ML17335A286
| ML17335A286 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/07/1998 |
| From: | Carpenter C NRC (Affiliation Not Assigned) |
| To: | Powers R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17335A287 | List: |
| References | |
| TAC-M93614, NUDOCS 9810150184 | |
| Download: ML17335A286 (5) | |
Text
'1 October 7, 1998 Mr. Robert P. Powers, Senior Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107-1395
SUBJECT:
EVALUATIONON THE ALTERNATIVETO 10 CFR 50.55a(g)(6)(ii)(A),
AUGMENTED REACTOR PRESSURE VESSEL EXAMINATION REQUIREMENTS FOR DONALDC. COOK NUCLEAR PLANT, UNIT2 (TAC NO. M93614)
Dear Mr. Powers:
By letter dated July 29, 1996, you submitted a request to the NRC staff for an alternative to 10 CFR 50.55a(g)(6)(ii)(A), augmented reactor pressure vessel examination requirements for the Donald C. Cook Nuclear Plant, Unit 2.
Sincerely, Original signed by:
Cynthia A. Carpenter, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-316
Enclosure:
Safety Evaluation w/att.
cc w/encl: See next page DISTRIBUTION Docket File PUBLIC EGA1 TMcLellan JCaldwell, Rill THiltz, EDO DOCUMENT NAME: G:)DCCOOK<CO93614.REL PD3-1 r/f OGC CCarpenter GHill (4)
- See Previous
/
sure E
~ Copy with ettechment/enclosure N
~ No copy To recehre e copy ot this document, Indlcete In the botu 'C
~ Cop w(thout ett hme The NRR staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the information provided in support of an augmented reactor pressure vessel examination.
The staff adopts the evaluation and conclusions presented in the Technical Letter Report (TLR) prepared by INEL. The enclosed safety evaluation incorporates the TLR and its findings. Based on the information submitted, the staff concludes that you have maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable hardship without a compensating increase in the level of quality and safety.
Therefore, your proposed alternative, the augmented reactor pressure vessel examination of the accessible weld volumes from the inside surface in combination with future reactor pressure vessel examinations, provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(ii)(A)(5).
OFFICE NAME DATE PM:PD31 E
CNolan 10/5/98 LA:PD32 E
EBarnhill 10/8/98 JS 10 E
ECGB TMcLellan" 9/21/98 OGC MYoung" 10/01/98 OFFICE NAME DATE PD:PD31 CCarpenter C
10
/98 98iOi50i84 98i007 PDR ADQCK 050003ih p
PDR Ij,jiffyL'(.2 B~L~)ZL~(.3 C~ià OFFICIAL RECORD COPY
October 7, 1998 Mr. Robert P. Powers, Senior Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107-1395
SUBJECT:
EVALUATIONON THE ALTERNATIVETO 10 CFR 50.55a(g)(6)(ii)(A),
AUGMENTEDREACTOR PRESSURE VESSEL EXAMINATION REQUIREMENTS FOR DONALDC. COOK NUCLEAR PLANT, UNIT2 (TAC NO. M93614)
Dear Mr. Powers:
By letter dated July 29, 1996, you submitted a request to the NRC staff for an alternative to 10 CFR 50.55a(g)(6)(ii)(A), augmented reactor pressure vessel examination requirements for the Donald C. Cook Nuclear Plant, Unit 2.
The NRR staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the information provided in support of an augmented reactor pressure vessel examination.
The staff adopts the evaluation and conclusions presented in the Technical Letter Report (TLR) prepared by INEL. The enclosed safety evaluation incorporates the TLR and its findings. Based on the information submitted, the staff concludes that you have maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable hardship without a compensating increase in the level of quality and safety. Therefore, your proposed alternative, the augmented reactor pressure vessel examination of the accessible weld volumes from the inside surface in combination with future reactor pressure vessel examinations, provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(ii)(A)(5).
Sincerely, Original signed by:
Cynthia A. Carpenter, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-316
Enclosure:
Safety Evaluation w/att.
ccw/encl: See next page IKKElJlM Docket File PUBLIC EGA1 TMcLellan JCaldwell, Rill, THiltz, EDO DOCUMENT NAME: G:iDCCOOKic093614.REL PD3-1 r/f OGC To resolve s copy of this document, Indicate In the born C
~ Copy without etts hme CCarpenter GHill (4)
- See Previous sure
'E' Cop with sttschment/enclosure N
a No copy OFFICE PM:PD31 E
LA:PD32 E
PM E
ECGB OGC NAME CNolan DATE 10///98 OFFICE PD:PD31 NAME CCarpenter C
DATE 10
/98 EBarnhill 10/5/98 JS 10 OFFICIAL RECORD COPY TMcLellan" 9/21/98 MYoung".
10/01/98
~p,R REO(g
\\
~o
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON, D.c. 20555-0001 October 7, 1998 Mr. Robert P. Powers, Senior Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107-1395
SUBJECT:
EVALUATIONON THE ALTERNATIVETO 10 CFR 50.55a(g)(6)(ii)(A),
AUGMENTEDREACTOR PRESSURE VESSEL EXAMINATION REQUIREMENTS FOR DONALDC. COOK NUCLEAR PLANT, UNIT2 (TAC NO. M93614)
Dear Mr. Powers:
By letter dated July 29, 1996, you submitted a request to the NRC staff for an alternative to 10 CFR 50.55a(g)(6)(ii)(A), augmented reactor pressure vessel examination requirements for the Donald C. Cook Nuclear Plant, Unit 2.
The NRR staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the information provided in support of an augmented reactor pressure vessel examination.
The staff adopts the evaluation and conclusions presented in the Technical Letter Report (TLR) prepared by INEL. The enclosed safety evaluation incorporates the TLR and its findings. Based on the information submitted, the staff concludes that you have maximized examination coverage to the extent practical, and that imposing additional examinations would result in a considerable hardship without a compensating increase in the level of quality and safety.
Therefore, your proposed alternative, the augmented reactor pressure vessel examination of the accessible weld volumes from the inside surface in combination with'future reactor pressure vessel examinations, provides an acceptable level of quality and safety and is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) and 10 CFR 50.55a(g)(6)(ii)(A)(5).
Sincerely, Docket Nos. 50-316
Enclosure:
Safety Evaluation w/att.
cc w/encl: See next page thia A. Carpenter, Director Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Robert P. Powers Indiana Michigan Power Company Donald C. Cook Nuclear Plant Units 1 and 2 CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Ml 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, Ml 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Ml 49127 Jeremy J.
Euto, Esquire 500 Circle Drive Buchanan, Ml 49107 Mayor, City of Bridgman P.O. Box 366 Bridgman, Ml 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Ml 48909 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P.O. Box 30630 CPH Mailroom Lansing, Ml 48909-8130 Jeb Kingseed Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495
4