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| author name = Dimitriadis A
| author name = Dimitriadis A
| author affiliation = NRC/RGN-I/DRP/PB5
| author affiliation = NRC/RGN-I/DRP/PB5
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000333
| docket = 05000333
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=Text=
=Text=
{{#Wiki_filter:(Addressee)
{{#Wiki_filter:(Addressee)
November 8, 2018
UNITED STATES NUCLEAR REGULATORY COMMISSION


Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
==REGION I==
 
2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 November 8, 2018 Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018003
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018003


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
Line 30: Line 29:
The NRC inspectors did not identify any findings or violations of more than minor significance.
The NRC inspectors did not identify any findings or violations of more than minor significance.


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 Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
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 Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely,/RA/ Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59  
Sincerely,
/RA/
Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59


===Enclosure:===
===Enclosure:===
Inspection Report 05000333/2018003  
Inspection Report 05000333/2018003


cc w/encl: Distribution via ListServ
==Inspection Report==
Docket Number: 50-333 License Number: DPR-59 Report Number: 05000333/2018003 Enterprise Identifier: I-2018-003-0065 Licensee: Exelon Generation Company, LLC (Exelon)
Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba, NY Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: J. Schussler, Acting Senior Resident Inspector G. Stock, Acting Senior Resident Inspector J. Bream, Physical Security Inspector P. Boguszewski, Project Engineer T. Daun, Resident Inspector, Susquehanna Nuclear Power Plant J. DeBoer, Emergency Preparedness Inspector S. Ghrayeb, Acting Resident Inspector E. Miller, Senior Resident Inspector, Nine Mile Point Nuclear Station M. Modes, Senior Reactor Inspector R. Rolph, Health Physicist B. Sienel, Resident Inspector, Nine Mile Point Nuclear Station Approved By: Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure


ML18313A068 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME JSchussler via email JAyala ADimitriadis DATE 10/31/18 11/8/18 11/8/18
=SUMMARY=
 
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
 
Docket Number: 50-333
 
License Number: DPR-59
 
Report Number: 05000333/2018003
 
Enterprise Identifier: I-2018-003-0065
 
Licensee: Exelon Generation Company, LLC (Exelon)  
 
Facility: James A. FitzPatrick Nuclear Power Plant
 
Location: Scriba, NY
 
Inspection Dates: July 1, 2018 to September 30, 2018
 
Inspectors: J. Schussler, Acting Senior Resident Inspector G. Stock, Acting Senior Resident Inspector J. Bream, Physical Security Inspector P. Boguszewski, Project Engineer T. Daun, Resident Inspector, Susquehanna Nuclear Power Plant J. DeBoer, Emergency Preparedness Inspector S. Ghrayeb, Acting Resident Inspector E. Miller, Senior Resident Inspector, Nine Mile Point Nuclear Station M. Modes, Senior Reactor Inspector R. Rolph, Health Physicist B. Sienel, Resident Inspector, Nine Mile Point Nuclear Station
 
Approved By: Anthony Dimitriadis, Chief
 
Reactor Projects Branch 5 Division of Reactor Projects
 
2


=SUMMARY=
FitzPatrick by conducting the baseline inspections described in this report 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.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelon's performance at FitzPatrick by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.


No findings or more-than-minor violations were identified.
No findings or more-than-minor violations were identified.


3
=PLANT STATUS=


=PLANT STATUS=
FitzPatrick began the inspection period at approximately 98 percent and gradually lowered power as it entered end-of-cycle coastdown operations. On September 10, 2018, operators commenced a shutdown from approximately 80 percent for a planned refueling and maintenance outage (RFO23). The unit remained shutdown for the remainder of the inspection period.
FitzPatrick began the inspection period at approximately 98 percent and gradually lowered power as it entered end-of-cycle coastdown operations. On September 10, 2018, operators commenced a shutdown from approximately 80 percent for a planned refueling and maintenance outage (RFO23). The unit remained shutdown for the remainder of the inspection period.


==INSPECTION SCOPES==
==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 performed plant status activities described in IMC 2515, Appendix D, "Plant Status," and conducted routine reviews using IP 71152, "Problem Identification and Resolution."  The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Exelon's performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Exelons performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.


