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Category:Inspection Plan
MONTHYEARML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23087A0852023-03-28028 March 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information IR 05000237/20220062023-03-0101 March 2023 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2022006 and 05000249/2022006) ML23037A9192023-02-0707 February 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000237/2023011 and 05000249/2023011 ML22318A1842022-11-15015 November 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000237/2023401; 05000249/2023401 ML22306A2172022-11-0202 November 2022 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Dresden Nuclear Power Station, Units 2 and 3 IR 05000237/20220052022-08-22022 August 2022 Updated Inspection Plan for Dresden Nuclear Power Station (Report 05000237/2022005; 05000249/2022005) ML22068A0862022-03-0909 March 2022 Reissue Dresden Nuclear Power Station, Units 2 and 3 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection ML22062B0522022-03-0404 March 2022 Information Request for an Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection IR 05000237/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000237/2021006 and 05000249/2021006) ML22027A3592022-01-26026 January 2022 U1: CY2022 Inspection Plan, Docket No. 05000010, License No. DPR-2 IR 05000237/20220102021-12-21021 December 2021 Notification of NRC DBAI (Programs) and Initial RFI Inspection Report 05000237/2022010 05000249/2022010 ML21265A2262021-09-22022 September 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000237/2021004 05000249/2021004 IR 05000237/20210052021-09-0101 September 2021 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3, Report 05000237/2021005 and 05000249/2021005 ML21096A1752021-04-0606 April 2021 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000237/2021011; 05000249/2021011 IR 05000237/20200062021-03-0404 March 2021 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2020006 and 05000249/2020006) ML20337A4242020-12-0202 December 2020 Information Request for the Cyber-Security Full Implementation Inspection, Notification to Perform Inspection 05000237/2021401 and 05000249/2021401 ML20302A4602020-10-28028 October 2020 Request for Information for an NRC Triennial Baseline Deisgn Bases Assurance Inspection (Team): Inspection Report 05000237/2021010; 05000249/202101 IR 05000237/20200052020-09-0101 September 2020 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2020005 and 05000249/2020005) IR 05000237/20190062020-03-0303 March 2020 Annual Assessment Letter for Dresden, Units 2 and 3 (Report 05000237/2019006 and 05000249/2019006, 05000237/2019006 and 05000249/2019006) ML19290G5152019-10-15015 October 2019 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Dresden Nuclear Power Station, Units 2 and 3 IR 05000237/20190052019-08-28028 August 2019 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2019005 and 05000249/2019005) ML19136A1852019-05-15015 May 2019 Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, and Quad Cities Nuclear Power Station-Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency IR 05000237/20180062019-03-0404 March 2019 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2018006 and 05000249/2018006) ML19008A3912019-01-0707 January 2019 Initial Information Request (Part 2) for the Upcoming Phase IV License Renewal Inspection, Dated 01/07/19 (DRS-J. Corujo-Sandin) IR 05000237/20180052018-08-28028 August 2018 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2018005 and 05000249/2018005) IR 05000237/20170062018-03-0202 March 2018 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2017006 and 05000249/2017006) IR 05000237/20170112018-01-0202 January 2018 NRC Temporary Instruction 2515/191, Mitigation Strategies, Spent Fuel Pool Instrumentation and Emergency Preparedness Inspection Report 05000237/2017011 and 05000249/2017011 ML17354B0352017-12-20020 December 2017 U1: CY2018 Master Inspection Plan IR 05000237/20170052017-08-28028 August 2017 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2017005 and 05000249/2017005) ML17240A2672017-08-25025 August 2017 Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Dresden, Units 2 and 3 ML17236A0742017-08-23023 August 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2017004; 05000249/2017004 IR 05000237/20160062017-03-0101 March 2017 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2016006 and 05000249/2016006) ML16351A1072016-12-15015 December 2016 Master Inspection Plan - Calendar Year 2017 IR 05000237/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3,(Report 05000237/2016005; 05000249/2016005) ML16242A0712016-08-26026 