ML20217Q541

Discusses Licensee Response to GL 92-01,Rev 1,Supplement 1, Rv Structural Integrity, Issued by NRC in May 1995. Requests That Ceco Reevaluate RPV Weld Chemistry Values That Ceco Previously Submitted as Part of Licensing Basis

ML20217Q541
Person / Time
Site:	Palisades, Quad Cities
Issue date:	05/04/1998
From:	Pulsifer R NRC (Affiliation Not Assigned)
To:	Kingsley O COMMONWEALTH EDISON CO.
References
GL-92-01, GL-92-1, TAC-MA1207, TAC-MA1208, NUDOCS 9805080174
Download: ML20217Q541 (7)

Text

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p uog y i UNITED STATES j

p ,2 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001 '

• • • • • ,o May 4, 1998-Mf, Oliver D. Kingsley, President l Nuclear Generation Group l Commonwealth Edison Company Executive Towers West lil

_ 1400 Opus Place, Suite 500 Downers Grove,IL 60515 r

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 (TAC NOS. MA1207 AND MA1208)

Dear Mr. Kingsley:

, Generic Letter 92-01, Revision 1, Supplement 1 (GL), " Reactor Vessel Structural Integrity" was l issued in May 1995. This GL requested licensees to perform a review of their reactor pressure l

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 Gpde 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 potentialimpact on low temperature overpressure (LTOP) limits or

pressure-temperature (P-T) limits.

After reviewing Comed's response, the NRC issued Comed a letter dated August 6,1996. In this letter the NRC acknowledged receipt of Comed's response, noted that additional RPV information may become available as a result of Owners Group efforts and requested that Comed provide the NRC with the results of the Owners Groups' programs relative to Quad Cities. 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 intamals 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 that contains all known data for Combustion Engineering (CE) fabricated welds in Pressurized Water Reactor (PWR) 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) FTl'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

' Hibachi was also included in the BWRVIP report.

, The staff is requesting timt Comed re-evaluate the RPV weld chemistry values that Comed has

, previously submitted as part of the licensing basis in light of tha information presonted in the CEOG, FTl and BWRVIP reports. The staff expects that Comed will assess this new information to determine whether any values of RPV weld chemistry need to be revised for Quad Cities.

Therefore, in order to provide a complete response to items 2,3 and 4 of the GL, the NRC requests that Comed provide a response 'o the enclosed request for additional information (RAI) within 90 days of receipt of this letter. If a question does not apply to Quad Cities, please

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- O. Kingsley 'May4, 1998 l-indicate this in the RAI response along with the technical basis and, per the GL, provide a i certification that previously submitted evaluations 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 Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If additional license amendments or assessments are necessary, the enclosed requests that '

Comed provide a schedule for such submittals.

If there should be any questions regarding this request, please contact me at (301) 415-3016.

Sincerely, l ORIG. SIGNED BY:

Robert M. Pulsifer, Project Manager Project Directorate lll-2 Division of Reactor Projects - lil/IV j Office of Nuclear Reactor Regulation Docket Nos. 50-254,50-265

Enclosure:

RAI cc w/ encl: See next page Distribution:

Docket File PUBLIC PDill-2 r/f E. Adensam, EGA1 S. Richards C. Moore

( R. Pulsifer OGC, O15818 ACRS, T2E26 M. Ring, Rlli A. Lee,07D4 -

l DOCUMENT NAME: G:\CMNTSP\ QUAD \QC1207 RAI Ta receive e copy of this document, indicese4n the ben: *C" = Copy without enclosures *E" = Copy with enclosures *N* = No copy OFFICE PM:PDill-2 ,

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__NAME RP,ULSIFEFF 'CfQl6OME SR,1 CHARDS %*

DATE 9)/ 0 3 /98 04/ 9 /98 Ob 4 /98 OFFICIAL RECORD COPY l

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O. Kingsley indicate this in the RAI response along with the technical basis and, per the GL, provide a i

certification that previously submitted evaluations 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 l

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 potentialimpact on P-T limits if additional license amendments or assessments are necessary, the enclosed requests that Comed provide a schedule for such submittals, l

if there should be any questions regarding this request, please contact me at (301) 415-3016.

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Sincerely,

' Robert M. Pulsifer, P ect Manager 1 Project Directorate 111-2 l Division of Reactor Projects - lil/IV l Office of Nuclear Reactor Regulation Docket Nos. 50-254, 50-265

Enclosure:

RAI cc w/ encl: See next page i

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Y, O. Kingsley Quad Cities Nuclear Power Station .

Commonwealth Edison Company Units 1 and 2 cc:

Michael I. Miller, Esquire Commonwealth Edison Company Sidley and Austin Site Vice President - Quad Cities One First National Plaza 22710 206th Avenue N.

Chicago, Illinois 60603 Cordova, Illinois 61242-9740-Commonwealth Edison Company Document Control Desk-Licensing Quad Cities Station Manager Commonwealth Edison Company 22710 206th Avenue N. 1400 Opus Place, Suite 400 Cordova, Illinois 61242-9740 Downers Grove, Illinois 60515 U.S. Nuclear Regulatory Commission Mr. David Helwig j Quad Cities Resident inspectors Office Senior Vice President 22712 206th Avenue N. Commonwealth Edison Company Cordova, Illinois S1242 Executive Towers West lli '

1400 Opus Place, Suite 900 q Chairman Downers Grove, IL 60515 j

Rock Island County Board i of Supervisors Mr. Gene H. Stanley j 1504 3rd Avenue PWR's Vice President Rock Island County Office Bldg. Commonwealth Edison Company RockIsland, Illinois 61201 Executive Towers West lli 1400 Opus Place, Suite 900 lilinois Department of Nuclear Safety Downers Grove, IL 60515 Office of Nuclear Facility Safety 1035 Outer Park Drive Mr. Steve Perry Springfield, Illinois 62704 BWR's Vice President Commonwealth Edison Company Regional Administrator Executive Towers West lll U.S. NRC, Region lli 1400 Opus Place, Suite 900 801 Warrenville Road Downers Grove, IL 60515 Lisle, Illinois 60532-4351 Mr. Dennis Farrar l William D. Leach Regulatory Services Manager 1 Manager- Nuclear Commonwealth Edison Company MidAmerican Energy Company Executive Towers West lll

- 907 Walnut Street 1400 Opus Place, Suite 500 l P.O. Box 657 Downers Grove,IL 60515  !

Des Moines, lows 50303 i Ms. Irene Johnson, Licensing Director Vice President- Law and Nuclear Regulatory Services Regulatory Affairs Commonwealth Edison Company MidAmerican Energy Company Executive Towers West lil One River Center Place 1400 Opus Place, Suite 500 106 E. Second Street Downers Grove,IL 60515 P.O. Box 4350 Davenport, lows 52808

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O. Kingsley Quad Cities Nuclear Power Plant . l l Commonwealth Edison Company . Units 1 and 2 l

Commonwealth Edison Company Reg Assurance Supervisor- Quad Cities 22710 206th Avenue N.

Cordova, Illinois 61242-9740 Mr. Michael J. Wallace Senior Vice President Commonwealth Edison Company

! Executive Towers We'st lii 1400 Opus Place, Suite 900 l Downers Grove,IL 60515 l

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=t .-_or REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY j 1

Section 1.0:- Assessment of Best-Estimate Chemistry The staff recently received the Boiling Water Reactor Vessel and Intemals Project (BWRVIP) report, l

" Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)."

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

With respect to Comed's 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 (Reference 1). The information in Reference 1 may be useful in helping to prepare the response.

In addition to the issues discussed in the referenced meeting, Comed 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 considnation when a l - menn-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 l aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, I 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 j then be provided for which assumption was chosen when the best-estimate chemistry was determined. l Section 2.0: P-T Limit Evaluation I

2. If the limiting material for Quad Cities changes or if the adjusted reference temperature for the limiting material increases as a result of the above evaluations, provide the revised RT, value for I 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.

Reference

.1. ' Memorandum 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," dated November 19,1997.

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