ML20217K736

Forwards RAI Re GL-92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, Issues in May 1995.GL Requested Licensees to Perform Review of RPV Structural Integrity Assessments in Order to Review,Collect & Rept Any New Data

ML20217K736
Person / Time
Site:	Fermi
Issue date:	04/24/1998
From:	Kugler A NRC (Affiliation Not Assigned)
To:	Gipson D DETROIT EDISON CO.
References
GL-92-01, GL-92-1, TAC-MA1189, NUDOCS 9805040086
Download: ML20217K736 (6)

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's NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 ON

%.....# April 24, 1998 Mr. Douglas R. Gipson Senior Vice President Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT FERMI 2 (TAC NO. MA1189)

Dear Mr. Gipson:

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, 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 requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR 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::05000341/LER-1996-010, Forward LER 96-010-00 Which Documents ESF Actuation Involving Transfer Af HPCI Suction Flow Path from CST to Suppression Pool.Caused by Radio Frequency Interference Driving Output of CST Level|letter dated August 19,1996]]. 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 (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 which contains all known data for CE fabricated welds in PWR [ pressurized-water reactor) and BWR i 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.

/. /h 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 j CEOG, FTl and BWRVIP reports. The staff expects that you will assess this new information to i 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 9805040086 990424 s PDR ADOCK 05000341 P PDR J

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o 0 D. Gipson April 24, 1998 requests that you provide a response to the enclosed request for additional information (RAI) 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, 1 Supp.1, provide a certification that previously submitted evaldations remain valid.

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 50.60, and i Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If i additional license amendments or assessments are necessary, we request that you provide a schedule for such submittals as stated in the enclosure.

I' If you should have any questions regarding this request, please contact me at 301-415-2828.

Sincerely, ORIGINAL SIGNED BY Andrew J. Kugler, Project Manager Project Directorate lll-1 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-341

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD3-1 RF OGC ACRS BBurgess, Rlli (BLB)

EAdensam, EGA1 ADLee DOCUMENT NAME: G:\WPDOCS\ FERMI \FE-A1189.RAI vo ,.c.w. . copy o,ini. nocum.nt indic t. in in. box c . copy wiinout ett cnmentiencio.ur. e . copy witn attachment /encio.ur. N . No copy OFFICE PM:PD31 lE LA:PD31 jE D:PD31 C NAME AKugler:db (hn_. CJamerson W CACarpentert 4(_

DATE 04/ 2.4-/98 U 04/ #f/98 // 04/l)4 /98 OFFICIAL RECORD COPY l

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l Mr. Douglas R. Gipson Fermi 2 Detroit Edison Company cc:

John Flynn, Esquire Senior Attorney Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 l Monroe County Emergency Management Civision 963 South Raisinville

, Monroe, Michigan 48161 Regional Administrator, Region lll U.S. Nuclear Regulatory Commission i 801 Warrenville Road Lisle, Illinois 60532-4351 Norman K. Peterson Director, Nuclear Licensing Detroit Edison Company Fermi 2 - 280 TAC 6400 North Dixie Highway Newport, Michigan 4816S 1

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I j REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY i

l Section 1.0: Assessment of Best-Estimate Chemistry l The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)."

Based on this information, in accordance with the provisions of Generic Letter 92-01, l 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.

l Based upon this reevaluation, supply the infomation necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. If the limiting material for i

your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.

L 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 [ Nuclear Energy Institute),' 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 l response.

l 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 we! ding input parameters, and using the same coil (or coils in the case of 4 tandem arc welds) of weld consumables, it may be appropriate to consider all chemistry l 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 l 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 I- best-estimate chemistry was determined.

ENCLOSURE

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Section 2.0: P-T Limit 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 ad.iusted RT, value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR Part 'i0 Appendix G is maintained.

Reference  !

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

• Meeting Summary for November 12,1997 Meeting with Owners Group i Representatives and NEl Regarding Review of Responses to Generic Letter 92-01,  !

Revision 1, Supplement 1 Responses."

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