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Category:Inspection Report
MONTHYEARIR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections IR 05000483/20230012023-04-12012 April 2023 Integrated Inspection Report 05000483/2023001 IR 05000483/20234022023-03-29029 March 2023 NRC Security Baseline Inspection Report 05000483/2023402 IR 05000483/20220062023-03-0101 March 2023 Annual Assessment Letter for Callaway Plant (Report 05000483/2022006) ML23019A0802023-01-19019 January 2023 Notification of Comprehensive Engineering Team Inspection (05000483/2023011) and Request for Information IR 05000483/20220042023-01-12012 January 2023 Integrated Inspection Report 05000483/2022004 IR 05000483/20220132022-11-15015 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2022013 IR 05000483/20220032022-10-17017 October 2022 Integrated Inspection Report 05000483/2022003 IR 05000483/20220102022-10-12012 October 2022 Biennial Problem Identification and Resolution Inspection Report 05000483-2022010 - Draft IR 05000483/20224032022-09-27027 September 2022 Security Baseline Inspection Report 05000483/2022403 IR 05000483/20220052022-08-23023 August 2022 Updated Inspection Plan for Callaway Plant (Report 05000483/2022005) IR 05000483/20224022022-08-11011 August 2022 NRC Security Inspection Report 05000483/2022402 (Cover Letter Only) IR 05000483/20220112022-08-0202 August 2022 Triennial Fire Protection Inspection Report 05000483 2022011 IR 05000483/20220022022-07-27027 July 2022 Integrated Inspection Report 05000483/2022002 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information IR 05000483/20220402022-05-0606 May 2022 95001 Supplemental Inspection Report 05000483/2022040 and Follow-Up Assessment Letter IR 05000483/20224012022-05-0505 May 2022 Cyber Security Inspection Report 05000483/2022401 IR 05000483/20220012022-04-26026 April 2022 Integrated Inspection Report 05000483/2022001 IR 05000483/20223012022-04-12012 April 2022 NRC Examination Report 05000483/2022301 ML22082A2012022-03-28028 March 2022 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2022011) and Request for Information IR 05000483/20224042022-03-24024 March 2022 Final Security Baseline Inspection Report 05000483/2022404 (Letter) IR 05000483/20210062022-03-0202 March 2022 Annual Assessment Letter for Callaway Plant (Report 05000483/2021006) IR 05000483/20210042022-01-0707 January 2022 Integrated Inspection Report - 05000483/2021004 IR 05000483/20210032021-11-0808 November 2021 Integrated Inspection Report 05000483/2021003 IR 05000483/20214202021-10-29029 October 2021 NRC Security Baseline Inspection Cover Letter 050004832021420 IR 05000483/20214022021-10-26026 October 2021 Security Baseline Inspection Report 05000483/2021402 IR 05000483/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Callaway Plant (Report 05000483/2021005) IR 05000483/20210022021-08-0505 August 2021 Integrated Inspection Report 05000483/2021002 and Independent Spent Fuel Storage Installation Report 07201045/2021001 IR 05000483/20214012021-05-26026 May 2021 Security Baseline Inspection Report 05000483/2021401 IR 05000483/20210012021-05-11011 May 2021 Integrated Inspection Report 05000483/2021001 IR 05000483/20214032021-04-15015 April 2021 Material Control and Accounting Program Inspection Report 05000483-2021403 (Public) IR 05000483/20200042021-02-0909 February 2021 CWY2020004-RP-DSB, Callaway Plant - Integrated Inspection Report and Assessment Follow-Up Letter (05000483/2020004) IR 05000483/20200032020-11-0202 November 2020 Integrated Inspection Report 05000483/2020003 IR 05000483/20204112020-10-27027 October 2020 Security Baseline Inspection Report 05000483/2020411 IR 05000483/20203012020-10-13013 October 2020 NRC Examination Report 05000483/2020301 IR 05000483/20200052020-09-0101 September 2020 Updated Inspection Plan for Callaway Plant (Report 05000483/2020005) IR 05000483/20200022020-07-29029 July 2020 Integrated Inspection Report 05000483/2020002 IR 05000483/20200102020-06-12012 June 2020 Biennial Problem Identification and Resolution Inspection Report 05000483/2020010 IR 05000483/20204102020-04-24024 April 2020 NRC Security Inspection Report 05000483/2020410 IR 05000483/20200012020-04-20020 April 2020 Integrated Inspection Report 05000483/2020001 IR 05000483/20200112020-04-15015 April 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000483/2020011 2024-01-19
[Table view] Category:Letter
MONTHYEARULNRC-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 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) 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 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) 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 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 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 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 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 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 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 ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION IV
