ML20248F358

Discusses GL 92-01,Rev 1,Supplement 1, Rv Structural Integrity, Issued on 950519 & Licensee Response for J Fitzpatrick Npp.Requests Reevaluation of RPV Weld Chemistry Values Previously Submitted

ML20248F358
Person / Time
Site:	FitzPatrick
Issue date:	06/01/1998
From:	Williams J NRC (Affiliation Not Assigned)
To:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
GL-92-01, GL-92-1, TAC-MA1190, NUDOCS 9806040210
Download: ML20248F358 (8)

Text

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2 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enmaa many t

L June 1, 1998

% * * * * * **l Mr. James Knubel

l. Chief Nuclear Officer

Power Authority of the State of l

New York 123 Main Street White Plains, NY 10601 l

l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR i

PRESSURE VESSEL INTEGRITY AT THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC No. MA1190)

Dear Mr. Knubel:

L Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity" was issued on May 19,1995. This GL requested licensees perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structuralintegrity of their RPVs

! and to assess the impact of those data on their RPV integrity analyses relative to the l requirements of 10 CFR 50.60,10 CFR 50.61,10 CFR Part 50 Appendices G and H (which i encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and l any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature l (P-T) limits.

After reviewing your response, the NRC issued you a letter dated September 6,1996 for the James A. FitzPatrick Nuclear Power Plant. In this letter, we acknowledged receipt of your response, noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant-specific TAC Number may be opened to review this material. . Following issuance of these letters, the Boiling Water Reactor Vessel and intemals Project (BWRVIP) submitted the repori" Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)." This report included bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 which contains all known data for CE fabricated welds in pressurized water i reactor and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are documented in NRC inspection Report 99901300/97-01 dated January 28,1998;

3) FTi's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T ,

limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance  ;

records. New data for one vessel fabricated by Hitachi was also included in the BWRVIP report.

l

. The staff is requesting that you re-evaluate the RPV weld chemistry values that you have ,

previously submitted as part of your licensing basis in light of the information presented in the  !

CEOG, FTl and BWRVIP reports. The staff expects that you will assess this new information to determine whether any values of RPV weld chemistry need to be revised for your facility. l Therefore, in order to provide a complete response to items 2, 3, and 4 of the GL, the NRC requests thi you provide a response to the enclosed request for additional information within 90 l days of rr eipt of this letter. If a question does not apply to your situation, please indicate this in j your RAI response along with your technical basis and, per GL 92-01, Rev.1, Supp.1, provide a  !

certification that previously submitted evaluations remain valid.

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• I June 1, 1993 J.Knubel The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).

Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potentialimpact on P-T limits. If additional license amendments or assessments are necessary, the enclosure requests that you provide a schedule for such submittals.

I If you should have any questions regarding this request, please contact me at (301) 415-1470. l Sincerely, i Original Signed by:

Joseph F. Williams, Project Manager Project Directorate I-1 l Division of Reactor Projects - 1/11 l Office of Nuclear Reactor Regulation i i

Docket No. 50-333

Enclosure:

Request for Additional Information cc w/ encl: See next page 006 dei File X l PUBLIC PDI-1 R/F J. Zwolinski (A)

S. Bajwa l J. Williams l S. Little OGC ACRS l C. Hehl, Region i DOCUMENT NAME:G:\FITZ\MA1190.RAI l To'geceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E"

=g with attachmerit/ enclosure "N" = No copy l- OFFICEN PM:PDI 1 [/I(/ lE LA:PDI1(l(_l l D:PDI-1 jd l l l j' NAME -

JWilliarrasld SLitt(e @

• SBaJwn 11V /

} DATE i $/ / /98 0$"/ 1 /98 ($/ l /98 05/ /98 05/ /98 Official Record Copy

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June 1, 1998 2

l J.Knubel The information provided wi:1 be used in updating the Reactor Vessel Integrity Database (RVID).

Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potentialimpact on P-T limits. If l additional license amendments or assessments are necessary, the enclosure requests that you l provide a senedule for such submittals.

