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Category:Inspection Report
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 IR 05000333/20220062023-03-0101 March 2023 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2022006) IR 05000333/20220032022-11-10010 November 2022 Integrated Inspection Report 05000333/2022003 IR 05000333/20220052022-08-31031 August 2022 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2022005) IR 05000333/20220022022-08-10010 August 2022 Integrated Inspection Report 05000333/2022002 IR 05000333/20220102022-06-27027 June 2022 Reissued Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 ML22153A2612022-06-0202 June 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000333/2022010 IR 05000333/20210142022-05-23023 May 2022 Problem Identification and Resolution Inspection Report 05000333/2021014 IR 05000333/20220012022-05-0505 May 2022 Integrated Inspection Report 05000333/2022001 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2022001 IR 05000333/20210062022-03-0202 March 2022 Annual Assessment Letter for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021006) IR 05000333/20210042022-01-27027 January 2022 Integrated Inspection Report 05000333/2021004 IR 05000333/20210402021-11-0808 November 2021 95001 Supplemental Inspection Report 05000333/2021040 and Assessment Follow-Up Letter IR 05000333/20210032021-11-0808 November 2021 Integrated Inspection Report 05000333/2021003 IR 05000333/20213012021-10-0505 October 2021 Initial Operator Licensing Examination Report 05000333/2021301 IR 05000333/20215012021-09-29029 September 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2021501 IR 05000333/20210052021-09-0101 September 2021 Updated Inspection Plan for the James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2021005) IR 05000333/20210132021-08-11011 August 2021 Biennial Problem Identification and Resolution Inspection Report 05000333/2021013 IR 05000333/20210022021-08-0303 August 2021 James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002 ML21176A0052021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20210902021-06-25025 June 2021 Acknowledgement of Dispute of Violations Associated with White Finding - NRC Inspection Report 05000333/2021090 IR 05000333/20214022021-06-0909 June 2021 Security Baseline Inspection Report 05000333/2021402 IR 05000333/20210112021-06-0303 June 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000333/2021011 IR 05000333/20210012021-05-0505 May 2021 Integrated Inspection Report 05000333/2021001 IR 05000333/20210122021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000333/2021012 IR 05000333/20214012021-04-19019 April 2021 Material Control and Accounting Program Inspection Report 05000333/2021401 (Letter Only) IR 05000333/20210102021-04-0707 April 2021 Triennial Fire Protection Inspection Report 05000333/2021010 IR 05000333/20200062021-03-0303 March 2021 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2020006) IR 05000333/20200042021-02-11011 February 2021 Integrated Inspection Report 05000333/2020004 IR 05000333/20200122021-01-21021 January 2021 Problem Identification and Resolution Report 05000333/2020012 and Preliminary White Finding and Apparent Violation IR 05000333/20204202020-12-10010 December 2020 Security Inspection Report 05000333/2020420 IR 05000333/20200032020-11-10010 November 2020 Integrated Inspection Report 05000333/2020003 IR 05000333/20204022020-09-16016 September 2020 Security Baseline Inspection Report 05000333/2020402 IR 05000333/20200052020-08-31031 August 2020 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2020005) IR 05000333/20200022020-08-10010 August 2020 Integrated Inspection Report 05000333/2020002 IR 05000333/20204012020-07-28028 July 2020 Cyber Security Inspection Report 05000333/2020401 (Letter Only) IR 05000333/20200112020-04-30030 April 2020 Problem Identification and Resolution Annual Sample Inspection Report 05000333/2020011 IR 05000333/20200012020-04-28028 April 2020 Integrated Inspection Report 05000333/2020001 2024-02-07
[Table view] Category:Letter
MONTHYEARIR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (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 JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, 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 JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 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 JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230052023-08-31031 August 2023 Updated Inspection Plan for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023005) JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report ML23228A1342023-08-16016 August 2023 Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20230022023-08-0707 August 2023 Integrated Inspection Report 05000333/2023002 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 JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance ML23208A1622023-07-27027 July 2023 Operator Licensing Examination Approval IR 05000333/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000333/2023402 IR 05000333/20230112023-07-25025 July 2023 Post-Approval Site Inspection for License Renewal - Phase 4 Inspection Report 05000333/2023011 IR 05000333/20235012023-07-20020 July 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000333/2023501 JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation IR 05000333/20234202023-06-26026 June 2023 