1600 E. LAMAR BLVD.
ARLINGTON, TX 76011-4511 October 3, 2017 Mr. Fadi Diya, Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Plant P.O. Box 620 Fulton, MO 65251 SUBJECT: CALLAWAY PLANT - INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/
STAFFING/MULTI-UNIT DOSE ASSESSMENT PLANS - INSPECTION REPORT 05000483/2017008
Dear Mr. Diya:
On September 1, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed the onsite portion of an inspection at the Callaway Plant. On September 26, 2017, the NRC inspectors discussed the results of this inspection with Ms. S. Banker, Senior Director, Engineering, and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection 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 communications, staffing, and multi-unit/source 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 findings or violations of more than minor significance associated with this inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA David Proulx Acting for/
Nicholas H. Taylor, Chief Project Branch B Division of Reactor Projects Docket No. 50-483 License No. NPF-30
Enclosure:
Inspection Report 05000483/2017008 w/ Attachment: Supplemental Information
REGION IV==
Docket: 05000483 License: NPF-30 Report: 05000483/2017008 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Steedman, Missouri Dates: August 28 - September 26, 2017 Inspectors: R. Alexander, Sr. Project Engineer (Team Leader)
S. Alferink, Reactor Inspector D. Bradley, Sr. Resident Inspector - Callaway M. Stafford, Project Engineer Approved Nicholas H. Taylor By: Chief, Project Branch B Division of Reactor Projects
Enclosure
SUMMARY
IR 05000483/2017008; 08/28/2017 - 09/26/2017; Callaway Plant;
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, issued December 23, 2015.
The inspection covered a one-week inspection by the resident inspector and three inspectors from the Region IV office. 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 5.
NRC-Identified and Self-Revealing Findings
None
Licensee-Identified Violations
None
REPORT DETAILS
4. Other Activities
4OA5 Other Activities (TI 2515/191)
The objective of 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, is to verify that licensees have adequately implemented the mitigation strategies as described in the licensees Final Integrated Plan (ADAMS Accession No. ML16189A304) and the NRCs plant safety evaluation (ADAMS Accession No. ML17010A332) and to verify that the licensees installed reliable water level measurement instrumentation in their spent fuel pools. The purpose of this TI is also to verify the licensees have implemented Emergency Preparedness (EP) enhancements as described in their site-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements to ensure that staffing is 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. ML12229A174) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation, (ADAMS Accession No. ML12056A044) are in place and are 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 walk downs 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 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 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 staffs 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.
b. Assessment Based on samples selected for review, the team 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 is generally in compliance with NRC Order EA-12-049. The team verified that the licensee satisfactorily:
- Developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events,
- Integrated their FSGs into their existing plant 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 means to ensure that the necessary off-site FLEX equipment will be available from off-site locations.
The team verified that any non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings identified.
2. Spent Fuel Pool (SFP) Instrumentation
a. Inspection Scope
The team examined the licensees newly installed spent fuel pool instrumentation.
Specifically, the team 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 are 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 team determined that the licensee satisfactorily installed and established control of the 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 team 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 submittal and safety evaluation;
- Installed the SFP instrumentation display in the location, environmental conditions and accessibility as described in the plant specific submittals; and
- Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.
The team verified that any non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings 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 the licensee has implemented required changes to staffing, communications equipment, and facilities to support an Extended Loss of All AC Power (ELAP) scenario as described in the licensees staffing assessment and the NRC safety assessment. The team also verified that the licensee has 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 dose assessment submittal. Documents reviewed are listed in the attachment.
b. Assessment The team 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 results in an extended loss of all ac power to the site and impedes access to the site.
The team verified the following:
- Licensee satisfactorily implemented required staffing change(s) to support an ELAP scenario,
- Implemented dose assessment capabilities (including releases from spent fuel pools)using the licensees site-specific dose assessment software and approach.
The team verified that any non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.
c. Findings
No findings identified.
4OA6 Exit
Exit Meeting Summary
On September 1, 2017, the team presented the on-site inspection results in a management debrief to T. Herrmann, Site Vice President, and other members of the site staff. The inspectors confirmed that proprietary information examined during the inspection had been returned to the licensee. The team lead completed an exit meeting conducted with S. Banker, Senior Director, Engineering, and other members of the site staff, via telephone on September 26, 2017, to discuss the final results of the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- S. Abel, Director, Engineering Projects
- A. Alley, Engineering Program Supervisor
- S. Banker, Senior Director Engineering
- F. Bianco, Director, Nuclear Operations
- J. Cortez, Director, Training
- M. Covey, Manager, Operations
- B. Cox, Senior Director Nuclear Operations
- D. Farnsworth, Director, Work Management
- T. Herrmann, Site Vice President
- T. Holland, Shift Manager
- B. Huhmann, Regulatory Affairs Supervisor
- B. Jungmann, Director, Maintenance
- S. Kovaleski, Director, Engineering Design
- G. Kremer, Director, Engineering Programs
- M. McLachlan, Senior Director Plant Support
- K. Mills, Director, Engineering Systems
- T. Moser, Director, Nuclear Projects
- J. Nurrenbern, FLEX Program Engineer
- E. Olson, Director, Engineering Programs
- J. Patterson, Director, Nuclear Projects
- E. Ptasznik, Licensing Engineer
- S. Sandbothe, Director, Plant Support
- D. Stepanovic, Manager, Materials
NRC Personnel
- S. Janicki, Resident Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Closed
Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency 2515/191 TI Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, issued December 23, 2015 Attachment
LIST OF DOCUMENTS REVIEWED