IR 05000333/2021002

James A. Fitpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2021002

ML21215A064
Person / Time
Site:	FitzPatrick
Issue date:	08/03/2021
From:	Erin Carfang NRC/RGN-I/DORS
To:	Rhoades D Exelon Generation Co, Exelon Nuclear
References
IR 2021002
Download: ML21215A064 (20)

Text

August 3, 2021

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2021002

Dear Mr. Rhoades:

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.

No findings or violations of more than minor significance were identified during this inspection.

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.

Sincerely, Digitally signed by Erin E.

Erin E. Carfang Date: 2021.08.03 Carfang 14:41:40 -04'00'

Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety Docket No. 05000333 License No. DPR-59

Enclosure:

As stated

Inspection Report

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

SUMMARY

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.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

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.

INSPECTION SCOPES

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.

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.

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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) 'A' emergency service water on April 15, 2021

(2) 4160-volt and 400-volt normal alternating current power distribution on April 26, 2021

(3) 'A' and 'C' emergency diesel generator (EDG) during 'B' and 'D' EDG testing on May 24, 2021

(4) High pressure coolant injection system following governor valve position indication repair on May 26, 2021

(5) Primary containment venting on June 15, 2021

(6) 'B' and 'D' residual heat removal (RHR) system during emergency Technical Specification amendment on June 21, 2021

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) Control rod drive system on April 8, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

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:

(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

(2) Reactor building 272 elevation, fire area X/RB-1B and IX/RB-1A, on April 6, 2021

(3) Site plan, fire area yard, on April 19, 2021

(4) ISFSI pad and switch yard, 345-kilovolt and 115-kilovolt yards, fire area yard, on April 20, 2021

(5) East electric fire bay, fire area/zone II/SW-2 on May 24, 2021

(6) West electric fire bay, fire area/zone IC/SW-1 on May 24, 2021

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(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.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1 Sample)

(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.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(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

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Core spray system on April 30, 2021

(2) Structural monitoring walkdown of the torus room on May 19, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (7 Samples)

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:

(1) Elevated risk (Action Green) during scheduled maintenance activities on 'C' EDG, week of April 19-22, 2021

(2) Elevated risk (Action Green) during planned maintenance on 71T-3 115 transformer on May 11, 2021

(3) Emergent risk associated with electro-hydraulic control turbine intercept valve movement on May 19, 2021

(4) Unplanned loss of 'A' reactor water recirculation speed control circuit on June 4, 2021

(5) 'B' RHR system during 'A' RHR planned maintenance on June 8, 2021

(6) Emergency license amendment protected equipment during 'A' RHR pump maintenance on June 13, 2021

(7) Fire risk protection due to 'A' RHR system unavailability exceeding 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> on June 14, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Control room emergency ventilation air supply system due to degraded 'B' ventilation supply fan, 70FN-6B, on April 2, 2021

(2) Emergency service water due to through-wall leakage on 'B' piping on April 13, 2021

(3) Control room emergency ventilation air system due to a degraded relay associated with 70FN-6B on May 10, 2021

71111.18 - Plant Modifications

Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)

(1) Revision to Severe Accident Management Guidelines

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (10 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) 'A' low pressure coolant injection inverter work on April 13, 2021

(2) 76P-2, electric-driven fire pump following pump replacement on April 16, 2021

(3) 'A' EDG following 'C' EDG scheduled maintenance activities on April 22, 2021

(4) 'B' EDG and 'D' EDG Force Parallel Logic Relay (93TD9M-1EDGB13) on May 4, 2021

(5) 'B' EDG following turbocharger replacement on May 6, 2021

(6) High pressure coolant injection system following governor valve position indication repair on May 26, 2021

(7) 'D' RHR service water pump breaker swap on June 2, 2021

(8) 'A' RHR pump after failed Baker testing on June 8, 2021

(9) 'A' RHR pump following motor replacement on June 17, 2021

(10) Control rod 26-35 following scram solenoid pilot valve replacement on June 26, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) ST-9BB, EDG B and D Full Load Test and ESW Pump Operability Test, on

April 2, 2021 Inservice Testing (IP Section 03.01) (4 Samples)

(1) ST-3PB, Core Spray Loop B Quarterly Operability Test, on June 4, 2021

(2) HPCI system review for Emergency License Amendment Review, on June 12, 2021

(3) 'B' and 'D' residual heat removal system for Emergency License Amendment Review, on June 12, 2021

(4) 'B' and 'D' emergency diesel generators for Emergency License Amendment Review, on June 12,

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(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.

