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Category:Inspection Report
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 RA-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 IR 05000413/20224202022-04-0707 April 2022 Security Inspection Report 05000413/2022420 and 05000414/2022420 RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System IR 05000413/20210062022-03-0202 March 2022 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2021006 and 05000414/2021006) IR 05000413/20224012022-02-18018 February 2022 Security Baseline Inspection Report 05000413/2022401 and 05000414/2022401 IR 05000413/20210042022-01-26026 January 2022 Integrated Inspection Report 05000413/2021004 and 05000414/2021004 ML22011A1802022-01-18018 January 2022 Review of the Spring 2021 Steam Generator Tube Inspection Report IR 05000413/20213012021-11-0808 November 2021 Operator Licensing Examination Report 05000413/2021301 and 05000414/2021301 IR 05000413/20214022021-11-0303 November 2021 Security Baseline Inspection Report 05000413/2021402 and 05000414/2021402 IR 05000413/20210032021-10-28028 October 2021 Integrated Inspection Report 05000413/2021003 and 05000414/2021003 IR 05000413/20210102021-09-27027 September 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000413/2021010 and 05000414/2021010 IR 05000413/20214042021-08-26026 August 2021 Material Control and Accounting Program Inspection Report 05000413/2021404 and 05000414/2021404 (OUO Removed) IR 05000413/20210022021-08-0505 August 2021 Integrated Inspection Report 05000413/2021002 and 05000414/2021002 IR 05000413/20210012021-04-29029 April 2021 Integrated Inspection Report 05000413/2021001 and 05000414/2021001 IR 05000413/20210112021-04-23023 April 2021 NRC Fire Protection Team Inspection Report 05000413/2021011 and 05000414/2021011 IR 05000413/20200062021-03-0303 March 2021 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - NRC Inspection Report 05000413/2020006 and 05000414/2020006 IR 05000413/20214012021-02-26026 February 2021 Security Baseline Inspection Report 05000413/2021401 and 05000414/2021401 IR 05000413/20200042021-01-28028 January 2021 Integrated Inspection Report 05000413/2020004 and 05000414/2020004 IR 05000413/20200112020-12-18018 December 2020 Biennial Problem Identification and Resolution Inspection Report 05000413/2020011 and 05000414/2020011 Dated December 18, 2020 IR 05000413/20204012020-11-23023 November 2020 Security Aseline Inspection Report 05000413/2020401 and 05000414/2020401 IR 05000413/20200032020-10-30030 October 2020 Integrated Inspection Report 05000413/2020003, 05000414/2020003 and 07200045/2020002 IR 05000413/20200052020-08-17017 August 2020 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (NRC Inspection Report 05000413/2020005 and 05000414/2020005) IR 05000413/20200022020-08-0303 August 2020 Integrated Inspection Report 05000413/2020002, 05000414/2020002 and 07200045/2020001 IR 05000413/20200012020-04-28028 April 2020 Integrated Inspection Report 05000413/2020001 and 05000414/2020001 IR 05000413/20200102020-03-10010 March 2020 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000413/2020010 and 05000414/2020010 IR 05000413/20190062020-03-0303 March 2020 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - NRC Inspection Report 05000413/2019006 and 05000414/2019006 IR 05000413/20190042020-01-27027 January 2020 Integrated Report 05000413/2019004 and 05000414/2019004 IR 05000413/20190102020-01-0909 January 2020 Reissue Catawba - Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2019010 and 05000414/2019010 ML19354A8562019-12-20020 December 2019 Design Basis Assurance Inspection (Programs) Inspection Report 0500413/2019010 and 05000414/2019010 IR 05000413/20194112019-11-26026 November 2019 U.S. Nuclear Regulatory Commission Security Inspection Report 05000413/2019411 and 05000414/2019411 IR 05000413/20190032019-11-0707 November 2019 Integrated Inspection Report 05000413/2019003 and 05000414/2019003 2024-02-02
[Table view] Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 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 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] |
Inspection Report - Catawba - 2017010 |
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 16, 2017
SUBJECT:
CATAWBA NUCLEAR STATION - NUCLEAR REGULATORY COMMISSION TEAM INSPECTION REPORT 05000413/2017010 AND 05000414/2017010
Dear Mr. Simril:
On October 19, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Catawba Nuclear Station Units 1 and 2. The NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The inspection examined activities conducted under your license 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 license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.
The NRC inspectors did not identify any finding or violation of more than minor significance. 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/
Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52
Enclosure:
IR 05000413/2017010, 05000414/2017010 w/Attachment: Supplemental Information
REGION II==
Docket No.: 50-413, 50-414 License No.: NPF-35, NPF-52 Report No.: 05000413/2017010, 05000414/2017010 Licensee: Duke Energy Carolinas, LLC Facility: Catawba Nuclear Station, Units 1 and 2 Location: York, SC 29745 Dates: October 16 - 19, 2017 Inspectors: R. Rodriguez, Senior Project Engineer (Team Leader)
R. Taylor, Senior Project Engineer M. Toth, Project Engineer J. Kent, Construction Inspector Approved by: Shane Sandal, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure
SUMMARY
IR 05000413/2017010, 05000414/2017010; 10/16/2017 - 10/19/2017; Catawba Nuclear
Station, Units 1 and 2; Temporary Instruction 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 two senior project engineers, one project engineer, and one construction inspector. No NRC-identified or self-revealing 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.
