ML20046A535
| ML20046A535 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/22/1993 |
| From: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Reid D VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| NUDOCS 9307290003 | |
| Download: ML20046A535 (2) | |
See also: IR 05000271/1993012
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JUL 2 21993
Docket No. 50-271
Mr. Donald A. Reid
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Vice President, Operations
Vermont Yankee Nuclear Power Corporation
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RD 5, Box 169
Ferry Road
Brattleboro, Vermont. 05301
Dear Mr. Reid:
SUBJECT: INSPECTION REPORT NO. 50-271/93-12
This refers to your July 2,1993, correspondence, in response to our June 4,1993, letter.
Thank you for informing us of the corrective and preventive actions documented in your
letter. These actions will be examined during a future inspection of your licensed program.-
Your cooperation with us is appreciated.
Sincerely,
Original Signed By:
Glenn W. Meyer
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Lee H. Bettenhausen, Chief
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Operations Branch
Division of Reactor Safety
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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. Tcfft, Administrator, Bureau of Radiological Health, State of New Hampshire
Chief, Safaty Unit, Office of the Attorney General, Commonwealth of Massachusetts
R. Gad, Esquire
G. Bisbee, Esquire
R. Sedano, Vermont Department of Pubiic Service
T. Rapone, Massachusetts Executive Office of Public Safety
K. Abraham, PAO (2) (w/ copy of letter dtd July 2,1993)
Public Document Room (PDR)
Iocal Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector, (w/ copy of letter dtd July 2,1993)
State of New Hampshire, SLO Designee (w/ copy of letter dtd July 2,1993)
State of Vermont, SLO Designee (w/ copy of letter dtd Jcly 2,1993)
Commonwealth of Massachusetts, SLO Designee (w/ copy of letter dtd July 2,1093)_
bec w/ encl:
Region I Docket Room (with concurrences)
bec w/enci (VIA FeMAIL):
V. McCree, OEDO
D. Dorman, NRR
W. Butler, NRR
(VIA E-MAIL AND NO ATTACIIMENTS)
L. Bettenhausen, DRS
R. Conte, DRS
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T. Walker, DRS
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NUCLEAR: POWER CORPORATION
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Ferry Road, erattleboro, VT 05301-7002
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July 2,1993
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U.S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, D.C. 20555
References: a)
License No. DPR-28 (Docket No. 50-271)
b)
Letter, USNRC to VYNPC, Emergency ' Operating -Procedure
inspection (Inspection Report No. 50-271/93-12), NVY 93-085,
dated 6/4/93
Subject:
Reply to a Notice of Violation, inspection Report 93-12
Pursuant to the provisions of 10CFR2.201, this letter is written in ' response to
Reference b) which documents that one of our activities was not conducted in full
compilance with NRC requirements. The Violation, classified at Severity Level V, was
identified during a special Safety inspection conducted by your office on May 11-12,
1993. Our response is provided below:
VIOLATION:
10 CFR 50, Appendix B, Criterion V, requires that activities affecting quality -
shall be prescribed by documented instructions, procedures, or drawings,
of a type appropriate to the circumstances and that the instructions,
procedures, or drawings shall include appropriate quantitative or
qualitative acceptance criteria for determining that important activities
have been satisfactorily accomplished.
Contrary to the above, OP 4110, " Reactor Recirc System Surveillance",
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Rev.17, dated July 11, 1991, did not contain appropriate' acceptance:
criteria for determining that the surveillance requirements of. Technical Specification 4.6.F.2 were met. OP 4110 was not adequate to ensure that
the baseline data for determining jet pump operability _during single loop
operation from November _9,1992, to November 13,1992, was acquired in -
accordance_with Technical Specification 4.6.F.3.
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VERMONT YANKEE NUCLEAR POWER CORPORATION
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U.S. Nuclear Regulatory Commission
July 2,1993
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RESPONSE:
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Based on our assessment, the root cause of this violation was our failure to ensure that
Technical Specification requirements were appropriately incorporated into the plant
procedures. As noted in the inspection Report (Reference b), Procedures OP-4110,
Reactor Recire System Surveillance and OP-2428, Single Loop Operation, have been
revised to provide specific instructions to correct this problem. Additionally, Procedure
OP-4110 has been revised to include OP-2428 as a reference.
Although this particular problem has been corrected, its occurrence highlights the
need for a more comprehensive review to ensure that Technical Specification
surveillance requirements are accurately incorporated into implementing procedures.
We will perform a review of procedures that implement Technical Specification
surveillance requirements to ensure management's expectations in this area are being
met. This review will begin in the near future and will address such items as the intent
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of the Technical Specification surveillance requirements, assumptions, trending,
administrative limits and clarity of procedural instructions. By December 1993, we will
be prepared to provide a summary of the progress of this effort and the projected
completion date.
We trust that the information provided in this response is adequate; however, should
you have questions or require additional information, please contact this office.
Sincerely,
Vermont Yankee Nuclear Power Corporation
D
&
Donald A. Reid
Vice President, Operations
USNR'C Reylonl A'dministrator:
cc: