ML17297B781
| ML17297B781 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/08/1982 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| ANPP-22232-WFQ, NUDOCS 8211120441 | |
| Download: ML17297B781 (6) | |
Text
~AC DOCKET 05000528 05000529 05000530 REGULATORY NFORMATION DISTRIBUTION SYS EM (RIDS)
ACCESSION NBR ~ 82111204' OC ~ DATE; 82/11/08 NOTARI D t NO FAGIL:STN~50 528 'Palo Ver de Nuclear Station(
Uni,t 1(
Ar izona Publ i STN 50 529 Palo Verde Nuclear Station(
Unit 2( Arizona Publi STN"50 530 Palo Verde Nuclear Statian(
Unit 3( Arizona Publi AUTH,NAME AUTHUR AFFILIATION VAN BRUNT(E,E, Arizona Public Service Go,
>REC IP ~ NAME RECIPIENT AFFILIATION NOVAK(T,MD Assistant Directar far Licensing
SUBJECT:
Revises util 810818 response ta Open Item 50 of 810408 auxiliary >sys independent review, Emergency Cooling Water Sys.adequately designed, Tube break need not be considered as, basic design event, DISTRIBUTION CODE 8001 S COPIES 'RECEIVED I T'R ENCL SIZE!
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Arizona Public Service Company P.o. BOX 21666
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PHOENIX, ARIZONA 65036 November 8,
1982 ANPP-22232 WFQ/KEJ Mr. T.
. Novak Assistant Director for Licensing.
Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission lIJashington, D.
C.
205S5
Subject:
Palo Verde Nuclear Generating Station
,(PVNGS) Units 1, 2 and 3
Docket Nos.
STN-SO-528/S29/530 File:
82-056-026; G.1.01.10
Reference:
Letter from E. E.
Van Brunt, Jr.,
APS, to Director of Nuclear Reactor Regulation, NRC, dated August 18, 1981.
Dear Mr. Novak:
The referenced letter forwarded final responses to open items of the Auxiliary Systems Independent Design Review for PVNGS held in Phoenix, Arizona on April 8, 1981.
The resolution of item SO stated that the ECNS pressure relieving capacity would accmmodate a double-ended guillotine break of one shutdown cooling heat exchanger tube.
This letter provides a revision to that response.
The relief valves in the ECNS are sized for thermal relief only, with additional relieving capacity provided at the surge tank.
The relieving capacity is less
~
than the in-leakage from the tube break.
An evaluation on the system was made to determine if additional relieving capacity to the ECNS was needed to mitigate the effects of a tube break of one shutdown cooling heat exchanger tube.
The evaluation concluded that the system is adequately designed and recommended that no design changes be implemented.
This conclusion is based on A) a tube: break is not believed to be coincidental with a single active failure, therefore, the break need not be considered as a basic design event, B) there are two independent redundant trains for the
- EC1IJS, each train has adequate cooling capacity for safe plant shutdown in the event of failure of the other train.
, 82iif2044i 821108 PDR ADOCK 05000528 i i,,I A
PDR I
Mr. T. H. Novak November 8, 1982 ANPP-22232 WFQ/KEJ Page 2
Ne feel that the above discussion resolves the concerns of item 850 addressed in the referenced letter.
If you have any questions concerning this matter, please contact me.
Very truly yours, C4>~
E.
E. Van Brunt, Jr.
APS Vice President, Nuclear Projects ANPP Project Director EEVBJr/1ZJ/sp cc:
E. Licitra L. Bernabei P. Hourihan J. Nermiel A. C. Gehr
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