Letter Sequence RAI |
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Results
Other: L-PI-03-016, Response to Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events, ML013480323, ML020020074, ML020020108, ML020030002, ML020410002, ML020570514, ML021060641, ML021070317, ML021140405, ML021140426, ML021610096, ML021990405, ML022140006, ML022600292, ML023290377, ML023640310, ML031010026, ML032040412, ML050900176, ML051030051
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MONTHYEARML0134803232002-01-0404 January 2002
Task Interface Agreement 2000-18, Design-Basis Assumptions for Non-Seismic Piping Failures at the Perry Plant
Project stage: Other
ML0200201082002-01-16016 January 2002
Opportunity for Comment on TIA 2001-04, Design-Basis Reliance on Non-Seismic and Non-Safety Related Equipment
Project stage: Other
ML0200300022002-01-16016 January 2002
Opportunity for Comment on TIA 2001-10, Design Basis Assumptions for Ability of Prairie Island, Units 2, Emergency Diesel Generators to Meet Single Failure Criteria for External Events
Project stage: Other
ML0200200742002-01-18018 January 2002
Opportunity for Comment on TIA 2001-02, Design Basis Assumptions for Non-Seismic Piping Failure
Project stage: Other
ML0204100022002-02-11011 February 2002
Report on the Status of Open TIAs Assigned to NRR
Project stage: Other
ML0208702382002-03-13013 March 2002
Response to Request for Additional Information (RAI) Regarding Technical Specification (TS) Change 01-10, One-Time Frequency Extension for Type a Test (Containment Integrated Leak Rate Test (Cilrt))
Project stage: Response to RAI
ML0208003112002-03-18018 March 2002
Day Response to Order for Interim Safeguards Security Compensatory Measures
Project stage: Request
ML0210100662002-04-0909 April 2002
TSC 01-10 - TVA Response to RAI
Project stage: Request
ML0211404052002-04-11011 April 2002
Additional Information for Technical Specification (TS) Change 01-10, One-Time Frequency Extension for Type a Test (Containment Integrated Leak Rate Test (Cilrt))
Project stage: Other
ML0210703172002-04-17017 April 2002
Memo to Raghavan from Manoly, Response to Task Interface Agreement (TIA 2001-15) for D. C. Cook, Units 1 and 2
Project stage: Other
ML0210606412002-05-0101 May 2002
Task Interface Agreement (TIA) 2001-07 from Region III Regarding Quad Cities Maintenance Rule (MR) Issues
Project stage: Other
ML0205705142002-05-0606 May 2002
Response to Task Interface Agreement - TIA 2001-12, Licensing Bases for the Standby Liquid Control System
Project stage: Other
ML0212904652002-05-10010 May 2002
Meeting with Nuclear Management Company, LLC to Discuss the Aspects of Security Orders
Project stage: Request
ML0215504192002-05-10010 May 2002
Response to Draft NRR Position on TIA 2001-04, Design Basis Reliance on Non-Seismic and Non-Safety Related Equipment
Project stage: Draft Other
ML0215504132002-05-10010 May 2002
Response to Draft NRR Position on TIA 2001-02, Design Basis Assumptions for Non-Seismic Piping Failure
Project stage: Draft Other
ML0211404262002-05-24024 May 2002
Memo Re Response to Task Interface Agreement 2001-009 Regarding Potential Unisolable Reactor Coolant Leak Outside Containment
Project stage: Other
ML0509001762002-05-28028 May 2002
Fire Hazard Analysis for Fire Zone 98-J, Emergency Diesel Generator Corridor and Fire Zone 99-M, North Electrical Switchgear Room, Arkansas Nuclear One, Unit 1
Project stage: Other
ML0214800332002-05-31031 May 2002
DC Cook, Units 1 & 2 - Request for Additional Information Regarding Containment Structure Conformance to Design-Basis Requirements
Project stage: RAI
ML0216100962002-06-11011 June 2002
Information Sent & Received by Electronic Mail Concerning Heavy Loads Request for Additional Infomration
Project stage: Other
05000237/LER-2002-003, Manual Valve Failures Prevent the Cooling Water Flow to Control Room Refrigeration Condensing Unit2002-07-0808 July 2002
Manual Valve Failures Prevent the Cooling Water Flow to Control Room Refrigeration Condensing Unit
Project stage: Request
ML0220301902002-07-16016 July 2002
Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements
Project stage: Response to RAI
ML0220303702002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Verification Manual, Pages A30.1 - A56.4
Project stage: Response to RAI
ML0220304002002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Verification Manual, Pages A57.1 - A80.10
Project stage: Response to RAI
ML0220304152002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Engineering Report SE 99-5, Attachment 6 to AEP:NRC:2520, Pages 1 - B29.6
