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| {{#Wiki_filter:August 3, 2021 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2021002
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| ==Dear Mr. Rhoades:==
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| On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant. On July 22, 2021, the NRC inspectors discussed the results of this inspection with Mr. Tim Peter, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
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| No findings or violations of more than minor significance were identified during this inspection.
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| 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
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| Sincerely, Digitally signed by Erin E.
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| Erin E. Carfang Date: 2021.08.03 Carfang 14:41:40 -04'00'
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| Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety Docket No. 05000333 License No. DPR-59
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| ===Enclosure:===
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| As stated
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| ==Inspection Report==
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| Docket Number: 05000333 License Number: DPR-59 Report Number: 05000333/2021002 Enterprise Identifier: I-2021-002-0043 Licensee: Exelon Nuclear Facility: James A. FitzPatrick Nuclear Power Plant Location: Oswego, NY Inspection Dates: April 01, 2021 to June 30, 2021 Inspectors: P. Boguszewski, Acting Senior Resident Inspector J. England, Resident Inspector H. Anagnostopoulos, Senior Health Physicist E. Dipaolo, Senior Reactor Inspector J. Dolecki, Resident Inspector M. Henrion, Health Physicist C. Hobbs, Reactor Inspector E. Miller, Senior Resident Inspector A. Patel, Senior Reactor Inspector B. Pinson, Reactor Inspector C. Swisher, Resident Inspector Approved By: Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety Enclosure
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| =SUMMARY=
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| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at James A. FitzPatrick Nuclear Power Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
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| ===List of Findings and Violations===
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| No findings or violations of more than minor significance were identified.
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| ===Additional Tracking Items===
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| None.
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| =PLANT STATUS=
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| FitzPatrick started the inspection period at rated thermal power. On June 25, 2021 reactor power was lowered to 70 percent for routine testing and a rod sequence change. Power was restored to 100 percent on June 26, 2021. FitzPatrick remained at or near rated thermal power for the remainder of the inspection period.
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| ==INSPECTION SCOPES==
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| Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
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| Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
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| As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
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| ==REACTOR SAFETY==
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| ==71111.01 - Adverse Weather Protection==
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| ===Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)===
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| : (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures for the switchyard and the 'A' and 'B' 125VDC battery rooms on June 2, 2021.
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| ==71111.04 - Equipment Alignment==
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| ===Partial Walkdown Sample (IP Section 03.01) (6 Samples)===
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| The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
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| : (1) 'A' emergency service water on April 15, 2021
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| : (2) 4160-volt and 400-volt normal alternating current power distribution on April 26, 2021
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| : (3) 'A' and 'C' emergency diesel generator (EDG) during 'B' and 'D' EDG testing on May 24, 2021
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| : (4) High pressure coolant injection system following governor valve position indication repair on May 26, 2021
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| : (5) Primary containment venting on June 15, 2021
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| : (6) 'B' and 'D' residual heat removal (RHR) system during emergency Technical Specification amendment on June 21, 2021
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| ===Complete Walkdown Sample (IP Section 03.02) (1 Sample)===
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| : (1) Control rod drive system on April 8, 2021
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| ==71111.05 - Fire Protection==
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| ===Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)===
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| The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
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| : (1) Main control room, control room HVAC room, elevation 300', and relay room 286', fire area VII/CR-1 and RR-1, on April 1, 2021
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| : (2) Reactor building 272 elevation, fire area X/RB-1B and IX/RB-1A, on April 6, 2021
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| : (3) Site plan, fire area yard, on April 19, 2021
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| : (4) ISFSI pad and switch yard, 345-kilovolt and 115-kilovolt yards, fire area yard, on April 20, 2021
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| : (5) East electric fire bay, fire area/zone II/SW-2 on May 24, 2021
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| : (6) West electric fire bay, fire area/zone IC/SW-1 on May 24, 2021
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| ==71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance==
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| ===Requalification Examination Results (IP Section 03.03) (1 Sample)===
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| : (1) The inspectors reviewed and evaluated the licensed operator requalification examination exam results for the annual operating exam and biennial written exam on June 29, 2021.
