ML17299A546

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Forwards,For Review,Changes to FSAR Sections 1.15 & 1.9. Changes Involve Updated Schedules for Completion & Commercial Operation Dates & Exceptions to Cessar.Changes Will Be Included in Next FSAR Update
ML17299A546
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 08/29/1985
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Knighton G
Office of Nuclear Reactor Regulation
References
ANPP-33289-EEVB, NUDOCS 8509030171
Download: ML17299A546 (15)


Text

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REGULATORY NFORMATION DISTRIBUTION S EM (RIDS)

ACCESSION NBR;850 9030171 DOC ~ DATE: 85/08/29 NOTARIZED;, YES DOCKET"'

FACIE.'tSTN"50 529 Palo Verde Nuclear Station~ Unit 2~ Arizona Publi 05000529 "STN~50-530 Palo Verde Nuclear" BYNAME Stations, Unit 3i Ar'izona Publi 05000530 AU'TH AUTHOR AfFILIATION VAN BRUNTpE ~ ED Arizona Nuclear Power Project (former ly Arizona Public Serv REC IP ~ RECIPIENT AFFILIATION NAME'NIGHTONg G iN ~ Licensing Branch 3

SUBJECT:

Forwardsifor revi ewichanges to FSAR Sections 1 15 ll 1 9; ~ ~

Changes involve u pdated schedules for completion,K commercial operat ion dates L exceptions"to CESSAR",Changes will be included in next FSAR update DISTRIBUTION CODE.:- 8001D COPIES RECEI VED: LTR ENCL>> SIZE:

TITLE:: Licensing Submittal PSAR/FSAR Amdts lt Related Correspondence'5000529 NOTES!Standardized plant.

Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME; LTTR ENCI. ID CODE/NAME LTTR ENCL' NRR/DI /ADL 1 0 NRR LB3 BC 0 NRR LB3.;LA 1 0 L'ICITRAg E 01 INTERNAL; ACRS 41 6 6 ADM/LFMB 1- 0.

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NN Arizona Nuclear Power Project P.o. 8OX 52034 ~ PHOENIX, ARIZONA85072-2034 Director of Nuclear Reactor Regulation August 29, 1985 Attention: Mr. George W. Knighton, Chief ANPP-33289-EEVB/3KO Licensing Branch 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 2 and 3 Changes to the FSAR (Chapter 1)

Docket Nos. STN-50-529/530 File: 85-056-026 G.1.01.10

Dear Mr. Knighton:

Attached for your review on PVNGS Units 2 and 3 are FSAR changes to sections 1.15 and 1.9. These changes involve: (1) updated schedules for completion and commercial operation dates; (2) exception to CESSAR Section 14.2.12.1.12 for the requirement to drain the Boric Acid Batching Tank ('BABT) to the Equipment Drain Tank (EDT); (3) exception to CESSAR Section 9.3;4.4 for the requirement that all pumps in the CVCS be tested initially to demonstrate head and capacity; (4) exception to CESSAR by deleting the necessity to test the Reactor Power Cutback System (RPCS) during five of the tests during the power ascension testing program.

We feel these changes are justified because (1) the FSAR needs to reflect the current schedules for all three units; (2) the as-built configuration does not include a drain path to the EDT, therefore, drainage from the BABT is routed to the Non-ESF Sump; (3) the Gas Stripper Pumps are not required post-accident and their only safety function is to maintain the pressure boundary; (4) deletion

, of the testing of the RPCS will not have an effect on the safety of PVNGS.

For PVNGS Unit 1, safety evaluations have been 'completed for implementation of these changes in accordance with the requirements of 10CFR 50.59. The safety reviews and evaluations have determined that- there are no unreviewed safety questions involved with the changes. These changes will be included in the next FSAR update.

G. M. Knighton

'Changes to the FSAR (Chap% 1)

ANPP-33289 Page 2 s

If you have any questions concerning these changes, please contact William Quinn of my staff.

Very truly yours, E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/MAJ/JKO/slh Attachment cc: E. A. Licitra M; Ley R. P. Zimmerman A. C. Gehr

0 STATE OF ARIZONA )

) ss.

COUNTY OF MARICOPA)

I, Edwin E. Van Brunt, Jr., represent that I am Executive Vice President, Arizona Nuclear Power Project, 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.

t Edwin E. Van Brunt, Jr.

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Swore to before me thie~cjP day of 1985.

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  • e Notary Public My Commis'sion Expires:

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tt f<l My Commfsslon Expires April 6, 9987

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PVNGS FSAR INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1.3 CONTAINMENT TYPE The containment for each unit is a single containment system consisting of a steel-lined, prestressed concrete, cylindrical structure, with a hemispherical dome. The containment struc-tures are designed by Bechtel Power Corporation (Bechtel).

1.1.4 THERMAL POWER LEVELS AND ELECTRICAL OUTPUT The rated core thermal power level at- which each NSSS will be operated is 3800 MWt plus 17'Wt net of heat from nonreactor sources, primarily pump heat, for a total of 3817 MWt for each unit.

The turbine generator electrical I

output. for 3817 MiWT is 1304 iiWe at 3.5 in. Hg abs backpressure. The nominal net output of eacn unit, is 1270 NWe.

1.1.5 SCHEDULED COMPLETION AND COMMERCIAL OPERATION DATES The scheduled completion or fuel loading dates and the

~ .scheduled commercial operation dates for PVNGS Units 1,2, and 3 are as follows:

PVNGS Scheduled Completion or Sc()eduled Commerc ie)

Unit ~eh-K ee ~ Daes 0 eration Date~"

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Not later than 1985 LaMalked QCCCtA4'L his 19gg Oe.KQ w boa.

2 Not later than Not later than g~vea~

D@C.e~t re 1985 5Qld C 1986 3 Not later than Not later than June 1987 OPLerah+n. I'QBL

a. ANPP terminology is firm power operation Gate in lieu of commercial operation date.

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The referenced Power Ascension Tests require the Reactor Power Cutback System (RPCS) to be used to maintain the NSSS within operating limits. The PVNGS testing program requires a deviation from CESSAR to allow these tests to be performed with or without the RPCS in service. The RPCS is a non-safety related control system which is described in CESSAR Section 7.7.1.1.6. The RPCS is not required to mitigate the consequences of any design basis accident and is not credited in any of the accident analyses. Failure to have the RPCS available during this testing will have no effect on plant safety since the NSSS will be controlled by several other control systems such as the RRS and the pressurizer pressure and level control systems.

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