ML17298B680

Forwards Draft Proposed FSAR Changes Reflecting Requirements for Condensate Storage Tank & Atmospheric Dump Valve Nitrogen Accumulator.Changes Also Reflect Util Intent to Verify Boron Mixing Under Natural Circulation

ML17298B680
Person / Time
Site:	Palo Verde
Issue date:	12/17/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
ANPP-31493-EEVB, NUDOCS 8412200226
Download: ML17298B680 (14)

Text

REGULATORY FORMATION DISTRIBUTION SY M (BIDS)

ACCESSION'BR: 8412200226 DOC, DATE! 84/12/17 NOTARIZED: YES DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station< Unit 1< Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station~ Unit 2< Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station~ Unit 3~ Arizona Publ-i 05000530 AUTH'AME AUTHOR AFFILIATION VAN BRUNTiE ~ E. Arizona Public Service Co, RECIP ~ NAME RECIPIENT AFFILIATION KNIGHTON<G.P( ~ , Licensing Branch 3

SUBJECT:

Forwards draft proposed FSAR changes reflectinp requirements for condensate storage tank 8 atmospheric dupm valve nitrogen accumulator .Changes also reflect".util intent to verify boron mixing under natural circulation, DISTRIBUTION CODE: B001D COPIES RECEIVED;LTR ENCL SIZE ~

TITLE: Licensing Submittal: PSAR/FSAR Amdts L Related Correspondence NOTES:Standardized plant ~ 05000528 Standardized plant, 05000529 Standardized plant, 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL' NRR/DL/ADL 0 NRR LB3 BC 0 NRR LB3 LA 1 0 LICITRAgE Ol 1 1 INTERNAL: ACRS 41 6 6 ADM/LFMB 0 ELD/HDS3 1 0 IE FILE 1 IE/DEPER/EPB 36 1 1 IE/DEPER/IRB 35 1 IE/DQASIP/QAB21 1 1 NRR ROEgMiL NRR/DE/AEAB 1 0 NRR/DE/CEB 11 1 NRR/DE/EHEB 1 1 NRR/DE/EQB 13 2 NRR/DE/GB 28 NRR/DE/MEB 18 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 1 NRR/DE/SGEB 25 1 1 NRR/DHFS/HFEB40 1 NRR/DHFS/LQB 32 1 NRR/DHFS/PSRB 1 NRR/Dl /SSPB 1 0 NRR/DSI/AEB 26 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 NRR/DSI/CSB 09 1 NRR/DSI/ICSB 16 1 NRR/DSI/METB 12 i NRR/DSI/PSB 19 ]<

NRR SI/RAB 22 1 1 NRR/DSI/RSB 23 1 G F IL 04 1 RGN5 3 I/MIB 0 EXTERNAL: BNL(AMDTS ONLY) 1 1 DMB/DSS (AMDTS) 1 FEMA REP DI V 39 1 LPDR 03 1 1 NRC PDR 02 1 NSIC 05 1 NTIS 1 1 PNL GRUEL'zR 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 ENCL 46

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Arizona Public Service Company ANPP-31493-EEVB/WFQ December 17, 1984 Director of Nuclear Reactor Regulation Mr. George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Natural Circulation Cooldown Testing File: 84-056-026'.1.01.10

References:

(A) Letter from A. E. Scherer, C-E, to D. G. Eisenhut, NRC, dated August 12, 1983 (LD-83-074).

(B) Letter from E. E. Van Brunt, Jr., APS, to G. W. Knighton, NRC, dated August 7, 1984 (ANPP-30141).

Dear Mr. Knighton:

As discussed with Mr. E. A. Licitra of your staff, attached are draft proposed FSAR changes for your information. These changes are necessary to make FSAR Appendix 5A consistent with the analyses and commitments provided by references (A) and (B), respectively. Specifically the draft proposed FSAR changes reflect the requirements for the Condensate Storage Tank and the Atmospheric Dump Valve Nitrogen Accumulator with regard to Branch Technical Position RSB 5-1. The attached proposed changes also reflect APS'ntent to verify adequate boron mixing under natural circula-tion conditions.

Please contact Mr. W. F. Quinn of my staff if you have any questions on this matter.

Very truly yours, E.Q.. Ua 5~g~

E. E. Van Brunt, Jr.

APS Vice President Nuclear Production ANPP Project Director EEVB/TFQ/mb Attachment E. A. Licitra R. P. Zimmerman A. C. Gehr 8412~ ooav6 <4i~~7 PDR'DO OCW 05000MB ll, .

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t ANPP-31493 STATE OF ARIZONA )

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COUNTY OF MARICOPA)

I, A. Carter Rogers, represent that I am Manager, Nuclear Engineering of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents and that to the best of my knowledge and belief, the statements made therein are true.

