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| | number = ML16083A073 | | | number = ML16083A073 |
| | issue date = 04/12/2016 | | | issue date = 04/12/2016 |
| | title = Nine Mile Point, Unit 2 - Response Regarding Phase 2 Staffing Submittal Associated with Near-Term Task Force Recommendation 9.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident | | | title = Response Regarding Phase 2 Staffing Submittal Associated with Near-Term Task Force Recommendation 9.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident |
| | author name = Brown T | | | author name = Brown T |
| | author affiliation = NRC/NRR/JLD/PMB | | | author affiliation = NRC/NRR/JLD/PMB |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000410 | | | docket = 05000410 |
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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Rd Warrenville, IL 60555 April 12, 2016 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 12, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Rd Warrenville, IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| NINE MILE POINT NUCLEAR STATION, UNIT 2 -RESPONSE REGARDING PHASE 2 STAFFING SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAl-ICHI NUCLEAR POWER PLANT ACCIDENT (CAC NO. MF7155) | | NINE MILE POINT NUCLEAR STATION, UNIT 2 - RESPONSE REGARDING PHASE 2 STAFFING SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAl-ICHI NUCLEAR POWER PLANT ACCIDENT (CAC NO. MF7155) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12053A340),*the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter), regarding Recommendations 2.1 (seismic and flooding evaluations), 2.3 (seismic and flooding walkdowns), and 9.3 (emergency preparedness communication and staffing) of the Near-Term Task Force (NTTF) review of insights from the Fukushima Dai-ichi accident. With respect to Recommendation 9.3, Enclosure 5 to the NRC's letter requested licensees and holders of construction permits to assess their means to power communications equipment onsite and offsite during a prolonged station blackout (SBO) event and to perform a staffing assessment to determine the staff required to fill all necessary positions in response to a multi-unit event. The 50.54(f) letter, in part, requested licensee responses pursuant to the provisions of 1 O CFR 50.54(f) pertaining to onsite and augmented staff availability to implement the strategies discussed in the emergency plan and plant operating procedures, including new staff or functions resulting from the assessment, identified collateral duties, an implementation schedule to perform the assessments, identified modifications, and any changes that have been made or will be made to the emergency plan regarding on-shift or augmented staffing. In addition, NTTF Recommendation 9.3 has a dependency on the implementation of NTTF Recommendation 4.2 (mitigating strategies). As a result of this dependency, licensees responded to the 50.54(f) letter in phases. The Phase 1 staffing assessment requested licensees to evaluate their ability to respond to a multi-unit extended loss of alternating current (ac) power (ELAP) event utilizing existing processes and procedures. The licensee responses to the 50.54(f) letter for Phase 1 staffing assessments for multi-unit sites were received and evaluated by the NRC staff. The NRC staff issued acknowledgement letters to all licensees with multi-unit sites, with the exception of San Onofre Nuclear Generating Station, by April 28, 2014. | | |
| B. Hanson Licensees were also requested to submit a Phase 2 staffing assessment for NRC staff review, which provides an assessment of the staffing necessary to perform the functions related to the strategies developed in response to NTTF Recommendation 4.2 and the resulting NRC Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events [BDBEE]" (ADAMS Accession No. ML 12054A736). Licensees were requested to provide their Phase 2 staffing assessments to the NRC no later than four months prior to the beginning of their second refueling outage (as used in the context of NRC Order EA-12-049). By letter dated December 4, 2015 (ADAMS Accession No. ML 15338A123), Exelon Generation Company, LLC (the licensee) submitted its Phase 2 staffing assessment for Nine Mile Point Nuclear Station, Unit 2 to the NRC in response to the 50.54(f) letter. The NRC staff reviewed the licensee's Phase 2 staffing assessment in accordance with the assumptions and guidelines of Sections 2.2, 2.3, and 3 of the Nuclear Energy Institute (NEI) guidance document NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities" (ADAMS Accession No. ML 12125A412), which was endorsed by the NRC staff by letter dated May 15, 2012 (ADAMS Accession No. ML 12131A043). The NRC staff noted that the licensee assessed its current onsite minimum staffing levels to identify any enhancements needed to respond following a beyond-design-basis large-scale natural event, and to ensure that the strategies contained in the existing emergency plan and plant operating