ML20003C621
| ML20003C621 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/03/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.D.1, TASK-TM L1L-036, L1L-36, NUDOCS 8103060628 | |
| Download: ML20003C621 (2) | |
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4 Metropolitan Edison Company Post Office Box 480 kI Middletown, Pennsylvania 17057 717 944-4041 Writer's Direct Dial Number March 3, 1981 Lil 036 "h
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Office of Nuclear Reactor Regulation 0
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Attn: Mr. D. G. Eisenhut, Director M
Division of Licensing
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U. S. Nuclear Regulatory Commission
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[d Washington, DC 20555 4
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Dear Sir:
t.n Three Mile Island Nuclear Station, Unit 1 (T!1I-1)
Operating License No. DPR-50 Docket No. 50-289 Response to NUREG-0737, Item II.D.1 As a sponsor of the EPRI Safety and Relief Valve Test Program, Met-Ed intends to comply with the technical requirements of NUREG-0578, Item 2.1.2.
In December 1980, R.C.
Youngdahl of Consumers Power Company provided the current PWR Utilities' positions on NUREG-0737, Item II.D.1 clarifications. Briefly, those positions are:
A.
Safety and Relief Valves and Piping: The EPRI " Program Plan for Performance Testing of PWR Safety and Relief Valves," Revision 1, dated July 1,1980, does provide a program that satifies the NRC requirements.
Discussion with the NRC staff and their consultants are resolving specific detailed issues.
B.
Block Valves: The EPRI Program has not formally included the test-ing of block valves. However, a small number of block valves have been tested at the Marshall Steam Station Test Facility. The PWR Utilities and EPRI cannot provide a detailed block valve test pro-gram until results of the Wyle and C-E relief valve tests are avail-able. Therefore, a block valve test program will not be provided before July 1981. The PWR Utilities and EPRI believe that the pro-per operation of the Tl11-2 and Crystal River block valves and other operational experience, plus knowledge of the Marshall tests, sup-port a less hurried and more rational approach to block valve test-ing.
C.
ATWS Testing: PWR Utilities will not support additional efforts for ATWS valve testing until regulatory issues are resolved. The major safety and relief valve test facility (C-E) is nearing com-pletion and some measures were taken to provide additional test capability beyond the current program requirements. The NRC should y, g 81030 606 28 g
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1 Mr. D. G. Eisenhut February-
, 1981 Page No. 2 i
i recognize that results from the current program are likely to pro-t vide most of the information necessary to address ATWS events (i.e.,
relief capability at high pressure).
We endorse the EPRI Program as described in Mr. Youngdahl's December letter and adopt them as our response for TMI-1.
Sincerely,
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'4I ' s ukIil Director, TMI-l i
HDH:CWS :bjo cc:
D. DiIanni 2
R. W. Reid H. Silver i
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