ML20198C753
| ML20198C753 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/10/1998 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Sellman M WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20198C757 | List: |
| References | |
| TAC-MA4160, NUDOCS 9812220157 | |
| Download: ML20198C753 (4) | |
Text
L
_ ~. _
- 4..
December 10, 1998 Mr. Michael B. Sellman Chief Nuclear Officer l
Wisconsin Electric Power Company i
i' 231 West Michigan Street-Milwaukee, WI 53201 L
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - EVALUATION OF PROPOSED ALTERNATIVE TO ASME CODE REQUIREMENTS FOR REACTOR i-PRESSURE VESSEL EXAMINATION (TAC NO. MA4160)
Dear Mr. Sellman:
The staff has reviewed and evaluated the information provided by Wisconsin Electric Power Company in its letter dated November 2,1998. You have proposed an alternative to the
[
American Society of Mechanical Engineers (ASME) Boiler and Pressure Vesstl Code (Code),
1986 Edition,Section XI requirement IWA-2232, to use the Performance Demonstration Initiative (PDI) Program during the reactor pressure vessel third 10-year Inservice Inspection Interval for Unit 2. The PDI is based on Appendix Vill,Section XI of the ASME Code,1992 Edition including the 10.1 addenda. You requested this based on 10 CFR 50.55a(a)(3)(i).
l The staff has concluded that the use of the aPernative method is authorized for the requested interval pursuant to 10 CFR 50.55a(a)(3)(i) since it provides an acceptable level of quality and safety. A copy of the staff's safety evaluation is enclosed.
If you have any questions, please contact Beth Wetzel at (301) 415-1355.
Sincerely, ORIGINAL SIGNED BY Cynthia A. Carpenter, Director Project Directorate lil-1 I
$Ty[Mg Division of Reactor Projects - Ill/IV l
0 PDR Office of Nuclear Reactor Regulation Docket No. 50-301
\\
\\
Enclosure:
Safety Evaluation cc w/ encl: See next page k
h I
\\'
]
DISTRIBUTION.
i Docket File' PUBLIC.
PD# 3-1 Reading T. Hiltz E. Adensam (EGA1) OGC THarris (TLH3)
B. Burgess, Rlli G. Hill (2)
ACRS-DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTBA4160.RR f
To rece:Ve a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E&opw chment/ enclosure N = No copy OFFICE PM:PD31 Es LA:PD31 sE B[F,0h kOGCAlh D:PD31 E
NAME BWetzel:5bWCJamerk MBagN1i h
CACarpente a
DATE 12/ 3
-/98-12/ /
h8 12/ h /98 12/ 7 -/98 12/ /D /98 L1d d]
r
'. OFFICIAL RECORD COPY l
j
- ~
December 10, 1998 E
Mr. Michael B. Sellman Chief Nuclear Officer Wisconsin Electric Power Company i
)
231 West Michigan Street Milwaukee, WI 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - EVALUATION OF PROPOSED ALTERNATIVE TO ASME CODE REQUIREMENTS FOR REACTOR PRESSURE VESSEL EXAMINATION (TAC NO. MA4160)
Dear Mr. Sellman:
The staff has reviewed and evaluated the information provided by Wisconsin Electric Power Company in its letter dated November 2,1998. You have proposed an attemative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
1986 Edition,Section XI requirement IWA-2232, to use the Performance Demonstration Initiative (PDI) Program during the reactor pressure vessel third 10-year Inservice Inspection Interval for Unit 2. The PDI is based on Appendix Vill,Section XI of the ASME Code,1992 Edition including the 1993 addenda. You requested this based on 10 CFR 50.55a(a)(3)(i).
The staff has concluded that the use of the attemative method is authorized for the requested interval pursuant to 10 CFR 50.55a(a)(3)(i) since it provides an acceptable level of quality and safety. A copy of the staff's safety evaluation is enclosed.
If you have any questions, please contact Beth Wetzel at (301) 415-1355.
Sincerely, ORIGINAL SIGNED BY Cynthia A. Carpenter, Director Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-301
Enclosure:
Safety Evaluation cc w/ encl: See next page DISTRIBUTION:
Docket File PUBLIC PD# 3-1 Reading T. Hiltz E. Adensam (EGA1) OGC THarris (TLH3)
B. Burgess, Rlll G. Hill (2)
ACRS 1
DOCUMENT NAME: G:\\WPDOCS\\PTBEACH\\PTBA4160.RR I
h To receive a copy of this document indicate in the box C= Copy w/o attachment / enclosure E=Cop wtu chment/ enclosure N = No copy OFFICE PM:PD31 Es LA:PD31 sE B[F,Oh kOGCn ((
D:PD31 E
BWetzel:dbW CJamerk Bage i
CACarpente NAME l
DATE 12/ 3
/98 12/ l k8 12/ h /98 12/ 7 /98 12/ / O
/98 l
OFFICIAL RECORD COPY
p ur p
- t UNITED STATES s
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30seMm01 l,
December 10, 1998 1
Mr. Michael B. Sellman Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street
)
i Milwaukee, WI 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - EVALUATION OF PROPOSED ALTERNATIVE TO ASME CODE REQUIREMENTS FOR REACTOR PRESSURE VESSEL EXAMINATION (TAC NO. MA4160)
Dear Mr. Sellman:
The staff has reviewed and evaluated the information provided by Wisconsin Electric Power Company in its letter dated November 2,1998. You have proposed an attemative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),
1986 Edition,Section XI requirement IWA-2232, to use the Performance Demonstration Initiative (PDl) Program during the reactor pressure vessel third 10-year Inservice inspection Interval for Unit 2. The PDI is based on Appendix Vill,Section XI of the ASME Code,1992 Edition including the 1993 addenda. You requested this based on 10 CFR 50.55a(a)(3)(i).
The staff has concluded that the use of the attemative method is authorized for the requested i
interval pursuant to 10 CFR 50.55a(a)(3)(i) since it provides an acceptable level of quality and safety. A copy of the staff's safety evaluation is enclosed.
If you have any questions, please contact Beth Wetzel at (301) 415-1355.
Sincerely, oau O Chnthia A. Carpenter, Director Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. 50-301
Enclosure:
Safety Evaluation
~cc w/ encl: See next page
l l
t i
Mr. Michael B. Sellman Point Beach Nuclear Plant Wisconsin Electric Power Company Units 1 and 2 cc:
Mr. John H. O'Neill, Jr.
Ms. Sarah Jenkins Shaw, Pittman, Potts & Trowbridge Electric Division 2300 N Street, NW Public Service Commission of Wisconsin Washington, DC 20037-1128 P.O. Box 7854 l
. Madison, Wisconsin 53707-7854 Mr. Richard R. Grigg 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 Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman 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 ill U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241 l
l l
october 1 sos