ML17312A541

Suppl Application for Amends to Licenses NPF-41,NPF-51 & NPF-74,implementing New Option B to 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.

ML17312A541
Person / Time
Site:	Palo Verde
Issue date:	02/09/1996
From:	Stwart W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17312A542	List: ML17312A541
References
102-03602-WLS-A, 102-3602-WLS-A, NUDOCS 9602220168
Download: ML17312A541 (8)

Text

CATEGORY 1 REGULATOR INFORMATION DISTRIBUTION STEM (RIDS)

ACCESSION @BR.:9602220168 DOC.DATE: 96/02/09 NOTARIZED: NO 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 Publi 05000530 AUTH. NAME AUTHOR AFFILIATION STWART,W.L. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Suppl application for amends to Licenses NPF-41,NPF-51 a NPF-74,implementing new Option B to 10CFRSO,App J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors."

DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR L ENCL SIZE: IO 8 TITLE: OR Submittal: Append J Containment Leak Rate Te ting Q

NOTES:STANDARDIZED PLANT 05000528 Standardized plant. 05000529 p Standardized plant. 05000530 R

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME "

LTTR ENCL PD4-2 LA 1 0 PD4-2 PD 1 1 HOLIANg B 1 1 THOMAS,C 1 1 INTERNAL: ACRS 6 6 LE CENTER 1 1 1 NRR/DE/ECGB 1 1 NRR DSSA SCSB 1 1 OGC/HDS2 ,1 1 RES/DE/SEB 1 1 D c

EXTERNAL: NOAC 1 1 NRC PDR 1 1 U

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL , 16

Arizona Public Service PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 PHOENIX, ARIZONA 85072-2034 102-03602-WLS/AKK/DRL WILLIAML. STEWART February 9, 1996 EXECUTIVE VICE PRESIDENT NUCLEAR U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Reference:

Letter No. 102-03567, dated December 19, 1995, from G. R. Overbeck, Vice President - Nuclear Support, APS to USNRC

Subject:

Palo Verde Nuclear Generating Station (PVNGS) ~

Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Supplement to Proposed Amendment for the Implementation of 10 CFR-Part 50, Appendix J, Option B The referenced letter requested a change to the PVNGS Technical Specifications for the purpose of implementing the new Option B to 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." In recent conversations with the Staff, APS and the Staff have agreed to minor revisions to the proposed changes to Surveillance Requirement 4.6.1.3.a, Bases 3/4.6.1.2, and Specification 6.16. Enclosure 1 contains the description and supporting justification for the proposed changes and Enclosure 2 contains the revised pages.

A copy of this letter and its enclosures have been provided to the Arizona Radiation Regulatory Agency pursuant to 10 CFR 50.91(b)(1).

Should you have any questions, please contact Scott A. Bauer at (602) 393-5978.

Sincerely, WLS/AKK/DR L/rv Enclosures cc: L. J. Callan (all w/enclosures)

K. E. Perkins B. E. Holian K. E. Johnston A. V. Godwin (ARRA) 9602220ib8 960209 PDR ADOCK 05000528 I PDR 22005g

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ENCLOSURE'I Supplement to Proposed Amendment for the Implementation of 10 CFR Part 50, Appendix J, Option B

1 A. Descri tion of the Pro osed Chan esto the Technical S ecification Amendment

~Re uest The proposed changes to the Technical Specification amendment request involve Surveillance Requirement 4.6.1.3.a, Bases 3/4.6.2.1, and Specification 6.16. The proposed changes are a result of recent discussions between the Staff and APS. The following changes are proposed:

1. Surveillance Re uirement 4.6.1.3.a is revised to read as follows:

Each containment airlock shall be demonstrated OPERABLE:

a. In accordance with the Containment Leakage Rate Testing Program at periodic intervals and following each closing as specified. The provisions of Specification 4.0.2 are not applicable to the overall airlock leakage test.

NEI 94-01, Section 10.2.2.1, "Containment Airlocks - Test Intervals" provides requirements for airlock. testing for periods of multiple containment entries. These requirements will be included in the Containment Leakage Rate Testing Program.

The revised, wording of the Surveillance Requirement will provide clearer guidance to Operations to consult the Containment Leakage Rate Testing Program for specific requirements for demonstrating airlock operability in these cases. The change eliminates the potential for interpreting the specification as requiring an airlock test following each closing during periods of multiple containment entries.

2. Bases 3/4.6.4.1.2 after "...Part 50" add "and Regulatory Guide. 1.163, dated September, 1995."

Specification 6.16 already has committed to Regulatory Guide 1.163 and the additional listing under Bases 3/4.6.1.2 is made for consistency.

S ecification 6.16 The last paragraph of the proposed Specification which discussed general visual inspections of the containment prior to Type A tests is being deleted.

This requirement will be included in the Containment Leakage Rate Testing Program and, therefore, it is redundant to address it in Section 6.16 as well.

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