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| ==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance==
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| Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
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| (1 Sample)
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| : (1) The inspectors observed reactivity operations to lower power to 70 percent for a control rod sequence exchange, control rod scram time testing, and turbine valve testing on June 25 - June 26, 2021.
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| ===Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors observed and evaluated operator performance in the simulator which included job performance measures to place the high pressure coolant injection system in pressure control operation, and reactor pressure vessel isolation on May 6, 2021
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| ==71111.12 - Maintenance Effectiveness==
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| ===Maintenance Effectiveness (IP Section 03.01) (2 Samples)===
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| The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
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| : (1) Core spray system on April 30, 2021
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| : (2) Structural monitoring walkdown of the torus room on May 19, 2021
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| ==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
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| ===Risk Assessment and Management Sample (IP Section 03.01) (7 Samples)===
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| The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
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| : (1) Elevated risk (Action Green) during scheduled maintenance activities on 'C' EDG, week of April 19-22, 2021
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| : (2) Elevated risk (Action Green) during planned maintenance on 71T-3 115 transformer on May 11, 2021
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| : (3) Emergent risk associated with electro-hydraulic control turbine intercept valve movement on May 19, 2021
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| : (4) Unplanned loss of 'A' reactor water recirculation speed control circuit on June 4, 2021
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| : (5) 'B' RHR system during 'A' RHR planned maintenance on June 8, 2021
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| : (6) Emergency license amendment protected equipment during 'A' RHR pump maintenance on June 13, 2021
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| : (7) Fire risk protection due to 'A' RHR system unavailability exceeding 60 hours on June 14, 2021
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| ==71111.15 - Operability Determinations and Functionality Assessments==
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| ===Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)===
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| The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
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| : (1) Control room emergency ventilation air supply system due to degraded 'B' ventilation supply fan, 70FN-6B, on April 2, 2021
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| : (2) Emergency service water due to through-wall leakage on 'B' piping on April 13, 2021
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| : (3) Control room emergency ventilation air system due to a degraded relay associated with 70FN-6B on May 10, 2021
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| ==71111.18 - Plant Modifications==
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| ===Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)===
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| : (1) Revision to Severe Accident Management Guidelines
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| ==71111.19 - Post-Maintenance Testing==
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| ===Post-Maintenance Test Sample (IP Section 03.01) (10 Samples)===
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| The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
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| : (1) 'A' low pressure coolant injection inverter work on April 13, 2021
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| : (2) 76P-2, electric-driven fire pump following pump replacement on April 16, 2021
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| : (3) 'A' EDG following 'C' EDG scheduled maintenance activities on April 22, 2021
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| : (4) 'B' EDG and 'D' EDG Force Parallel Logic Relay (93TD9M-1EDGB13) on May 4, 2021
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| : (5) 'B' EDG following turbocharger replacement on May 6, 2021
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| : (6) High pressure coolant injection system following governor valve position indication repair on May 26, 2021
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| : (7) 'D' RHR service water pump breaker swap on June 2, 2021
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| : (8) 'A' RHR pump after failed Baker testing on June 8, 2021
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| : (9) 'A' RHR pump following motor replacement on June 17, 2021
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| : (10) Control rod 26-35 following scram solenoid pilot valve replacement on June 26, 2021
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| ==71111.22 - Surveillance Testing==
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| The inspectors evaluated the following surveillance tests:
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| ===Surveillance Tests (other) (IP Section 03.01)===
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| {{IP sample|IP=IP 71111.22|count=1}}
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| : (1) ST-9BB, EDG B and D Full Load Test and ESW Pump Operability Test, on
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| ===April 2, 2021 Inservice Testing (IP Section 03.01) (4 Samples)===
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| : (1) ST-3PB, Core Spray Loop B Quarterly Operability Test, on June 4, 2021
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| : (2) HPCI system review for Emergency License Amendment Review, on June 12, 2021
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| : (3) 'B' and 'D' residual heat removal system for Emergency License Amendment Review, on June 12, 2021
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| : (4) 'B' and 'D' emergency diesel generators for Emergency License Amendment Review, on June 12,
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| ==RADIATION SAFETY==
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| ==71124.01 - Radiological Hazard Assessment and Exposure Controls==
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| ===Radiological Hazard Assessment (IP Section 03.01) (1 Sample)===
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| : (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials, and how the licensee assesses radiological hazards.
