ML20217Q628

Forwards RAI Re GL 92-01,Rev 1 Suppl 1, Rv Structural Integrity. GL Requested Licensees to Perform Review of RPV in Order to Identify,Collect & Rept Any New Data Pertinent to Analyses of Structural Integrity of RPVs

ML20217Q628
Person / Time
Site:	Clinton
Issue date:	05/05/1998
From:	Hopkins J NRC (Affiliation Not Assigned)
To:	Sipek J ILLINOIS POWER CO.
References
GL-92-01, GL-92-1, TAC-MA1184, NUDOCS 9805080247
Download: ML20217Q628 (8)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SOfAH001

\*****/ May 5, 1998 Mr. Joseph V. Sipek Director- Licensing Clinton Power Station Mail Code V920 Clinton, IL 61727

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT CLINTON POWER STATION (TAC NO. MA1184)

Dear Mr. Sipek:

Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor i Vessel Structural integrity," was issued in May 1995. This GL requebted licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and repost any new data pertinent to the analysis of the structural integrity 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 Raoulations (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 dated August 16,1996. 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. W , further indicated that a plant-specific

. TAC number may be opened to review this material. Following issuance of these letters, the

. BWR Vessel and Intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity lasues (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 and BWR vessels; (2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds (analyses 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.

- The staff is requesting that you re-evaluate the RPV weld chemistry values that you have 1 previously submitted as part of your licensing basis in light of the information presented in the

- CEOG, FTI, 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.

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

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l L indicate this in your RAI response along with your technical basis and, per GL 92-01, Rev.1, L Supp.1, provide a certification that previously submitted evaluations remain valid.

l,. The information provided will be Used in updating the Reactor Vessel integrity Database (RVID).

L' 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 you provide a schedule for such submittals.

1 Please contact me if you have any questions. '

Sincerely, l

)

I t Jon B. Hopkins, Senior Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/lV

! Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosure:

RAI cc w/ encl: See next page l

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e ' Mr. J. Sipek May 5,1998

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~ 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 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 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If

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additional license amendments or assessments are necessary, the enclosed requests that you .

i ' provide a schedule for such submittals.

. Please contact me if you have any questions.

Sincerely,  !

l Original signed by:

! Jon B.. Hopkins, Senior Project Manager

l. Project Directorate lil-3~

l Division of Reactor Projects lil/IV l Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosure:

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i  ; cc w/ encl: See next page 2 l -. Distribution I. . Docket File -

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' GGrant, Rill Document Name: G \CLINTONNr_rv.ral l l0FFICE PM:PDIII-3 g JE LA:PDIII.3 -l E h lNAME. JHopkins- M EBarnhill S /y- '

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, Mr. J. Sipek May 5, 1998 l

i 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.

l The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).

l Also, please note that RPV integrity analyses utilizing newly identified data cou!d result in the i 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 potentialimpact on P-T limits. If i additional license amendments or assessments are necessary, the enclosed requests that you provide a schedule for such submittals.

Please contact me if you have any questions.

Sincerely, Original signed by:

Jon B. Hopkins, Senior Project Manager Project Directorate ill-3 l l Division of Reactor Projects Ill/IV l Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosure:

RAI cc w/ encl: See next page ,

1 Distribution Docket File PUBLIC

. Alee EGA1 RBellamy OGC ACRS GGrant, Rlll Document Name: G:\CLINTON\bwr_rv.rai 0FFICE PM:PDIII-3 g J E LA:PDIII-3 lE NAME JHopkins \% EBarnhill Pfy DATE f /.c /98 7 \\ 05 /o4498 0FFICIAL RECORD COPY

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., Joseph V. Sipek l . Clinton Power Station, Unit 1 Illinois Power Company .i cc:

p Walter G.: MacFarland IV lilinois Department of Nuclear Safety Senior Vice President Office of Nuclear Facility Safety Clinton Power Station 1035 Outer Park Drive P,0. Box 678 Springfield, IL .62704 Clinton,IL 61727 I

L Wayne Romberg l Manager Nuclear Station

! Engineering Department Clinton Power Station P.O. Box 678 Clinton,IL 61727 i-Resident inspector ,

l- U.S. Nuclear Regulatory Commission j l RR#3, Box 229 A 1 Clinton,IL 61727

. R. T. Hill L Licensing Services Manager '

l General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA 95125 H

Regional Administrator, Region 111 L U.S. Nuclear Regulatory Commission f

801 Warrenville Road .

Lisle, IL 60532-4351 Chairman of DeWitt County

. clo County Clerk's Office l' DeWitt County Courthouse Clinton, IL

61727 J. W. Blattner Project Manager

(. Sargent & Lundy Engineers 55 East Monroe Street Chicago, IL _60603

l.

. REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY Section 10: Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity lasues (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 vessei's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.

i -

- 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 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, j 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 I should be evaluated both by assum:ng 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 the assumption chosen when the best-estimate chemistry was determined. i L

Enclosure l

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L 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 material increases as a result of the above evaluations, provide the revised

! RT, value for the limiting material. In addition, if the adjusted Rb value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.

Reference .

l- 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 l and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, l

Supplement 1 Responses." l

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