ML20206E706
| ML20206E706 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/01/1987 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20206E710 | List: |
| References | |
| EA-87-036, EA-87-36, NUDOCS 8704130694 | |
| Download: ML20206E706 (3) | |
See also: IR 05000423/1986039
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APR 011987
Docket No. 50-423
License No. NPF-49
EA 87-36
Northeast Nuclear Energy Company
ATTN: Mr. E. J. Mroczka
Senior Vice President - Nuclear
Engineering and Operations Group
P. O. Box 270
Hartford, Connecticut 06141-0270
Gentlemen:
Subject: NOTICE OF VIOLATION
(Inspection No. 50-423/86-39)
This refers to the NRC resident safety inspection conducted between December
29, 1986 and January 7, 1987 at the Millstone Nuclear Power Station, Unit 3,
Waterford, Connecticut. The inspection report was sent to you on January 21,
1987. During the inspection, NRC inspectors reviewed the circumstances
associated with a violation of a technical specification limiting condition for
operating (LCO) which was identified by a member of your staff and reported to
the NRC. The violation, which is described in the enclosed Notice, involved
the inoperability of one of the two safety injection systems. On February 27,
1987, an enforcement conference was conducted with you and members of your
staff to discuss the violations, their causes, and your corrective act'ons.
The one safety injection system (SI) was inoperable in that a service water
outlet vahe to the SI pump cooler was closed, thereby preventing the flow of
service cooling water to the pump cooler which in turn provides cooling for the
pump lubricating oil. As a result, the pump could have failed during opera-
tion. The valve was closed by a shift supervisor staff assistant (SSSA) during
a weekly test to determine fouling of the service water side of the heat
exchanger. However, the SSSA encountered difficulty in obtaining a needed
power supply, and he did not complete the test or reopen the valve.
The NRC is concerned that this SSSA, a recent college graduate with no prior
operating experience, was allowed to perform this test without adequate
training and supervision.
Further, the test procedure was deficient in that it
did not:
(1) specify that the valve would be manipulated; (2) require a valve
lineup verification; (3) require shift supervisor approval prior to
implementing; and (4) indicate that an LCO would be affected. As a result, the
individual manipulated plant equipment which affected a safety system, and the
shift supervisor was unaware of this activity. Manipulation of plant equipment
without the knowledge of the shift supervisor is a significant concern to the
NRC.
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The NRC is also concerned that the SSSA had documented a record indicating
that the test was completed, even though the test had not been performed.
These events demonstrate the need for, and importance of, better review and
evaluation of procedures prior to approval, and enhanced training and super-
vision of employees, particularly those employees without any prior operating
experience, to ensure that performance of activities by these individuals does
not adversely affect operation of the facility. Therefore, although the vio-
lation nas been classified at Severity Level IV in accordance with the " General
Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2,
Appendix C (Enforcement Policy) (1986), we emphasize that any similar viola-
tions in the future may result in additional enforcement action.
You are required to respond to the enclosed Notice and, in preparing your res-
ponse, you should follow the instruction specified in the Notice.
In your res-
ponse, you should document the actions taken or planned to prevent recurrence.
After reviewing your response to the Notice, including your proposed corrective
actions and the results of future inspections, the NRC will determine whether
further enforcement action is necessary to ensure compliance with NRC
regulatory requirements.
In accordance with 10 CFR 2.790, a copy of this letter and its enclosure will
be placed in the NRC Public Document Room.
The responses directed by this letter and the enclosed Notice are not subject
to the clearance procedures of the Office of Management and Budget, otherwise
required by the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely,
William F. Kane, Director
Division of Reactor Projects
Enclosure:
cc w/ encl:
W. D. Romberg, Vice President, Nuclear Operations
D. O. Nordquist, Manager of Quality Assurance
R. M. Kacich, Manager, Generation Facilities Licensing
S. E. Scace, Station Superintendent
Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Senior Resident Inspector
State of Connecticut
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Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
DRP Section Chief
L. Prividy, RI, BV-2
T. Rebelowski, SRI, Millstone 1&2
B. Doolittle, LPM, NRR
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