ML20205H118

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Advises That IGSCC Insp Results & Repairs Performed During 1986 Refueling & Maint Outage Provide Assurance That Facility Can Be Safely Operated for Next 18-month Fuel Cycle.Safety Evaluation Encl
ML20205H118
Person / Time
Site: Quad Cities 
Issue date: 03/23/1987
From: Rajender Auluck
Office of Nuclear Reactor Regulation
To: Farrar D
COMMONWEALTH EDISON CO.
Shared Package
ML20205H123 List:
References
TAC-64338, TAC-64484, TAC-64573, TAC-64574, NUDOCS 8703310627
Download: ML20205H118 (3)


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March 23, 1987

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Docket No. 50-265 Mr. Dennis L. Farrar Director of Nuclear Licensing Commorwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

Dear Mr. Farrar:

SUBJECT:

SAFETY EVALUATION OF REACTOR COOLANT PIPING SYSTEMS INSPECTION AND REPAIR (TAC N0s. 64338, 64484, 64573, 64574) l Re:

Quad Cities Nuclear Power Station, Unit 2 By submittals dated December 24, and 30, 1986 and January 15 and 19, 1987, Commonwealth Edison Company (CECO) provided NRC staff with information related to inspections and repairs performed on the reactor coolant piping system during the 1986 refueling and maintenance outage. Based on the information provided NRC staff concludes that the Intergranular Stress Corrosion Cracking f

inspection results and repairs perfomed during the 1986 refueling and maintenance outage provide assurance that Quad Cities Nuclear Power Station, Unit 2 can be safely operated for the next 18-month fuel cycle.

To provide added assurances in piping integrity, the NRC staff requests the Ceco to perform the following additional piping inspection or mitigation during the next three refueling outages:

(1) All induction heating stress improvement (IHSI) treated welds should be reinspected over the next two refueling cycles' because some question exists regarding the five new flawed welds, which were treated with IHSI in previous outages.

(2) Welds 285-F14 and 28S-512 should continue to be inspected since some uncertainty exists in the interpretation of the ultrasonic testing signals.

'(3) Additional mitigation should be applied to the overlay repaired end cap weld 02A-S10 during the next refueling outage because the overlay thickness did not meet NRC staff's criteria for full structural or standard overlay design. NRC staff strongly recommends the replacement of weld 02A-510 since the tensile residual stresses in the weld metal are expected to promote further growth of the deep flaws that are present.

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F, Mr. Dennis L. Farrar March 23, 1987' Because of uncertainties about the long term behavior of the piping, NRC staff requires-that the plan for inspection and/or modification to the recirculation and any other service sensitive austenitic stainless steel piping systems operating over 200"F during the next operating cycle, be submitted at least three months before the start of the next refueling and maintenance outage.

A copy of our related Safety Evaluation is enclosed.

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If you have any questions regarding the information presented above or any of ithe NRC staff conclusions, please contact your NRC Quad Cities Power Station

~ Project Manager.

Sincerely, t

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Rajender Auluck, Acting Director BWR Project Directorate #1 Division of BWR Licensing

Enclosure:

As state'd cc w/ enclosure:

See next page

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Mr. Dennis L. Farrar Quad Cities Nuclear Power Station Commonwealth Edison Company Unit 2 cc:

Mr. B. C. O'Brien President Iowa-Illinois Gas and Electric Company 206 East Second Avenue Davenport, Iowa 52801 Mr. Michael I. Miller Isham, Lincoln & Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 Mr. Nick Kalivianakis Plant Superintendent Quad Cities Nuclear Power Station 22710 - 206th Avenue - North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors Rock Island County Court House Rock Island, Illinois 61201 Mr. Michael E. Parker Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

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