ML20138J986
| ML20138J986 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/06/1997 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | Richard Anderson NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20138J990 | List: |
| References | |
| TAC-M97737, TAC-M97738, NUDOCS 9705090225 | |
| Download: ML20138J986 (4) | |
Text
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- Mr. Roger 0. Anderson, Director May 6, 1997
- Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - SAFETY EVALUATION AUTHORIZING ALTERNATIVE TO THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME). CODE REPAIRS (TAC NOS. M97737 AND M97738)
Dear Mr. Anderson:
By letter dated March 6,19'96, the Nuclear Regulatory Commission (NRC) authorized alternative inspections to the ASME Code paragraph N-518.4 for surface examination of the control rod drive mechanism canopy seal welds pursuant to 10 CFR 50.55a(a)(3)(i). The NRC safety evaluation of March 6, 1996, listed. weld' locations H6 and G7 on Unit 1 and F6 and G7 on Unit 2.
In your letter dated February 14, 1997, you requested clarification that our acceptance of the alternative applied to all seven locations that you requested in your January 19, 1996, submittal.
Based on our feview, we have d'etermined that weld locations H8, F6, and F8 on Unit-l' also should.have been evaluated and listed as locations that were acceptableLfor performance of the alternative inspections.
)
The enclosed safety evaluation addresses the three weld locations that were inadsertently omitted e The staff has approved use of the proposed alternative inspections pursua~nt to:10 CFR,50.55a(a)(3)(i) for weld locations H8, F6, and F8'for Unit:l'during the winter;1996 outage, s
If you have"an'y' questions regarding the above clarifications, please contact O
Beth Wetzel at (30,1)'415-1355.
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'Sincereh, E
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Or4gine, signeo ny:
John N. Hannon, Director Project Directorate III-1 9705090225 970506 PDR ADOCK 05000282 Division of Reactor Projects - III/IV e
PDR Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Revised Safety Evaluation cc w/ encl:- See next page
)
DISTRIBUTION:
I
\\-
DocketiFile J. Roe G. Hill (4)
{I PUBLIC E. Adensam (EGAl)
ACRS PD 3-1 R/F G. Gerogiev B. McCabe, ED0 OGC J.M. Jacobson, RIII DOCUMENT NAME: G:\\WPDOCS\\ PRAIRIE \\PI97737.RLF To rective a copy of this doctament, Indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy 0FFICE PM:PD31 E
LA:PD31 E
- BC:ECGB OGP2(1/
PD:PD31 /
t NAME 1Netze1M CJamersonObGBagchi MYoung JHannon b97f) 4/10/97
'/ AI/97
(/[9/97 DATE-
//g/97 5/
/
0FFICIAL RECORD COPY
May 6, 1997 Mr. Roger 0. Anderson, Director Licensing and Manag: ment Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - SAFETY EVALUATION AUTHORIZING ALTERNATIVE TO THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE REPAIRS (TAC NOS. M97737 AND M97738)
Dear Mr. Anderson:
By letter dated March 6,1996, the Nuclear Regulatory Commission (NRC) authorized alternative inspections to the ASME Code paragraph N-518.4 for surface examination of the control rod drive mechanism canopy seal welds pursuant to 10 CFR 50.55a(a)(3)(1). The NRC safety evaluation of March 6, 1996, listed weld locations H6 and G7 on Unit I and F6 and G7 on Unit 2.
In your letter dated February 14, 1997, you requested clarification that our acceptance of the alternative applied to all seven locations that you requested in your January 19, 1996, submittal.
Based on our review, we have determined that veld locations H8, F6, and F8 on Unit I also should have been evaluated and listed as locations that were j
acceptable for performance of the alternative inspections.
The enclosed safety evaluation addresses the three weld locations that were inadvertently omitted. The staff has approved use of the proposed alternative inspections pursuant to 10 CFR 50.55a(a)(3)(1) for weld locations H8, F6, and F8 for Unit I during the winter 1996 outage.
