ML20196J713

Informs of Closure of Response to Requests for Addl Info to GL 92-01,Rev 1,Supplement 1, Reactor Vessel Structural Integrity, for Clinton Power Station Unit 1

ML20196J713
Person / Time
Site:	Clinton
Issue date:	06/30/1999
From:	Hopkins J NRC (Affiliation Not Assigned)
To:	Sipek J ILLINOIS POWER CO.
References
GL-92-01, GL-92-1, TAC-MA1184, NUDOCS 9907070406
Download: ML20196J713 (3)

Text

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.j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30e06 0001 June 30, 1999 Mr. Joseph V. Sipek Director- Licensing Clinton Power Station

- P.O. Box 678 -

Mall Code V920 Clinton,IL 61727.

SUBJECT:

CLOSURE OF RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMAYlON TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1,

" REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE CLINTON POWER STATION, UNIT 1 (TAC NO. MA1184)

Dear Mr. Sipek:

On May 19,1995, the U. S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Suppl.1), " Reactor Vessel Structural Integrity," to holders of operating licenses. In issuing the GL, the staff required addressees of the GL to:

(1) Identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federal Regulations (Appendices G and H to 10 CFR Part 50).

On August 16,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1 and provided the requested information relative to the structural integrity assessments for the Clinton Power Station. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 16,1996. However, since the time of the staff's closure letter, the Combustion Engineering (CE) Owners Group and the Babcock 1 and Wilcox (B&W) Owners Group have each sub.nmed additional data regarding the alloying chemistries of beltline welds in CE and B&W fabricated vessels. The additional alloying data

\ g were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NPSD 1119, Revision 1, for CE fabricated RPV welds, and BAW-2325. Revision 1, for B&W fabricated RPV welds. le i addition, Chicago Bridge and Iron (CB&l) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additional /

information was necessary relative to the structural integrity assessments for your plant. On L May 5,1998, we requested additional information (RAI) in regard to the alloying chemistries of

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beltline welds, your assessment of surveillance data for your facility, and pressure-temperature (P-T) limits, for the Clinton Power Station. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the appUcable topical report, and 9907070406 990630

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' i y J. Sipek 2 l provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant.

You provided your response to the staff's RAI for the Clinton Power Station on August 4,1998.

As a result of the staff's review of your responses to GL 92-01, Rev.1; GL 92-01, Rev.1, Supp.

1; and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc.aov/NRR/RVID/index html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional ,

information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits, or upper shelf energy (USE) should reference the most current information.  !

This closes the staff's efforts in regard to TAC No. MA1184. The staff appreciates your efforts in regard to this matter. i Contact me if you have any questions.

Sincerely, J

Original Signed By Jon B. Hopkins, Senior Project Manager Project Directorate 111-2 Division of Licensing Project Management

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

l Docket File PUBLIC

! cc: See next page PD3-2 R/F ACRS OGC GGrant, Rlll JZwolinski Alee r

Document Name: G:\PDill 2\CLINTON\GL92-01.WPD g 0FFICE PM:PDIII-2 af l E LA:PDIII-2 E SC;fpf/I-2l NAME JHopkins M EBarnhille/>r. 18#M4fa DATE (, /30 /99 I\\ 6 /J') /99 //, b /99 OFFICIAL RECORD COPY

Is Joseph V. Sipok Clinton Power Station, Unit i lilinois Power Company cc:

John. P. McElwain Illinois Department of Nuclear Safety Senior Vice President Office of Nuclear Facility Safety Clinton Power Station ATTN: Mr. Frank Nizidlek  ;

P.O. Box 678 1035 Outer Park Drive Clin;on,IL 61727 Springfield,IL 62704 Wayne Romberg Leah Manning Stetzner Manager Nuclear Station VP, General Counsel & Corp. Secretary Engineering Department 500 South 27th Street Clinton Power Station Decatur,IL 62525 P.O. Box 678 Clinton,IL 61727 Resident inspector U.S. Nuclear Regulatory Commission RR#3, Box 22g A Clinton,IL 61727 R. T. Hill Licensing Services Manager General Electric Company 175 Curtner Avenue, M/C 481 San Jose, CA 95125 Regional Administrator, Region lll U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Chairman of DeWitt County c/o County Clerk's Office DeWitt County Courthouse Clinton,IL 61727 J. W. Blattner Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago,IL 60603 i

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