ML17254A440
| ML17254A440 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/08/1985 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17254A441 | List: |
| References | |
| NUDOCS 8507160488 | |
| Download: ML17254A440 (4) | |
See also: IR 05000244/1985010
Text
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Docket No. 50-244
Rochester
Gas
and Electric Corporation
ATTN:
Mr. Roger
W. Kober
Vice President
Electric and
Steam Production
49 East Avenue
Rochester,
New York 14649
Gentlemen:
Subject:
Inspection
50-24 /85-10
This refers to the routine safety inspection
conducted
by Mr. W. A. Cook
of this office on May 1,
1985 through June
15,
1985 at the
R.
E. Ginna Nuclear
Power Plant of activities authorized
by
NRC license
No.
DPR-18 and to the
discussions
of our findings by Mr. Cook with Mr. B. A.
Snow and other members
of your staff periodically during the inspection.
Areas
examined during this inspection
are described
in the
NRC Region I
Inspection
Report which is enclosed with this letter.
Within these
areas,
the
inspection consisted
of selective
examinations of procedures
and
representative
records,
interviews with personnel
and observations
by the
inspector.
Based
on the results of this inspection, it appears
that one of your
activities was not conducted
in full compliance with the
NRC requirements,
as
set forth in the Notice of Violation, enclosed
herewith
as Appendix A.
Specifically,
upon review of the compensatory
measures
taken for the
inoperability of Technical Specification Fire Detection
Systems,
the inspector
determined that the containment
temperature
monitoring system
used, is not
incorporated
in any of the station's
routine surveillance
programs.
Although
the temperature
monitoring system
was calibrated, this is the second
instrument identified, within the past
few months,
which is utilized in
a
safety-related
capacity
and not incorporated into a surveillance
program.
This violation indicates
the need for more careful
review and controls
on
instrumentation
and/or equipment
used directly or indirectly to monitor
safety-related
systems
and components.
This violation has
been categorized
by severity level in accordance
with the
revised
NRC Enforcement Policy (10 CFR 2, Appendix C) 1985.
You are required
to respond
to this letter and in preparing your response,
you should follow
the instructions in Appendix A.
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OFFICIAL RECORD
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The responses
directed
by this letter and the accompanying
Notice are not
subject to the clearance
procedures
of the Office of Management
and Budget
as
required
by the Paperwork Reduction Act of 1980,
PL 96-511.
In addition, the reactor trip of June
6,
1985
and similar maintenance
and
troubleshooting
related events
which have occurred over the past
few months
provide indications of a trend of insufficient preplanning
and managerial
oversight.
Me look forward to reviewing your analysis of the June
6 reactor
trip event in this regard.
Your cooperation with us in these
matters is appreciated.
Sincerely,
Ori81n81 Sig ea BVS
Samuel J. Collins, Chief
Projects
Branch
No.
2
Division of Reactor Projects
Enclosure:
NRC Region I Inspection
Report
Number 50-244/85-10 with Attachments
cc w/encl.
Harry H. Voigt, Esquire
Central
Records
(4 copies)
Director,
Power Division
Public Document
Room (PDR)
Local Public Document
Room (LPDR)
Nuclear Safety Information Center
(NSIC)
NRC Resident
Inspector
State of New York
bcc w/encl:
Region I Docket
Room (with concur rences)
Senior Operations Officer (w/o encls)
Section Chief,
Director,
DETP
RP:RI
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6/A/85
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OFFICIAL RECORD
COPY
IR GINNA 85-10 - 0001.0.1
06/27/85
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