ML20217Q676

Refers to GL 92-01,Rev 1,Supplement 1, Rv Structural Integrity, Issued in May 1995.Discusses Pse&G Responses to GL 92-01.Forwards RAI Re RPV Integrity

ML20217Q676
Person / Time
Site:	Hope Creek
Issue date:	05/04/1998
From:	Richard Ennis NRC (Affiliation Not Assigned)
To:	Keiser H Public Service Enterprise Group
References
GL-92-01, GL-92-1, TAC-MA1194, NUDOCS 9805080288
Download: ML20217Q676 (7)

Text

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Ousuq\ . UNITED STATES g' j ' NUCLEAR REGULATORY COMMISSION o 8 WASHINGTON. o.C. 30666-0001

%,g . May 4, 1998 l

Mr. Harold W. Keiser Executive Vice President-Nuclear Business Unit i Public Service Electric SiGas 1 Company Post Office Box 236 1 Hancocks Bridge, NJ 08038 l l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT HOPE CREEK GENERATING STATION (TAC NO. MA1194)

Dear Mr. Keiser:

Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity," was issued in May 1995. This GL requested licensees to perform a ,

review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, l collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of that data on their RPV integrity enalyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reculations (10 CFR Part 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.

After reviewing your response, the NRC issued you a letter dated August 2,1996, for Hope Creek Generating Station. 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 our August 2,1996, letter, the BWR Vessel and Intemals Project (BWRVIP) submitted the report " 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

/l which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Frematome Technologies incorporated (FTI) analyses of Unde 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.

9805080288 980504 '

gDR ADOCK 05000354 PDR ,

30 FILF CENTER COPY

H. Keiser The staff is requesting that you reevaluate 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 that you provido a response to the enclosed request for additional information within 90 {

days of receipt of this letter. If a question does not apply to your situation, please indicate this in 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.

The information provided will be used in updating the Reactor Vessel integrity Deusbase. 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 additionallicense amendments or assessments are necessary, the enclosure requests that you provide a schedule for such submittals.

If you should have any questions regarding this request, please contact me at (301) 415-1420. '

Sincerely, l t

/S/

Richard B. Ennis, Acting Project Manager Project Directorate 1-2 Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

Request for Additional -

Information cc: See next page DISTRIBUTION:

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OFFICE PDI-2/PM POI-3A.A/* / PDI-2/D NAME T'Ennis:rb b TCJerk [ RCapra 9F DATE T /30 198 Lh' t 6/ 'f /98 OFFICIAL RECORD COPY DOCUMENT NAME: HC1194.RAI '  ;

1 i

H. Keiser l The staff is requesting that you reevaluate the RPV weld chemistry valusa 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 inforrnation to

' determine whether any values of RPV weld chemistry need to be revised for your facility.

. Therefore, in order to provide a complete response to itema 2,3 and 4 of the GL, the NRC requests that you provide a response to the enclosed request for additional information within 90 days of receipt of this letter. If a question does not apply to your situation, please indicate this in 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.

i The information provided will be used in updating the Reactor Vessel Integrity Database.' 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 potential impact on P-T limits. If additional license amendments oi assessments are necessary, the enclosure requests that you provide a schedule -

for such submittals.  ;

If you should have any questions regarding 'Nis request, please contact me at (301) 4151420.

Sincerely, Richard B. Ennis, Acting Project Manager Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket No. 50-354

Enclosure:

Request for Additioral information cc: See next page

1 Mr. Harold W. Keiser Hope Creek Generating Station Public Service Electric & Gas Company cc:

Jeffrie J. Keenan, Esquire Manager-Joint Generation l Nuclear Business Unit - N21 Atlantic Energy P.O. Box 236 -

6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg Harbor Twp., NJ 08234-4130 Hope Creek Resident inspector Richard Hertung

U.S. Nuclear Regulatory Commission Electric Service Evaluation l Drawer 0509 Board of Regulatory Commissioners i Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department clo Mary O. Henderson, Clerk l l

P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 General Manager - Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Manager- Licensing and Regulation Hancocks Bridge, NJ 0803C Nuclear Business Unit - N21 l P.O. Box 236 l Hancocks Bridge, NJ 08038 Regional Administrator, Region i U.S. Nuclear Regulatory Commissien 475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Prcicdion and Energy CN 415 Trenton, NJ 08625-0415

O-

• i REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY 6ection 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)". .i i

Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:

1

1. An evaluation of the bounding assessment in the reference above and its applicability to '

l 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 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 Meeting 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 meanof-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 wold 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 tand-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 informa' ion is not availeble to confirm the aforementioned details, but sufficient evidence exists to reasonab;y 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". Ajustification should then be provided for which assumption was chosen when the best-estimate chemistry was determined.

Enclosure w

l ,.

l..

I ' l Section 2,0 P-T Limit Evaluation l

2. If the limiting material for your plant changes orif the adjusted reference temperature for the limiting material increases 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.

l Reference

1. Memorandum dated Nnvember 19,1997, from Keith R. Wichtnan 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.' ' l

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