A. Carter Rogers Sworn to before me this ~ldey 1984.

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My Commlssjotl Expires April 6, 1987 My Commis'sion Expires:

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INSERT A to Page 5A.14 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby plus 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation to reach cold shutdown under natural circulation conditions.

INSERT B to Page 5A-15 Testing will also be conducted to verify adequate boron mixing under natural circulation conditions and the ability to perform a natural, circulation cooldown agd a plant depressurization to shutdown cooling indicating conditions.<

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PVNGS F SAR APPENDIX 5A circulation conditions must be available to the operator. Summarize these procedures.

Question Discuss the availability of the Seismic Category I auxiliary feedwater supply for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot shutdown plus cooldown to the RHR system cut-in based on longest time for the availability of only onsite or only offsite power and assuming a single failure. If this cannot be achieved, discuss the availability of an adequate alternate Seismic Category I water source.

Question 5. What provisions in natural circulation cool-down methods have been made to account for possible upper head void formation?

RESPONSE: The response will be provided on the CESSAR docket. Additional clarification is provided as follows:

l.a. PVNGS provides, as a backup to the instrument air system, safety grade nitrogen accumulators to operate the steam generator atmospheric dump

.valves (ADVs) The accumulators provide nitroge

/0 5 supply for Mhours of operation of these valves. (a)~hid e

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nitrogen accumulator is provided for each ADV. A'ne A single failure will not result in loss of capability to vent the minimum required amount of steam necessary for decay heat removal and plant cooldown.

1.b. The response to NRC Question 440.9 discusses power lockout for the safety injection tank (SIT) vent

a. Re-evaluation of the Nitrogen Accumulators to the ADVs, will be performed when the C-E Owners Group effort on NUREG-0737, Item II.K.2.17, Potential for Voiding in the Reactor Coolant System during transients, is completed.

Amendment 7 'A-14 December 1981

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PVNGS FSAR APPENDIX 5A and isolation valves. Additionally, power can be restored to the SIT vent valves from the control room to depressurize the SITs. Each SIT can be isolated or vented'rom the control room. There is no single failure which could result in the opening of all SIT isolation valves or could preclude RCS depressurization.

1.c. As stated in section 9.3.4.1, the charging pumps are not automatically sequenced onto the emergency buses. The charging pumps can be loaded onto the emergency buses from the control room.

2. RHR pressure relief discharge piping is provided with a sparger that, is located at the bottom of the containment emergency sump. On that basis, no direct steam flow would be directed toward any personnel.

3. Cooldown under natural circulation conditions was analy-tically modeled and positively confirmed following two events at an operating C-E reactor plant. St. Lucie Unit 1 (Docket No. 50-335) performed two natural circu-lation cooldowns following a reactor trip from full power conditions in 1977 and in 1980. A test to verify natural circulation for System 80 is scheduled to be

~&eM conducted as part of the power ascension testing. Bee.

San Onofre

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Unit 2 is scheduled to conduct a boron

~~se87 B mixing test during their upcoming power ascension testing. Since the boron mixing in the RCS is accomplished in a similar environment and by the same process, the San Onofre natural circulation flow boron mixing test results are considered proto-typical for the System 80 standard design. Following completion of the San Onofre test, the results will be (Q)

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1982 P)GAGS g, j. QAnt+Eo&P) 2g, GIPSY 7 I'pl'0 (Anl/'P Bord')

QM~t 5A-15 g-assessed for the applicability to System 80.

CD G, + /(<g I Amendment 8

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PVNGS FSAR APPENDIX 5A Specific natural circulation and natural circulation cooldown operator guidelines have been prepared by C-E for the C-E Owners Group. These guidelines were trans-mitted in CEN-152 to the NRC for review (June, 1981).

These guidelines provide instruction to avoid void formation in the reactor vessel upper head that could occur during natural circulation conditions. Also included are instructions that deal with the symptoms and follow-up actions for a condensable reactor vessel void if one should occur.

The condensate storage tank (CST) is discussed in section 9.2.6. The tank is designeg to provide suffici-ent auxiliary feedwater supply for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby Cmetu4iag-ee~ ~ ~

(b)

A single failure will not result in loss of water supply such that cooling to RHR initiation cannot be achieved. Pumps, valves, and piping required for essential operation are redundant, separated, and o gd~eo,/~et~~ 5 ~~ c~~~~

protected from adverse environmental effects.

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b. LD~~

D. G. Eisenhut, NRC, dated,,

Letter from A E. Scberer Report on Natural Circulation Cooldown of g-E, to CE provided a A'aV1$ 4-O System 80 NSSS.

This report verifies the CST design is adequate.

Amendment 12 5A-15A February 1984

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