Letter Sequence Request |
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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
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SAFEGUARDS INFORMATION Committed toNuclear Eclec Commitd to N rExcelhn-Nuclear Management Company, LLC March 18, 2002 10 CFR 50.4 Mr. Samuel J. Collins, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North Room 5 D2, Mail Stop 0-5 E7 11555 Rockville Pike Rockville, MD 20852
Dear Mr. Collins:
DOCKETS 50-282 AND 50-306 20-DAY RESPONSE TO ORDER FOR INTERIM SAFEGUARDS SECURITY COMPENSATORY MEASURES FOR PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 On February 25, 2002, the U. S. Nuclear Regulatory Commission issued an Order that modifies the current operating license for Prairie Island Nuclear Generating Plant (PINGP)
Units 1 and 2 to require compliance with the specified interim safeguards and security compensatory measures.
The Order requires the following actions to be taken by the Nuclear Management Company, LLC (NMC) at PINGP Units 1 and 2 within 20 days of issuance of the Order:
- 1. Item B.1 - Notify the Commission if (1) we are unable to comply with any of the requirements described in Attachment 2 of the Order, (2) if compliance is unnecessary in PINGP specific circumstances, or (3) if implementation of any of the requirements would cause PINGP to be in violation of the provisions of any Commission regulation or the facility license.
- 2. Item B.2 - Notify the Commission if implementation of any of the requirements described in Attachment 2 to the Order would adversely impact safe operation of the facility, provide the basis for this determination, and provide a proposal for achieving the same objectives specified in the Attachment 2 requirement in question, or a schedule for modifying the facility to address the adverse safety condition. If neither approach is appropriate, NMC must supplement its response to Condition B1 of the Order to identify the condition as a requirement with which it cannot comply.
- 3. Item C.1 - Submit to the Commission a schedule for achieving compliance with each requirement described in Attachment 2.
4 700 First Street
- Hudson, Wisconsin 54016 Telephone: 715.377,3300
- Fax: 715,386.1013 a Toll-Free: 800,701.4941 SAFEGUARDS INFORMATION
SAFEGUARDS INFORMATION Page 2 The NMC 20-day response to the Commission for PINGP Units 1 and 2 is enclosed. The enclosure to this letter contains SAFEGUARDS INFORMATION, and as such, is exempt from public disclosure in accordance with 10 CFR 2.790 and 10 CFR 73.21. Upon separation from its enclosure, this letter does not contain safeguards information.
NMC endorses the NRC's initiatives as detailed in the Order. NMC is continuing to evaluate its response contained in the enclosure and to work with NRC staff and industry groups in addressing the requirements of the Order. NMC will keep the NRC staff informed of its plans and activity under this Order and may supplement this response, if required.
Additional questions or clarifications required associated with this submittal should be directed to Dr. M. P. Findlay, Director-Security, NMC at 715/377-3310.
I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge. Executed on March 18, 2002.
Michael B. Sellman President and Chief Executive Officer Nuclear Management Company, LLC Enclosure SAFEGUARDS INFORMATION