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Category:Letter
MONTHYEARIR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 2024-02-01
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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