ML20204F230
| ML20204F230 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/29/1986 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20204F236 | List: |
| References | |
| NUDOCS 8608040130 | |
| Download: ML20204F230 (2) | |
See also: IR 05000271/1986010
Text
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,
JUL 2 91986
Docket No. 50-271
Vermont Yankee Nuclear Power Corporation
ATTN:
Mr. Warren P. Murphy
Vice President and Manager of Operations
RD 5, Box 169
Ferry Road
Brattleboro, Vermont
05301
Gentlemen:
Subject:
Inspection Report No. 50-271/86-10
This refers to the routine resident safety inspection conducted by Mr. W. J. Raymond
of this office on May 6 - June 30, 1986, at the Vermont Yankee Nuclear Power Sta-
tion, Vernon, Vermont.
The inspection findings were based on observation of acti-
vities, interviews with personnel and document reviews.
The results of the in-
spection are described in the NRC Region I Inspection Report enclosed with this
letter and were discussed with Mr. J. P. Pelletier of your staff at the conclusion
of the inspection.
Our inspector reviewed the actions taken in response to the violation involving
the standby liquid control (SLC) system described in our letter to you dated March
11, 1986, Inspection Report 86-05.
We found that your corrective actions were
completed per the commitments made in your letter FVY 86-43 dated May 22, 1986.
We have no further questions regarding the actions taken to restore the SLC system
to an operable status prior to reloading the core in May, 1986.
However, in regard
to the matter of Technical Specifications requirements for functional testing of
the SLC system, based on our telephone conversation July 15, 1986, we understand
that you will propose a c.hange to Technical Specification 4.4. A to better reflect
the revised and upgraded functional test requirements now contained in Revision
8 of OP 4203, " Maintenance and Testing of SLC Squib Valves". We understand further
that the Technical Specifications proposed change will be submitted to NRC by the
end of calendar year 1986 to permit its use prior to the next operability demon-
stration of the squib valves scheduled for the 1987 refueling outage.
If your
plans are different than as stated above, please contact this office within 10
working days of your receipt of this letter.
No violations were identified within the scope of this inspection.
No reply to this letter is required.
Your cooperation with us in this matter is
appreciated.
Sincerely,
07181Da1 S1 Ded Byt
8
Edward C. Wenzinger, Chief
Projects Branch No. 3
8608040130 860729
Division of Reactor Projects
ADOCK 05000271
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Corporation
Enclosures:
1.
NRC Region I Inspection Report No. 50-271/86-10
2.
Attachment I - Status of Inspectior. Findings
3.
Attachment II - Operator Interviews
4.
Attachment III - References and Procedures Reviewed
cc w/encls:
Mr. R. W. Capstick, Licensing Engineer
Mr. J. Gary Weigand, Presiderst and Chief Executive Officer
Mr. J. P. Pelletier, Plant Manager
Mr. Donald Hunter, Vice President
Mr. Cort Richardson, Vermont Public Interest Research Group, Inc.
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
State of New Hampshire
State of Vermont
NRC Resident Inspector
bcc w/encls:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encis)
DRP Section Chief
DRP Branch Chief
M. McBride, SRI, Pilgrim
H. Eichenholz, SRI, Yankee
V. Rooney, LPM, NRR
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