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| ===Instructions to Workers (IP Section 03.02) (1 Sample)===
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| The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
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| : (1) The inspectors reviewed the following:
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| Radiation Work Packages
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| * RWP JF-1-21-00302 TIP Area Activities
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| * RWP JF-1-21-00202 Radwaste Activities
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| * RWP JF-1-21-00209 Transportation of Radioactive Material Electronic Alarming Dosimeter Alarms
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| * EAD Alarm on May 18, 2020
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| * EAD Alarm on September 19, 2020
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| * EAD Alarm on September 21, 2020 Labeling of Containers
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| * LSA trash bins
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| * Bagged laundry
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| * Bagged portable vacuums
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| ===Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)===
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| The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors:
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| : (1) Observed licensee survey of tools, filters, and meters for release from the radiologically controlled area
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| : (2) Observed workers exiting radiologically controlled area and using the small articles monitor at the main access point
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| : (3) Inspected radwaste packages that are stored and awaiting shipment
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| ===Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)===
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| The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of the following radiological work activities:
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| : (1) Replacement of 12P-1A RWCU pump in January 2021
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| : (2) Testing and maintenance of 'A' residual heat removal motor-operated valves
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| : (3) Replacement of 'A' feed pump cooling coils High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)
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| The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
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| : (1) Reactor building decontamination room
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| : (2) Reactor traversing in-core probe
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| : (3) Fuel pool cooling
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| : (4) Reactor water cleanup hold pump room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
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| : (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
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| ==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation==
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| ===Permanent Ventilation Systems (IP Section 03.01) (2 Samples)===
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| The inspectors evaluated the configuration of the following permanently installed ventilation systems:
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| : (1) Reactor building ventilation system
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| : (2) Control room ventilation system
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| ===Temporary Ventilation Systems (IP Section 03.02) (2 Samples)===
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| The inspectors evaluated the configuration of the following temporary ventilation systems:
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| : (1) Decontamination booth in radwaste
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| : (2) Reactor building decontamination room
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| ===Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)===
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| : (1) The inspectors evaluated the licensees use of respiratory protection devices.
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| ===Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)===
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| : (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
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| ==OTHER ACTIVITIES - BASELINE==
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| ===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
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| BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===
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| {{IP sample|IP=IP 71151|count=1}}
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| : (1) January 1, 2020 through December 31, 2020
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| ===BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)===
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| : (1) April 1, 2020 through March 31, 2021
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| ==71152 - Problem Identification and Resolution==
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| ===Semiannual Trend Review (IP Section 02.02) (1 Sample)===
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| : (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in that might be indicative of a more significant safety issue.
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| ===Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)===
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| The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:
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| : (1) IR 4267056 - Spent Fuel Pool Thermal Dispersion Criteria Not Maintained
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| ===71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03) ===
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| {{IP sample|IP=IP 71153|count=1}}
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| : (1) Half scram following blown fuse on reactor protection system channel A1 during response time testing of master trip unit 05MTU-212A on May 18,
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| ==INSPECTION RESULTS==
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| Minor Violation 71152 Minor Violation: On July 25, 2019, Exelon Nuclear Oversight conducted an audit at FitzPatrick and discovered that fuel assemblies discharged into the spent fuel pool (SFP) at the end of the last refueling outage (J1R23), which ended in October 2018, had not conformed to the B.5.b thermal dispersion pattern committed to by FitzPatrick. Specifically, four fuel bundles discharged into the northeast corner of the SFP did not meet the separation criteria specified in NF-AB-309, "BWR Special Nuclear Material and Core Component Move Sheet Development," Attachment 8, which describes a Knight's Move, 6-cell pattern, similar to the way the knight piece moves in a game of chess. In this pattern, recently discharged fuel bundles that have been out of the core for less than 275 days do not share an adjacent location in the SFP with another fuel bundle that has also been discharged from the reactor core for less than 275 days. This arrangement of recently discharged fuel bundles in the SFP is a mitigation strategy to cope with the requirements of Section B.5.b of Commission Order EA-02-026 for protection against loss of large areas of the plant due to fire or explosion, and is codified in Title 10 of the Code of Federal Regulations (10 CFR) 50.155 (b)(2), "Mitigation of Beyond-Design-Basis Events."
