ML19337A442
| ML19337A442 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/19/1980 |
| From: | Marsolais L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19337A444 | List: |
| References | |
| WVY-80-132, NUDOCS 8009260458 | |
| Download: ML19337A442 (2) | |
Text
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X VERMONT Y AN KEE NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET B.3.2.1 RUTLAND. VERMONT 05701 WY 80-132 REPLY 70
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ENGINEERING OFFICE TURNPIKE RO AD WESTOORO. M AS$ ACHUSETTS 01581 September 19, 1980 Tr'erwoNeair3..-ioni United States Nuclear Regulatory Commission Washington, D.C.
20555 l
Attention: Office of Nuclear Reactor Regulation
Reference:
(a) License No. DPR-28 (Docket No. 50-271)
(b) USNRC Letter to YAEC dated March 21, 1980 (c) VYNPC Letter (WVY 75-95) to USNRC dated September 9, 1975
Subject:
Appendix J - Supplemental Information
Dear Sfr:
On September 9, 1975, Vermont Yankee responded to an NRC generic letter regarding compliance with the requirements of 10CFR50, Appendix J.
As part of our study of containment testing, we identified and listed certain penetrations and valves which we felt should be exempt from the requirements of Appendix J.
Our request for exemption was transmitted to the NRC in Reference (c). Subsequently, two inspections were conducted by personr.el from the NRC's Office of Inspecticn and Enforcement regarding Appendix J.
On both occasions the inspectors identified certain areas needing amplification.
These items were categorized as " unresolved, pending completion of NRC review"; no additional action was required by Vermont Yankee at that time.
On January 29, 1980, representatives of Vermont Yankee and Franklin Research Center met tiith the NRC staff at the NRC's request. The purpose of the meeting was to determine the status of Vermont Yankee's requests for exemption and the NRC I&E inspection items. At the conclusion of the meeting, it was agreed that we would review our containment isolation valve leak testing practices, as well as the outstanding items identified in the inspection reports, and propose a local leak rate test program that addresses all aspects of Appendix J requirements. Our proposed program is delineated in the attached pages.
Implementation of this proposed program, in some cases, will require piping modifications.
As such, our schedule for complete implementation is contingent on your acceptance of our program and the time frame necessary to procure and install the equipment and revise our technical specifications. It is anticipated that compliance with this program will be achieved during the refueling outage scheduled for the fall of 1981.
8009260 '[6 7
United States Nuclear Regulatory Commission September 19, 1980 Office of Nuclear Peactor Regulation Page 2 We trust that the attached information is sufficient for yque review; powever, should you have any questions we are willing to discus 4 this subject With you at your convenience.
i Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION N
N L. D. Marsolais Project Manager Attachment l
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