ML17334B292
| ML17334B292 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/30/1989 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17334B293 | List: |
| References | |
| TAC-64962, TAC-64963, NUDOCS 8902030119 | |
| Download: ML17334B292 (3) | |
Text
January 30, 1989 Docket Nos.
50-315 and 50-.316 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
DISTRIBUTION:
Docket FHes I NRC PDR~
Local PDR TMeeks(8)
Wanda Jones MVirgilio JStang RIngram r
DHagan EJordan BGrimes OGC ARM/LFMB EButcher GPA/PA ACRS(10)
SUBJECT:
CHANGE TO LICENSING BASIS FOR SI AND RHR CROSSTIES (TACS NOS.
64962 AND 64963)
By letter dated March 23, 1987, as supplemented May 13, 1987, August 22, 1988, and January 17, 1989, you requested NRC staff concurrence with your interpretation of Technical Specifications (TSs) 3. 5. 2. e and 3. 5. 3. d for Donald C.
Cook Nuclear Plant, Units 1 and 2, concerning emergency core cooling system (ECCS) subsystem operability.
Your letter included technical justification for the interpretation.
Your 'nterpretation of the TSs is such that the flow path portion of one ECCS subsystem is considered operable when a Residual Heat Removal (RHR) pump or Safety Injection (SI) pump can deliver flow to two instead of four Reactor Coolant System (RCS) loops because of crosstie valve closure.
This configuration is such that flow from a single operating RHR or SI pump can be delivered to only two RCS loops with the other pump aligned to deliver flow to four loops.
The NRC staff has reviewed your interpretation
- and, based on the enclosed Safety Evaluation, finds that two-loop injection in lieu of four-loop.injection for the RHR or SI systems is allowable.
This approval does not permit operation at reduced temperature and pressure (RTP) conditions.
On October 14, 1988, you submitted additional analyses supporting the RTP program.
We are currently reviewing this submittal, and it will be handled as a future licensing action.
The staff understands that you will be changing your Updated Final Safety Analysis Report to reflect your analysis.
Sincerely,
Enclosure:
Safety Evaluation elga@eftyef Sy John F. Stang, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects cc w/enclosure:
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50-315 and 50-316 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 January 30, 1989 Mr. Milton P. Alexich, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Alexich:
SUBJECT:
CHANGE TO LICENSING BASIS FOR SI AND RHR CROSSTIES (TACS NOS.
64962 AND 64963)
By letter dated March 23,
- 1987, as supplemented May 13, 1987, August 22, 1988, and January 17, 1989, you requested NRC staff concurrence with your interpretation of Technical Specifications (TSs) 3.5.'2.e and 3'.3.d for Donald C.
Cook Nuclear Plant, Units 1 and 2, concerning emergency core cooling system (ECCS) subsystem operability.
Your letter included technical justification for the interpretation.
Your interpretation of the TSs is such that the flow path portion of one ECCS subsystem is considered operable when a Residual Heat Removal (RHR) pump or Safety Injection (SI) pump can deliver flow.to two instead of four Reactor Coolant System (RCS) loops because of crosstie valve closure.
This configuration is such that flow from a single operating RHR or SI pump can be delivered to only two RCS loops with the other pump aligned to deliver flow to four loops.
The NRC staff has reviewed your interpretation
- and, based on the enclosed Safety Evaluation, finds that two-loop injection in lieu of four-loop injection for the RHR or SI systems is allowable.
This approval does not permit operation at reduced temperature and pressure (RTP) conditions.
On October 14, 1988, you submitted additional analyses supporting the RTP program.
Me are currently reviewing this submittal, and it will be handled as a future licensing action.
The staff understands that you will be changing your Updated Final Safety Analysis Report to reflect your analysis.
S
- cerely, 0
ohn F.- Stang Project Manager roject Direc orate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects
Enclosure:
Safety Evaluation cc w/enclosure:
See next page
Mr. Milton Alexich Indiana Michigan Power Company Donald C.
Cook Nuclear Plant CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgeman, Michigan 49106 W.
G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvil le, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Divis ion of Radi ologi cal Heal th Department of Publ ic Heal th 3500 N.
Logan Street Post Office Box 30035 Lansing, Michigan 48909 Mr.
S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio "43216