August 2016 Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000237/2017007; 05000249/2017007 ML16070A1102016-03-0909 March 2016 Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000237/2016009; 05000249/2016009 IR 05000237/20150062016-03-0202 March 2016 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Inspection Report 05000237/2015006 and 05000249/2015006) ML16011A4852016-01-11011 January 2016 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Dresden Nuclear Power Station, Units 2 and 3 ML15357A1282015-12-21021 December 2015 Master Inspection Plan - Calendar Year 2016 ML15322A3722015-11-18018 November 2015 IR 05000237/2016008; 05000249/2016008 February 8 - 12, 2016; and February 22 - 26, 2016, Dresden Nuclear Power Station, Units 2 and 3; Request for Information for an NRC Pilot Component Design Bases Inspection IR 05000237/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2015005; 05000249/2015005) IR 05000237/20140012015-03-0404 March 2015 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3, (Report 05000237/2014001; 05000249/2014001) IR 05000237/20130012014-03-0404 March 2014 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2013001; 05000249/2013001) ML14003A2832014-01-0303 January 2014 Fire Protection Request for Information ML13308B2322013-11-0404 November 2013 Ltr 11/4/13 Dresden, Unit 2 and 3, Notification to Perform an Inspection of Temporary Instruction 2201/004, Inspection of Implementation of Interim Cyber Security Milestone 1-7 and Request for Information IR 05000237-14-405; 05000249-144-40 ML13301A7352013-10-28028 October 2013 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Dresden Nuclear Power Station, Units 2 and 3 ML13246A2172013-09-0303 September 2013 2013 Dresden MOC Letter Combined IR 05000237/20120012013-03-0404 March 2013 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2012001 and 05000249/2012001) ML12277A1872012-10-0303 October 2012 ISI Request for Information 2023-07-06
[Table view] Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 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 ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] |
Inspection Report - Dresden - 2017011 |
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Text
UNITED STATES ary 2, 2018
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 NRC TEMPORARY INSTRUCTION 2515/191, MITIGATION STRATEGIES, SPENT FUEL POOL INSTRUMENTATION AND EMERGENCY PREPAREDNESS INSPECTION REPORT 05000237/2017011 and 05000249/2017011
Dear Mr. Hanson:
On December 1, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed a 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 inspection at your Dresden Nuclear Power Station, Units 2 and 3. On December 19, 2017, the NRC inspectors discussed the results of this inspection with Mr. John Washko 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 findings or violations during this inspection.
B.Hanson -2-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, Request for Withholding.
Sincerely,
/RA/
Ann Marie Stone, Team Leader Technical Support Staff Division of Reactor Projects Docket Nos. 50-237; 50-249 License Nos. DPR-19; DPR-25
Enclosure:
Inspection Report 05000237/2017011; 05000249/2017011
REGION III==
Docket Nos: 05000237; 05000249 License Nos: DPR-19; DPR-25 Report No: 05000237/2017011; 05000249/2017011 Licensee: Exelon Generation Company, LLC Facility: Dresden Nuclear Power Station, Units 2 and 3 Location: Morris, IL Dates: November 27 through December 1, 2017 Inspectors: Stuart Sheldon, Project Engineer Charles Zoia, Senior Operations Engineer Gregory Roach, Senior Resident Inspector Lionel Rodriguez, Reactor Inspector Approved by: Ann Marie Stone, Team Leader Technical Support Staff Division of Reactor Projects
SUMMARY
Inspection Report 05000237/2017011, 05000249/2017011; 11/27/2017 - 12/01/2017; Dresden
Nuclear Power Station, Units 2 & 3; Temporary Instruction 2515/191 Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans.
This inspection was performed by three NRC regional inspectors and one resident inspector.
One Green finding associated with performance verification was identified by the licensee and since the finding did not involve a violation, no further documentation per NRC Inspection Manual Chapter 0612 Appendix B is required. The significance of inspection findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated April 29, 2015. Cross-cutting aspects are determined using IMC 0310, Aspects Within the Cross-Cutting Areas, dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy, dated November 1, 2016. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision
NRC-Identified and Self-Revealing Findings
None.
