NRC-93-0038, Application for Amend to License NPF-43,modifying Leakage Testing Requirements for Primary Containment Isolation Valves in Injection Flow Paths of LPCI Mode of RHR Sys
| ML20044G453 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/24/1993 |
| From: | Gipson D DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20044G454 | List: |
| References | |
| CON-NRC-93-0038, CON-NRC-93-38 NUDOCS 9306030127 | |
| Download: ML20044G453 (3) | |
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Douglas R. Gipson Senior Vee President
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Nuclear Generaten Detroit rmnu 6400 North 0;xpe Highway
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f Newpod. Machspn 46106 acn s8Swo May 24,1993 NRC-93-0038 i
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.
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Reference Fermi 2 NRC Docket No. 50-341 a
NRC License No. NPF-43
Subject:
Proposed Technical Specification Change (License-Amendment) and Exemption Request - Primary Containment Isolation Valves Pursuant to 10CFR50.90, Detroit Edison Company hereby proposes to amend Operating License NPF-43 for the Fermi 2 plant by incorporating the enclosed changes into the Plant Technical Specifications. The proposed change modifies the leakage testing requirements for the primary containment isolation valves in the. injection flow paths of i
the Low Pressure Coolant Injection (LPCI) mode of the Residual Heat Removal (RHR) system. As a result of a history of local leak rate test (LLRT) failures in this penetration, Detroit Edison conducted a review of the design requirements associated with these valves. This study showed that the leakage tests specified are currently f
inappropriately strict for the valves' design function. This situation has led to unnecessary corrective maintenance and the associated radiation exposure. To alleviate 'this problem,. new leakage test requirements are being proposed for these valves.
Additionally, the proposed test requirements represent an alternative test than that required by 10CFR50 Appendix J.
However; since the i
proposed test meets the objective of Appendix J. a proposal for specific exception from these requirements in accordance with 10CFR50.12 is included. contains an evaluation of the proposed Technical Specification changes and exemption. Enclosure 2 is a summary of an i
engineering evaluation of the subject primary containment penetration. Enclosure 3 contains the proposed Technical Specificaton page changes. Detroit Edison has evaluated the proposed Technical' Specifications against the criteria of 10CFR50.92 and determined.that no significant hazards consideration is involved..The Fermi 2 Onsite g
Review Organization has approved and the Nuclear Safety Review Group has reviewed the proposed Technical Specifications and concurs with 9306030127 930524 0I PDR ADOCK 05000341 a
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USNRC May.24, 1993 NRC-93-0038 Page 2 the enclosed determinations. In accordance with 10CFR50.91. Detroit Edison ~ has provided a copy of this letter to the State of. Michigan.
i If you have any questions, please contact Mr. Glen D. Ohlemacher at (313) 586-4275.
Sincerely, Enclosure cc:
T. G. Colburn 4
A. B. Davis W. J. Kropp M. P., Phillips Supervisor, Electric Operators, Michigan Public Service Commission - J. R. Padgett 4
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.USNRC May 24, 1993 NRC-93-0038 Page 3 I
i I, DOUGLAS R. GIPSON, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to
-i the best of my knowledge and belief.
i DOUGLAS R. GIPSON l
Senior Vice Eresident c
On this day of
, 1993, before me personally appeared Douglas R. Gipson,1[eing first duly sworn.and says that he executed the foregoing as his free act and deed, i
A/AI No'tary Public nanF k
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