==REACTOR SAFETY==
==REACTOR SAFETY==


==71111.04 - Equipment Alignment==
==71111.04 - Equipment Alignment     Partial Walkdown==
{{IP sample|IP=IP 71111.04|count=4}}


===Partial Walkdown (4 Samples)===
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
: (1) 'A' and 'B' emergency service water on July 9, 2018
: (1) A and B emergency service water on July 9, 2018
: (2) Reactor core isolation cooling (RCIC) system on July 12, 2018
: (2) Reactor core isolation cooling (RCIC) system on July 12, 2018
: (3) 'B' and 'D' emergency diesel generators (EDGs) on July 25, 2018
: (3) B and D emergency diesel generators (EDGs) on July 25, 2018
: (4) Decay heat removal system on September 27, 2018  
: (4) Decay heat removal system on September 27, 2018


===Complete Walkdown (1 Sample)===
===Complete Walkdown (1 Sample)===
The inspectors evaluated system configurations during a complete walkdown of the 'B' residual heat removal system on September 12, 2018.
The inspectors evaluated system configurations during a complete walkdown of the B     residual heat removal system on September 12, 2018.


==71111.05A/Q - Fire Protection Annual/Quarterly==
==71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection==
{{IP sample|IP=IP 71111.05A/Q|count=8}}


===Quarterly Inspection (8 Samples)===
The inspectors evaluated fire protection program implementation in the following selected areas:
The inspectors evaluated fire protection program implementation in the following selected areas:
: (1) Screenwell, fire area (FA) SH-1, on July 5, 2018
: (1) Screenwell, fire area (FA) SH-1, on July 5, 2018
: (2) Safety pump rooms, FA SP-1, FA SP-2, FA FP-1, and FA-FP-3, on July 5, 2018 4
: (2) Safety pump rooms, FA SP-1, FA SP-2, FA FP-1, and FA-FP-3, on July 5, 2018
: (3) Auxiliary boiler room, FA AS-1, on July 9, 2018
: (3) Auxiliary boiler room, FA AS-1, on July 9, 2018
: (4) Cable spreading room, FA CS-1, on July 9, 2018
: (4) Cable spreading room, FA CS-1, on July 9, 2018
Line 107: Line 83:
: (8) Drywell, FA PC-1, on September 25, 2018
: (8) Drywell, FA PC-1, on September 25, 2018


==71111.07 - Heat Sink Performance==
==71111.07 - Heat Sink Performance   Heat Sink==
 
{{IP sample|IP=IP 71111.07|count=1}}
===Heat Sink (1 Sample)===


The inspectors evaluated Exelon's monitoring and maintenance of the 'A' residual heat removal heat exchanger performance.
The inspectors evaluated Exelons monitoring and maintenance of the A residual heat removal heat exchanger performance.


==71111.08 - Inservice Inspection Activities==
==71111.08 - Inservice Inspection Activities==
{{IP sample|IP=IP 71111.08|count=1}}
{{IP sample|IP=IP 71111.08|count=1}}


The inspectors evaluated Exelon's non-destructive examination and welding activities at FitzPatrick by reviewing the volumetric examination by manual ultrasonic encoded examination of Reactor Nozzle N1 and Reactor Nozzle N2 during the period September 17- 20, 2018, for compliance to the requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.
The inspectors evaluated Exelons non-destructive examination and welding activities at FitzPatrick by reviewing the volumetric examination by manual ultrasonic encoded examination of Reactor Nozzle N1 and Reactor Nozzle N2 during the period September 17- 20, 2018, for compliance to the requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.
 
==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance==


===Operator Requalification (1 Sample)===
==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance    Operator Requalification==
{{IP sample|IP=IP 71111.11|count=1}}


The inspectors observed and evaluated a simulator scenario including a trip of the 'A' core spray loop holding pump, a trip of the 'A' condensate pump, a trip of the 'A' service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable high pressure coolant injection (HPCI) steam leak into the rector building requiring emergency depressurization on July 17, 2018.
The inspectors observed and evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable high pressure coolant injection (HPCI) steam leak into the rector building requiring emergency depressurization on July 17, 2018.


===Operator Performance (1 Sample)===
===Operator Performance (1 Sample)===
The inspectors observed operations personnel during downpower to 15 percent after end-of-cycle coastdown to open the unit output breakers for the start of RFO23 on September 9, 2018.
The inspectors observed operations personnel during downpower to 15 percent after end-of-cycle coastdown to open the unit output breakers for the start of RFO23 on September 9, 2018.


==71111.12 - Maintenance Effectiveness==
==71111.12 - Maintenance Effectiveness    Routine Maintenance Effectiveness==
{{IP sample|IP=IP 71111.12|count=1}}


Routine Maintenance Effectiveness (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
: (1) Flexible mitigating strategies equipment on August 6, 2018  
: (1) Flexible mitigating strategies equipment on August 6, 2018


==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
Line 137: Line 111:


The inspectors evaluated the risk assessments for the following planned and emergent work activities:
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
: (1) 'B' service air compressor out of service for maintenance on July 31, 2018
: (1) B service air compressor out of service for maintenance on July 31, 2018
: (2) 'B' core spray system out of service for maintenance on August 1, 2018
: (2) B core spray system out of service for maintenance on August 1, 2018
: (3) 'A' core spray system inoperable for hold pump planned maintenance on August 9, 2018
: (3) A core spray system inoperable for hold pump planned maintenance on August 9, 2018
: (4) Differential voltage relay testing on both offsite power lines on August 31, 2018
: (4) Differential voltage relay testing on both offsite power lines on August 31, 2018
: (5) Phase 1 outage risk management on September 12, 2018
: (5) Phase 1 outage risk management on September 12, 2018
: (6) Station battery 'A' out of service for maintenance on September 20, 2018
: (6) Station battery A out of service for maintenance on September 20, 2018


==71111.15 - Operability Determinations and Functionality Assessments==
==71111.15 - Operability Determinations and Functionality Assessments==
Line 150: Line 124:
: (1) RCIC operability with condensate storage tank (CST) low-level transmitter 13LS-76B inoperable on August 16, 2018
: (1) RCIC operability with condensate storage tank (CST) low-level transmitter 13LS-76B inoperable on August 16, 2018
: (2) Pitting identified on drywell liner on September 24, 2018
: (2) Pitting identified on drywell liner on September 24, 2018
: (3) 'A' and 'C' residual heat removal service water pump bolt material type on September 30, 2018
: (3) A and C residual heat removal service water pump bolt material type on September 30, 2018


==71111.18 - Plant Modifications==
==71111.18 - Plant Modifications==
Line 158: Line 132:
: (1) Engineering Change 620602 - Replace all 11 two-stage safety relief valves with three-stage valves, on September 30, 2018
: (1) Engineering Change 620602 - Replace all 11 two-stage safety relief valves with three-stage valves, on September 30, 2018


==71111.20 - Refueling and Other Outage Activities==
==71111.20 - Refueling and Other Outage Activities The inspectors evaluated RFO23 activities from September 10, 2018 through September 30, 2018.
 
The inspectors evaluated RFO23 activities from September 10, 2018 through September 30, 2018.


==71111.19 - Post Maintenance Testing==
==71111.19 - Post Maintenance Testing==
{{IP sample|IP=IP 71111.19|count=7}}
{{IP sample|IP=IP 71111.20|count=7}}
 
The inspectors evaluated post maintenance testing for the following maintenance/repair


activities:
==
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
: (1) Torus leak rate outboard isolation valve testing following unplanned maintenance on July 17, 2018
: (1) Torus leak rate outboard isolation valve testing following unplanned maintenance on July 17, 2018
: (2) Diesel fire pump 76-P1 relief valve replacement on July 19, 2018
: (2) Diesel fire pump 76-P1 relief valve replacement on July 19, 2018
Line 174: Line 145:
: (5) Low pressure coolant injection inverter replacement and testing on September 26, 2018
: (5) Low pressure coolant injection inverter replacement and testing on September 26, 2018
: (6) MSIV 85 percent open position switch replacement on September 28, 2018
: (6) MSIV 85 percent open position switch replacement on September 28, 2018
: (7) Residual heat removal 'A' containment spray outboard isolation valve 10MOV-26A following planned maintenance on September 30, 2018 6
: (7) Residual heat removal A containment spray outboard isolation valve 10MOV-26A following planned maintenance on September 30, 2018


==71111.22 - Surveillance Testing==
==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:   Routine==
 
{{IP sample|IP=IP 71111.22|count=3}}
The inspectors evaluated the following surveillance tests:  
: (1) ST-9BA, A and C EDG Full Load Test and Emergency Service Water Pump Operability Test, on July 9, 2018
 
===Routine (3 Samples)===
: (1) ST-9BA, 'A' and 'C' EDG Full Load Test and Emergency Service Water Pump Operability Test, on July 9, 2018
: (2) ST-1B, MSIV Fast Closure Test, on September 12, 2018
: (2) ST-1B, MSIV Fast Closure Test, on September 12, 2018
: (3) ST-9CA, 'A' Division Loss of Offsite Power/Loss of Cooling Accident Test, on September 29, 2018
: (3) ST-9CA, A Division Loss of Offsite Power/Loss of Cooling Accident Test, on


===Inservice (1 Sample)===
===September 29, 2018    Inservice (1 Sample)===
: (1) ST-6HB, 'B' Standby Liquid Control Quarterly Operability Test, on July 26, 2018  
: (1) ST-6HB, B Standby Liquid Control Quarterly Operability Test, on July 26, 2018


===Containment Isolation Valve (1 Sample)===
===Containment Isolation Valve (1 Sample)===
: (1) ST-39B-X7A, 'A' MSIV As-Found Local Leak Rate Test, on September 14, 2018
: (1) ST-39B-X7A, A MSIV As-Found Local Leak Rate Test, on September 14, 2018


==71114.02 - Alert and Notification System Testing==
==71114.02 - Alert and Notification System Testing==
Line 199: Line 167:
{{IP sample|IP=IP 71114.03|count=1}}
{{IP sample|IP=IP 71114.03|count=1}}


The inspectors conducted a review of Exelon's emergency response organization (ERO)augmentation staffing requirements and the process for notifying and augmenting the ERO.
The inspectors conducted a review of Exelons emergency response organization (ERO)augmentation staffing requirements and the process for notifying and augmenting the ERO.


==71114.05 - Maintenance of Emergency Preparedness==
==71114.05 - Maintenance of Emergency Preparedness==
{{IP sample|IP=IP 71114.05|count=1}}
{{IP sample|IP=IP 71114.05|count=1}}


The inspectors reviewed a number of activities to evaluate the efficacy of Exelon's efforts to maintain FitzPatrick's emergency preparedness programs.
The inspectors reviewed a number of activities to evaluate the efficacy of Exelons efforts to maintain FitzPatricks emergency preparedness programs.
 
==71114.06 - Drill Evaluation==
 
===Emergency Planning Drill (1 Sample)===


The inspectors evaluated the conduct of a routine emergency planning drill observation on August 1, 2018.
==71114.06 - Drill Evaluation    Emergency Planning Drill==
{{IP sample|IP=IP 71114.06|count=1}}


===Drill/Training Evolution (1 Sample)===
The inspectors evaluated the conduct of a routine emergency planning drill observation on


The inspectors evaluated a simulator scenario including a trip of the 'A' core spray loop holding pump, a trip of the 'A' condensate pump, a trip of the 'A' service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable HPCI steam leak into the reactor building which required a site area emergency declaration on July 17, 2018.
===August 1, 2018.
Drill/Training Evolution (1 Sample)===
The inspectors evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable HPCI steam leak into the reactor building which required a site area emergency declaration on July 17,


==RADIATION SAFETY==
==RADIATION SAFETY==


==71124.01 - Radiological Hazard Assessment and Exposure Controls==
==71124.01 - Radiological Hazard Assessment and Exposure Controls   Radiological Hazard Assessment==
 
{{IP sample|IP=IP 71124.01|count=1}}
===Radiological Hazard Assessment (1 Sample)===


The inspectors reviewed recent plant radiation surveys to ensure radiological hazards to onsite workers and to members of the public were identified. The inspectors evaluated assessments and controls for new radiological hazards.
The inspectors reviewed recent plant radiation surveys to ensure radiological hazards to onsite workers and to members of the public were identified. The inspectors evaluated assessments and controls for new radiological hazards.


===Instructions to Workers (1 Sample)===
===Instructions to Workers (1 Sample)===
The inspectors evaluated instructions provided to workers.
The inspectors evaluated instructions provided to workers.


Line 234: Line 199:


===Radiological Hazards Control and Work Coverage (1 Sample)===
===Radiological Hazards Control and Work Coverage (1 Sample)===
The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walk-downs and observation of radiological work activities. The inspectors assessed posted surveys, radiation work permits, worker radiological briefings, the use of continuous air monitoring, and dosimetry monitoring to determine if they were consistent with the present conditions.
The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walk-downs and observation of radiological work activities. The inspectors assessed posted surveys, radiation work permits, worker radiological briefings, the use of continuous air monitoring, and dosimetry monitoring to determine if they were consistent with the present conditions.


===High Radiation Area and Very High Radiation Area Controls (1 Sample)===
High Radiation Area and Very High Radiation Area Controls (1 Sample)
 
The inspectors evaluated risk-significant high radiation area and very high radiation area controls including postings and physical barriers.
The inspectors evaluated risk-significant high radiation area and very high radiation area controls including postings and physical barriers.


===Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)===
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician radiological performance.
The inspectors evaluated radiation worker and radiation protection technician radiological performance.
==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls    Verification of Dose Estimates and Exposure Tracking Systems==
{{IP sample|IP=IP 71124.02|count=1}}


==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls==
===The inspectors evaluated dose estimates and exposure tracking.
Radiation Worker Performance===
{{IP sample|IP=IP 71124.02|count=1}}


===Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
The inspectors evaluated dose estimates and exposure tracking.
===Radiation Worker Performance (1 Sample)===
The inspectors evaluated radiation worker and radiation protection technician performance.
The inspectors evaluated radiation worker and radiation protection technician performance.


==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation==
==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation   Engineering Controls==
 
{{IP sample|IP=IP 71124.03|count=1}}
===Engineering Controls (1 Sample)===


The inspectors observed the setup and use of ventilation systems and the use of monitoring instrumentation.
The inspectors observed the setup and use of ventilation systems and the use of monitoring instrumentation.