Security Baseline Inspection Report 05000333 2023420 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 ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML23152A0042023-06-0101 June 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000333/2023401 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 JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report IR 05000333/20230012023-05-0303 May 2023 Integrated Inspection Report 05000333/2023001 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report IR 05000333/20230122023-04-13013 April 2023 Quadrennial Fire Protection Inspection Report 05000333/2023012 ML23095A3722023-04-0505 April 2023 2023 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations IR 05000333/20220042023-03-20020 March 2023 Integrated Inspection Report 05000333/2022004 JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 2024-02-07
[Table view] |
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{{#Wiki_filter:ber 10, 2016
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2016003
Dear Mr. Sullivan:
On September 30, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your James A. FitzPatrick Nuclear Power Plant (FitzPatrick). On October 20, 2016, 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.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
The finding did not involve a violation of NRC requirements.
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 the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Arthur L. Burritt, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket No. 50-333 License No. DPR-59
Enclosure:
Inspection Report 05000333/2016003 w/Attachment: Supplementary Information
REGION I==
Docket No. 50-333 License No. DPR-59 Report No. 05000333/2016003 Licensee: Entergy Nuclear Northeast (Entergy)
Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba, NY Dates: July 1, 2016, through September 30, 2016 Inspectors: E. Miller, Senior Resident Inspector B. Sienel, Resident Inspector S. Barr, Senior Emergency Preparedness Inspector R. Rolph, Health Physicist Approved by: Arthur L. Burritt, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure
SUMMARY
Inspection Report 05000333/2016003; 07/01/2016 - 09/30/2016; James A. FitzPatrick Nuclear
Power Plant (FitzPatrick); Follow-Up of Events and Notices of Enforcement Discretion.
This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. The inspectors identified one finding of very low safety significance (Green). The significance of most 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 August 1, 2016. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.
Cornerstone: Initiating Events
- Green.
A self-revealing Green finding (FIN) was identified for Entergy staffs failure to properly implement the requirements of EN-DC-324, Preventive Maintenance Program,
Revision 16, to ensure proper preventive maintenance (PM) was implemented for non-safety-related 4KV transformer 71T-5. Specifically, Action Request (AR) 127566, PM change request to perform inspection, cleaning, and electrical testing of 4KV transformer 71T-5 was retired without a review by engineering as required by the PM program. As a result, transformer 71T-5 remained in service beyond its effective life without proper condition monitoring and maintenance, leading to its failure and a reactor scram on June 24, 2016.
Entergy staff developed corrective actions to address the failure which included replacement of the transformer and re-establishing the condition monitoring and PM task. Entergy also performed an extent of condition review that confirmed the PM to clean, inspect, and test similar non-safety-related dry-type transformers was still active and performed within its required frequency.
This finding is more than minor because it is associated with the Equipment Performance attribute of the Initiating Events cornerstone and affected the cornerstone objective of limiting the likelihood of those events that upset plant stability and challenge critical safety functions during power operations. Specifically, Entergy staff failed to ensure an adequate PM was in place for transformer 71T-5. The PM to ensure adequate cleaning and testing was cancelled in 2011, and transformer 71T-5 ultimately failed on June 24, 2016, resulting in a manual reactor scram. In accordance with IMC 0609.04, Initial Characterization of Findings, and Exhibit 1 of IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, issued June 19, 2012, the inspectors determined that this finding is of very low safety significance (Green) because although the performance deficiency caused a reactor scram, it did not result in the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition. The inspectors did not assign a cross-cutting aspect to this finding because it is not indicative of current licensee performance. Specifically, the performance deficiency was determined to have occurred in 2011, the guidance in EN-DC-324 is clear regarding the PM change process, and no additional failures to follow the process have resulted in significant reactor transients. (Section 4OA3)
REPORT DETAILS
Summary of Plant Status
FitzPatrick began the inspection period shut down due to a forced outage associated with a reactor scram on June 24, 2016. On July 6, operators commenced a reactor startup and achieved criticality. On July 7, operators synchronized the turbine-generator to the electrical grid.