Project stage: Response to RAI
ML0220304172002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Verification Manual, Pages A81.1 - 1.2
Project stage: Response to RAI
ML0220304462002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Verification Manual, Pages B30.1 - B67.6
Project stage: Response to RAI
ML0220304482002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Solvia Verification Manual, Attachment 6, Pages B68.1 - Attachment 7
Project stage: Response to RAI
ML0220303342002-07-16016 July 2002
Attachment to Response to NRC Request for Additional Information Re Containment Structure Conformance to Design Basis Requirements. Attachment 5, Solvia Engineering Report SE 99-4
Project stage: Response to RAI
ML0219904052002-07-18018 July 2002
Supplemental Fire Modeling for Fire Zone 98-J, Emergency Diesel Generator Corridor & Fire Zone 99-M, North Electrical Switchgear Room, Arkansas Nuclear One, Unit 1
Project stage: Other
ML0224100432002-08-23023 August 2002
Supplement to Nuclear Regulatory Commission Request for Additional Information Regarding Containment Structure Conformance to Design Basis Requirements
Project stage: Supplement
ML0223805242002-08-23023 August 2002
License Amendment Request for One-Time Extension of Essential Service Water System Allowed Outage Time-Additional Information
Project stage: Request
ML0221400062002-08-29029 August 2002
Response to Task Interface Agreement (TIA 2001-02) &Tia 2001-04 Evaluation of Service Water System Design Basis Requirements
Project stage: Other
ML0224201372002-09-11011 September 2002
Cover Letter - Draft Response to Task Interface Agreement 2001-13 Concerning the Reactor Building Crane and Heavy Loads
Project stage: Draft Other
ML0226002922002-09-17017 September 2002
Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR
Project stage: Other
ML0231000392002-11-11011 November 2002
Examples of Risk-Informed Licensing Actions for Acrs/Acnw
Project stage: Request
ML0236403102002-12-30030 December 2002
Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design-Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events
Project stage: Other
ML0510300512003-01-13013 January 2003
Response to Task Interface Agreement (TIA 2001 -15) Regarding Evaluation of Containment Structure Conformance to Design-basis Requirements
Project stage: Other
ML0232903772003-01-13013 January 2003
Task Interface Agreement (TIA 2001-15) Evaluation of Containment Structure Conformance to Design-Basis Requirement
Project stage: Other
ML0224200972003-02-21021 February 2003
Draft - NRR Response to TIA 2001-13, Backfitting Requirements for Dresden Units 2 & 3 Reactor Building Crane
Project stage: Draft Other
ML0310100262003-02-21021 February 2003
NRC Response to TIA 2001-13, Backfitting Requirements for Dresden Units 2 & 3 Reactor Building Crane
Project stage: Other
L-PI-03-016, Response to Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events2003-04-21021 April 2003
Response to Opportunity for Comment on Task Interface Agreement (TIA) 2001-10, Design Basis Assumptions for Ability of Prairie Island, Unit 2, Emergency Diesel Generators to Meet Single-Failure Criteria for External Events
Project stage: Other
ML0320404122003-09-0404 September 2003
Response to TIA 2001-10, Design Basis Assumptions for Ability of Emergency Diesel Generators to Meet Single Failure Criteria for External Events
Project stage: Other
ML0411204872004-04-13013 April 2004
License Amendment Request to Use Yield Strength Determined from Measured Material Properties for Reinforcing Bar in Structural Calculations for Control Rod Drive Missile Shields
Project stage: Request
2002-05-28
[Table View] |
Similar Documents at Cook |
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Text
May 31, 2002 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION, REGARDING CONTAINMENT STRUCTURE CONFORMANCE TO DESIGN-BASIS REQUIREMENTS (TAC NOS. MB3603 AND MB3604)
Dear Mr. Bakken:
The Nuclear Regulatory Commission (NRC) staff performed a design audit of the structural calculations and other documentation to verify conformance with the design-basis requirements for various structural elements within the containment structure. Based on its review of the design records, the NRC staff has identified that it does not have adequate technical information in sufficient detail to enable the staff to make an independent assessment regarding the containment structure conformance to design-basis requirements. The NRC staff finds that the additional information is needed as identified in the enclosed request for additional information (RAI).
