ML20058A335
| ML20058A335 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/12/1993 |
| From: | Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Reid D VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20058A337 | List: |
| References | |
| NUDOCS 9312010048 | |
| Download: ML20058A335 (3) | |
See also: IR 05000271/1993021
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NOV I 21993
Docket No. 50-271
- Mr. Donald Reid
Vice President, Operations
Vermont Yankee Nuclear Power Corporation
RD 5, Box 169
Ferry Road
Brattleboro, Vermont 05301
Dear Mr. Reid:
SUBJECT:
VERMONT YANKEE INSPECTION 93-21
This refers to the safety inspection conducted by Messrs H. Eichenholz, P. Harris, and
T. Shediosky on September 12 - October 9,1993, at the Vermont Yankee Nuclear Power
Station, Vernon, Vermont. The preliminary results were discussed with Mr. R. Wanczyk at the
conclusion of the inspection. The inspection focused on issues important to public health and
safety, and consisted of performance observations of the conduct of operations and maintenance,
and independent assessment of safety system status and quality records.
Good outage performance was evident in many instances including recovery of the dropped fuel
bundle, testing of the Vernon Tie blackout source, troubleshooting of a ground on the startup
transformer, inspection of the reactor vessel core shroud,'and residual heat removal heat
exchanger repairs.
We are, however, concerned regarding your staff's interpretation - of your Technical
Specifications. Specifically. your justification to voluntarily remove an emergency diesel
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generator from service during a time when secondary containment integrity was required was
inappropriately based on a Technical Specification requirement associated with core and
containment cooling. Your staff apparently recognized the ambiguity of the applicable Technical
Specification, but relied on past conversations with the NRC (referenced in a July 9,1984
Vermont Yankee letter to the NRC) that addressed this interpretation and failed to implement
your Limiting Condition of Operation Maintenance Guidelines.- We recommend that you
consider a change to your Technical Specifications to clarify the performance of fuel handling
activities with one eme gency diesel generator out of service. This initiative should reduce any
such ambiguity, and place your license more in line with licensed conditions at other boiling
water reactor facilities.
9312010048 931112
ADOCK 05000271
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NOV I 21993
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Mr. Donald Reid
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No response is required to this letter, and your cooperation with us during this inspection was
appreciated.
Sincerely,
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. mes C. Linville, Ch'
Reactor Projects Bra - 3
Division of Reactor Projects
Enclosure: NRC Inspection Report 50-271/93-21
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cc w/ encl:
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R. Wanczyk, Plant Manager
J. Thayer, Vice President, Yankee Atomic Electric Company
L. Tremblay, Senior Licensing Engineer, Yankee Atomic Electric Company
J. Gilroy, Director, Vermont Public Interest Research Group, Inc.
D. Tefft, Administrator, Bureau of Radiological Health, State of New Hampshire
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Chief, Safety Unit, OfGee of the Attorney General, Commonwealth of Massachusetts
R. Gad, Esquire
G. Bisbee, Esquire
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R. Sedano, Vermont Department of Public Service
T. Rapone, Massachusetts Executive Office of Public Safety
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
K. Abraham, PAO (2 copies)
NRC Resident inspector
State of New Hampshire, SLO Designee
State of Vermont, SLO Designee
Commonwealth of Massachusetts, SLO Designee
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Mr. Donald Reid
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bec w/ encl:
Region 1 Docket Room (with concurrences)
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E. Kelly, DRP
J. Shediosky, DRP
M. Oprendek, DRP
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bec w/ encl (VIA E-MAIL):
V. McCree, OEDO
D. Dorman, NRR
W. Butler, NRR
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