If you have any questions regarding the above clarifications, please contact Beth Wetzel at (301) 415-1355.
Sincerely, Original signed by:
John N. Hannon, Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation i
Docket Nos. 50-282 and 50-306
Enclosure:
Revised Safety Evaluation cc w/ encl: See next page DISTRIBUTION:
Docket File J. Roe G. Hill (4)
PUBLIC E. Adensam (EGAI)
ACRS PD 3-1 R/F G. Gerogiev B. McCabe, ED0 OGC J.M. Jacobson, RIII DOCUMENT NAME: G:\\WPDOCS\\ PRAIRIE \\PI97737.RLF To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure W = No copy 0FFICE PN: PD31 E
LA:PD31 E
- BC:ECGB OGPM @
PD:PD31 /
t NAME NetzelY CJamersonObGBagchi MYoung JHannon b97f) 4/10/97 1'/M /97
(/[f/97 DATE y'/g/97 5/
/
/
0FFICIAL RECORD COPY
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x 4
UNITED STATES g
g NUCLEAR REGULATORY COMMISSION 3
o, WASHINGTON, D.C. 2066M001 9
- ,o May 6, 1997 9
Mr. Roger 0. Anderson, Director Licensing and Management Issues Northern States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - SAFETY EVALUATION AUTHORIZING ALTERNATIVE TO THE AMERICAN SOCIETY OF i
MECHANICAL ENGINEERS (ASME) CODE REPAIRS (TAC NOS. M97737 AND I
M97738)
Dear Mr. Anderson:
By letter dated March 6,1996, the Nuclear Regulatory Commission (NRC) authorized alternative inspections to the ASME Code paragraph N-518.4 for surface examination of the control rod drive mechanism canopy seal welds pursuant to 10 CFR 50.55a(a)(3)(i). The NRC safety evaluation of March 6, 1996, listed weld locations H6 and G7 on Unit I and F6 and G7 on Unit 2.
In your letter dated February 14, 1997, you requested clarification that our acceptance of the alternative applied to all seven locations that you requested in your January 19, 1996, submittal.
Based on our review, we have determined that weld locations H8, F6, and F8 on Unit I also should have been evaluated and listed as locations that were acceptable for performance of the alternative inspections.
The enclosed safety evaluation addresses the three weld locations that were inadvertently omitted. The staff has approved use of the propo:;sd alternative inspections pursuant to 10 CFR 50.55a(a)(3)(i) for weld locations 118, F6, and F8 for Unit I during the winter 1996 outage.
If you have any questions regarding the above clarifications, please' contact Beth Wetzel at (301) 415-1355.
Sincerely, John N. Hannon, Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Revised Safety Evaluation cc w/ encl: See next page i
Mr. Roger 0. Anderson, Director Prairie Island Nuclear Generating 4
Northern States Power Company Plant cc:
J. E. Silberg, Esquire Tribal Council c
Shaw, Pittman, Potts and Trowbridge Prairie Island Indian Community 2300 N Street, N. W.
ATTN:
Environmental Department Washington DC 20037 5636 Sturgeon Lake Road Welch, Minnesota 55089 Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East Welch', Minnesota 55089 Adonis A. Nebiett Assistant Attorney General Office of the Attorney General 455 Minnesota Street Suite 900 St. Paul, Minnesota 55101-2127 U.S. Nuclear Regulatory Commission Resident Inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089-9642 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Mr. Jeff Cole, Auditor / Treasurer i
Goodhue County Courthouse Box 408 Red Wing, Minnesota 55066-0408 Kris Sanda, Commissioner Department of Public Service 121 Seventh Place East Suite 200 St. Paul, Minnesota 55101-2145 Site Licensing Prairie Island Nuclear Generating Plant Northern States Power Company 1717 Wakonade Drive East l
Welch, Minnesota 55089 Neuen tM6 i
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