ML17335A165
| ML17335A165 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/05/1998 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | Sampson J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17335A166 | List: |
| References | |
| GL-88-20, TAC-M83609, TAC-M83610, NUDOCS 9808110232 | |
| Download: ML17335A165 (10) | |
Text
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>>+*~a UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20555-0001 August 5, 1998 Mr. John R. Sampson, Site Vice President Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, Ml 49107
SUBJECT:
DONALDC. COOK NUCLEAR PLANT, UNITS 1 AND 2 REVIEWOF INDIVIDUAL PLANT EXAMINATIONOF EXTERNALEVENTS (TAC NOS. M83609 AND M83610 )
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Dear Mr. Sampson:
By letter dated May 1, 1992, Indiana Michigan Power Company (the licensee) in accordance with Supplement 4 to Generic Letter (GL) 88-20 documented the individual plant examination of external events (IPEEE) report for D.C. Cook Units 1 and 2. By letters dated July 22, 1993, February 11, 1994, and February 15, 1995, additional information to support the IPEEE report was provided. The NRC staff has reviewed the IPEEE report and the additional information, and the staff findings are documented in the enclosed Staff Evaluation Report (SER) (Enclosure 1).
The NRC staff performed a "Step 1" review of the IPEEE report. A Step 1 review examines the IPEEE results for their "reasonableness" considering the design and operation of D.C. Cook. On the basis of the Step 1 review, the staff concluded that the aspects of high winds, floods, and
= transportation and others were adequately addressed by the licensee in the IPEEE; however, the seismic and fire portions of the IPEEE needed a more detailed review. The NRC staff performed a Step 2 review of the seismic and fire protection portions of the IPEEE because of specific concerns related to seismic response and fragilityanalyses and fire modeling, detection, and suppression analyses.
The staff contracted with Energy Research, Inc. (ERI) in February 1994 to support the Step 2 review, mainly to perform walkdowns and to evaluate the licensee's technical analyses and documentation held at the site. A site audit was conduct in July 1994 by the NRC staff and ERI.
The Technical Evaluation Report written by ERI is included as Enclosure 2.
The licensee originally estimated a seismic core damage frequency (CDF) of 1.8E-5 per reactor-year (RY), using a site-specific hazard curve developed by Rizzo Associates, and 3.1E-4/RY, using the 1989 seismic hazard estimates developed by Lawrence Livermore National Laboratory (LLNL). The seismic CDF was revised to 3.2E-6/RY after the licensee refined the fragilitycalculations i~ response to concerns raised before and during the site audit. The licensee originally estimated a."ire CDF of 1.7E-7/RY and later revised it to 3.8E-6/RY as a result of adding a few scenarios to its fire risk analyses, during the site audit. (The licensee estimated a CDF due to internal events at about 6.3E-5/RY, including internal flooding.) Other external events (e.g.,
external floods and high winds) are considered by the licensee as insignificant contributors to 9S0SXXOaS2 VSOSOS PDR ADOCK 05000Sl5 p
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~s August 5, 1998 John R. Sanipson insignificant contributors to severe accidents at the D.C. Cook site. The licensee did not define "vulnerability" and did not identify any vulnerabilities associated with external events.
- However, minor plant improvements and procedural changes, primarily in the seismic area, were implemented at the D.C. Cook plant site.
In addition, the licensee's IPEEE submittal contains some specific information that addresses the external event aspects of certain generic safety issues (e.g., Generic Safety Issue (GSI)-147),
"Fire-Induced Alternate Shutdown/Control Room Panel Interactions," GSI-148, "Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156, "Systematic Evaluation-Program (SEP)," and GSI-172, "MultipleSystem Responses Program (MSRP)." The specific information associated with each issue is identified and discussed in the enclosed SER.
Based on the staffs and contractor's reviews of the information contained in the submittal, the staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues.
On the basis that no vulnerabilities associated with the external event aspects of these issues were identified at D.C. Cook, the staff considers these issues resolved for the D.C. Cook facility.
On the basis of the Step 1 and Step 2 reviews, the staff concludes that the licensee's IPEEE process is capable of identifying the most likely severe accidents and severe accident vulnerabilities and, therefore, that the D.C. Cook IPEEE has met the intent of Supplement 4 to Generic Letter (GL) 88-20. The staffs review of the D.C. Cook IPEEE does not constitute NRC approval or endorsement of any IPEEE material for the purposes other than those associated with meeting the intent of Supplement 4 to GL 88-20. This completes the staffs review of the D.C.
Cook IPEEE and considers TAC Nos. M83609 and M83610 to be closed.
Ifyou have any questions concerning this issue, please contact me at 301-415-1345.
