ML17265A525
| ML17265A525 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/29/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17265A526 | List: |
| References | |
| 50-244-91-201, TAC-M84947, NUDOCS 9902030181 | |
| Download: ML17265A525 (9) | |
See also: IR 05000244/1991201
Text
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Dr. Robert C. Mecredy
Vice President, Nuclear Operations
Rochester Gas and Electric Corporation
89 East Avenue
Rochester, NY 14649
UNITED STATES
NUCLEAR REGULATORY COIVIMISSION
WASHINGTON> D.C. 20555-0001
january
29,
1999
SUBJECT: SERVICE WATER SYSTEM AT R.E. GINNA NUCLEAR POWER PLANT
Dear Dr. Mecredy:
The service water (SW) system operational performance inspection was conducted from
December 2 through 20, 1991, at the Ginna Nuclear Power Plant. The findings were reported
in Inspection Report 50-244/91-201.
Several outstanding issues were identified in the
inspection report for further licensee review and resolution.
Six issues were identified for
further review by the NRC staff. The issues are as follows:
2.
3.
4
5.
6.
Application of hydraulic model to the service water system (SWS)
SW pump discharge check valve single failure vulnerability
Basis for the SWS low pressure setpoint
Single failure vulnerabilities with open cross-connect valves
Resolution of preoperational test discrepancies
Technical Specification requirements for operable pumps
You submitted your response
in a letter dated April6, 1992. Our initial review found that each
of the outstanding issues in the inspection report was addressed
and there were no immediate
safety concern.
However, several action items required further review; in particular, the item
regarding the number of pumps required for post-loss-of-coolant-accident
(LOCA) recirculation
phase.
You submitted additional information between April9, 1992, and November 4, 1998, in
response to the action items. Our review identified an additional item regarding the licensing
basis for the cross-connection
and isolation valves. The review for all of the items have been
completed and are discussed
in the enclosed safety evaluation.
As an interim measure while the NRC continued to evaluate your analyses supporting the use
of only one SW pump during the recirculation phase, by letter dated April6, 1992, you
implemented compensatory measures
in the Ginna administrative controls. These measures
require operability of three SW pumps (while the reactor is at power) and provisions to utilize
the bus tie breaker between 480-v safeguards ac buses 17 and 18 during the recirculation
phase post-LOCA in order to provide power to two SW pumps from a single diesel generator.
The administrative controls requires that ifat least three SW pumps are not restored to
operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then place the plant in hot shutdown within a completion time
of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within a completion time of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
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Dr. Mecredy
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Based on our findings regarding this issue, you can now remove the administrative controls
that required operability of three SW pumps and the provisions to utilize the bus tie breaker
between 480-v safeguards ac buses 17 and 18 during the recirculation phase post-LOCA in
order to provide power to two SW pumps from a single diesel generator.
Your operation may
continue in accordance with Technical Specifications.
This completes our effort on TAC
No. M84947.
Sincerely,
Original signed
by:
Guy S. Vissing, Senior Project Manager
Project Directorate l-1
Division of Reactor Projects - I/II
Office of Nuclear Reactor Regulation
Docket No. 50-244
Enclosure:
Safety Evaluation
ccw/encl: See next page
PUBLIC
DISTRIBUTION:
~Docket File
PDI-1 R/F
J. Zwolinski
S. Bajwa
S. Little
G. Vissing
G. Hubbard
D. Jackson
T. Harris (e-mail SE only)
R. Blough, Region
I
DOCUMENT NAME: G:hGINNA)LTR84947.WPD
To receive
a copy of this docunent,
indicate in the box:
"C" = Copy without attachment/enclosure
"E" = Copy with
attachment/enclosure
"N" = No co
OFFICE
PM:PDI-1
GVissing:lcc
NAME
DATE
01/ %99
LA:PDI-
SLittl
01/
99
D:PDI-1
SBajwa
01/
/99
SPLB
LMarsh
01/
/99
OFFICIAL RECORD COPY
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january
29,
1999
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,~
Dr. Mecredy
-2-
Based on our findings regarding this issue, you can now remove the administrative controls
that required operability of three SW pumps and the provisions to utilize the bus tie breaker
between 480-v safeguards
ac buses 17 and 18 during the recirculation phase post-LOCA in
order to provide power to two SW pumps from a single diesel generator.
Your operation may
continue in accordance with Technical Specifications.
This completes our effort on TAC
No. M84947.
Sincerely,
Original signed
by:
4
Guy S. Vissing, Senior Project Manager
Project Directorate I-1
Division of Reactor Projects - I/II
Office of Nuclear Reactor Regulation
Docket No. 50-244
Enclosure:
Safety Evaluation
cc w/encl: See next page
PUBLIC
DISTRIBUTION:
Docket File
PDI-1 R/F
J. Zwoiinski
S. Bajwa
S. Little
G. Vissing
G. Hubbard
D. Jackson
T. Harris (e-mail SE only)
R. Blough, Region
I
DOCUMENT NAME: G:LGINNA)LTR8494?.WPD
To receive
a copy of this docunent,
indicate in the box:
>>C>> >> Copy without attachment/enclosure
>>E>> = Copy with
attachment/enclosure
>>li>> >> Iio co
OFFICE
PII:PDI-1
TAHE
GViss ing: Icc
DATE
01/ &99
LA:PDI-
SLittl
01/
99
0:PD I.1
SBa
wa
01/
/99
SPLB
LHarsh
01/
/99
OFFICIALRECORD COPY
j
a
Dr. Mecredy
-2-
Based on our findings regarding this issue, you can now remove the administrative controls
that required operability of three SW pumps and the provisions to utilize the bus tie breaker
between 480-v safeguards ac buses 17 and 18 during the recirculation phase post-LOCA in
order to provide power to two SW pumps from a single diesel generator.
Your operation may
continue in accordance with the Technical Specifications.
This completes our effort on TAC
No. M84947.
Sincerely,
Guy S. Vissing, Senior Project Manager
Project Directorate I-1
Division of Reactor Projects - I/II
Office of Nuclear Reactor Regulation
Docket No. 50-244
Enclosure:
Safety Evaluation
cc w/encl: See next page
Dr. Robert C. Mecredy
Rochester Gas and Electric Company
R.E. Ginna Nuclear Power Plant
CC:
Peter D. Drysdale, Sr. Resident Inspector
R.E. Ginna Plant
U.S. Nuclear Regulatory Commission
1503 Lake Road
Ontario, NY 14519
Regional Administrator, Region
I
U.S. Nuclear Regulatory Commission
475 Allendale Road
King of Prussia, PA 19406
Mr. F. WilliamValentino, President
New York State Energy, Research,
and Development Authority
Corporate Plaza West
286 Washington Avenue Extension
Albany, NY 12203-6399
Charles Donaldson, Esquire
Assistant Attorney General
New York Department of Lalw
120 Broadway
New York, NY 10271
Nicholas S. Reynolds
Winston & Strawn
1400 S Street N.W.
Washington, DC 20005-3502
Ms. Thelma Wideman, Director
Wayne County Emergency Management
Office
Wayne County Emergency Operations Center
7336 Route 31
Lyons, NY 14489
Ms. Mary Louise Meisenzahl
Administrator, Monroe County
Office of Emergency Preparedness
111 West FaIls Road, Room 11
Rochester,
NY 14620
Mr. Paul Eddy
New York State Department of
Public Service
3 Empire State Plaza, 10th Floor
Albany, NY 12223
)
I