ML17180A935
| ML17180A935 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 09/27/1994 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| GL-94-03, GL-94-3, TAC-M90088, TAC-M90110, NUDOCS 9410030017 | |
| Download: ML17180A935 (5) | |
Text
UNITED STATES
- u~~:iu WASHINGTON, D.C. 20555-0001 50*-~3~5 NUCLEAR REGULATORY COMMISSION September 27, 1994 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West Ill, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING GENERIC LETTER 94-03, 11 INTERGRANULAR STRESS CORROSION CRACKING OF CORE SHROUDS IN BOILING WATER REACTORS 11 (TAC NOS. M90088 AND M90110)
Dear Mr. Farrar:
By letter dated July 25, 1994, the NRC issued Generic Letter (GL) 94-03, 11 Interg.ranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors." The purpose of the generic letter was to request each licensee to inspect the core shroud no later than the next refueling outage, and perform a safety analysis supporting continued operation of the facility until inspections are conducted.
By letter dated August 23, 1994, ComEd responded to the GL.
The NRC staff has reviewed the response for Dresden Unit 2 and Quad Cities Unit 2 and found the response to be incomplete concerning the safety analysis supporting continued operation of the units.
Enclosed is a request for additional information (RAI) which is required in order for the staff to complete its review of your response to GL 94-03:
We request that you provide a response within 10 days from the date of this letter.
The reporting and/or record keeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
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9410030017 940927 I
.PDR' ADOCK.0500~~~7 p
COPY
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D. L. Farrar
.2 -
September 27, 1994 If you have any questions, please contact me at 504-1345.
Docket Nos. 50-237 and 50-265 Sincerely, Original signed by:
John F. Stang, Project Manager Project Directorate III-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl : See next page DISTRIBUTION:
Docket File PD II I-2 R/F NRC & Local PDRs J. Roe J. Zwolinski E. Adensam C. Moore J. Stang R. Capra OGC ACRS (10)
E. Greenman, RIII DOCUMENT NAME: G:\\CMRCJR\\DRESDEN RA!.
R To receive a copy of this docunent, indicat i the box:
11c11 = Copy without enclosures 11E11 = Copy with enclosures "N" = No co y OFFICE NAME DATE 09/ /94
Mr. D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. J. Stephen Perry Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Mr. J. Eenigenburg Station Manager, Unit 2 Dresden Nuclear Power Station 6500 North Dresden Road Morrjs, Illinois 60450-9765 Mr. D. Bax Station Manager, Unit 3 Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road Morris, Illinois 60450-9766 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administration Building 1320 Union Street Morris, Illinois 60450 Dresden Nuclear Power Station Unit Nos. 2 and 3
Mr. D. L. Farrar Commonwealth Edison Company cc:
Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. 0. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Guy Campbell Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Illinois Department of Nuclear Safety 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 Quad Cities Nuclear Power Station Unit Nos. 1 and 2
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REQUEST FOR ADDITIONAL INFORMATION CONCERNING GENERIC LETTER 94-03 INTERGRANULAR STRESS CORROSION CRACKING OF CORE SHROUDS IN BOILING WATER REACTORS FOR DRESDEN UNIT 2 AND QUAD CITIES UNIT 2 After reviewing the licensee's response to Generic Letter (GL) 94-03, the staff found that the response to reporting requirement lb concerning a safety analysis supporting continued operation of the units until inspections are conducted was not complete.
Your response referenced only the previous analysis which was performed for the HS weld for Dresden Unit 3 and Quad Cities Unit 1. That analysis was reviewed and approved by the NRC staff for operation for up to lS months for the existing 360 circumferential cracks in the HS weld of the core shroud found at recent core shroud inspections during the Dresden Unit 3 and Quad Cities Unit 1 refueling outages.
Your response indicated that for Dresden Unit 2 and Quad Cities Unit 2 the worse case possible cracking of the core shrouds would be at the HS welds.
The staff cannot rule out that other welds in Dresden Unit 2 and Quad Cities Unit 2 may have worse case possible cracking. Therefore, in order to evaluate your basis for continued operation, the staff requires that Commonwealth Edison Company provide a detailed assessment as required by lb of GL 94-03 for the H2/H3 weld location of the core shroud for Dresden Unit 2 and Quad Cities Unit 2.
The analysis should provide the shroud response to the structural loadings resulting from design basis events (e.g., steam line break, recirculation line break, seismic loads, and combined accident and seismic loads), and assess the ability of the plants' safety features to perform their intended functions considering the shroud response to structural loadings (e.g., control rod insertion, ECCS injection).