On July 8, operators achieved 84 percent power, and subsequently reduced power to 64 percent following the identification of an oil sheen on Lake Ontario. Following resolution of the oil sheen, operators restored power to 84 percent. Maximum power was limited to 84 percent due to repairs associated with a condensate booster pump. On July 28, operators reduced reactor power to 75 percent to perform condenser waterbox cleaning and a rod pattern adjustment. The unit was restored to 84 percent power on July 29. On August 19, following repairs to the condensate booster pump, operators raised reactor power to 93 percent. The reduced power of 93 percent was the maximum power achievable due to fuel depletion as FitzPatrick is at the end of this operating cycle. The maximum power will continue to decrease (coast down) until the refueling outage which is planned for the first quarter of 2017. On August 21, FitzPatrick experienced an unexpected trip of the A reactor water recirculation (RWR) pump and a 44 percent runback of the B RWR pump. Operators maintained power at 44 percent following the transient. On August 22, operators raised reactor power to 51 percent following restoration of the B RWR pump to full speed. On August 24, power was again reduced to 44 percent when operators experienced a runback of the B RWR pump during feedwater (FW) system calibration. Operators restored power to 49 percent following troubleshooting of the B RWR runback on August 25. On August 26, following repairs to the A RWR system, operators began power ascension concurrently with post-maintenance testing of the RWR system. On August 28, reactor power was restored to 91 percent and coastdown to the refueling outage continued. On September 14, 2016, FitzPatrick experienced a trip of the B FW pump, and runback of the RWR system to 54 percent. On September 21, operators restored reactor power to approximately 83 percent following repairs to the B FW pump. FitzPatrick coasted down to 80 percent power by the end of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
==1R04 Equipment Alignment
.1 Partial System Walkdown
Main article: IP 71111.04 ==
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems:
B control room emergency ventilation air system (CREVAS) during planned A CREVAS maintenance on August 16, 2016 A residual heat removal (RHR) system during planned B RHR maintenance on August 23, 2016 A standby liquid control (SLC) system during planned B SLC maintenance on August 24, 2016 High pressure coolant injection (HPCI) system during emergent reactor core isolation cooling system maintenance on September 13, 2016 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the updated final safety analysis report (UFSAR), technical specifications (TSs), work orders (WOs), condition reports (CRs), and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies.
The inspectors also reviewed whether Entergy staff had properly identified equipment issues and entered them into the corrective action program (CAP) for resolution with the appropriate significance characterization. Documents reviewed for each section of this report are listed in the Attachment.
b. Findings
No findings were identified.
.2 Full System Walkdown
Main article: IP 71111.04S
a. Inspection Scope
From August 23 - August 31, 2016, the inspectors performed a complete system walkdown of accessible portions of the HPCI system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, drawings, surveillance tests, equipment lineup check-off lists, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hanger and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the system to verify system components and support equipment were aligned correctly and operable. The inspectors confirmed that systems and components were aligned correctly, free from interference from temporary services or isolation boundaries, environmentally qualified, and protected from external threats. The inspectors also examined the material condition of the components for degradation and observed operating parameters of equipment to verify that there were no deficiencies.
Additionally, the inspectors reviewed a sample of related CRs to ensure Entergy personnel appropriately evaluated and resolved any deficiencies.
b. Findings
No findings were identified.
==1R05 Fire Protection
.1 Resident Inspector Quarterly Walkdowns
Main article: IP 71111.05Q