ML17333A759
| ML17333A759 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/27/1997 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | Fitzpatrick E INDIANA MICHIGAN POWER CO. |
| References | |
| TAC-M92498, NUDOCS 9702040252 | |
| Download: ML17333A759 (5) | |
Text
t Iv January,'7, iv997 Nr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, NI 49107
SUBJECT:
STAFF REVIEW OF CYCLE 13 IPC ASSESSMENT REPORT FOR DONALD C.
COOK NUCLEAR PLANT, UNIT 1 (TAC NO. -H92498)
Dear Hr. Fitzpatrick:
On March 15,
- 1994, we issued Amendment No.
178 which modified the technical specification of D.C.
Cook Unit 1, and approved the use of a 2.0 volt steam generator tube support plate interim plugging criterion for Cycle 14.
The safety evaluation associated with that amendment required that you perform an assessment of the effectiveness of the methodology described in WCAP-13187, Rev.
0 for predicting the end-of-cycle voltage distribution.
By letter dated June 13,
- 1994, you submitted that evaluation.
We then forwarded that evaluation to Pacific Northwest National Laboratory (PNNL) for an independent review.
A copy of the PNNL report is enclosed.
Based on the independent assessment of the licensee's 90-day outage report, the NRC staff concludes that the end-of-cycle 14 projections of the steam generator tube degradation for tubes affected by outside-diameter stress corrosion cracking are acceptable per the guidance in the NRC safety evaluation dated March 15,
- 1994, "Donald C.
Cook Nuclear Plant, Unit No. 1-Issuance of Amendment Re: Incorporation of 2.0 Volt Steam Generator Tube Support Plate Interim Plugging Criteria for Cycle 14."
The staff's conclusion is supported by the low estimate of the conditional tube burst probability and the projection of an end-of-cycle accident leakage below the plant-specific primary-to-secondary leak rate limit.
Please contact me at (301) 415-3017 if you have any questions regarding the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
PNNL Report cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC GNarcus EGAl PRush 'OGC DOCUMENT NAME:
G:i!,DCCOOK!tC096356.LTR To receive ~ copy of thta doctanent. Indcete!n the hox: 'C' Copy without attachment/enctoatve
- JRoe, ACRS PD¹3-3 Reading JCal.dwell, RIII F ~ Copy with attachment/enc/oatve N
~ No copy OFFICE PH:PD33 E
NAME JHickman.
DATE
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'anuary 27, 1997
'r.
E.
E. Fitzpatrick, Tice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, HI 49107
SUBJECT:
STAFF REVIEW OF CYCLE 13 IPC ASSESSMENT REPORT FOR DONALD C.
COOK NUCLEAR PLANT, UNIT 1 (TAC NO. H92498)
Dear Hr. Fitzpatrick:
On March 15,
- 1994, we issued Amendment No.
178 which modified the technical specification of D.C.
Cook Unit 1, and approved the use of a 2.0 volt steam generator tube support plate interim plugging criterion for Cycle 14.
The safety evaluation associated with that amendment required that you perform an assessment of -the effectiveness of the methodology described in WCAP-13187, Rev.
0 for predicting the end-of-cycle voltage distribution.
By letter dated June 13,
- 1994, you submitted that evaluation.
We then forwarded that evaluation to Pacific Northwest National Laboratory (PNNL) for an independent review.
A copy of the PNNL report is enclosed.
Based on the independent assessment of the licensee's 90-day outage report, the NRC staff concludes that the end-of-cycle 14 projections of the steam generator tube degradation for tubes affected by outside-diameter stress corrosion cracking are acceptable per the guidance in the NRC safety evaluation dated March 15,
- 1994, "Donald C.
Cook Nuclear Plant, Unit No. 1-Issuance of Amendment Re: Incorporation of 2.0 Volt Steam Generator Tube Support Plate Interim Plugging Criteria for Cycle 14."
The staff's conclusion is supported by the low estimate of the conditional tube burst probability and the projection of an end-of-cycle accident leakage below the plant-specific primary-to-secondary leak rate limit.
Please contact me at (301) 415-3017 if you have any questions regarding the above.
Sincerely, Original signed by:
John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
PNNL Report cc w/encl:
See next page DISTRIBUTION:
GMarcus EGAl Docket File PUBLIC PRush OGC JRoe ACRS PD¹ 3-3 Reading JCaldwell, RIII DOCUMENT NAME:
G:ItDCCOOKItC096356.LTR To recelee ~ copy of thie documoe4 Incacete In the hect: C'opy without ettechment/enctcetce
'F ~ Copy with ettechment/enctoetce
/t No copy OFFICE PH:PD33 E
LA:PD33 E
NAME JHickman EBarnhill DATE
// /gW/9
/
/97 OFFICIAL RECORD COPY
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 27, 1997 Mr. E.
E. Fitzpatrick, Vice President Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, MI 49107
SUBJECT:
STAFF REVIEW OF CYCLE 13 IPC ASSESSMENT REPORT FOR DONALD C.
COOK NUCLEAR PLANT, UNIT 1
Dear Mr. Fitzpatrick On March 15,
- 1994, we issued Amendment No.
178 which modified the technical specification of D.C.
Cook Unit 1, and approved the use of a 2.0 volt steam generator tube support plate interim plugging criterion for Cycle 14.
The safety evaluation associated with that amendment required that you perform an assessment of the effectiveness of the methodology described in WCAP-13187, Rev.
0 for predicting the end-of-cycle voltage distribution.
By letter dated June 13, 1994, you submitted that evaluation.
We then forwarded that evaluation to Pacific Northwest National Laboratory (PNNL) for an independent review.
A copy of the PNNL report is enclosed.
Based on the independent assessment of the licensee's 90-day outage report, the NRC staff concludes that the end-of-cycle 14 projections of the steam generator tube degradation for tubes affected by outside-diameter stress
'orrosion cracking are acceptable per the guidance in the NRC safety evaluation dated March 15,
- 1994, "Donald C.
Cook Nuclear Plant, Unit No. 1 Issuance of Amendment Re: Incorporation of 2.0 Volt Steam Generator Tube Support Plate Interim Plugging Criteria for Cycle 14."
The staff's conclusion is supported by the low estimate of the conditional tube burst probability and the projection of an end-of-cycle accident leakage below the plant-specific primary-to-secondary leak rate limit.
Please contact me at (301) 415-3017 if you have any questions regarding the above.
Sincerely, Docket No. 50-315
Enclosure:
PNNL Report cc w/encl:
See next page ohn B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Hr. E.
E. Fitzpatrick Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General
Department of Attorney General 525 West Ottawa Street
- Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Site Vice President Donald C.
Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Hichigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Mayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol
- Lansing, Michigan 48909 Drinking Water and Radiological Protection Division Hichigan Department of Environmental guality 3423 N. Hartin Luther -King Jr Blvd P. 0.
Box 30630 CPH Mailroom
- Lansing, Michigan 48909-8130 Donald C. Cook Nuclear Plant Hr. Steve J.
Brewer Indiana Michigan Power Nuclear Generation Group 500 Circle Drive
- Buchanan, Michigan 49107