Sincerely, Original signed by:
John F. Stang, Senior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Staff Evaluation Report
- 2. Technical Evaluation Report cc w/encls: See next page Dis ribution w/e Is Docket File GGrant, Rill ACRS PUBLIC RBellamy OGC PD3-3 Reading EAdensam(EGA1)
DOCUMENT NAME'iDCCOOKiIPEEE.WPD OFFICE PD NAME JSt DATE 8/
PD33:LA EBarnhill 3 /
/98 E
4'aUB OFFICIAL RECORD COPY
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August 5, 1998 John R. Sampson t
2 insignificant contributors to severe accidents at the D.C. Cook site. The licensee did not define "vulnerability" and did not identify any vulnerabilities associated with external events.
- However, minor plant improvements and procedural changes, primarily in the seismic area, were implemented at the D.C. Cook plant site.
In addition, the licensee's IPEEE submittal contains some specific information that addresses the external event aspects of certain generic safety issues (e.g., Generic Safety Issue (GSI)-147),
"Fire-Induced Alternate Shutdown/Control Room Panel Interactions," GSI-148, "Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156, "Systematic Evaluation Program (SEP)," and GSI-172, "Multiple System Responses Program (MSRP)." The specific information associated with each issue is identified and discussed in the enclosed SER.
Based on the staffs and contractor's reviews of the information contained in the submittal, the staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues.
On the basis that no vulnerabilities associated with the external event aspects of these issues were identified at D.C. Cook, the staff considers these issues resolved for the D.C. Cook facility.
On the basis of the Step 1 and Step 2 reviews, the staff concludes that the licensee's IPEEE process is capable of identifying the most likely severe accidents and severe accident vulnerabilities and, therefore, that the D.C. Cook IPEEE has met the intent of Supplement 4 to Generic Letter (GL) 88-20. The staff's review of the D.C. Cook IPEEE does not constitute NRC approval or endorsement of any IPEEE material for the purposes other than those associated with meeting the intent of Supplement 4 to GL 88-20. This completes the staffs review of the D.C.
Cook IPEEE and considers TAC Nos. M83609 and M83610 to be closed.
Ifyou have any questions concerning this issue, please contact me at 301-415-1345.
Sincerely, Original signed by:
'ohn F. Stang, Senior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Staff Evaluation Report
- 2. Technical Evaluation Report cc w/encls:
See next page Dis ribu ion w/encl
'ocket File GGrant, Rill ACRS PUBLIC RBellamy OGC PD3-3 Reading EAdensam(EGA1)
DOCUMENT NAME'iDCCOOKiIPEEE.WPD OFFICE NAME DATE PD3 Jst S/9 E
PD33 LA EBarnhill
/98 OFFICIALRECORD COPY
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John R. Sampson severe accidents at the D.C. Cook site. The licensee did not define "vulnerability" and did not identify any vulnerabilities associated with external events.
However, minor plant improvements and procedural changes, primarily in the seismic area, were implemented at the D.C. Cook plant site.
In addition, the licensee's IPEEE submittal contains some specific information that addresses the external event aspects of certain generic safety issues.(e.g.,
Generic Safety Issue (GSI)-147),
"Fire-Induced Alternate Shutdown/Control Room Panel Interactions," GSI-148, "Smoke Control and Manual Fire-Fighting Effectiveness," GSI-156, "Systematic Evaluation Program (SEP)," and GSI-172, "MultipleSystem Responses Program (MSRP)." The specific information associated with each issue is identified and discussed in the enclosed SER.
Based on the staffs and contractor's reviews of the information contained in the submittal, the staff considered that the licensee's process is capable of identifying potential vulnerabilities associated with these issues.
On the basis that no vulnerabilities associated with the external event aspects of these issues were identified at D.C. Cook, the staff considers these issues resolved for the D.C. Cook facility.
On the basis of the Step 1 and Step 2 reviews, the staff concludes that the licensee's IPEEE process is capable of identifying the most likely severe accidents and severe accident
.vulnerabilities and, therefore, that the D.C. Cook IPEEE has met the intent of Supplement 4 to Generic Letter (GL) 88-20. The staff's review of the D.C. Cook IPEEE does not constitute NRC approval or endorsement of any IPEEE material for the purposes. other than those associated with meeting the intent of Supplement 4 to GL 88-20. This completes the staffs review of the D.C.
Cook IPEEE and considers TAC Nos. M83609 and M83610 to be closed.
Ifyou have any questions concerning this issue, please contact me at 301-415-1345.
Sincerely, ohn F. Stang, enior Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosures:
- 1. Staff Evaluation Report
- 2. Technical Evaluation Report cc w/encls: See next page
John R. Sampson 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, MI 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 Steve J. Brewer 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
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