REPORT DETAILS
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 the licensee has adequately implemented the mitigation strategies as described in the licensees Final Integrated Plan [for] Mitigation Strategies for a Beyond-Design-Basis External Event (ADAMS Accession No. ML16230A487), and the NRCs safety evaluation (ADAMS Accession No. ML17037C929) and to verify the licensee installed reliable water-level measurement instrumentation in their spent fuel pool. The purpose of this TI was also to verify the licensee had implemented Emergency Preparedness enhancements as described in their site-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements to ensure staffing is sufficient and communications can be maintained during such an event.
The inspection also verifies 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) 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 inspectors discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walk downs to verify 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.
This inspection closes TI 2515/191 for the Dresden Nuclear Power Station, Units 2 and 3.
.1 Mitigation Strategies for Beyond-Design Basis External Events
a. Inspection Scope
The inspectors examined the licensees established guidelines and implementing procedures for the beyond-design basis mitigation strategies. The inspectors 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 inspectors 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 inspectors verified a preventive maintenance program had been established for the Diverse and Flexible Coping Strategies (FLEX) portable equipment and periodic equipment inventories were in place and being conducted. Additionally, the inspectors examined the introductory and planned periodic/refresher training provided to the Operations staff most likely to be tasked with implementation of the FLEX mitigation strategies. The inspectors 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 the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined the licensee is in compliance with NRC Order EA-12-049. The inspectors verified the licensee satisfactorily:
- developed and issued FLEX Support Guidelines (FSG) 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 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 their availability and capability;
- trained their staff to assure personnel proficiency in the mitigation of beyond-design basis events; and
- developed the means to ensure the necessary off-site FLEX equipment would be available from off-site locations.
The inspectors verified non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program as appropriate.
c. Findings
No findings were identified.
.2 Spent Fuel Pool Instrumentation
a. Inspection Scope
The inspectors 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 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 inspectors determined 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 the licensee is in compliance with NRC Order EA-12-051.
The inspectors verified 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; and
- developed and issued procedures for maintenance, testing and use of the reliable SFP instrumentation.
The inspectors verified 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 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 inspectors verified the licensee has implemented required changes to staffing, communications equipment and facilities to support a multi-unit extended loss of AC power (ELAP) scenario as described in the licensees staffing assessment and the NRC safety assessment. The inspectors also verified the licensee has implemented multi-unit 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 results in an ELAP to all site units and impedes access to the site. The inspectors verified the following:
- the licensee satisfactorily implemented required staffing change(s) to support a multi-unit ELAP scenario;
- the licensee implemented multi-unit dose assessment capabilities (including releases from spent fuel pools) using the licensees site-specific dose assessment software and approach.
The inspectors verified 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 were identified.
4OA6 Management Meeting
.1 Exit Meeting Summary
On December 19, 2017, the inspectors presented the inspection results to Mr. John Washko and other members of the licensees staff. The licensee acknowledged the issues presented. The inspectors confirmed none of the potential report input discussed was considered proprietary.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- P. Karuba Jr., Site Vice President
- J. Washko, Station Plant Manager
- P. Hansett, Operations Director
- J. Reda, Engineering Manager
- D. Thomas, Training Director
- H. Bush, Radiation Protection Manager
- D. Doggett, Emergency Preparedness Manager
- D. Francis, Operations Services Manager
- K. Koller, Operations Support Manager
- M. Martin, Operations Support Manager
- B. Franzen, Regulatory Assurance Manager
- R. Bauman, Shift Operations Superintendent
- N. Kopczynski, Engineering
- D. Walker, Regulatory Assurance - NRC Coordinator
U.S. Nuclear Regulatory Commission
Ann Marie Stone, Team Leader, Division of Reactor Projects, Technical Support Staff
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None
LIST OF DOCUMENTS REVIEWED