ML20032A843
| ML20032A843 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/27/1981 |
| From: | Jackson E VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| EVY-81-148, NUDOCS 8111020459 | |
| Download: ML20032A843 (1) | |
Text
1 VERMONT YAN KEE NUCLEAR POWER CORPORATION SEVENTY SEVEN GROVE STREET RUTLAND, VERMONT 05701 FVY 81-148 REPLY TO:
ENGINEERING OFFICE 3r 27, 1981 te7 woacESrEn noAo FR AMINGH AM, M ASSACH USETTS 0170:
TELEPHONE st7 e73 etoo United States Nuclear Rigulator
, 'ssion Washington, D.C.
23555 (D
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Attention:
Office of Nuclear Reactor Regulation FI O
References:
(a) License No. DPR-28 (Docket No. 50-271)
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lU (b) VYNPC Letter (WVY 80-132) to USNRC, OCT3 01981 dated September 19, 1980 J
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Dear Sir:
Subject:
Appendix J, Type B and C Test Program By Reference (b), Vermont Yankee transmitted a proposed local leak rate test program to the NRC which addressed all aspects of the requirements of Appendix J.
Integrated within our letter was a commitment to implement the major aspects of our program by the fall 1981 refueling outage contingent upon NRC acceptance of our program and the availability of equipment.
The purpose of this letter is to inform the NRC of our plans regarding the installation of check valves in our feedwater system. Despite the fact that the NRC has not commented on our proposal, we are in a position to install one outboard check valve in each of our feedwater lines during the upcoming outage. Based on a preliminary investigation, we believe, however, that it may be desirable to retain the present exemption to Type C testing requirements for the inboard check valves for ALARA reasons.
It is our intent to conduct a formal ALARA analysis and investigation during the upcoming outage; the results of this study will form the basis for our pcsition to ins 311, or not to install, the inboard valve.
By March, 1982, Vermont Yankee s 11 inform the NRC of our plans. During the interim period, existing mrtor operated valves in the feedwater system will continue to be designated as containment isolation valves and leak tested to containment isolation criteria.
We trust that this information is satisfactory; however, should you have any questions do not hesitate to call.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION
(
. 'h E.W.
ackson Manager of Operations E!U/dm cc: USNRC, Washington 17 Attn:
Mr. D. Collins l
Radiological Assessment Branch 0
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