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Category:Inspection Report
MONTHYEARIR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 IR 05000220/20230012023-05-0505 May 2023 Integrated Inspection Report 05000220/2023001 and 05000410/2023001 IR 05000220/20233012023-03-29029 March 2023 Initial Operator Licensing Examination Report 05000220/2023301 IR 05000220/20220062023-03-0101 March 2023 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022006 and 05000410/2022006) IR 05000220/20220042023-01-23023 January 2023 Integrated Inspection Report 05000220/2022004 and 05000410/2022004 IR 05000220/20220102022-11-22022 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000220/2022010 and 05000410/2022010 IR 05000220/20220032022-11-0404 November 2022 Integrated Inspection Report 05000220/2022003 and 05000410/2022003 IR 05000220/20220052022-08-31031 August 2022 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022005 and 05000410/2022005) IR 05000220/20224012022-08-30030 August 2022 Security Baseline Inspection Report 05000220/2022401 and 05000410/2022401 IR 05000220/20220022022-08-0808 August 2022 Integrated Inspection Report 05000220/2022002 and 05000410/2022002 and Independent Spent Fuel Storage Installation Report 07201036/2022001 IR 05000220/20210042022-05-19019 May 2022 Reissued Integrated Inspection Report 05000220/2021004 and 05000410/2021004 IR 05000220/20220012022-04-29029 April 2022 Integrated Inspection Report 05000220/2022001 and 05000410/2022001 IR 05000220/20210062022-03-0202 March 2022 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021006 and 05000410/2021006) ML22026A3502022-01-26026 January 2022 Integrated Inspection Report 05000220/2021004 and 05000410/2021004 IR 05000220/20210122022-01-10010 January 2022 Biennial Problem Identification and Resolution Inspection Report 05000220/2021012 and 05000410/2021012 IR 05000220/20210032021-11-0909 November 2021 Integrated Inspection Report 05000220/2021003 and 05000410/2021003 and Independent Spent Fuel Storage Installation Report 07201036/2021001 IR 05000220/20215012021-10-14014 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2021501 and 05000410/2021501 IR 05000220/20214012021-09-0101 September 2021 Material Control and Accounting Program Inspection Report 05000220/2021401 and 05000410/2021401 (Letter Only) IR 05000220/20210052021-09-0101 September 2021 Updated Inspection Plan for the Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021005 and 05000410/2021005) IR 05000220/20210102021-08-24024 August 2021 Triennial Fire Protection Inspection Report 05000220/2021010 and 05000410/2021010 IR 05000220/20210022021-08-10010 August 2021 Integrated Inspection Report 05000220/2021002 and 05000410/2021002 and Independent Spent Fuel Storage Installation Report 07201036/2021002 IR 05000220/20214022021-06-22022 June 2021 Security Baseline Inspection Report 05000220/2021402 and 05000410/2021402 IR 05000410/20213022021-05-12012 May 2021 Initial Operator Licensing Examination Report 05000410/2021302 IR 05000220/20210012021-05-0505 May 2021 Integrated Inspection Report 05000220/2021001 and 05000410/2021001 IR 05000220/20210112021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000220/2021011 and 05000410/2021011 IR 05000220/20200062021-03-0303 March 2021 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2020006 and 05000410/2020006) IR 05000220/20200042021-02-11011 February 2021 Integrated Inspection Report 05000220/2020004 and 05000410/2020004 and Independent Spent Fuel Storage Installation Report 07201036/202004 IR 05000220/20203012021-01-25025 January 2021 Initial Operator Licensing Examination Report 05000220/2020301 IR 05000220/20204202020-12-0909 December 2020 Security Inspection Report 05000220/2020420 and 05000410/2020420 2020 Report ML20343A0112020-12-0909 December 2020 Security Inspection Report Cover Letter 05000220/2020420 and 05000410/2020420 IR 05000220/20200102020-11-24024 November 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000220/2020010 and 05000410/2020010 IR 05000220/20200032020-11-10010 November 2020 Integrated Inspection Report 05000220/2020003 and 05000410/2020003 IR 05000220/20200052020-08-31031 August 2020 Updated Inspection Plan for the Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2020005 and 05000410/2020005) IR 05000220/20204012020-07-29029 July 2020 Security Baseline Inspection Report 05000220/2020401 and 05000410/2020401 ML20149K4122020-05-29029 May 2020 Request for Information for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000220/2020010 and 05000410/2020010 IR 05000220/20200012020-05-0404 May 2020 Integrated Inspection Report 05000220/2020001 and 05000410/2020001 and Independent Spent Fuel Storage Installation Inspection Report 07201036/2020001 IR 05000220/20190062020-03-0303 March 2020 Annual Assessment Letter for the Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2019006 and 05000410/2019006) IR 05000410/20193012020-02-11011 February 2020 Initial Operator Licensing Examination Report 05000410/2019301 2024-02-01
[Table view] Category:Letter
MONTHYEARNMP1L3570, 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 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)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] |
Text
ber 19, 2017
SUBJECT:
NINE MILE POINT NUCLEAR STATION - TEMPORARY INSTRUCTION 2515/191 INSPECTION REPORT 05000220/2017008 AND 05000410/2017008
Dear Mr. Hanson:
The enclosed report documents the inspection results, which were discussed on August 25, 2017, with Mr. Jim Tsardakas, Director Site Training, and other members of your staff. An exit was conducted with Mr. Dennis M. Moore, Regulatory Assurance Manager, via telephone on September 13, 2017, to discuss the final results of the inspection. The results of this inspection are documented in the enclosed report.