==71124.04 - Occupational Dose Assessment==
==71124.04 - Occupational Dose Assessment   Source Term Characterization==
{{IP sample|IP=IP 71124.04|count=1}}


===Source Term Characterization (1 Sample)===
The inspectors evaluated Exelons source term characterization at FitzPatrick.
The inspectors evaluated Exelon's source term characterization at FitzPatrick.


===Special Dosimetric Situations (1 Sample)===
===Special Dosimetric Situations (1 Sample)===
The inspectors evaluated Exelons performance for special dosimetric situations.


The inspectors evaluated Exelon's performance for special dosimetric situations.
==71124.05 - Radiation Monitoring Instrumentation   Walkdowns and Observations==
 
{{IP sample|IP=IP 71124.05|count=1}}
==71124.05 - Radiation Monitoring Instrumentation==


===Walkdowns and Observations (1 Sample)===
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
The inspectors evaluated radiation monitori ng instrumentation during plant walkdowns.


===Calibration and Testing Program (1 Sample)===
===Calibration and Testing Program (1 Sample)===
The inspectors evaluated Exelon's calibration and testing program.
The inspectors evaluated Exelons calibration and testing program.
 
==71124.06 - Radioactive Gaseous and Liquid Effluent Treatment==


===Walkdowns and Observations (1 Sample)===
==71124.06 - Radioactive Gaseous and Liquid Effluent Treatment    Walkdowns and Observations==
{{IP sample|IP=IP 71124.06|count=1}}


The inspectors walked down the gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.
The inspectors walked down the gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.


===Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)===
Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)
 
The inspectors evaluated Exelons gaseous and liquid effluent monitor instrument calibration and testing.
The inspectors evaluated Exelon's gaseous and liquid effluent monitor instrument calibration and testing.


===Sampling and Analyses (1 Sample)===
===Sampling and Analyses (1 Sample)===
The inspectors evaluated radioactive effluent sampling and analysis activities.
The inspectors evaluated radioactive effluent sampling and analysis activities.


===Instrumentation and Equipment (1 Sample)===
===Instrumentation and Equipment (1 Sample)===
The inspectors reviewed radioactive effluent discharge system surveillance test results and reviewed the methodology used to determine the radioactive effluent stack and vent flow rates based on technical specifications/off site dose calculation manual (TS/ODCM)acceptance criteria.
The inspectors reviewed radioactive effluent discharge system surveillance test results and reviewed the methodology used to determine the radioactive effluent stack and vent flow rates based on technical specifications/off site dose calculation manual (TS/ODCM)acceptance criteria.


===9 Dose Calculations (1 Sample)===
===Dose Calculations (1 Sample)===
The inspectors reviewed several liquid and gaseous discharges to evaluate public dose calculations (monthly, quarterly, and annual) and the annual radiological effluent release reports for 2017 and 2018.
The inspectors reviewed several liquid and gaseous discharges to evaluate public dose calculations (monthly, quarterly, and annual) and the annual radiological effluent release reports for 2017 and


==OTHER ACTIVITIES - BASELINE==
==OTHER ACTIVITIES - BASELINE==


===71151 - Performance Indicator Verification===
===71151 - Performance Indicator Verification ===
{{IP sample|IP=IP 71151|count=12}}
{{IP sample|IP=IP 71151|count=12}}
The inspectors verified Exelon performance indicators submittals listed below for the period from December 2017 through June 2018:
The inspectors verified Exelon performance indicators submittals listed below for the period from December 2017 through June 2018:
Line 312: Line 269:
: (10) MS10, MSPI Cooling Water Systems The inspectors verified Exelon performance indicator submittals listed below for the period from January 2017 through June 2018:
: (10) MS10, MSPI Cooling Water Systems The inspectors verified Exelon performance indicator submittals listed below for the period from January 2017 through June 2018:
: (11) PR01, RETS/ODCM Radiological Effluent Occurrence The inspectors verified Exelon performance indicator submittals listed below for the period from August 2017 through August 2018:
: (11) PR01, RETS/ODCM Radiological Effluent Occurrence The inspectors verified Exelon performance indicator submittals listed below for the period from August 2017 through August 2018:
: (12) OR01, Occupational Exposure Control  
: (12) OR01, Occupational Exposure Control


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
Line 326: Line 283:


On October 22, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
On October 22, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
11


