ML20033G645
| ML20033G645 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/03/1990 |
| From: | Swenson W Office of Nuclear Reactor Regulation |
| To: | Fay C WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-72027, TAC-72028, NUDOCS 9004100456 | |
| Download: ML20033G645 (3) | |
Text
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April 3,1990 i
Docket Nos. 50-266 DISTRIBUTION:
and 50-301 BRDTTYHT~e NRC & Local PDRs m PD!ll-3 r/f JZwolinski JHannon WSwenson LDaniels PKreotzer OGC-WF1 EJordan Mr. C. W. Fay, Vice President ACR$(10)
RJones Nuclear Power Department PDill-3 Gray Wisconsin Electric Power Company 231 W. Michigan Street, Room 308 Milwaukee, Wisconsin 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - STEAM GENERATOR TUBE RUPTURE ANALYSIS (TACS 72027/72028)
By letter dated February 22, 1989, we requested additional information con-cerning the Point Beach steam generator tube rupture (SGTR) analysis used to support your increased core power peaking factor amendment application.
We requested that WEPCO justify the 30-minute safety injection (SI) termi-nation time or reevaluate the SGTR event in accordance with the current, staff-approved methodology, i.e., WCAP-10698A.
In your submittal dated March 10, 1989, you responded to our request for additional information.
After reviewing your response, the staff believes that WEPCO has adequately justifiel the 30-minute assumption for SI termination res)onse time.
Further, the staff has concluded that this response time is wit 11n your licensing basis.
As a result, we believe that further NRC review of your SGTR analysis is not required.
This concludes our review effort on TACS 72027 and 72028.
Sincerely,
/s/
Warren H. Swenson, Project Manager Project Directorate 111-3 j
Division of Reactor Projects - Ill, IV, V and Special Projects l
Office of Nuclear Reactor Regulation cc: See next page DOCUMENT NAME: 72027/28 CLOSEOUT e
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April 3, 1990 Docket Nos. 50-?66 and 50-301 l
l Mr. C. W. Fay, Vice President Nuclear Power Department Wisconsin Electric Power Company 231 W. Michigan Street, Room 308 Milwaukee, Wisconsin 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - STEAM GENERATOR TUBE RUPTURE ANALYSIS (TACS 72027/72028)
By letter dated February 22, 1989, we requested additional information con-cerning the Point Beach steam generator tube ^ rupture (SGTR) analysis used t
l to support your increased core power peaking factor amendment application.
We requested thr.t WEPC0 justify the 30-minute safety injection (SI) termi-nation time or reevaluate the SGTR event in accordance with the current, staff-approved methodology, i.e., WCAP-10698A.
In your submittal dated March 10, 1989, you responded to our request for additional information. After reviewing your response, the staff believes that WEPC0 has adequately justified the 30-minute assunotion for $1 termination response time.
Further, the staff has concluded that tiis response time is l
within your licensing basis.
l As a result, we believe that further NRC review of your SGTR analysis is not required. This concludes our review effort on TACS 72027 nd 72028.
Sincerely, 1
Warren H. Swenson, Proje anager Project Directorate III-3 l
Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation cc: See next page l
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Mr. C. W. Fay Point Beach Nuclear Plant i
Wisconsin Electric Power Company Units 1 and 2 cc:
Ernest L. Blake, Jr.
Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washingt]n, DC 20037 Mr. James J. Zach, Manager Point Beach Nuclear Plant l
Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Town Chairman i
Town of Two Creeks l
Route 3 Two Rivers, Wisconsin 54241 Chairman Public Service Ccmmission of Wisconsin Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region !!!
U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 l
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