If you should have any questions regarding this request, please contact me at (301) 415-1470.

Sincerely, Original Signed by:

Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Request for Additional Information cc w/ encl: See next page Docket File PUBLIC PDI-1 R/F J. Zwolinski (A)

S. Bajwa J. Williams S. Little OGC ACRS C. Hehl, Region I DOCUMENT NAME:G:\FITZWIA1190.RAI To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" a Copy with attachmerit/ enclosure "N" = No copy 0FFICE PM:PDI-1 [pVg/ lE LA:PDI1O{l l D:PDI 1 jd l l l !

NAME JWilliamsst/6 SLitt( M SBeJwe M/

DATE $/ / /98 Of/ I /98 $/l /98 05/ /98 05/ /98 Official Record Copy

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i J.Knube' l The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).  !

Also, please note that RPV integrity analyses utilizing newly identified data could result in the i need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potentialimpact on P-T limits. If additional license amendments or assessments are necessary, the enclosure requests that you provide a schedule for such submittals. i If you should have any questions regarding this request, please contact me at (301) 415-1470. i Sin rely, /  ;

l Joseph F. Williams, Project Manager Project Directorate 1-1  ;

Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation j Docket No. 50-333 I

Enclosure:

Request for Additional Information cc w/ encl: See next page  !

< I E.____.______________________________________-_________----.___________________________________________

- - - - - - -~~ -

'~ -

-f James Knubel James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc:

Mr. Gerald C. Goldstein Regional Administrator, Region i Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President New York State Energy, Research, Resident inspector's Office and Development Authority U. S. Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington Avenue Extension I.ycoming, NY 13093 Albany, NY 12203-6399 Mr. Harry P. Salmon, Jr., V.P. Mr. Richard L. Patch, Director Nuclear Operations Quality Assurance Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street Wriite Plains, NY 10601 White Plains, NY 10601 Ms. Charlene D. Faison Mr. Gerard Goering Director Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of New York 123 Main Street Mr. James Gagliardo White Plains, NY 10601 Safety Review Committee 708 Castlewood Avenue Supervisor Arlington, TX 76012 Town of Scriba Route 8, Box 382 Mr. Arthur Zaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41 President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State Mr. Paul Eddy of New York New York State Dept. of 123 Main Street Public Service White Plains, NY 10601 3 Empire State Plaza,10th Floor Albany, NY 12223 Chartes Donaldson, Esquire Assistant Attomey General New York Department of Law 120 Broadway New York, NY 10271

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REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY l

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Section 1.0: Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6 i Reactor Pressure Vessel integrity issues (BWRVIP-46)."

Based on this information, in accordance with the provisions of Generic Letter 92-01~ Revision 1,

- Supplement 1, the NRC requests the following:

1. An evaluation of the bounding assessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. If the limiting material for your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 l for the limiting material also.

With respect to your response to this question, the staff notes that some issues regarding the evaluation of the data were discussed in a public meeting between the staff, NEl, and industry representatives on November 12,1997. A summary of this meeting is documented in a meeting summary dated November 19,1997, " Meeting Summary for November 12,1997 Meetin0 with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses"(Reference 1). The information in Reference 1 may be useful in helping you to prepare your response.

In addition to the issues discussed in the referenced meeting, you should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best estimate chemistry. If a weld (or welds) were fabricated as weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case of tandem -

arc welds) of weld consumables, it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry determination. If information is not available to confirm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry should be evaluated both by assuming the data came from "one weld" and by assuming that the data came from an appropriate number of" multiple welds". A justification should then be provided for which assumption was chosen when the best-estimate chemistry was determined.

Section 2.0: P-T Umit Evaluation

2. If the limiting material for your plant changes or if the adjusted reference temperature for the limiting materialincreases as a result of the above evaluations, provide the revised RT, value for the limiting material. In addition, if the adjusted RTa value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR Part 50 Appendix G is maintained.

Enclosure

.e 9

Reference

1. Memorandum dated November 19,1997, from Keith R. Wichman to Edmund J. Sullivan,

" Meeting Summary for November 12,1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses."

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