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


71111.04 Procedures AOP-68A, Loss of Decay Heat Removal, Revision 7
71111.04
Procedures
AOP-68A, Loss of Decay Heat Removal, Revision 7
FM-133A, Decay Heat Removal Flow Diagram, Revision 9
FM-133A, Decay Heat Removal Flow Diagram, Revision 9
FM-133B, Decay Heat Removal Flow Diagram, Revision 8
FM-133B, Decay Heat Removal Flow Diagram, Revision 8
OP-13D, Residual Heat Removal Shutdown Cooling, Revision 31 OP-21, Emergency Service Water, Revision 38 OP-22, Diesel Generator Emergency Power, Revision 62
OP-13D, Residual Heat Removal Shutdown Cooling, Revision 31
OP-21, Emergency Service Water, Revision 38
OP-22, Diesel Generator Emergency Power, Revision 62
OP-30B, Decay Heat Removal System, Revision 19
OP-30B, Decay Heat Removal System, Revision 19
OP-60, Diesel Generator Room Ventilation, Revision 9
OP-60, Diesel Generator Room Ventilation, Revision 9
Issue Reports 04092020 04099657 04117175 04117285
Issue Reports
04092020           04099657             04117175             04117285
04117659
04117659
Drawings FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 072
Drawings
FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 072
FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 073
FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 073
FM-22A, Flow Diagram Reactor Core Isolation Cooling System 13, Revision 57
FM-22A, Flow Diagram Reactor Core Isolation Cooling System 13, Revision 57
FM-46B, Flow Diagram Emergency Service Water System 46 and 15, Revision 57 ISI-FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 18
FM-46B, Flow Diagram Emergency Service Water System 46 and 15, Revision 57
ISI-FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 18
ISI-FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 16
ISI-FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 16
Miscellaneous Engineering Report No. JAF-RPT-05-AMM02, Aging Management Review of Residual Heat Removal System, Revision 3 FPSSK-100, Fire Barrier Penetrations Arrangement Plan Below Elevation 272' 0", Revision 5 FPSSK-206, Fire Barrier Penetrations Arrangement Fire Area Zone XII/SP-1 Elevation 255' 0", Revision 2
Miscellaneous
71111.05 Procedures PFP-PWR09, Auxiliary Boiler Room, Elevation 272' and 285', Revision 4
Engineering Report No. JAF-RPT-05-AMM02, Aging Management Review of Residual Heat
PFP-PWR11, Cable Spreading Room, Elevation 272', Revision 3
Removal System, Revision 3
PFP-PWR18, Drywell Area Elevation 268', Fire Area Zone XIV/PC-1, Revision 0
FPSSK-100, Fire Barrier Penetrations Arrangement Plan Below Elevation 272 0, Revision 5
PFP-PWR19, Drywell Area Elevation 292', Fire Area Zone XIV/PC-1, Revision 0
FPSSK-206, Fire Barrier Penetrations Arrangement Fire Area Zone XII/SP-1 Elevation 255 0,
PFP-PWR22, Standby Gas Filter Room. Elevation 272', Revision 6 PFP-PWR34, Screenwell House and Water Treatment Area, Elevation 235', 255', and 260', Revision 05 PFP-PWR33, Pump Rooms (Screenwell), Elevation 255', Revision 02
Revision 2
PFP-PWR42, Turbine Building - North / Elev. 252', Revision 03
71111.05
PFP-PWR43, Turbine Building - South / Elev. 252', Revision 05
Procedures
PFP-PWR45, Turbine Building - North / Elev. 272', Revision 06 PFP-PWR46, Turbine Building - South / Elev. 272', Revision 04 PFP-PWR48, Turbine Building Elev. 300', Revision 04  
PFP-PWR09, Auxiliary Boiler Room, Elevation 272 and 285, Revision 4
 
PFP-PWR11, Cable Spreading Room, Elevation 272, Revision 3
71111.07 Procedures ST-2YA, Residual Heat Removal Heat Exchanger 'A' Performance Test, Revision 5  
PFP-PWR18, Drywell Area Elevation 268, Fire Area Zone XIV/PC-1, Revision 0
 
PFP-PWR19, Drywell Area Elevation 292, Fire Area Zone XIV/PC-1, Revision 0
Drawings 4.95-5, RHR Heat Exchanger 'A" Tube Plugging Map 10E-2A, Revision 2  
PFP-PWR22, Standby Gas Filter Room. Elevation 272, Revision 6
 