procedures, such as those used in response to a SBO, can be performed by the site staff. The licensee's assessment assumed that a large-scale natural event causes: (1) an ELAP, (2) all units on the site to be affected, and (3) access to the site to be impeded for a minimum of six hours. The licensee also assessed its capability to perform the site-specific functions related to the strategies developed in response to Order EA-12-049. The licensee conducted independent reviews and concluded, based on its staffing assessment, that the existing on-shift minimum staff is sufficient to implement the loss of all ac power, unit event response strategies, including those strategies developed to support the of Order EA-12-049, while supporting performance of the required emergency planning duties without unacceptable collateral duties. The NRC staff reviewed the licensee's Phase 2 staffing submittal and confirmed that the licensee's existing emergency response resources, as described in its emergency plan, are sufficient to perform the required plant actions and emergency plan functions, and implement the multi-unit event response strategies that were developed in response to Order EA-12-049 without the assignment of collateral duties that would impact the performance of assigned emergency plan functions. As a result, the NRC staff concludes that the licensee's Phase 2 staffing submittal adequately addresses the response strategies needed to respond to a BDBEE using its procedures and guidelines. The NRC staff will verify the implementation of the licensee's staffing capabilities through the inspection program. | | By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340),*the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter), regarding Recommendations 2.1 (seismic and flooding evaluations), 2.3 (seismic and flooding walkdowns), and 9.3 (emergency preparedness communication and staffing) of the Near-Term Task Force (NTTF) review of insights from the Fukushima Dai-ichi accident. With respect to Recommendation 9.3, Enclosure 5 to the NRC's letter requested licensees and holders of construction permits to assess their means to power communications equipment onsite and offsite during a prolonged station blackout (SBO) event and to perform a staffing assessment to determine the staff required to fill all necessary positions in response to a multi-unit event. |
| B. Hanson If you have any questions regarding this letter, please contact Stephen Philpott at (301) 415-2365 or via email at Stephen.Philpott@nrc.gov. Docket No. 50-410 cc: Distribution via Listserv Tony Brow , Acting Branch Chief Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation | | The 50.54(f) letter, in part, requested licensee responses pursuant to the provisions of 10 CFR 50.54(f) pertaining to onsite and augmented staff availability to implement the strategies discussed in the emergency plan and plant operating procedures, including new staff or functions resulting from the assessment, identified collateral duties, an implementation schedule to perform the assessments, identified modifications, and any changes that have been made or will be made to the emergency plan regarding on-shift or augmented staffing. |
| : ML 16083A073 OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NAME SPhiloott Slent DATE 03/23/2016 03/23/2016 Sincerely, IRA/ Tony Brown, Acting Branch Chief Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation RidsNrrPMNineMilePoint CMurray, NSIR RidsRgn1 MailCenter ARivera, NSIR TBrown, NRR SPhilpott, NRR *via email NSI R/DPR/N RLB/BC* NRR/JLD/JOMB/BC(A) ARivera (CMurrav for) TBrown 04/11/2016 04/12/2016}} | | In addition, NTTF Recommendation 9.3 has a dependency on the implementation of NTTF Recommendation 4.2 (mitigating strategies). As a result of this dependency, licensees responded to the 50.54(f) letter in phases. The Phase 1 staffing assessment requested licensees to evaluate their ability to respond to a multi-unit extended loss of alternating current (ac) power (ELAP) event utilizing existing processes and procedures. The licensee responses to the 50.54(f) letter for Phase 1 staffing assessments for multi-unit sites were received and evaluated by the NRC staff. The NRC staff issued acknowledgement letters to all licensees with multi-unit sites, with the exception of San Onofre Nuclear Generating Station, by April 28, 2014. |
| | |
| | B. Hanson Licensees were also requested to submit a Phase 2 staffing assessment for NRC staff review, which provides an assessment of the staffing necessary to perform the functions related to the strategies developed in response to NTTF Recommendation 4.2 and the resulting NRC Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events [BDBEE]" (ADAMS Accession No. ML12054A736). |
| | Licensees were requested to provide their Phase 2 staffing assessments to the NRC no later than four months prior to the beginning of their second refueling outage (as used in the context of NRC Order EA-12-049). By letter dated December 4, 2015 (ADAMS Accession No. ML15338A123), Exelon Generation Company, LLC (the licensee) submitted its Phase 2 staffing assessment for Nine Mile Point Nuclear Station, Unit 2 to the NRC in response to the 50.54(f) letter. |