No findings were identified.
REPORT DETAILS
OTHER ACTIVITIES
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity, and Emergency Preparedness
4OA5 Other Activities (TI 2515/191)
The objectives of Temporary Instruction (TI) 2015/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, were to verify that the licensee has adequately implemented the mitigation strategies as described in the licensees Final Integrated Plan, which was described in letters February 15, 2016, (ADAMS Accession No. ML16049A041), March 31, 2016, (ADAMS Accession No. ML16095A208) and September 27, 2016, (ADAMS Accession No.
ML16273A303) and the NRCs plant safety evaluation (ADAMS Accession No.
ML16277A404), to verify that the licensee installed reliable water-level measurement instrumentation in the spent fuel pools. The purpose of this TI was also to verify the licensee has implemented Emergency Preparedness (EP) enhancements as described in the site-specific submittals and the NRCs safety assessments, including multi-unit dose assessment capability and enhancements to ensure that staffing was sufficient and communications can be maintained during such an event.
The inspection 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. ML12054A736) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation, (ADAMS Accession No. ML12054A679) were in place and were being implemented by the licensee. Additionally, the inspection verified implementation of staffing and communications information provided in response to the March 12, 2012, request for information letter and multiunit 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 plant staff, reviewed documentation and, where appropriate, performed plant walkdowns to verify that the strategies could be implemented as stated in the licensees 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.
1. Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The team examined the licensees established guidelines and implementing procedures for the beyond-design-basis mitigation strategies. The team assessed how the licensee 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 walkdowns with licensed operators and responsible plant staff to assess:
- (1) the adequacy and completeness of the procedures;
- (2) the familiarity of operators with the procedure objectives and specific guidance;
- (3) the staging and compatibility of equipment; and
- (4) 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 Operations and Security 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. Documents reviewed are listed in the Attachment.
b. Assessment Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined that the licensee was generally in compliance with NRC Order EA-12-049. The inspectors verified that the licensee satisfactorily:
- Developed and issued FLEX Support Guidelines (FSG) to implement the FLEX strategies for postulated external events.
- Integrated the FSGs into existing plant procedures such that entry into and departure from the FSGs were 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 its availability and capability.
- Trained the staff to assure personnel proficiency in the mitigation of beyond-design-basis events.
- Developed means to ensure that the necessary off-site FLEX equipment would be available from off-site locations.
The inspectors verified that noncompliances with the current licensing requirements, and other issues identified during the inspection, were entered into the licensees corrective action program.
c. Findings
No findings were identified.
2. Spent Fuel Pool Instrumentation
a. Inspection Scope
The team examined the licensees newly installed spent fuel pool instrumentation.
Specifically, the inspectors verified the sensors were installed as described in the plant-specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel were physically and electrically separated. Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the Attachment.
b. Assessment Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the spent fuel pool (SFP)instrumentation as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-051. The inspectors verified that the licensee 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 location, environmental conditions and accessibility as described in the plant specific submittals.
- Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.
- Developed and issued procedures for maintenance, testing, and use of the reliable SFP instrumentation.
The inspectors verified that noncompliances with the current licensing requirements, and other issues identified during the inspection, were entered into the licensees corrective action program.
c. 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 walkdowns, the team verified that the licensee had implemented required changes to staffing, communications equipment, and facilities to support a multi-unit extended loss of offsite power scenario as described in the licensees staffing assessment and the NRC safety assessment. The team also verified that the licensee had implemented dose assessment (including releases from spent fuel pools) capability using the licensees site-specific dose assessment software and approach as described in the licensees multi-unit dose assessment submittal. Documents reviewed are listed in the Attachment.
b. Assessment The inspectors reviewed information provided in the licensees multi-unit dose submittal and in response to the NRCs March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that resulted in an extended loss of all alternating current power (ELAP) to the site and impedes access to the site. The inspectors verified the following:
- Licensee satisfactorily implemented required staffing change(s) to support an ELAP scenario.
- EP communications equipment and facilities were sufficient for dealing with an ELAP scenario.
- Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensees site-specific dose assessment software and approach.
The inspectors verified that noncompliances with the current licensing requirements, and other issues identified during the inspection, were entered into the licensee's corrective action program.
c. Findings
No findings were identified.
4OA6 Exit
Exit Meeting Summary
On October 19, 2017, the inspectors presented the inspection results to Mr. R. T. Simril and other members of the site staff. The inspectors confirmed that proprietary information was not provided or examined during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- C. Curry, Plant Manager
- C. Fletcher, Regulatory Affairs Manager
- T. Simril, Site Vice-President
- T. Owusu, Regulatory Affairs
- B. Price, Catawba Fukushima Response
- D. Davies, FLEX Program Engineer
- S. Andrews, Senior Engineer Operations
LIST OF REPORT ITEMS
Opened and Closed
None
Discussed
None
Complete
TI-2515/191, Appendix A, Mitigating Strategies for Beyond Design Basis Events TI-2515/191, Appendix B, Spent Fuel Pool Instrumentation TI-2515/191, Appendix C, Staffing and Communications Request for Information
LIST OF DOCUMENTS REVIEWED