ML20081B318
| ML20081B318 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/21/1983 |
| From: | Wells D DETROIT EDISON CO. |
| To: | Keepler J, James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 14, EF2-65286, FF2-65286-55E, NUDOCS 8310270447 | |
| Download: ML20081B318 (2) | |
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Donald A. Wells Managu Ouanty Assurance (3131 237 % 57 2000 Second Avenue 31 3-October 21, 1983 EF2-65286 Mr. James G. Keppler, Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Final Report of 10CFR50.55(e) Item on RHR Heat Exchanger Relief Valves (#14)
Dear Mr. Keppler:
This is Detroit Edison's final report concerning action taken on the RHR Heat Exchanger Relief Valves as a result of concerns expressed by Mr. H. S. Phillips of NRC Region III to Detroit Edison Messrs.
R. W. Barr, M. K. Deora and T. O'Keefe by telephone on May 5,1983.
A previous investigation in this matter had been reported to Mr. G. Fiorelli of NRC Region III by Detroit Edison (letter EF2-49822, dated September 5,1980). At that time, the investigation disclosed a design deficiency in the size of three (3) QA Level I relief valves; V22-2042, V22-2045 and V22-2049. Commitments were made to modify the design replacing the three (3) valves and associated piping.
The design was modified via Design Change Notices (DCNs), which required the undersized relief valves and associated piping to be replaced by appropriate sized valves.
Subsequent to the design change, a potential water hammer problem was identified in the heat exchanger in the steam condensing mode of the RHR.
The steam condensing mode of the RHR and the start-up and preoperational test requirements were deleted to reduce the vulner-ability to IGSCC problems with the heat exchanger tubes.
This action directly affected relief valve V22-2585, which was to have replaced valve V22-2042. Deletion of the RHR steam condensing mode required removal of piping, piping supports, valves and equipment not used in the RHR system design, of which valve V22-2585 wa s a pa rt.
The above design changes have been implemented and are now couplete. Although the specifics of the original commitment have not been completely implemented, the full intent of that commitment has been satisfied.
10 8310270447 831021 PDR ADOCK 05000341
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Y Mt. James G. Keppler, Regional Administrator October 21, 1983 EF2-65286 Page Two If you have questions concerning this matter, please contset Mr. G.M. Trahey, Assistant Director - Project Quality Assurance.
Very truly yours,
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Mr. Richard DeYoung, Director Office lof Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Paul Byron, Senior Resident Inspector U.S. Nuclear Regulatory Commission 6450 North Dixie Highway Newport, Michigan 48166 l
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