Draft questions were discussed with Mr. Toby Woods et al., of your staff on May 28, 2002. The questions in the enclosed RAI are the same as the draft questions with the exception of minor modifications that were made to provide clarification. A mutually agreeable target date of July 02, 2002, for your response was established.
If circumstances result in the need to revise the target date, please contact me at (301) 415-1345 at the earliest opportunity.
Sincerely,
/RA/
John F. Stang, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
RAI cc w/encl: See next page
May 31, 2002 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION, REGARDING CONTAINMENT STRUCTURE CONFORMANCE TO DESIGN-BASIS REQUIREMENTS (TAC NOS. MB3603 AND MB3604)
Dear Mr. Bakken:
The Nuclear Regulatory Commission (NRC) staff performed a design audit of the structural calculations and other documentation to verify conformance with the design-basis requirements for various structural elements within the containment structure. Based on its review of the design records, the NRC staff has identified that it does not have adequate technical information in sufficient detail to enable the staff to make an independent assessment regarding the containment structure conformance to design-basis requirements. The NRC staff finds that the additional information is needed as identified in the enclosed request for additional information (RAI).
Draft questions were discussed with Mr. Toby Woods et al., of your staff on May 28, 2002. The questions in the enclosed RAI are the same as the draft questions with the exception of minor modifications that were made to provide clarification. A mutually agreeable target date of July 02, 2002, for your response was established.
If circumstances result in the need to revise the target date, please contact me at (301) 415-1345 at the earliest opportunity.
Sincerely,
/RA/
John F. Stang, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
RAI DISTRIBUTION PUBLIC ACRS CCarpenter PD III-1 r/f OGC AVegel, RIII JStang THarris ADAMS ACCESSION NO.: ML021480033 OFFICE PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME JStang THarris LRaghavan /RA/ by TKim DATE 05/31/02 05/31/02 05/31/02 OFFICIAL RECORD COPY
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR DONALD C. COOK, UNITS 1 AND 2 CONTAINMENT STRUCTURAL ISSUES 1.
During the audit, the Nuclear Regulatory Commission (NRC) staff discovered the use of yield strength values for steel rebar obtained from certified mill test reports (CMTRs) in structural calculations. These values are, respectively, 19 percent and 26 percent higher than the code-required minimum guaranteed design-basis yield strength of 40 ksi. The NRC staff has, in principle, not accepted the use of material CMTR properties (e.g.,
yield strength) in lieu of nominal specified code properties. The licensee provided information concerning the acceptance of the use of CMTR values at Crystal River Unit 3. At Crystal River, the licensee used rebar minimum yield strengths which exceeded code requirements by only 1 percent.
Provide additional justification for using material CMTR yield strength values for rebar in the reevaluation of the containment structures. The justification should include all assumptions and starting points. Provide the specific areas inside the containment where the CMTR values are used in the structural calculations. In addition for each structural element where CMTR values are necessary to be used to meet the load combinations listed in the updated final safety analysis report, provide the percentage in reduction in margin when the CMTR values are not used.
2.
During the audit, the NRC staff discovered the use of a computer code SOLVIA for some of the structural element calculations. The NRC staff is unfamiliar with the use of the SOLVIA code.
Provide a list of all areas where the code was used. Provide detailed documentation for the validation of the use of the SOLVIA code. The documentation should include all assumptions used in the code. In addition, the documentation should include bench marking data to provide a comparison to a code which has been approved by the NRC staff.
3.
During the audit, the NRC staff found that in some calculations, the size of subcompartment openings has been increased based on the localized effects a design-basis accident (DBA) will have on duct work and other objects passing through the openings. The increase in subcompartment openings results in a reduction in subcompartment pressure following a DBA. The NRC staff has not accepted the use of localized effects to increase the size of subcompartment openings.
Provide justification for increasing the actual measured opening between subcompartments following a DBA. Specifically, provide all assumptions, calculations, computer analysis, and codes used in justifying what the localized effects of a DBA will have on duct work and other object trays passing through the openings between subcompartments.
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, MI 48913 Township Supervisor Lake Township Hall P.O. Box 818 Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, MI 49127 David W. Jenkins, Esquire Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Drinking Water and Radiological Project Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr. Blvd.
P. O. Box 30630, CPH Mailroom Lansing, MI 48909-8130 Scot A. Greenlee Director, Nuclear Technical Services Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107 David A. Lochbaum Union of Concerned Scientists 1616 P Street NW, Suite 310 Washington, DC 20036-1495 Michael J. Finissi Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 Joseph E. Pollock Site Vice President Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