| | The NRC staff reviewed the licensee's Phase 2 staffing assessment in accordance with the assumptions and guidelines of Sections 2.2, 2.3, and 3 of the Nuclear Energy Institute (NEI) guidance document NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities" (ADAMS Accession No. ML12125A412), |
| | which was endorsed by the NRC staff by letter dated May 15, 2012 (ADAMS Accession No. ML12131A043). The NRC staff noted that the licensee assessed its current onsite minimum staffing levels to identify any enhancements needed to respond following a beyond-design-basis large-scale natural event, and to ensure that the strategies contained in the existing emergency plan and plant operating procedures, such as those used in response to a SBO, can be performed by the site staff. The licensee's assessment assumed that a large-scale natural event causes: (1) an ELAP, (2) all units on the site to be affected, and (3) access to the site to be impeded for a minimum of six hours. The licensee also assessed its capability to perform the site-specific functions related to the strategies developed in response to Order EA-12-049. |
| | The licensee conducted independent reviews and concluded, based on its staffing assessment, that the existing on-shift minimum staff is sufficient to implement the loss of all ac power, multi-unit event response strategies, including those strategies developed to support the r~quirements of Order EA-12-049, while supporting performance of the required emergency planning duties without unacceptable collateral duties. |
| | The NRC staff reviewed the licensee's Phase 2 staffing submittal and confirmed that the licensee's existing emergency response resources, as described in its emergency plan, are sufficient to perform the required plant actions and emergency plan functions, and implement the multi-unit event response strategies that were developed in response to Order EA-12-049 without the assignment of collateral duties that would impact the performance of assigned emergency plan functions. |
| | As a result, the NRC staff concludes that the licensee's Phase 2 staffing submittal adequately addresses the response strategies needed to respond to a BDBEE using its procedures and guidelines. The NRC staff will verify the implementation of the licensee's staffing capabilities through the inspection program. |
| | |
| | B. Hanson If you have any questions regarding this letter, please contact Stephen Philpott at (301) 415-2365 or via email at Stephen.Philpott@nrc.gov. |
| | Tony Brow , Acting Branch Chief Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-410 cc: Distribution via Listserv |
| | : ML16083A073 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NSI R/DPR/N RLB/BC* NRR/JLD/JOMB/BC(A) |
| | NAME SPhiloott Slent ARivera (CMurrav for) TBrown DATE 03/23/2016 03/23/2016 04/11/2016 04/12/2016}} |
Letter Sequence Other |
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MONTHYEARML16083A0732016-04-12012 April 2016
Response Regarding Phase 2 Staffing Submittal Associated with Near-Term Task Force Recommendation 9.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident
Project stage: Other
2016-04-12
[Table View] |
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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024
Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
IR 05000220/20230042024-02-0101 February 2024
Integrated Inspection Report 05000220/2023004 and 05000410/2023004
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
CFR 50.46 Annual Report
ML24004A2122024-01-0808 January 2024
Senior Reactor and Reactor Operator Initial License Examinations
ML23354A0012024-01-0404 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
2024-09-04
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 12, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Rd Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - RESPONSE REGARDING PHASE 2 STAFFING SUBMITTALS ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAl-ICHI NUCLEAR POWER PLANT ACCIDENT (CAC NO. MF7155)
Dear Mr. Hanson:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340),*the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter), regarding Recommendations 2.1 (seismic and flooding evaluations), 2.3 (seismic and flooding walkdowns), and 9.3 (emergency preparedness communication and staffing) of the Near-Term Task Force (NTTF) review of insights from the Fukushima Dai-ichi accident. With respect to Recommendation 9.3, Enclosure 5 to the NRC's letter requested licensees and holders of construction permits to assess their means to power communications equipment onsite and offsite during a prolonged station blackout (SBO) event and to perform a staffing assessment to determine the staff required to fill all necessary positions in response to a multi-unit event.
