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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits 2024-09-04
[Table view] Category:Congressional Correspondence
MONTHYEARCY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 19712011-07-14014 July 2011 G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 ML0927506252009-10-22022 October 2009 G20090534/LTR-09-0459/EDATS: SECY-2009-0422- Senator Joseph T. Lieberman Letter Release of Radionuclides by Millstone Power Station ML0927208922009-08-17017 August 2009 G20090534/LTR-09-0459/EDATS: SECY-2009-0422 - Ltr. Senator Joseph I. Lieberman Release of Radionuclides by Millstone Power Station ML0532600772005-12-13013 December 2005 G20050762/LTR-05-0571 - Hon. Timothy Bishop Ltr Response to Brian Farber'S Email Dated November 4, 2005 ML0531401872005-11-0404 November 2005 G20050762 - Brian Farber of Representative Timothy Bishop'S Staff e-mail Re Millstone Nuclear ML0529800352005-11-0404 November 2005 G20050698/LTR-05-0499 - Christopher J. Dodd Ltr Re. Licensing Employees Who Perform HVAC Work at the Millstone Nuclear Power Plant ML0528701082005-10-0707 October 2005 G20050698/LTR-05-0499 - Sen Christopher Dodd Ltr. Millstone Nuclear Power Plant (Robert Vivari, Jr.) Licensing Employees Who Perform HVAC Work ML0514404752005-05-27027 May 2005 G20050330/LTR-05-0250 - Sen. C. J. Dodd Letter Dated 4/27/05 Regarding Millstone Unit 3 (Nancy Burton, Connecticut Coalition Against Millstone) ML0514603082005-03-17017 March 2005 Invitation Letters for Millstone Annual Assessment Public Meeting on 29 March 2005 ML0504101612005-03-10010 March 2005 G20050111 - Congressman Timothy Bishop Ltr. Millstone-Evacuation Concerns ML0505403882005-02-0808 February 2005 G20050111 - Rep. Timothy Bishop (Brian D. Farber) e-mail Re Millstone - Evacuation Concerns ML0426104722004-11-0909 November 2004 G20040598/LTR-04-0555 - Ltr to Rep. Rob Simmons, Protection of Millstone ML0426700232004-10-0808 October 2004 G20040618/LTR-04-0565 - Senator Joseph I. Lieberman Ltr. Re. Storage of Nuclear Waste and Chemical and Radiologic Pollutants at the Millstone Power Station ML0425905412004-08-25025 August 2004 G20040618/LTR-04-0565 - Sen Joseph I. Lieberman Ltr Express Concerns About Safety and Environmental Issues Related to Millstone Nuclear Power Plant ML0419401442004-07-0202 July 2004 Ltr to Congressman Christopher Shays from K. Cyr Millstone Nuclear Power Plant ML0408906392004-03-11011 March 2004 Invitee Letters to March 25, 2004 NRC Annual Assessment Meeting of Millstone Power Station ML0405700802004-02-23023 February 2004 Connecticut Coalition Against Millstone V. NRC, No. 04-0109, Dated 02/23/04 ML0306601412003-04-14014 April 2003 G20030086/LTR-03-0102 - W. D. Travers Ltr. to Sen. Joseph I. Lieberman Ltr. Re Safety Issues with Millstone (Gertrude Birk) ML0305902022003-02-14014 February 2003 G20030086/LTR-03-0102 - Sen. Joseph I. Lieberman Ltr. Safety Issues with Millstone (Gertrude Birk) ML0302800322003-01-22022 January 2003 G20030034/LTR-03-0035 - Sen. Hiliary Rodham Clinton Ltr Request Commission Review Draft Report by Witt Associates Regarding Emergency Preparedness for Areas of New York State Around Indian Point & Millstone Nuclear Power Plants ML0212703592002-05-29029 May 2002 G20020236/LTR-02-0287 - Sen. Joseph I. Lieberman Ltr. Re Concerns Missing Nuclear Spent Fuel Rods from Nuclear Utilities (Laurel Pierce) 2011-07-14
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Text
November 9, 2004 The Honorable Rob Simmons United States House of Representatives Washington, D.C. 20515
Dear Congressman Simmons:
On behalf of the Nuclear Regulatory Commission (NRC), I am responding to your letter dated February 26, 2004, to the Assistant Secretary of Defense for Legislative Affairs. Your letter forwarded correspondence from a constituent, Mayor Gerard Gaynor of New London, Connecticut, requesting that ground-to-air defense capability be installed to protect the Millstone Nuclear Power Station. I apologize for the untimely response. Unfortunately, your letter was processed by both the Department of Defense and the Department of Energy before it was forwarded to the NRC on August 17, 2004.
In response to Mayor Gaynors request, installation of anti-aircraft defenses at U.S. nuclear power plant sites would present very difficult command and control issues, and the use of such weaponry could lead to significant collateral damage to plant workers and members of the public. Although the decision whether to deploy anti-aircraft capability must rest with the military, the NRC believes that the best approach to dealing with threats from aircraft is through strengthening airport and airline security measures. Efforts associated with enhancing security at airports and on airplanes themselves are an important part of reducing the threat from malevolent use of commercial aircraft for all civilian infrastructure, most of which does not have the robust capacity of a nuclear power plant. The NRC supports the steps taken to improve aircraft security, including enhanced passenger and baggage screening, strengthening of cockpit doors, the Air Marshal program and the federal flight deck officer program under the Arming Pilots Against Terrorism Act. The U.S. intelligence community and various Federal law enforcement agencies have also increased efforts to identify potential terrorists and prevent potential attacks before they occur. For example, the Federal Aviation Administration (FAA) and Department of Defense (DOD) have acted to protect airspace above nuclear power plants from threats -- threats that were later judged to be non-credible.
Moreover, as part of a comprehensive review of security for NRC-licensed facilities, the NRC conducted detailed site-specific engineering studies of a limited number of nuclear power plants to assess potential vulnerabilities of deliberate attacks involving large commercial aircraft. In conducting these studies, the NRC drew on national experts from several DOE laboratories using state-of-the-art structural and fire analyses. The agency also enhanced its ability to predict accident progression and radiological consequences realistically. For the facilities analyzed, the vulnerability studies confirm that the likelihood of both damaging the reactor core
and releasing radioactivity that could affect public health and safety is low. Even in the unlikely event of a radiological release due to terrorist use of a large aircraft, there would be time to implement mitigating actions and offsite emergency plans such that the NRCs emergency planning basis remains valid. Additional site-specific studies of operating nuclear power plants are underway or being planned to determine the need, if any, for additional mitigating capability on a site-specific basis.
I hope that this adequately addresses the concerns raised by your constituent. If you have any additional questions, please contact me.
Sincerely,
/RA/
Luis A. Reyes Executive Director for Operations
November 9, 2004 and releasing radioactivity that could affect public health and safety is low. Even in the unlikely event of a radiological release due to terrorist use of a large aircraft, there would be time to implement mitigating actions and offsite emergency plans such that the NRCs emergency planning basis remains valid. Additional site-specific studies of operating nuclear power plants are underway or being planned to determine the need, if any, for additional mitigating capability on a site-specific basis.
I hope that this adequately addresses the concerns raised by your constituent. If you have any additional questions, please contact me.
Sincerely,
/RA/
Luis A. Reyes Executive Director for Operations DISTRIBUTION:
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