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Category:Letter
MONTHYEARML24298A0552024-10-30030 October 2024 Response to Alternative RR-10, Auxiliary Feedwater Valve Testing ML24283A1192024-10-28028 October 2024 Letter to Shawn Hafen, Re Monticello Subsequent License Renewal Schedule Change IR 05000282/20244032024-10-25025 October 2024 – Security Baseline Inspection Report 05000282/2024403 and 05000306/2024403 IR 05000483/20240032024-10-23023 October 2024 Integrated Inspection Report 05000483/2024003 05000282/LER-2024-001-01, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-10-22022 October 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program IR 05000483/20240132024-10-21021 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2024013 L-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI IR 05000483/20244012024-10-0909 October 2024 Material Control and Accounting Program Inspection Report 05000483/2024401 Public ML24277A1012024-10-0303 October 2024 Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software ML24277A0202024-10-0303 October 2024 Operator Licensing Examination Approval Monticello Nuclear Generating Plant, October 2024 ML24199A1752024-10-0101 October 2024 Issuance of Amendment No. 212 Revise Technical Specification 3.8.6, Battery Parameters, Surveillance Requirement 3.8.6.6 IR 05000263/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000263/2024011 ULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter) ML24221A3622024-09-27027 September 2024 Issuance of Amendment Nos. 245 and 233 Revise Technical Specification 3.8.1, AC Sources-Operating, Surveillance Requirement 3.8.1.2, Note 3 L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML24241A1682024-09-23023 September 2024 Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation 05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024 Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies IR 05000282/20243012024-09-13013 September 2024 NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301 L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI ML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary IR 05000263/20240052024-08-30030 August 2024 Updated Inspection Plan and Follow-Up Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2024005) L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality IR 05000282/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005) IR 05000483/20244032024-08-28028 August 2024 Security Baseline Inspection 05000483-2024-403 ML24222A1822024-08-27027 August 2024 – Proposed Alternative Request VR-09 to the Inservice Testing Requirements of the ASME OM Code for Main Steam Safety Relief Valves 05000263/LER-2024-002, Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure2024-08-27027 August 2024 Low Pressure Coolant Injection Inoperable Due to Motor Valve Failure L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter IR 05000263/20244202024-08-21021 August 2024 Security Baseline Inspection Report 05000263/2024420 - Cover Letter IR 05000263/20240022024-08-14014 August 2024 Integrated Inspection Report 05000263/2024002 IR 05000483/20240052024-08-14014 August 2024 Updated Inspection Plan for Callaway Plant (Report 05000483/2024005) IR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24218A2282024-08-0505 August 2024 Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval IR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24215A2992024-07-23023 July 2024 Minnesota State Historic Preservation Office Comments on Monticello SLR Draft EIS ML24198A2372024-07-18018 July 2024 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Monticello Nuclear Generating Plant IR 05000483/20240022024-07-18018 July 2024 And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 2024-09-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 2, 2014 The Licensees of Operating Power Reactors on the Enclosed List
SUBJECT:
ACKNOWLEDGEMENT OF LICENSEE DOSE ASSESSMENT SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT: USE OF RASCAL In the U.S. Nuclear Regulatory Commission's (NRC's) Near-Term Task Force (NTTF) Report, "Recommendations for Enhancing Reactor Safety in the 21st Century," issued July 12, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111861807), the NTTF recommended that an order be issued requiring licensees to develop and add guidance to their emergency plan regarding how to perform multi-unit dose assessments. The Fukushima Dai-ichi accident highlighted the importance of the availability of a multi-unit dose assessment capability in responding to a similar event. By letter dated February 27, 2013 (ADAMS Accession No. ML13029A632), NRC staff requested that the Nuclear Energy Institute (NEI) provide additional information on the number of sites that currently have multi-unit dose assessment capabilities, and the date by which all sites will have these capabilities. By letter dated March 14, 2013 (ADAMS Accession No. ML13073A522), NEI informed the staff that each licensee would provide, to the NRC, their multi-unit and/or multi-source dose assessment capabilities no later than June 30, 2013.
