Letter Sequence Supplement |
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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
Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1395 INDIANA MICHIGAN POWER August 23, 2002 AEP:NRC:2520-01 10 CFR 50.90 Docket No.:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 SUPPLEMENT TO NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTAINMENT STRUCTURE CONFORMANCE TO DESIGN BASIS REQUIREMENTS (TAC NOS. MB3603 AND MB33604)
Reference:
1 Letter from J. F. Stang (NRC) to A. C. Bakken III (I&M), "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),"
dated May 31, 2002 2
Letter from S. A. Greenlee (I&M) to U. S. Nuclear Regulatory Commission Document Control Desk, "Response to Nuclear Regulatory Commission Request for Additional Information Regarding Containment Structure Conformance to Design Basis Requirements (TAC Nos. MB3603 And MB3604),"
dated July 16, 2002 This letter provides supplemental information in response to a Nuclear Regulatory Commission (NRC) request for additional information regarding conformance of the containment structures at Donald C. Cook Nuclear Plant to design basis requirements.
In Reference 1, the NRC noted that Indiana Michigan Power Company (I&M) had used values for rebar yield strength obtained from certified material test
U. S. Nuclear Regulatory Commission AEP:NRC:2520-01 Page 2 reports (CMTRs) in containment structural calculations at Donald C. Cook Nuclear Plant. The NRC requested that I&M provide justification for use of the CMTR yield strength values in lieu of nominal specified code properties.
I&M provided its response to the NRC request in Reference 2. In that response, I&M identified the structural calculation for the ice condenser endwalls as one of the calculations in which CMTR data had been used for rebar strength. I&M also stated that the ice condenser endwall structural calculation contained overly conservative inputs and assumptions, and that revision of these inputs and assumptions was expected to eliminate the need for reliance on CMTR values for rebar strength.
I&M committed to provide the NRC results of the revised endwall calculation with respect to required rebar yield strength. Background information pertaining to the revision and the results of the revision are provided below.
To support completion of containment structural calculations in the first half of 2001, I&M elected to use preliminary pressure values in some of the calculations, including the ice condenser endwall calculation. Prior to approving the endwall calculation, I&M confirmed that the preliminary pressure values bounded the final pressure values. However, the results determined by the approved calculation continued to be based on the preliminary pressure values.
Using the preliminary pressure values, the calculation determined that the required endwall capacity could only be achieved by crediting as-built CMTR values for the rebar strength.
Consistent with the commitment made in Reference 2, I&M has revised the ice condenser endwall structural calculation to incorporate the final endwall differential pressures and to use only the nominal specified code rebar strength of 40 ksi. This revision demonstrates that the ice condenser endwall meets the required capacity without reliance on as-built rebar strength.
There are no new commitments made in this letter.
Should you have any questions, please contact Mr. Gordon P. Arent, Manager of Regulatory Affairs, at (269) 697-5553.
AEP:NRC:2520-01 U. S. Nuclear Regulatory Commission Page 3 Sincerely, Scot A. Greenlee Director of Nuclear Technical Services JRW/jen c:
K. D. Curry J. E. Dyer MDEQ - DW & RPD, NRC Resident Inspector R. Whale
U. S. Nuclear Regulatory Commission AEP:NRC:2520-01 Page 4 bc:
G.P. Arent A. C. Bakken III P. B. Cowan S. A. Greenlee S. B. Haggerty D. W. Jenkins J. A. Kobyra J. E. Pollock J. F. Stang, Jr., - NRC Washington, DC T. R. Stephens T. K. Woods