The inspection examined activities conducted under your licenses as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, your compliance with the Commissions rules and regulations, and with the conditions of your operating licenses. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with plant personnel.
Based on the results of this inspection, no violations of NRC requirements were identified. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Anne E. DeFrancisco, Acting Chief Technical Support and Assessment Branch Division of Reactor Projects Docket Nos. 50-220 and 50-410 License Nos. DPR-63 and NPF-69
Enclosure:
Inspection Report 05000220/2017008 and 05000410/2017008 w/Attachment: Supplementary Information
REGION I==
Docket Nos. 50-220 and 50-410 License Nos. DPR-63 and NPF-69 Report No. 05000220/2017008 and 05000410/2017008 Licensee: Exelon Generation Company, LLC (Exelon)
Facility: Nine Mile Point Nuclear Station, LLC (NMPNS) Units 1 and 2 Location: Oswego, New York Dates: August 21 - 25, 2017 Inspectors: F. Arner, Senior Reactor Analyst, Division of Reactor Safety (DRS)
T. Dunn, Operations Engineer, DRS G. Stock, Resident Inspector, Division of Reactor Projects Approved by: Anne E. DeFrancisco, Acting Chief Technical Support and Assessment Branch Division of Reactor Projects Enclosure
SUMMARY
Inspection Report 05000220/2017008 and 05000410/2017008; 08/21/2017 - 08/25/2017;
NMPNS, Units 1 and 2; Temporary Instruction (TI) 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans.
The inspection covered a one week inspection by a senior reactor analyst, an operations engineer, and a resident inspector. No findings were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Other Activities
TI 2515/191 - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/
Multi-Unit Dose Assessment Plans The objective of TI 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, is to verify:
- (1) that licensees have adequately implemented the mitigation strategies as described in the licensees Final Integrated Plan (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML15163A097, ML16188A265 and ML16188A271)and the NRCs plant safety evaluation (ADAMS Accession No. ML17009A141);
- (2) that the licensees installed reliable water-level measurement instrumentation in their spent fuel pools (SFPs); and
- (3) that licensees have implemented emergency preparedness enhancements as described in their site-specific submittals and NRC safety assessments, including dose assessment capability, enhancements to ensure that staffing is sufficient, and that communications can be maintained during beyond-design-basis external events.
The team verified that plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events, (ADAMS Accession No. ML12054A735) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation, (ADAMS Accession No. ML12056A044) were in place and were being implemented by Exelon. The team also verified that Exelon had implemented staffing and communications plans provided in response to the March 12, 2012, request for information letter and dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013 (ADAMS Accession No. ML12339A262).
The team discussed the plans and strategies with Exelon personnel, reviewed documentation, completed a tabletop exercise involving a beyond design basis event leading to an extended loss of offsite power and, where appropriate, performed plant walk downs to verify that the strategies could be implemented as stated in Exelons submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the teams inspection activities are described in the following sections. Documents reviewed for each section of this report are listed in the Attachment.
1. Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The team examined Exelons established guidelines and implementing procedures for the beyond-design-basis mitigation strategies. The team assessed how the Exelon staff coordinated and documented the interface/transition between existing off-normal and emergency operating procedures with the newly developed mitigation strategies.
The team selected a number of mitigation strategies and conducted plant walk downs with licensed operators and responsible plant staff to assess: the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment; and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios.
The team verified that a preventive maintenance program had been established for the Diverse and Flexible Coping Strategies (FLEX) portable equipment and that periodic equipment inventories were in place and being conducted. Additionally, the team examined the introductory and planned periodic/refresher training provided to the Exelon staff most likely to be tasked with implementation of the FLEX mitigation strategies. The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel.
Assessment Based on samples selected for review, the inspectors verified that Exelon satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittal(s) and the associated safety evaluation (ADAMS Accession No.
ML17009A141) and determined that Exelon was in compliance with NRC Order EA-12-049.
The team verified that Exelon satisfactorily:
- Developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events;
- Integrated their FSGs into their existing emergency operating procedures and off-normal procedures such that entry into and departure from the FSGs are clear when using existing plant procedures;
- Protected FLEX equipment from site-specific hazards;
- Developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability;
- Trained their staff to assure personnel proficiency in the mitigation of beyond-design-basis events, and;
- Developed procedures to ensure that the necessary off-site FLEX equipment will be available from off-site locations.
The team verified that inspector observations identified during the inspection were entered into Exelons corrective action program, where appropriate.
b. Findings
No findings were identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
Assessment Based on samples selected for review, the team determined that Exelon satisfactorily installed and established appropriate operating and maintenance controls for the SFP instrumentation as described in the plant specific submittals and the associated safety evaluation. The team determined that Exelon was in compliance with NRC Order EA-12-051.
The team verified that Exelon satisfactorily:
- Installed the SFP instrumentation sensors, cabling, and power supplies to provide physical and electrical separation as described in the plant specific submittals and safety evaluation;
- Installed the SFP instrumentation display in the accessible location, and environmental conditions as described in the plant specific submittals;
- Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation; and,
- Developed and issued procedures for maintenance, testing, and use of the reliable SFP instrumentation.
The team verified that issues identified during the inspection were entered into Exelons corrective action program.
b. Findings
No findings were identified.
3. Staffing and Communication Request for Information
a. Inspection Scope
Through discussions with plant staff, review of documentation, and plant walk downs, the team verified that Exelon had implemented required changes to staffing, communications equipment, and facilities to support an extended loss of all AC power (ELAP) scenario as described in Exelons staffing assessment and the NRC safety evaluation. The team also verified that Exelon had implemented dose assessment (including releases from SFPs) capability using site-specific dose assessment software, as described in Exelons dose assessment submittal.
Assessment The team reviewed information provided in Exelons dose assessment submittal and in response to the NRCs March 12, 2012, request for information letter (ML12053A340),and verified that Exelon satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3, response to a large scale natural emergency event that results in an ELAP and impedes access to the site.
The team verified the following:
- Exelon satisfactorily implemented required staffing changes to support an ELAP scenario;
- Exelon implemented dose assessment capabilities (including releases from SFPs)using Nine Mile Points site-specific dose assessment software and approach.
The team verified that issues identified during the inspection were entered into Exelons corrective action program.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On August 25, 2017, the team debriefed the inspection results to Mr. Jim Tsardakas, Director Site Training, and other members of the Nine Mile Point Nuclear Station staff.
An exit was conducted with Mr. Dennis M. Moore, Regulatory Assurance Manager via telephone on September 13, 2017, to discuss the final results of the inspection.
The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- R. Kreider, Plant Manager
- D. Moore, Regulatory Assurance Manager
- J. Thompson, Director Site Operations
- M. Busch, Director Site Maintenance
- M. Khan, Director Site Engineering
- R. Pritchard, Regulatory Assurance
- J. Tsardakas, Director Site Training
- M. Checola, Senior Engineering Analyst
- R. Corieri, Senior Design Engineer
- B. Balzer, Unit 1 Operations Shift Supervisor
- J. Revelle, Operations Support Manager
- D. Morley, Senior Design Engineer
- K. Yurkon, Site Emergency Planning Manager
- W. Revelle, Senior Site Emergency Planning Specialist
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened and Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED