JPN-96-020, Submits Revised Response to Rev 1,Suppl 1 GL 92-01, Rv Structural Integrity

Submits Revised Response to Rev 1,Suppl 1 GL 92-01, Rv Structural Integrity

ML20108D151
Person / Time
Site:	FitzPatrick
Issue date:	05/02/1996
From:	William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, JPN-96-020, JPN-96-20, NUDOCS 9605070301
Download: ML20108D151 (7)

Text

. 123 Main Stuet i

, Whe P:ains. New York 10601

, , 914-681-6840 914-287-3309 (FAX)

. William J. Cahill, Jr.

U$0nh Ch!ef Nuclear 0+ feer May 2,1996 JPN-96-020 l U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D.C. 20555 l Subjact: James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 i Generic Letter 92-01, Revision 1, Supplement 1 j Reactor Vessel Structural Inteority - Revised Sir Month Resoonse

References:

1. NYPA let+er, W. J. Cahill, Jr. to USNRC (JPN-95-050), " Generic Letter 92- j 01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity - Six Month Response," dated November 20,1995.

2. NRC Generic Letter 92-01, Revision 1, Supplement 1, " Reactor Vessel Structural Integrity," dated May 19,1995.

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Dear Sir:

, This letter submits a revised Attachment 1 to replace the Attachment 1 submitted with Reference 1. The revised attachment corrects the value for the revised nickel content for weld wire heat numbers 13253/12008 as shown in the table on page 1 of Attachment 1. The revision changes the nickel content value reported in the table from 0.060 % to 0.804 %,

which is consistent with the data shown in Attachment 2 of Reference 1. This resulted from an incorrect transfer of data during the preparation of the submittal.

j Reference 1 reported new chemistry data pertinent to the analysis of structuralintegrity of the FitzPatrick reactor pressure vessel (RPV), and was in response to an NRC request (Reference 2). Since the correct chemistry values were considered in the analysis performed pursuant to Reference 2, the revision discussed above does not change the conclusions, as previously reported in Reference 1, that the new chemistry data confirms the validity of the RPV temperature limits in the Technical Specifications, and confirms compliance with the structuralintegrity requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50.

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There are no new commitments associated with this submittal. If you have any l questions, please contact Ms. C. D. Faison. ,

I Very truly yours, William J. ahill, Jr. l' Chief Nuclear Officer l

STATE OF NEW YORK COUNTY OF WESTCHESTER Subscriped and sworn to before me thi

• day of , 1996.

• / M i otary Public /  % sm att: as stated Ys%gg &w

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4 cc: Regional Administrator - Region l l U.S. Nuclear Regulatory Commission l 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Ms. K. Catton, Acting Project Manager Project DL ectorate 1-1 Division at Reactor Projects 1/11 U.O. Nuclear Regulatory Commission Washington, DC 20555 t

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l ATTACHMENT TO JPN-96-020 8

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Attachment 1, Revision 1, to JPN-95-050 Generic Letter 92-01, Revision 1, Supplement 1 l Reactor Vessel Structural Integrity - Six Month Response

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i for j James A. FitzPatrick Nuclear Power Plant

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4 ATTACHMENT 1, REVISION 1, to JPN-95-050 1

GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 REACTOR VESSEL STRUCTURAL INTEGRITY - SIX MONTH RESPONSE for James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 l

l New York Power Authority

9 Attachment 1, Revision 1, to JPN-95-050 James A. FitzPatrick Nuclear Power Plant l

Docket No. 50-333 Generic Letter 92-01, Revision 1, Supplement 1 Reactor Vessel Structural intearity - Sir Month Resoonse This report provides a response to information requested in Parts 2,3, and 4 of NRC Generic Letter 92-01, Revision 1, Supplement 1, for the James A. FitzPatrick Nuclear Power Plant.