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| An Extent of Condition analysis was conducted in IR 04267056, and it was determined that the software program utilized for planning and executing fuel moves in the SFP had not correctly modeled the dimensions between racks in the SFP in the northeast corner of the pool. This was a latent error that had existed since FitzPatrick first began using the ShuffleWorks software for planning fuel moves in the 2004 through 2006 timeframe. On August 23, 2007, FitzPatrick adopted a License Amendment committing to the offloading of fuel assemblies into the Knight's Move B.5.b dispersal pattern in the SFP. Exelon determined that the four fuel assemblies identified on July 25, 2019, had already been in the SFP for greater than 275 days, therefore, it was not necessary to move the fuel into a new location in the pool. Additional corrective actions taken by Exelon included a review of FitzPatrick refueling procedures, an update to the ShuffleWorks fuel movement software, and fleet actions to have each Exelon plant perform a check to determine if the fuel movement software at that facility modeled the actual physical rack dimensions in the SFP at that facility.
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| For the review of FitzPatrick refueling procedures, Exelon determined that adequate steps already existed in OS-66.001, "Management of Refueling Activities," and NF-AB-309, "BWR Special Nuclear Material and Core Component Move Sheet Development" to describe the B.5.b fuel thermal dispersion pattern, and to incorporate this strategy into reactor core offloads during refueling outages. Therefore, Exelon determined that no procedural changes were necessary. The ShuffleWorks program at FitzPatrick was modified to place a constraint violation on the locations in the SFP that do not meet the B.5.b thermal dispersion distance separation requirements, so that a warning box appears if a fuel assembly is placed in one of these locations during fuel movement planning operations. The inspectors conducted interviews with reactor engineers, and reviewed the corrective actions taken by Exelon in response to the B.5.b thermal dispersion issue identified on July 25, 2019, and determined they were adequate.
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| Corrective Action Reference: IR 04267056 Screening: The inspectors determined the performance deficiency was minor. The inspectors determined that the failure to comply with the B.5.b thermal dispersion pattern described in NF-AB-309, Attachment 8 was a performance deficiency. Specifically, NF-AB-309, "BWR Special Nuclear Material and Core Component Move Sheet Development," Revision 3, Step 4.4.9 requires that fuel move sheets are generated using approved and controlled move planning software, that ensures the required prerequisites and recommended constraints are followed, and that the move planning software is up-to-date.
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| The inspectors determined that the performance deficiency was minor due to the low number of fuel assemblies impacted, and that the small dimensional discrepancy between assemblies would not have a significant effect on the heat removal capability of the SFP during a postulated Beyond Design Basis scenario.
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| =====Enforcement:=====
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| FitzPatrick License Condition 2R.(b)(7), "Mitigation Strategy License Condition," requires in part that SFP mitigation measures are developed and maintained to address large fires and explosions. Contrary to the above, from August 23, 2007, the date the License Condition was implemented, until July 25, 2019, fuel assemblies loaded into the northeast corner of the SFP from the reactor core in every other refueling outage, were not in compliance with the B.5.b thermal dispersion separation requirements specified in NF-AB-309,"BWR Special Nuclear Material and Core Component Move Sheet Development."
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| Following identification of the issue, Exelon took corrective actions to restore compliance.
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| This failure to comply with License Condition 2R.(b)(7) constitutes a minor violation that is not subject to enforcement action in accordance with the NRC's Enforcement Policy.
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| Observation: Semi-Annual Trend 71152 The inspectors evaluated a sample of issues and events that occurred over the first and second quarters of 2021. The evaluation did not reveal any new trends that could indicate a more significant safety issue. The inspectors determined that, in most cases, the issues were appropriately evaluated by Exelon staff for potential trends at a low threshold, and resolved within the scope of the corrective action program. The inspectors identified a trend associated with additional equipment failure that resulted in additional monitoring and unplanned maintenance, which included the 'A' reactor water cleanup pump seal failure, an immersion heater failure associated with the 'C' emergency diesel generator, unexpected movement of the turbine intercept valves, and failure of the 'A' residual heat removal pump motor. The inspectors also identified a trend with increasing failure of emergency battery lights.
