ML20135B689

Discusses Evaluation of Augmented Exam of Reactor Pressure Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A) for Plant, Unit 2 Provided by Comed on 961010

ML20135B689
Person / Time
Site:	Quad Cities
Issue date:	12/03/1996
From:	Pulsifer R NRC (Affiliation Not Assigned)
To:	Johnson I COMMONWEALTH EDISON CO.
References
TAC-M96937, NUDOCS 9612050099
Download: ML20135B689 (3)

Text

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, g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30866-0001 o

4 s...../ December 3, 1996 Ms. Irene Johnson, Acting Manager Nuclear Regulatory Services Comonwealth Edison Company Executive Towers West III 1400 Opus Place, Suite 500 Downers Grove, IL 60515

SUBJECT:

EVALUATION OF THE AUGMENTED EXAMINATION OF THE REACTOR PRESSURE VESSEL SHELL WELDS PURSUANT TO 10 CFR 50.55a(g)(6)(ii)(A) FOR QUAD CITIES NUCLEAR POWER STATION, UNIT 2 (TAC NO. M96937)

Dear Ms. Johnson:

The staff has reviewed the information provided by Comonwealth Edison Company (Comed. the licensee) in its letter dated October 10, 1996,- related to the augmented examination of the reactor pressure vessel shell welds pursuant to 10 CFR 50.55a(g)(6)(ii)(A) for Quad Cities Nuclear Power Station Unit 2. Our evaluation follows.

In its letter dated October 10, 1996, the licensee proposed that the augmented reactor pressure vessel shell weld (American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI Category B.A. Item  !

Bl.10 shell welds) examinations be ultrasonically examined (a) remotely from the inside of the reactor vessel to the extent possible, and (b) manually from the outside of the vessel where remote inside examination is not achieved and

, where scheduled bioshield wall blocks and insulation materials disassembly allows access.

In addition, the licensee proposed that the remote examinations will be performed in accordance with the remote ultrasonic examination 3rocedure developed by General Electric, which has been demonstrated at t1e Performance Demonstration Initiative Qualification in accordance with the rules of i Appendix VIII of the ASME Code Section XI, 1992 Edition through 1993 Addenda. I Based on the results of the Quad Cities Unit 2, reactor vessel accessibility study performed by the licensee before the installation of the core shroud repair hardware, it concluded that the examination coverage from the inside of the vessel would be approximately 68.7 percent of the reactor pressure vessel shell weld volume. Quad Cities does not intend to remove any shroud repair hardware to perform the remote internal examination. Therefore, the reactor pressure vessel shell weld volume coverage, with the shroud repair hardware  !

installed, is approximately 65.1 percent. Furthermore, as noted above, the licensee will supplement the remote internal examinations with manual ultrasonic examinations from the outside surface of the reactor pressure  ;

vessel to the extent possible.

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- .I. Johnson The staff believes that the licensee's proposed examination plan to meet the augmented reactor pressure vessel shell weld inspection requirements contained in 10 CFR 50.55a(g)(6)(ii)(A) is appropriate. Upon completion of the augmented reactor vessel shell welds examinations, if the examination volume for each weld examined is less than 90 percent, the licensee is to submit to the NRC an alternative to its augmented reactor pressure vessel shell weld examinations pursuant to 10 CFR 50.55a(g)(6)(ii)(A).

Sincerely, Original signed by:

Robert M. Pulsifer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-265 cc: See next page Distribution:

Docket File PUBLIC PDIII-2 r/f J. Roe, JWR E. Adensam. EGA1 l R. Capra C. Moore R. Pulsifer  !

G. Bagchi. 07H15 OGC. 015B18 i ACRS, T2E26 i P. Hiland , RIII i DOCUMENT NAME: G:\0C96937.LTR To etceive e copy of this document. Indicete irAs box; "C" = Copy witMut e sures *E" = Copy with enclosures "N" - No copy 0FFICE PM:PDIll-2 _l 1 L4: PMR-2 l6 D:GGW l r0: PDIll-2/ 4E I NAME RPulsifer:# F CRDOKE \ f/aochi j,RCAPRA  ?)V DATE 11h7/96 11(_U 96 M 'Y96 (/ 17tc3/96' 0FFICIAL RECORD COPi

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I. Johnson Quad Cities Nuclear Power Station ,

Commonwealth Edison Company Unit Nos. I and 2 l l

cc:

Michael I. Miller, Esquire Document Control Desk-Licensing i Sidley and Austin Commonwealth Edison Company l One First National Plaza 1400 Opus Place, Suite 400 Chicago, Illinois 60603 Downers Grove, Illinois 60515 Mr. L. William Pearce Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board 1 of Supervisors 1504 3rd Avenue 1 Rock Island County Office Bldg.

Rock Island, Illinois 61201 i Illinois Department of Nuclear Safety j Office of Nuclear Facility Safety '

1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Richard J. Singer Manager - Nuclear .

MidAmerican Energy Company 907 Walnut Street P.O. Box 657 Des Moines, Iowa 50303 Brent E. Gale, Esq.

Vice President - Law and Regulatory Affairs MidAmericar, Energy Company One RiverCeate:r Place 106 East Second Street .

P.O. Box 4350 l Davenport, Iowa 52808 l

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