ML17250B154
| ML17250B154 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/09/1990 |
| From: | Hodges M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17250B156 | List: |
| References | |
| NUDOCS 9005160099 | |
| Download: ML17250B154 (4) | |
See also: IR 05000244/1989081
Text
lHAY 0 9
doggo
Docket No. 50-244
Rochester
Gas
and Electric Corporation
ATTN:
Mr. Robert
C. Mecredy
General
Manager
Nuclear Production
49 East Avenue
Rochester,
14649
Gentlemen:
Subject:
NRC Safety
System Functional
Inspection
Team Report
No. 50-244/89-81
This letter forwards the report of the Safety
System Functional
Inspection
(SSFI) performed
by an
NRC team from November
6 to December 8, 1989,"at the
R.
E. Ginna Nuclear
Power Plant.
The team's findings and preliminary conclusions
were
summarized for you and members of your staff at the exit meeting held at
the
R.
E. Ginna site
on December
8,
1989.
The objective of the
was to assess
the capability of the residual
heat
removal
(RHR) system to perform its design basis
safety functions.
The team
evaluated
the adequacy
of operational
procedures,
test practices,
and maintenance
policies as they contribute to
RHR system reliability.
The team also addressed
the quality of engineering support'activities.
The team did not identify any
conditions that would prohibit the
RHR system
from performing its intended
functions
under
normal
and design basis accident conditions.
However,
complete
verification of system reliability was not possible
since the design basis
calculati.ons for the
RHR system were not readily available
and in some
cases
do not exist.
The team concluded that numerous
weaknesses
exist in engineering
support
and plant modification activities.
These
weaknesses
are listed in
Section
2. 1,
and are discussed
in Section 2.2 of the enclosed
report,
and have
been assigned
unresolved
item. number 89-81-11.
Additionally, you are requested
to promptly resolve
the discrepancy identified in Section 2.2.4. 1 regarding
the
flooding of the
RHR pump room.
You are requested
to provide us your written
evaluation of these deficiencies. and any planned corrective actions within 120
days of your receipt of this report.
In addition, it appears
that two activities were not conducted
in full compliance
with NRC requirements,
as set forth in the Notice of Violation (NOV) enclosed
herewith as Appendix A.
The violations have
been categorized
by severity level
in accordance
with the "General
Statement
of Policy and Procedure for NRC
Enforcement Actions," 10 CFR Part 2, Appendix
C (Enforcement Policy).
You are
required to respond to this letter and in preparing your response,
you should
follow the instructions in Appendix A.
We also request that, in your response
to the
NOV, you include your schedule for resolving the unresolved
items
(exclusive of 89-81-11 discussed
above) identified in the report.
5'0051600'PS'00509
ADOCK 05000244
9
gpss
Ol
OFFICIAL RECORD
COPY
SC GINNA SSFI " 0001.0.0
05/09/90
l
Rochester
Gas 5 Electric
Corporation
MAY 0 9 lggP
Sincerely,
Original Signed Qy:
Marvin \\V. Hodges
Marvin W. Hodges, Director
Division of Reactor Safety
Enclosures:
1. Appendix A, Notice of Violation
2.
NRC Region I Inspection
Report 50-244/89-81
cc w/encl:
Harry H. Voigt, Esquire
Central
Records
(4 copies)
Director,
Power Division
State of New York, Department of Law
Public Document
Room (PDR)
Local Public Document
Room (LPDR)
Nuclear Safety Information Center
(NSIC)
NRC Resident
Inspector
w York,
SLO Designee
State of Ne
bcc w/encl:
Region I Docket
Room (with concurrences)
Management Assistant,
DRMA (w/o encl)
DRP Section Chief
Monte conner,
SALP Reports
Only
A. Johnson,
PM,
J. Johnson,
E.
McCabe,
Your cooperation with us in this matter is appreciated.
RI:DRS
RI:DRS
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Chaudhary/rw'trosnider
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Hodges
P/g/90
OFFICIAL RECORD
COPY
SC GINNA SSFI " 0002.0.0
04/24/90
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