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| Based on the overall results of the semi-annual trend review, the inspectors determined that Exelon had generally identified adverse trends at FitzPatrick before they could become more significant safety problems. The inspectors independently evaluated the deficiencies noted above for significance in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and Appendix E, "Examples of Minor Issues," and determined them to be minor.
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| ==EXIT MEETINGS AND DEBRIEFS==
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| The inspectors verified no proprietary information was retained or documented in this report.
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| * On July 22, 2021, the inspectors presented the integrated inspection results to Mr. Tim Peter, Site Vice President, and other members of the licensee staff.
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| * On June 10, 2021, the inspectors presented the radiological hazard assessment and exposure controls inspection results to Mr. Mohamed Khan, Director, Site Engineering, and other members of the licensee staff.
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| * On June 10, 2021, the inspectors presented the spent fuel pool inspection results to Mr. Philip Nichols, Reactor Engineering Manager, and other members of the licensee staff.
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| THIRD PARTY REVIEWS Inspectors reviewed Institute of Nuclear Power Operations reports that were issued during the inspection period for the evaluation conducted in February 2021.
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| =DOCUMENTS REVIEWED=
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| 71111.01 Procedures WC-JF-107-1000 Seasonal Readiness T&RM for JAF 3
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| Work Orders 05042019
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| 71111.04 Drawings FE-1B Main One line Diagram Sheet 2 Station Service 19
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| Transformers
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| FM-20A Flow Diagram Residual Heat Removal System 10 73
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| FM-27A Flow Diagram Control Rod Drive System 03 39
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| FM-46A Flow Diagram Service Water System 46 94
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| FM-46B Flow Diagram Emergency Service Water System 46 & 15 57
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| ISI-FM-27B ISI Drawing 13
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| Procedures OP-21 Emergency Service Water (ESW) 41
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| OP-22 Diesel Generator Emergency Power 71
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| OP-25 Control Rod Drive Hydraulic System 93
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| OP-46A 4160V and 600V Normal AC Power Distribution 71
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| TSG-9 Primary Containment Venting Without AC Power 5
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| 71111.05 Corrective Action 04414983
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| Documents 04417967
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| Resulting from 04417970
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| Inspection 04417972
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| 04417989
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| Fire Plans Site Plan 5
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| FPP-3.56 Portable Fire Extinguisher Inspection Procedure 6
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| PFP-OUT39 ISFSI Pad Location, Elevation 272' Fire Area/Zone/Yard 3
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| PFP-PWR12 Relay Room/Elev. 286' Fire Area/Zone Vii/RR-1 5
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| PFP-PWR13 Main Control Room and Control Room HVAC Equipment 8
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| Rooms/Elev. 300' Fire Area/Zone VII/CR-1
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| PFP-PWR20 Reactor Building - East/Elev. 272' Fire Area/Zone IX/RB- 05
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| 1A