Agagssment of Channes in Best-Estimate Chemistry NRC Request (GL 92-01, Rev.1, Supp.1, Part 2):

Provide an assessment of any change in best-estimate chemistry based on consideration of all relevant data, j 1

Response: l The search of available data bases confirms that the baseplate chemistry (copper-nickel content) remains unchanged. The confirmation consisted of reviewing the actual material certifications from the plate mill, the NRC Reactor Vessel Integrity Database-Summary File for Upper Shelf Energy and Summary File for PTS, and, for copper, data from the plate manufacturer. The copper content data is based on ladle analysis values. The nickel content data is based on check analysis values.

The search of the available data bases resulted in the following changes in the weld chemistry data associated with the circumferential and axial welds in the beltline region:

Heat No. Previous Copper Revised Copper Previous Nickel Revised Nickel Weld Content % Content % Content % Content %

3253/12008 0.26 0.253 0.87 0.804 l i Lwr-Int. Shell Axial  !

27204/12008 0.25 0.183 0.99 1.008 Lwr. Shell Axial 305414 0.33 0.337 0.59 0.600 Circ.

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The search located 10 datapoints for Heat No. 13253/12008,6 datapoints for Heat No. i 27204/12008, and 4 datapoints for Heat No.305414. The revised values in the table above l were computed by averaging the datapoints. The sources of the weld chemistry data are: 1 i e NRC - Reactor Vessel Integrity Database, Version 1.1, July 1995 ,

I j e WOG - Reactor Vessel Database RPV Data, September 1995 (pre-release version) l l

a See Attachment 2 for a compilation of the plate and weld chemistry data identified, and j i the calculation of the average chemistry content considered in the evaluation.  ;

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1 Need for the Use of the Reaulatorv Guide 1.99 Ratio Procedure i 1

NRC Request (GL 92-01, Rev.1, Supp.1, Part 3) l Provide a determination of the need for use of the ratio procedure in accordance with

! the established Position 2.1 of Regulatory Guide 1.99, Revision 2, for those licensees that use surveillance data to provide a basis for the RPV integrity evaluation.

1 Response:

1 The FitzPatrick RPV material evaluations do not use the ratio procedure because only j one surveillance sample has been removed and analyzed for the FitzPatrick RPV. The l second sample is scheduled for removal during the next refueling outage.

Results of Anv Revisions to the Evaluation of RPV Intearity NRC Request (GL 92-01, Rev.1, Supp.1, Part 4)

Provide a written report providing r,y newly acquired data as specified above and (1) i the results of any necessary revisiw. to the evaluation of RPV integrity in accordance  ;

with the requirements of 10 CFR 50.60,10 CFR 50.61, Appendices G and H to 10 i CFR Part 50, and any potential impact on LTOP or P-T limits in the technical specifications or (2) a certification that previously submitted evaluations remain valid.

Revised evaluations and certifications should include consideration of Position 2.1 of '

Regulatory Guide 1.99, Revision 2, as applicable, and any new data.

Response

Cc8culations using the new chemistry data discussed above confirm that the FitzPatrick reactor vessal continues to be limited by the lower shell axial welds 2-233 A-C. The new Page 2

chemistry data results in a lower Adjusted Reference Temperature (ART) for this limiting weld.

Accordingly, the P-T curves in the FitzPatrick Technical Specifications, presented for up to12, 14, and 16 EFPY of operation, remain valid. The new calculation yields the following limiting value for the RPV:

ART @16 EFPY = 107 F (previously 116 F)

This value remains well within the lirnits of 200 F maximum for the ART. The revised chemistry values remain within the bounding chemistry assumed in the Upper Shelf Energy Equivalent Margin Analysis submitted by References 1 and 2, and approved by the NRC in Reference 3.

References:

1. NYPA letter, W. A. Josiger to NRC (JPN-94-021), " Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity," dated April 29,1994.

2. NYPA letter, W. A. Josiger to NRC (JPN-94-041), " Generic Letter 92-01, Revision 1,  !

" Reactor Vessel Structural Integrity," dated August 10,1994. I

3. NRC letter, L. B. Marsh to W. J. Cahill Jr., " Applicability of GE Topical Report NEDO-32205, Revision 1, For The James A. FitzPatrick Nuclear Power Plant (TAC No.

M89580), dated March 30,1995.

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