ML17264A795
| ML17264A795 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/09/1997 |
| From: | Doerflein L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17264A796 | List: |
| References | |
| NUDOCS 9701170246 | |
| Download: ML17264A795 (5) | |
See also: IR 05000244/1996011
Text
January 9,
1997
Dr. Robert C. Mecredy,
Vice President,
Ginna Nuclear Operations
Rochester
Gas and Electric Corporation
89 East Avenue
Rochester,
NY 14649
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-244/96-11
Dear Dr. Mecredy:
This report transmits the findings of safety inspections conducted by NRC inspectors at the
Ginna Nuclear Power Plant from October 6 through November 16, 1996. At the
conclusion of the inspection, the findings were discussed with members of your staff.
Overall, we observed safe plant operation.
During this inspection period, Ginna was shut
down for seventeen
days to replace the station's main output transformer.
We noted that
the high combustible gas concentrations
that led to the replacement were detected very
early by your staff and prevented
a potentially hazardous
situation.
We concluded the
transformer replacement reflected a high regard for overall plant safety.
We also noted
your staff took advantage
of the outage to accomplish several significant maintenance
and
modification activities.
The repairs and upgrades
on auxiliary feedwater, residual heat
removal, and condenser
steam dump valves and improvements
in the microprocessor
rod
position indication equipment enhanced
operational safety of the plant.
We found the
contribution and close involvement of your engineering
organization in all activities were
key factors in meeting the goals of the outage in a timely fashion.
We noted an instance where miscommunication between the in-plant and control room
operators resulted in shutting the safety injection system pump discharge valve breakers
during a mode change before allowed by procedure.
We also noted another instance
where control room operators expressed
difficultywith interpreting the requirements of the
improved technical specifications regarding the auxiliary feedwater system.
While neither
of the specific events resulted in safety significant consequence,
we have noted similar
problems in the past and it appears
continued management
attention is warranted in these
areas.
OFFICIAL RECORD
COPY
IE: 01
970ii70246 970i09
ADOCK 05000244
8
Dr. Robert C. Mecredy
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.
We appreciate your cooperation.
Sincerely,
Original Signed by:
Lawrence T. Doerflein, Chief
Reactor Projects Branch
1
Division of Reactor Projects
Docket No.:
License No.:
Enclosure:
50-244
NRC Region
I Inspection Report 50-244/96-11
cc w/encl:
R. Smith, Senior Vice President,
Customer Operations
Central Records
(7 copies)
P. Eddy, 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
/ w
)
Dr. Robert C. Mecredy
Distribution w/encl:
Region
I Docket Room (with concurrences)
PUBLIC
NRC Resident Inspector
Nuclear Safety Information Center (NSIC)
D. Screnci, PAO (17) SALP Reports and (1) All Inspection Reports
R. Correia, NRR
R. Frahm, Jr., NRR
L. Cunningham,
D. Barss, NRR
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)
DOCUMENT NAME: G:IIBRANCH1IIIR96-11.GIN
To receive a copy of this document. Indicate In the box:
C
~ Copy without anachment/enclosure
E
~ Copy with attachment/enclosure
N
No copy
OFFICE
NAME
DATE
RI/DRP
Drysdale
01/q/97
Rl/DRP
Doe rflein
01 / /97
OFFICIAL RECORD COPY