ML20212J452

Discusses Closure of TAC MA1188 Re Response to RAI to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

ML20212J452
Person / Time
Site:	Duane Arnold
Issue date:	06/25/1999
From:	Mozafari B NRC (Affiliation Not Assigned)
To:	Protsch E IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
References
GL-92-01, GL-92-1, TAC-MA1188, NUDOCS 9907060006
Download: ML20212J452 (5)

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y UNITED STATES 5 e NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 40M

• • • • • June 25, 1999 j Mr. Eliot Protsch President IES Utilities Inc.

200 First Street, SE.

P.O. Box 351 Cedar Rapids, IA 52406-0351

SUBJECT:

CLOSURE REGARDING RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1,

" REACTOR VESSEL STRUCTURAL INTEGRITY," DUANE ARNOLD ENERGY CENTER (TAC NO. MA1188)

Dear Mr. Protsch:

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, Supp.1), " Reactor Vessel Structural Integrity," to l holders of nuclear operating licenses. In issuing the GL the staff required addressees of the GL  ;

to: l (1) identify, collect, and report any new data pertinent to the analysis of the 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 recuirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federal Replations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G 1 and H to Part 50 of Title 10 of the Code of FederalRegulations (Appendices G and H to 10 l- CFR Part 50).

l On August 17,1995, you submitted your initial response to Generic Letter (GL) 92-01, l

Revision 1, Supplement 1, and provided the requested information relative to the structural integrity assessment for the Duane Arnold Energy Center (DAEC). The NRC staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on January 3,1997. However, since the time of the NRC staffs closure letter, the i' Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B&W) Owners (

Group have each submitted additional data regarding the alloying chemistries of beltline welds 0 in CE and B&W fabricated vessels. The additional alloying data were submitted in Topical l

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. In addition, Chicago Bridge and / o\

Iron (CB81) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additionalinformation was necessary relative to the structuralintegrity assessments for your plants. On April 21,1998, the NRC staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline weldy,

l. your assessment of surveillance data for your facility, and pressure-temperature (P-T) limas for i DAEC. In general, with respect to the contents of the RAI, the NRC staff requested that you

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., Eliot Protsch reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and 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 our RAI for DAEC on July 20,1998. As a result of our review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the July 20,1998, response to the RAI, the NRC 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. gov /NRR/RVID/index.html). We recommend that you review this information. if we do not receive comments from you 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 etructuralintegrity assessments. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.

This completes our efforts with regard to TAC No MA1188. We appreciate your efforts in regard to this matter, if you have any questions, please contact me at 301-415-2020.

Sincerely, W d Brenda L. Mozafari, Project anager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331 cc: See next page.

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, Mr. Eliot Protsch Duane Arnold Energy Center IES UtilitiesInc.

cc:

Jack Newman, Esquire Al Gutterman, Esquire Morgan, Lewis, & Bockius 1800 M Street, NW.

Washington, DC 20036-5869 Chairman, Linn County Board of Supervisors Cedar Rapids, IA 52406 IES Utilities Inc.

ATTN: Gary Van Middlesworth Plant Superintendent, Nuclear 3277 DAEC Road Palo,IA 52324 John F. Franz, Jr.

Vice President, Nuclear Duane Amold Energy Center 3277 DAEC Road Palo,IA 52324 .

Ken Peveler Manager of Regulatory Performance I Duane Amold Energy Center J 3277 DAEC Road

. Palo, IA 52324 U.S. Nuclear Regulatory Commission

- Resident inspector's Office Rural Route #1 Palo,IA 52324 l

Regional Administrator, Rlll i U.S. Nuclear Regulatory Commission 801 Warrenville Road

. Lisle, IL 60532-4531

]

Parween Baig Utilities Division Iowa Department of Commerce Lucas Office Building,5th floor Des Moines,IA 50319 ,

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, Eliot Protsch June 25, 1995 reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and 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 our RAI for DAEC on July 20,1998. As a result of our review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the July 20,1998, response to the RAl, the NRC staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes arc posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information, if we do not receive comments from you 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 structural integrity assessments. Future submittals on P-T limits or upper shelf energy (USE) v.nould reference the most current information.

This completes our efforts with regard to TAC NotMA1188. We appreciate your efforts in regard to this matter.

If you have any questions, please contact me at 301-415-2020.

Sincerely, Original signed by:

Brenda L. Mozafari, Project Manager, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation

- Docket No. 50-331 ~

cc: See next page DISTRIBUTION Docket File PUBLIC Zwolinski/SBlack OGC ACRS GGrant, Rill CCraig/CThomas Alee, EMCB MMitchell, EMCB l DOCUMENT NAME: G:\PDill-1\DUANEARN\gl9201cis.wpd "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE SC:LPD31 i PM:LPD31 [ Ea LA:LPD31 E NAME BMozaferif3JFEBarnhillify CCraig(\1 ((' l DATE 6/ 7 H/99 6/ pf/99 6/W/99 l OFFICIAL RECORD COPY l l

Eliot Protsch June 25, 1995

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. reassess the alioying chemistries for the beltline welds and RPS surveillance welds relative to the chemistries provided in the applicable topical report, and 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 our RAI for DAEC on July 20,1998. As a result of our review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the July 20,1998, response to the RAI, the NRC 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. gov /NRRiRVID/index.html). We recommend that you review this information. If we do not receive comments from you 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 structural integrity assessments. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.

This completes our efforts with regard to TAC No.MA1188. We appreciate your efforts in regard to this matter.

l if you have any questions, please contact me at 301-415-2020.

Sincerely, Original signed by:

Brenda L. Mozafari, Project Manager, Section 1 Project Directorate ill l Division of Licensing Project Management Office of Nuclear Reactor Regulation f

Docket No. 50-331 cc: See next page DISTRIBUTION Docket File PUBLIC

. Zwolinski/SBlack OGC ACRS GGrant, Rlli CCraig/CThomas Atee, EMCB  !

MMitchell, EMCB i DOCUMENT NAME: G:\PDill-1\DUANEARN\gl9201 cts.wpd  ;

"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy  !

l OFFICE PM:LPD311 E,, LA:LPD31 E SC:LPD31 l'6 lNAME BMozaieriF f 'EBarnhilliff CCraig(\1 H' lDATE 6/ 7 /96 6/ Sfl99 6/ 6 /99 '

OFFICIAL RECORD COPY i