' 'ISTRIBUTION

0~et-Fi.l e~LPDRPRC SystemPBD7 ReadingJLee

DOCKET NO(S). STN 50-528Hr. E. E. Van Brunt, JreExecutive Vice PresidentArizona Nuclear Power ProjectPost Office Box 52034Phoanic,, Arizona„ 85072-2034

SUBJECT: ARIZONA PUBLIC SERVICE COIIPANYPALO VERDE NUCLEAR GENERATING STATION, UNIT 1

The following documents concerning our review of.the subject facility are transmitted for your information.

D Notice of Receipt of Application, dated

D Draft/Final Environmental Statment, dated

CI Notice of Availabilityof Draft/Final Environmental Statement, dated

CI Safety Evaluation Report, or Supplement No. , dated

CI Notice of Hearing on Application for Construction Permit, dated

D Notice of Consideration of Issuance of Facility Operating License, datedB4-Meekly

Ijg)ggggp Notice; Applications and Amendments to Operating Licenses Involving:no Significant HazardsConsiderations, dated 2).

O Application and Safety Analysis Report, Volume

D Amendment N'o. to Application/SA R dated

D Construction Permit No. CPPR-

O Facility Operating License No.

, Amendment No.

, Amendment No.

dated

, dated

O Order Extending Construction Completion Date, dated

D Other (Specifyf

Enclosures:As stated

Office of Nuclear Reactor Regulation

'ee next page

OPSICK~

SURNAME&

OAVe> 86~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~

NRC FORM 3'18 (1/84) NRCM 0240

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r ~

~ ~

~~

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~S AE00P

+ OCy A,

0O

I

O

IP+%*4+

t~ j+UNtTED STATESNUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

kNR 3 lauu

DOCKET NO(S). STN 50-528Nr. E. E. Van Brunt, Jr.Executive Vice PresidentArizona Nuclear Power ProjectPost Office Box 52034Phoenix, Arizona 85072-2034

~ SUBJECT: ARIZONA PUBLIC SERVICE COMPANYPALO VERDE NUCLEAR GENERATING STATION, UNIT 1

The following documents concerning our review of the subject facility are transmitted for your information.

D Notice of Receipt of Application, dated

D Draft/Final Environmental Statment, dated

D Notice of Availabilityof Draft/Final Environmental Statement, dated

D Safety Evaluation Report, or Supplement No. , dated

D Notice of Hearing on Application for Construction Permit, dated

D Notice of Consideration of Issuance of Facility Operating License, datedBi-Meekly

GB NCN8$ Notice; Applications and Amendments to Operating Licenses Involving no Significant HazardsConsiderations, dated 2 12 86 See a e 5282) .

D Application and Safety Analysis Report, Volume

D Amendment No. to Application/SAR dated

D Construction Permit No. CPPR-, Amendment No. dated

D Facility Operating License No. , Amendment No. , dated

D Order Extending Construction Completion Date, dated

D Other (Specify)

Office of Nuclear Reactor Regulation

Enclosures:As stated

cc'ee next page

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-- rv ~

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Hr. E. E. Van Brunt, Jr.Arizona Nuc>ear Power Proiect Pal o Verde

CC:Arthur C. Gehr, Esq.Snell 5 Wilmer3100 Valley CenterPhoenix, Arizona 85073

- Nr. James N. Flenner, Chief CounselArizona Corporation Commission1200 West WashinqtonPhoenix, Arizona 85007

Charles R. Kocher, Esq. AssistantCouncil

James A. Boeletto, Esq.Southern California Edison CompanyP. 0. Box 800Rosemead, California 91770

Nr. Nark GinsbergEnerqy DirectnrOffice of Economic Planninq

and Development1700 West Washinaton - 5th floorPhoenix, Arizona 85007

Mr. Wayne ShirleyAssistant Attorney GeneralBataan Memorial BuildinqSanta Fe, New Mexico 87503

Nr. Roy ZimmermanU.S. Nuclear Regulatory CommissionP. 0. Box 239Arlington, Arizona 85322

Ns. Patricia Lee Hourihan6413 S. 26th StreetPhoenix, Arizona 85040

Regional Administrator, Reqinn VU. S. Nuclear Requlatory Commission1450 Maria LaneSuite 210Walnut Creek, California 94596

Kenneth Berlin, Esq.Winston & StrawnSuite 5002550 M Street, NW

Washinaton, DC 20037

Ns. Lynne BernabeiGovernment Accountability Proiect

of the Institute fnr Policy Studies1901 Que Street, NW

Washinqton, DC 20009

Ns. Jill Morrison522 E. ColgateTemoi, Arizona 85238

Mr. Charles B. Brinkman, ManagerWashinaton Nuclear Opera tinnsCombustion Engineering, Inc.7910 Woodmont Avenue Suite 1310Bethesda, Maryland 20814

Nr. Ron RavnerP. 0. Box 1509Goodyear, AZ 85338

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ChairmanArizona Corporation Commission2222 West WashingtonPhoenix, Arizona 85007

Arizona Radiation Regulatory AgencyATTN: Ms. Clara Palovic, Librarian925 South 52nd StreetTempe, Arizona 85238

Hr. Charles Tedford, DirectorArizona Radiation Regulatory Agency924 South 52nd Street, Suite 2Tempe, Arizona 85281

ChairmanMaricopa County Board of SupervisorsillSouth Third AvenuePhoenix, Arizona 85003

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