ML20196J416
| ML20196J416 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/30/1999 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | Sellman M WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20196J423 | List: |
| References | |
| TAC-MA4321, TAC-MA4322, NUDOCS 9907070270 | |
| Download: ML20196J416 (3) | |
Text
F
)
f %,\\
j s f UNITED STATES
..'f j
NUCLEAR REGULATORY COMMISSION
)
WASHINGTON, D.C. - aaa1
\\*****.
June 30, 1999 Mr. Michael B. Sellman Senior Vice President and Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201'
SUBJECT:
EVALUATION OF PUMP AND VALVE INSERVICE TESTING PROGRAM REQUESTS FOR RELIEF FOR POINT BEACH NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. MA4321 AND MA4322)
Dear Mr. Sellman:
In a letter dated September 30,1998, Wisconsin Electric (WE), licensee for Point Beach Nuclear Power Plant, Units 1 and 2, submitted relief requests for their Pump and Valve Inservice Testing (IST) Program, Revision 5. A conference call was held with licensee personnel on February 18, 1999. In response to the call, the licensee submitted a letter dated April 19,1999, clarifying its alternative testing methods against the requirements of Section XI of the American Society of Mechanical Engineers (ASME) " Boiler and Pressure Vessel Code" pursuant to Section 50.55a of Part 50 to Title 10 of the Code of FederalRegulations.
The licensee's IST program was developed in accordance with the 1986 Edition of the ASME Code,Section XI, Subsections IWP and IWV. However, portions of the 1989 Edition of the ASME Code,Section XI have been adopted per 10 CFR 50.55a(f)(4)(iv). The licensee specified which portions of the 1989 Code it has adopted in its letter dated April 19,1999.
l The staff reviewed WE's relief requests VRR-01, VR-02, PRR-01, and ROJ-16 described in the September 30,1998 letter. The results of the staff's review are provided in the attached safety evaluation. The proposed alternatives provided reasonable assurance of operational readiness. The proposed alternatives described in VRR-01 and ROJ-16 are authorized pursuant to 10 CFR 50.55a(a)(3)(ii). Compliance with the specified Code requirements would result in hardship or unusual difficulty without compensating increase in the level The proposed alternatives to the Code requirements described in PRR-01 and VRR-02 4g' asfurcensem m nan 9907070270 990630 PDR ADOCK 05000266 P
PDR w-
f:
t
- Mr. Michael B. Sellmon.
are authorized pursuant to 10 'CFR 50.55a(a)(3)(i) based en the alternatives providing an acceptable level of quality and safety.
Sincerely, L
h b CA.
b
(
s Claudia M. Craig, Chief, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Safety Evaluation cc w/ encl: See next page l
l l
I t
E Mr. Michael B. Sellman Point Beach Nuclear Plant
~ '
Wisconsin Electric Power Company Units 1 and 2 cc:
l l
Mr. John H. O'Neill, Jr.
Ms. Sarah Jenkins Shaw, Pittman, Potts & Trowbridge Electric Division 2300 N Street, NW Public Service Cortmission of Wisconsin Washington, DC 20037-1128 P.O. Box 7854 Madison, Wisconsin 53707-7854 Mr. Richard R. Grigg l
President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Mark E. Reddemann Site Vice President Point Beach Nuc'aar Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman l
Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region lil U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office l
U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 October 1998 L-