ML17264A703
| ML17264A703 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/18/1996 |
| From: | Doerflein L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17264A704 | List: |
| References | |
| NUDOCS 9610290072 | |
| Download: ML17264A703 (3) | |
See also: IR 05000244/1996007
Text
October 18,
1996
Dr. Robert C. Mecredy
Vice President,
Ginna Nuclear Production
Rochester
Gas and Electric Corporation
89 East Avenue
Rochester,
NY 14649
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-244/96-07
Dear Dr. Mecredy:
From July 21 through August 24, 1996, the NRC conducted
an inspection at your Ginna
reactor facility. At the conclusion of the inspection, the results were discussed with Mr. J.
Widay of your staff. The enclosed report presents the results of that inspection.
During this inspection period we noted several examples of good maintenance
and testing
activities.
For example, we found the upgrade of the residual heat removal system core
deluge valve actuators was well coordinated
and implemented.
Also, the installation and
testing of a replacement
service water pump motor was well coordinated
and effectively
performed.
Good involvement by engineering
and management
led to the timely resolution
of the defective motors.
In addition, the diagnostic testing and thermography survey of
the emergency diesel generators
were viewed as proactive and good initiatives.
However, we concluded that problems with safety injection system accumulator leakage
and a steam leak on a feedwater system valve were not aggressively
pursued.
Also, your
staff's decision to return the plant to power operations within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> following the
automatic reactor trip on August 20, 1996, without correcting the degraded
conditions
lacked the conservative
operating philosophy usually noted.
In addition, we noted another
instance where equipment configuration and work control problems during a forced outage
challenged operators
and resulted in an engineered
safety feature system actuation during
a main turbine control valve test.
In accordance
with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter
and its enclosures will be placed in the NRC Public Document Room.
Sincerely,
Original Signed
by:
Lawrence T. Doerflein, Chief
Reactor Projects Branch
1
Division of Reactor Projects
qb10290072
'PbiOi8
ADQCK 05000244
8
OFFICIAL RECORD
COPY
IE: 01
(f
Dr. Robert C. Mecredy
Docket No.:
50-244
License No.:
Enclosure:
NRC Region
I Inspection Report 50-244/96-07
cc w/encl:
R. Smith, Senior Vice President,
Customer Operations
Central Records
(7 copies)
Director, Electric Division, Department of Public Service, State of New York
State of New York, Department of Law
N. Reynolds, Esquire
F. William Valentino, President,
New York State Energy Research
and Development Authority
J. Spath, Program Director, New York State Energy Research
and Development Authority
I
~
~
Dr. Robert C. Mecredy
Distnbution w/encl:
Region
I Docket Room (with concurrences)
PUBLIC
NRC Resident Inspector
Nuclear Safety Information Center (NSIC)
D. Screnci, PAO (1)
L. Doerflein, DRP
T. Moslak, DRP
R. Junod,
Distribution w/encl (VIAE-MAIL):
W. Dean, OEDO
S. Bajwa, NRR
G. Vissing, NRR
A. Dromerick, NRR
M. Campion, ORA
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
R. Frahm, Jr., NRR
DOCUMENT NAME: A:IR96-07.GIN
To receive a copy of this document, indicate in the box: "C" = Copy without
attachment/enclosure
"E" = Copy with attachment/enclosure
"N" = No copy
OFFICE
RI/DRP
NAME
PDrysdale
P
DATE
1 0/!8/96
RI/DRP
LDoerflein
10/Ig/96
OFFICIAL RECORD COPY