Instructions to Workers (IP Section 03.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.

(1) The inspectors reviewed the following:

Radiation Work Packages

• RWP JF-1-21-00302 TIP Area Activities

• RWP JF-1-21-00202 Radwaste Activities

• RWP JF-1-21-00209 Transportation of Radioactive Material Electronic Alarming Dosimeter Alarms

• EAD Alarm on May 18, 2020

• EAD Alarm on September 19, 2020

• EAD Alarm on September 21, 2020 Labeling of Containers

• LSA trash bins

• Bagged laundry

• Bagged portable vacuums

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors:

(1) Observed licensee survey of tools, filters, and meters for release from the radiologically controlled area

(2) Observed workers exiting radiologically controlled area and using the small articles monitor at the main access point

(3) Inspected radwaste packages that are stored and awaiting shipment

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of the following radiological work activities:

(1) Replacement of 12P-1A RWCU pump in January 2021

(2) Testing and maintenance of 'A' residual heat removal motor-operated valves

(3) Replacement of 'A' feed pump cooling coils High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Reactor building decontamination room

(2) Reactor traversing in-core probe

(3) Fuel pool cooling

(4) Reactor water cleanup hold pump room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Reactor building ventilation system

(2) Control room ventilation system

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Decontamination booth in radwaste

(2) Reactor building decontamination room

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===

(1) January 1, 2020 through December 31, 2020

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) April 1, 2020 through March 31, 2021

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in that might be indicative of a more significant safety issue.

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issue:

(1) IR 4267056 - Spent Fuel Pool Thermal Dispersion Criteria Not Maintained

71153 - Follow Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)

(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,

INSPECTION RESULTS

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."

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.

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.

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.

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.

Enforcement:

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."

Following identification of the issue, Exelon took corrective actions to restore compliance.

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.

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.

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.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• 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.

• 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.

• 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.

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.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures WC-JF-107-1000 Seasonal Readiness T&RM for JAF 3

Work Orders 05042019

71111.04 Drawings FE-1B Main One line Diagram Sheet 2 Station Service 19

Transformers

FM-20A Flow Diagram Residual Heat Removal System 10 73

FM-27A Flow Diagram Control Rod Drive System 03 39

FM-46A Flow Diagram Service Water System 46 94

FM-46B Flow Diagram Emergency Service Water System 46 & 15 57

ISI-FM-27B ISI Drawing 13

Procedures OP-21 Emergency Service Water (ESW) 41

OP-22 Diesel Generator Emergency Power 71

OP-25 Control Rod Drive Hydraulic System 93

OP-46A 4160V and 600V Normal AC Power Distribution 71

TSG-9 Primary Containment Venting Without AC Power 5

71111.05 Corrective Action 04414983

Documents 04417967

Resulting from 04417970

Inspection 04417972

04417989

Fire Plans Site Plan 5

FPP-3.56 Portable Fire Extinguisher Inspection Procedure 6

PFP-OUT39 ISFSI Pad Location, Elevation 272' Fire Area/Zone/Yard 3

PFP-PWR12 Relay Room/Elev. 286' Fire Area/Zone Vii/RR-1 5

PFP-PWR13 Main Control Room and Control Room HVAC Equipment 8

Rooms/Elev. 300' Fire Area/Zone VII/CR-1

PFP-PWR20 Reactor Building - East/Elev. 272' Fire Area/Zone IX/RB- 05

1A

PFP-PWR21 Reactor Building - West/Elev. 272' Fire Area/Zone X/RB- 05

1B

PFP-PWR29 Switchgear Room East, Elevation 272', Fire Area 2/Fire 4

Zone SW-2

Inspection Type Designation Description or Title Revision or

Procedure Date

PFP-PWR51 Switch Yard, 345 and 115 kV Yards, Elevation 272'0" Fire 0

Area Yard/Fire Zone Yard

PFP-PWR30 Switchgear Room West Elevation 272', Fire Area/Fire 2

Zone IC/SW-1

Work Orders 05099562

71111.11Q Procedures OP-AB-300-1003 BWR Reactivity Maneuver Guidance 18

RAP-7.4.01 Control Rod Scram Time Evaluation 31

ST-1L Main Turbine Control Valve Instrument Channel and Valve 37

Operability Check

71111.12 Corrective Action 04404301

Documents 04390733

04394058

04404883

04404967

04412087

04416039

Corrective Action 04424860

Documents 04424863

Resulting from 04424885

Inspection 04424886

04424889

04424891

04424960

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