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| PFP-PWR21 Reactor Building - West/Elev. 272' Fire Area/Zone X/RB- 05
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| 1B
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| PFP-PWR29 Switchgear Room East, Elevation 272', Fire Area 2/Fire 4
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| Zone SW-2
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| PFP-PWR51 Switch Yard, 345 and 115 kV Yards, Elevation 272'0" Fire 0
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| Area Yard/Fire Zone Yard
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| PFP-PWR30 Switchgear Room West Elevation 272', Fire Area/Fire 2
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| Zone IC/SW-1
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| Work Orders 05099562
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| 71111.11Q Procedures OP-AB-300-1003 BWR Reactivity Maneuver Guidance 18
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| RAP-7.4.01 Control Rod Scram Time Evaluation 31
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| ST-1L Main Turbine Control Valve Instrument Channel and Valve 37
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| Operability Check
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| 71111.12 Corrective Action 04404301
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| Documents 04390733
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| 04394058
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| 04404883
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| 04404967
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| 04412087
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| 04416039
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| Corrective Action 04424860
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| Documents 04424863
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| Resulting from 04424885
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| Inspection 04424886
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| 04424889
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| 04424891
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| 04424960
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| 04424973
| |
| 04424997
| |
| Engineering JAF-RPT-07- Maintenance Rule Structural Monitoring Report 006
| |
| Evaluations 00006
| |
| JAF-RPT-07- Maintenance Rule Structural Monitoring Report 005
| |
| 00006
| |
| Miscellaneous Maintenance Core Spray System
| |
| Rule System
| |
| Basis Document,
| |
| System 14
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| Procedures ST-9BB EDG B and D Full Load Test and ESW Pump Operability Revision 19
| |
| Test
| |
| 71111.13 Corrective Action 04422793
| |
| Documents 04424128
| |
| 04427658
| |
| Corrective Action 04423185
| |
| Documents
| |
| Resulting from
| |
| Inspection
| |
| Drawings 1.11-466 Load Control Unit C
| |
| 1.11-472 Intercept: Valve Pre-Amp
| |
| 1.11-545 Schematic Wiring Diagram Valve Test Logic IV-1 & IV-3
| |
| 1.11-588 Schematic Wiring Diagram Intercept Valve No. 1 Position B
| |
| Unit
| |
| FM-31A Flow Diagram Extraction Steam System 31 25
| |
| FM-31B Flow Diagram Moisture Separator Reheater Drain System 52
| |
| S94-003.cdr EHC Hydraulics 0
| |
| Miscellaneous James A. 1
| |
| FitzPatrick
| |
| Technical
| |
| Support
| |
| Guidelines,
| |
| TSGS
| |
| Procedures AP-16.14 Hazard Barrier Controls 8
| |
| EOP-PC Hot Primary Containment Control 0
| |
| EP-6 Post Accident Containment Venting and Gas Control 012
| |
| JF-CRM-004 Development of Risk Management Actions for the 1
| |
| Inclusion of Fire Insights into James A. FitzPatrick
| |
| Configuration Risk Management Program
| |
| JF-PRA-005.15 JAF PRA Emergency Diesel Generators System 0
| |
| Notebook
| |
| MP-093.05 EDG Power Assembly Maintenance 14
| |
| MP-093.11 EDG System Mechanical PM 55
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| OP-AA-108-111 Adverse Condition Monitoring and Contingency Plan 15
| |
| OP-AA-108-117 Protected Equipment Program 006
| |
| OP-AA-108-117 Protected Equipment Program 6
| |
| OP-AA-201-012- Operations On-Line Fire Risk Management 4
| |
| 1001
| |
| Severe Accident RPV, Containment, and Radioactive Release Control (1-4) 5
| |