The 50.54(f) letter, in part, requested licensee responses pursuant to the provisions of 10 CFR 50.54(f) pertaining to onsite and augmented staff availability to implement the strategies discussed in the emergency plan and plant operating procedures, including new staff or functions resulting from the assessment, identified collateral duties, an implementation schedule to perform the assessments, identified modifications, and any changes that have been made or will be made to the emergency plan regarding on-shift or augmented staffing.
In addition, NTTF Recommendation 9.3 has a dependency on the implementation of NTTF Recommendation 4.2 (mitigating strategies). As a result of this dependency, licensees responded to the 50.54(f) letter in phases. The Phase 1 staffing assessment requested licensees to evaluate their ability to respond to a multi-unit extended loss of alternating current (ac) power (ELAP) event utilizing existing processes and procedures. The licensee responses to the 50.54(f) letter for Phase 1 staffing assessments for multi-unit sites were received and evaluated by the NRC staff. The NRC staff issued acknowledgement letters to all licensees with multi-unit sites, with the exception of San Onofre Nuclear Generating Station, by April 28, 2014.
B. Hanson Licensees were also requested to submit a Phase 2 staffing assessment for NRC staff review, which provides an assessment of the staffing necessary to perform the functions related to the strategies developed in response to NTTF Recommendation 4.2 and the resulting NRC Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events [BDBEE]" (ADAMS Accession No. ML12054A736).
Licensees were requested to provide their Phase 2 staffing assessments to the NRC no later than four months prior to the beginning of their second refueling outage (as used in the context of NRC Order EA-12-049). By letter dated December 4, 2015 (ADAMS Accession No. ML15338A123), Exelon Generation Company, LLC (the licensee) submitted its Phase 2 staffing assessment for Nine Mile Point Nuclear Station, Unit 2 to the NRC in response to the 50.54(f) letter.
The NRC staff reviewed the licensee's Phase 2 staffing assessment in accordance with the assumptions and guidelines of Sections 2.2, 2.3, and 3 of the Nuclear Energy Institute (NEI) guidance document NEI 12-01, "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities" (ADAMS Accession No. ML12125A412),
which was endorsed by the NRC staff by letter dated May 15, 2012 (ADAMS Accession No. ML12131A043). The NRC staff noted that the licensee assessed its current onsite minimum staffing levels to identify any enhancements needed to respond following a beyond-design-basis large-scale natural event, and to ensure that the strategies contained in the existing emergency plan and plant operating procedures, such as those used in response to a SBO, can be performed by the site staff. The licensee's assessment assumed that a large-scale natural event causes: (1) an ELAP, (2) all units on the site to be affected, and (3) access to the site to be impeded for a minimum of six hours. The licensee also assessed its capability to perform the site-specific functions related to the strategies developed in response to Order EA-12-049.
The licensee conducted independent reviews and concluded, based on its staffing assessment, that the existing on-shift minimum staff is sufficient to implement the loss of all ac power, multi-unit event response strategies, including those strategies developed to support the r~quirements of Order EA-12-049, while supporting performance of the required emergency planning duties without unacceptable collateral duties.
The NRC staff reviewed the licensee's Phase 2 staffing submittal and confirmed that the licensee's existing emergency response resources, as described in its emergency plan, are sufficient to perform the required plant actions and emergency plan functions, and implement the multi-unit event response strategies that were developed in response to Order EA-12-049 without the assignment of collateral duties that would impact the performance of assigned emergency plan functions.
As a result, the NRC staff concludes that the licensee's Phase 2 staffing submittal adequately addresses the response strategies needed to respond to a BDBEE using its procedures and guidelines. The NRC staff will verify the implementation of the licensee's staffing capabilities through the inspection program.
B. Hanson If you have any questions regarding this letter, please contact Stephen Philpott at (301) 415-2365 or via email at Stephen.Philpott@nrc.gov.
Tony Brow , Acting Branch Chief Orders Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-410 cc: Distribution via Listserv
- ML16083A073 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NSI R/DPR/N RLB/BC* NRR/JLD/JOMB/BC(A)
NAME SPhiloott Slent ARivera (CMurrav for) TBrown DATE 03/23/2016 03/23/2016 04/11/2016 04/12/2016
