ML17299A634
| ML17299A634 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/30/1985 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0857, RTR-NUREG-857 ANPP-33608-EEVB, NUDOCS 8510020009 | |
| Download: ML17299A634 (6) | |
Text
REGULATO NFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION'NBR:8510020009 OOC,DATE: 85/09/30 NOTARIZED: NO DOCKET FACIL!STN 50~528 Palo Verde Nuclear 'Stat)one Unit li Arizona Publi 05000528 STN~50 529 Palo Verde Nuclear- Station~ Unit 2i Ar)zona Publi 05000529 STN 50 530 Palo Verde Nuclear Statiani Unit 3~ Ar izona Publi 05000530 AUTH ~ NAME AUTHOR AFFII IATION VAN BRUNTiE' E ~ Arizona Nuclear Power Project (formerly Ar izona Public Serv RECIP,NAME~ REClPIENT AFFILIATION KNIGHTONiG ~ Ww, Licensing Branch 3 SUBJECT! Pravides descr iption of program to rebieW praposed changes.
to plant & potential impact on Chapter 15 analysesiper SSER 8 (NUREG."0857) ~
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Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 Director of Nuclear Reactor Regulation September 30, 1985 Attention: Mr. George W. Knighton, Chief ANPP-33608-EEVB/KLM 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 (License No. NPF-41)/529/530 Program Summary for Evaluation of Future Design Changes File: 85-056-026; G.l.01.10
References:
- 1) Safety Evaluation Report, related to the operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3, NUREG-0857 Supplement No. 8, dated May, 1985
- 2) Letter to G. W. Knighton, NRC, from E. E. Van Brunt, Jr.,
ANPP, dated April 23, 1985 (ANPP-32465);
Subject:
Revised Chapter 15 Analyses Addi,tional Information
Dear Mr. Knighton:
As required, per Reference 1), this letter provides the description of the program to review proposed changes to PVNGS and their potential impact on the Chapter 15 analyses. This program was discussed by ANPP in Reference 2).
The description of this program is as follows:
The ANPP Corporate and Station Manual Procedures incorporate provisions for review of design changes, and tests or experiments with consideration given to the potential impact on the FSAR Chapter 6/15 accident analyses. This potential impact will be noted on the 10CFR 50.59 Review and Evaluation Form. If the 10CFR50.59 Review and Evaluation results in the identification of a potential unreviewed safety question, the Manager of Nuclear Licensing is informed and is responsible for its review.
Nuclear Fuel Management will review the potential unreviewed safety question, when FSAR Chapter 6/15 accident analyses are potentially affected, per the request of the Manager of Nuclear Licensing, in accordance with established ANPP responsibility delegation. Nuclear
Mr. G. W. Knighton, Chief U. S. Nuclear Regulatory Commission Page Two ANPP-33608 Fuel Management will review those noted changes for impact on the PSAR Chapter 6/15 analyses during the course of review and dispositioning of the potential unreviewed safety question. Zn this way, "multiple" changes which may individually provide adverse impact on the accident analyses will be evaluated in concert with the combined effects of previous changes to ensure the complete impact is assessed.
Please contact Mr. W. P. guinn of my staff if you have any questions on this matter.
Very truly yours, E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/KLM/)le cc: E. A. Licitra R. P. Zimmerman A. C. Gehr
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