| Operating
| |
| Guideline
| |
| (SAOG)-2
| |
| TSG-9 Primary Containment Venting without AC Power 5
| |
| Work Orders 05158736
| |
| 71111.15 Corrective Action 04412368
| |
| Documents 04412368
| |
| 04416041
| |
| 04416224
| |
| 04416742
| |
| 04416743
| |
| Procedures ESK-6FM HVAC Emergency Air Supply FN-6A and 6B Control 12
| |
| Room
| |
| ISP-85 Control Room Ventilation Temperature and Differential 26
| |
| Pressure Instrument Calibration
| |
| 71111.18 Miscellaneous Reactor Oversight Process Changes to Address Severe February 23,
| |
| Accident Management Guidelines 2016
| |
| (ML16032A029)
| |
| JAFP-15-0145 Commitment to Maintain Severe Accident Management December 15,
| |
| Guidelines 2015
| |
| NEI 14-01 Emergency Response Procedures and Guidelines for
| |
| Beyond Design Basis Events and Severe Accidents
| |
| TSGS James A. FitzPatrick Nuclear Power Plant Technical 1
| |
| Support Guidelines
| |
| Procedures SAOG-1 RPV and Primary Containment Injection Control (1-4) 1
| |
| SAOG-2 RPV, Containment, and Radioactivity Release Control (1- 5
| |
| 4)
| |
| SAOG-3 RPV Controls 5
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| SAOG-4 Containment and Radioactivity Release Control (5) 0
| |
| 71111.19 Corrective Action 04418483
| |
| Documents
| |
| Miscellaneous ST-76B Electric Fire Pump 76P-2 Operational Check March 18, 2021
| |
| ST-76J24 Electric Fire Pump 76P-2 Performance Test March 18, 2021
| |
| Procedures MA-AA-723-330 Electrical Testing of AC Motors using Baker Instrument 6
| |
| Advanced Winding Analyzer
| |
| MP-054.05 4.16 kV Magne-Blast Breaker Swap/Replacing 03
| |
| ST-16GA A LPCI MOV Independent Power Supply Test 005
| |
| ST-2AL RHR Loop A Quarterly Operability Test (IST)* 042
| |
| ST-9BA EDG A and C Full Load Test and ESW Pump Operability 20
| |
| Test
| |
| Work Orders 04832790
| |
| 04879904-47
| |
| 04932365
| |
| 05125609
| |
| 05129031
| |
| 05135425
| |
| 4915588-02
| |
| 26005
| |
| 71111.20 Miscellaneous NFPA 20-1970 Standard for the Installation of Centrifugal Fire Pumps 1970
| |
| 71111.22 Corrective Action 04372229
| |
| Documents 04377749
| |
| Procedures ST-3PB Core Spray Loop B Quarterly Operability Test 31
| |
| ST-43I Remote Shutdown Instrument Check
| |
| ST-9BB EDG B and D Full Load Test and ESW Pump Operability 19
| |
| Test
| |
| ST-9CB EDG B and D Load Sequencing Test and 4kV Emergency 6
| |
| Power System Voltage Relays Instrument Functional Test
| |
| ST-9QB EDG B and D Full Load Test (8 Hour Run) 0
| |
| Work Orders 4684948
| |
| 4886078
| |
| 4973154
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 5047948
| |
| 5100611
| |
| 23482
| |
| 25380
| |
| 5130230-01
| |
| 5141387
| |
| 5148131
| |
| 51568506
| |
| 71151 Procedures ST-40D Daily Surveillance and Channel Check 124
| |
| 71152 Calculations JAF-RPT-08- GNF2 Fuel Design Cycle Independent Analysis for 1
| |
| 00013 Entergy FitzPatrick
| |
| Corrective Action 04155271
| |
| Documents 04174769
| |
| 267056
| |
| 277344
| |
| 04355560
| |
| Corrective Action 04428127
| |
| Documents
| |
| Resulting from
| |
| Inspection
| |
| Drawings Drawing No. Pool Layout - Spent Fuel Pool Storage Racks 1
| |
| 3.52-73
| |
| UFSAR Figure Arrangement of Aluminum High Density Racks 4
| |
| No. 9.3-1
| |
| UFSAR Figure Arrangement of Spent Fuel Racks with Stainless Steel 2
| |
| No. 9.3-6 High Density Racks
| |
| Miscellaneous DPR-59 FitzPatrick Renewed Facility Operating License No. DPR-
| |
| NRC Information Spent Fuel Storage or Transportation System Misloading
| |
| Notice 2014-09
| |
| NRC Information Potential Safety Enhancements to Spent Fuel Pool
| |
| Notice 2014-14 Storage
| |
| UFSAR FitzPatrick Updated Final Safety Analysis Report 7
| |
| Procedures NF-AA-309 Special Nuclear Material and Core Component Move 10
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| Sheet Development
| |
| NF-AA-310 Special Nuclear Material and Core Component Movement 23
| |
| NF-AB-110-1170 Generation of Fuel Moves Using ShuffleWorks 13
| |
| NF-AB-309 BWR Special Nuclear Material and Core Component 3
| |
| Move Sheet Development
| |
| OSP-66.001 Management of Refueling Activities 15
| |
| 71153 Corrective Action 04424276
| |
| Documents
| |
| Procedures ISP-107A RPS Drywell Pressure Instrument Response Time Test 6
| |
| (ATTS)
| |
| Work Orders 82603706
| |
| 18
| |
| }} | | }} |