By letters dated in June 2013, you provided a submittal to the NRC regarding multi-unit and/or multi-source dose assessment capabilities. On September 5, 2013, the NRC staff conducted a teleconference with you regarding a generic technical issue (ADAMS Accession No. ML13266A390) contained in your initial submittal. The NRC staff identified that your permanent multi-unit/multi-source dose assessment capability appeared to be contingent on the timing of the NRC release of RASCAL. The NRC staff communicated the expectation that licensees describe a plan to update their software to have the capability to conduct multi-unit/multi-source dose assessment without a dependency on the NRC release of RASCAL. By letters dated in October 2013, you supplemented your submittal to implement new/modified software that will ensure multi-unit/multi-source dose assessment capability by December 31, 2014 without a reliance on the release of RASCAL.
The NRC staff reviewed the supplemented information and noted that the combined initial and supplemental responses provided: a summary of your current capabilities to perform multi-unit and/or multi-source dose assessments; and the anticipated schedule with due dates to establish it on an interim and/or permanent basis (if these are not current capabilities), with a final implementation date for permanent multi-unit and/or multi-source dose assessment capabilities that did not exceed December 31, 2014. In reviewing these capabilities, the NRC staff considered whether your automated computer program would demonstrate the ability to model offsite dose assessment conducive to developing Protective Action Recommendations.
The NRC staff expects that, as part of the implementation of these new dose assessment capabilities, an appropriate level of site procedures and training will be provided to ensure adequate integration and licensee staff familiarity. NRC staff will verify the implementation of these dose assessment capabilities through the inspection program.
Should you have any questions regarding this letter, please contact Brian K. Harris at (301) 415-2277.
Sincerely, Michele G. Evans, Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Operating Power Reactor Licensees
- 2. Table of Licensee Submittals cc: Additional Distribution via listserv
Operating Power Reactors Callaway Plant Union Electric Company Mrs. Karen D. Fili Docket No. 50-483 Site Vice President License No. NPF-30 Northern States Power Company -
Minnesota Mr. Fadi Diya Monticello Nuclear Generating Plant Senior Vice President and Chief 2807 West County Road 75 Nuclear Officer Monticello, MN 55362-9637 Ameren Missouri Callaway Plant Prairie Island Nuclear Generating Plant P.O. 620 Northern States Power Company -
Fulton, MO 65251 Minnesota Docket Nos. 50-282 and 50-306 Monticello Nuclear Generating Plant License Nos. DPR-42 and DPR-60 Northern States Power Company -
Minnesota Mr. Kevin K. Davison Docket No. 50-263 Site Vice President License No. DPR-22 Northern States Power Company -
Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642 Enclosure 1
Table of Licensee Submittals Plant Initial Submittal Supplemental
Response
Callaway ML13179A037 ML13283A180 Monticello ML13171A011 ML13296A745 Prairie Island ML13169A351 ML13296A745 Enclosure 2
ML14080A418 OFFICE NRR/JLD/PMB NRR/JLD/ LA NRR/JLD/PMB I NRR/JLD/PMB NRR/DORL NAME BHarris SLent MMitchell I BHarris ME vans DATE 03/21/14 03/21/14 03/24/14 I o3t24t14 04/02/14 Letter from Michele G. Evans to Operating Power Reactor Plants on the Enclosed list dated April 2, 2014.
SUBJECT:
ACKNOWLEDGEMENT OF LICENSEE DOSE ASSESSMENT SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT ACCIDENT: USE OF RASCAL DISTRIBUTION:
PUBLIC RidsNrrDoriLpl2-1 RidsNrrLASRohrer LPL 1-1 R/F RidsNrrDoriLpl2-2 RidsNrrLAMHenderson LPL 1-2 R/F RidsNrrDoriLpl3-1 RidsNrrLASLent LPL2-1 R/F RidsNrrDoriLpl3-2 RidsNrrPMCallaway LPL2-2 R/F Rids NrrDorl Lpl4-1 RidsNrrPMMonticello LPL3-1 R/F Rids NrrDorl Lpl4-2 RidsNrrPMPrairielsland LPL3-2 R/F RidsOgcMaiiCenter RidsRgn1 MaiiCenter Resource LPL4-1 R/F RidsNrrLAABaxter RidsRgn2MaiiCenter Resource LPL4-2 R/F RidsN rrLAJBurkhardt RidsRgn3MaiiCenter Resource RidsNrrDorl RidsNrrLABCiayton RidsRgn4MaiiCenter Resource RidsNrrDoriLp11-1 RidsNrrLASFigueroa RidsNrrDoriLpl1-2 RidsNrrLAKGoldstein BHarris, NRR KWilliams, NSIR MMitchell, NRR