PFP-PWR34, Screenwell House and Water Treatment Area, Elevation 235, 255, and 260,
Miscellaneous 14620.9033, Total Available Tube Plugging Margin in the RHR Heat Exchanger at Related Conditions, Revision 0
Revision 05
71111.11 Procedures OP-65, Startup and Shutdown Procedures, Revision 123 OP-65B, Shutdown Operations, Revision 7
PFP-PWR33, Pump Rooms (Screenwell), Elevation 255, Revision 02
71111.12 Issue Reports 04045089 04086665 04087668 04098168
PFP-PWR42, Turbine Building - North / Elev. 252, Revision 03
04126033 04149166
PFP-PWR43, Turbine Building - South / Elev. 252, Revision 05
71111.13 Procedures AP-10.09, Outage Risk Assessment, Revision 37
PFP-PWR45, Turbine Building - North / Elev. 272, Revision 06
71111.15 Procedures ISP 75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
PFP-PWR46, Turbine Building - South / Elev. 272, Revision 04
ER-AA-335-018, Visual Examination of ASME IWE Class MC and Metallic Liners of IWL Class CC Components, Revision 13
PFP-PWR48, Turbine Building Elev. 300, Revision 04
71111.07
Procedures
ST-2YA, Residual Heat Removal Heat Exchanger A Performance Test, Revision 5
Drawings
4.95-5, RHR Heat Exchanger A Tube Plugging Map 10E-2A, Revision 2
Miscellaneous
14620.9033, Total Available Tube Plugging Margin in the RHR Heat Exchanger at Related
Conditions, Revision 0
71111.11
Procedures
OP-65, Startup and Shutdown Procedures, Revision 123
OP-65B, Shutdown Operations, Revision 7
71111.12
Issue Reports
04045089             04086665           04087668             04098168
04126033             04149166
71111.13
Procedures
AP-10.09, Outage Risk Assessment, Revision 37
71111.15
Procedures
ISP 75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
ER-AA-335-018, Visual Examination of ASME IWE Class MC and Metallic Liners of IWL Class
CC Components, Revision 13
Issue Reports
Issue Reports
04164618 04164660
04164618
04164660
04174135
04174135
04178640 Work Orders
04178640
Work Orders
C04799709
C04799709
C04832920  
C04832920
 
Miscellaneous
Miscellaneous Design Equivalent Change Package 625754
Design Equivalent Change Package 625754
DWG 2.28-5, Sectional Allis Chalmers H16 x 12VTMC-3, Revision 003
DWG 2.28-5, Sectional Allis Chalmers H16 x 12VTMC-3, Revision 003
Engineering Change (EC) 625691  
Engineering Change (EC) 625691
 
71111.18
71111.18 Drawings DWG 6.32-80, Model 7567F 6 x 10 Relief Valve Alternate Configuration, Revision 4
Drawings
Miscellaneous EC 620602, UFSAR Change Request Form per LA-AA-107-1001, Revision 7
DWG 6.32-80, Model 7567F 6 x 10 Relief Valve Alternate Configuration, Revision 4
EC 620602, Engineering Calculation, Evaluation of SRV QBUBS Load Changes on Torus Shell, Torus Attached Piping and Internal Structures, Revision 0 EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for ADS Line B, Revision 0 EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for Non-ADS Line L, Revision 0 ECN 624214, Target Rock ASME Design Report 8692, Revision D
Miscellaneous
EC 620602, UFSAR Change Request Form per LA-AA-107-1001, Revision 7
EC 620602, Engineering Calculation, Evaluation of SRV QBUBS Load Changes on Torus Shell,
Torus Attached Piping and Internal Structures, Revision 0
EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for ADS Line B, Revision 0
EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for Non-ADS Line L,
Revision 0
ECN 624214, Target Rock ASME Design Report 8692, Revision D
JAF-RPT-11-00003, Operational Leakage Action Levels for Target Rock Three Stages Safety
JAF-RPT-11-00003, Operational Leakage Action Levels for Target Rock Three Stages Safety
Relief Valves, Revision 1 JAF-SCN-18-056, 50.59 Screening Form for EC 620602, Revision 0
Relief Valves, Revision 1
JAF-SCN-18-056, 50.59 Screening Form for EC 620602, Revision 0
James  
James  
: [[contact::A. FitzPatrick Nuclear Power Plant]], Technical Proposal for 3-Stage Main Steam Safety
: [[contact::A. FitzPatrick Nuclear Power Plant]], Technical Proposal for 3-Stage Main Steam Safety
Relief Valves
Relief Valves
Report No. 8696, Temperature/Seat Leakage Correlation Report for Three Stage Pilot Operated 6x10 Safety Relief Valve SRV, Target Rock Model: 0867F-001, Revision D Report TERI 081, Technical Evaluation of 3-Stage 6x10 MS-SRV Upgrade to Address Limited Flow Test Induced Defect (Model 0867F) Ref: Problem Report 080 and CAR 15-045,
Report No. 8696, Temperature/Seat Leakage Correlation Report for Three Stage Pilot Operated
6x10 Safety Relief Valve SRV, Target Rock Model: 0867F-001, Revision D
Report TERI 081, Technical Evaluation of 3-Stage 6x10 MS-SRV Upgrade to Address Limited
Flow Test Induced Defect (Model 0867F) Ref: Problem Report 080 and CAR 15-045,
Revision A
Revision A
71111.19 Procedures ISP-75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
71111.19
Procedures
ISP-75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
MP-200.03, Replacement of NAMCO EA-180 and EA-740 Position Switches, Revision 11
MP-200.03, Replacement of NAMCO EA-180 and EA-740 Position Switches, Revision 11
MST-029.02, Main Steam Line Isolation Valve 85 Percent Open (RPS) Position Switch Calibration Surveillance, Revision 19 ST-1CA, Outside Primary Containment Isolation Valve Exercise Test, Revision 1
MST-029.02, Main Steam Line Isolation Valve 85 Percent Open (RPS) Position Switch
ST-2AL, RHR Loop 'A' Quarterly Operability Test (IST), Revision 038
Calibration Surveillance, Revision 19
ST-76J23, West Diesel Fire Pump 76P-1 Performance Test, Revision 22  
ST-1CA, Outside Primary Containment Isolation Valve Exercise Test, Revision 1
 
ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 038
Issue Reports 04109193 04156252 04164618 04164660
ST-76J23, West Diesel Fire Pump 76P-1 Performance Test, Revision 22
04167340 04176976  
Issue Reports
 
04109193             04156252               04164618             04164660
Work Orders C04644984 C04732717 C80161193 C80403118 C82503567
04167340             04176976
71111.22 Procedures IMP-71.25, Test Equipment Set Up for 10500 and 10600 Emergency Bus Sequencing Test ST- C, Revision 10 ST-1B, MSIV Fast Closure Test, Revision 26
Work Orders
ST-6HB, Standby Liquid Control Quarterly Operability Test (IST), Revision 9 ST-9BA, EDG 'A' and 'C' Full Load Test and ESW Pump Operability Test, Revision 16
C04644984             C04732717             C80161193           C80403118
ST-9CA, EDG 'A' and 'C' Load Sequencing Test and 4kV Emergency Power System Voltage Relays Instrument Functional Test, Revision 4 ST-39B-X7A, Type 'C' Leak Test Main Steam Line 'A' MSIVs, Revision 16
C82503567
71111.22
Procedures
IMP-71.25, Test Equipment Set Up for 10500 and 10600 Emergency Bus Sequencing Test
ST- C, Revision 10
ST-1B, MSIV Fast Closure Test, Revision 26
ST-6HB, Standby Liquid Control Quarterly Operability Test (IST), Revision 9
ST-9BA, EDG A and C Full Load Test and ESW Pump Operability Test, Revision 16
ST-9CA, EDG A and C Load Sequencing Test and 4kV Emergency Power System Voltage
Relays Instrument Functional Test, Revision 4
ST-39B-X7A, Type C Leak Test Main Steam Line A MSIVs, Revision 16
Issue Reports
Issue Reports
04178600
04178600
Work Orders
Work Orders
C82606584
C82606584
71124.01 Procedures NISP-RP-004, Radiological Posting and Labeling, Revision 00 NISP-RP-005, Access Controls for High Radiation Areas, Revision 0 RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1
71124.01
Procedures
NISP-RP-004, Radiological Posting and Labeling, Revision 00
NISP-RP-005, Access Controls for High Radiation Areas, Revision 0
RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1
RP-AA-300, Radiological Survey Program, Revision 15
RP-AA-300, Radiological Survey Program, Revision 15
RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 34
RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 34
RP-AA-503, Unconditional Release Survey Method, Revision 14
RP-AA-503, Unconditional Release Survey Method, Revision 14
Issue Reports 04171228 04174941 04175570 04175765
Issue Reports
04176037 04176242  
04171228             04174941             04175570             04175765
 
04176037             04176242
RWPs/ALARA Plans
RWPs/ALARA Plans
RWP   Description   ALARA Plan JF-1-18-00506 DW Scaffold   AP-18-0506
RWP                 Description                       ALARA Plan
JF-1-18-00510 DW SRV Activities   AP-18-0510
JF-1-18-00506       DW Scaffold                       AP-18-0506
JF-1-18-00513 DW CRD Drive Exchange AP-18-0513 JF-1-18-00516 DW RW Recirc Pump and Motor AP-18-0516 JF-1-18-00541 DW 12RWC-46 and 12MOV-15 AP-18-0541  
JF-1-18-00510       DW SRV Activities                 AP-18-0510
 
JF-1-18-00513       DW CRD Drive Exchange             AP-18-0513
JF-1-18-00516       DW RW Recirc Pump and Motor       AP-18-0516
JF-1-18-00541       DW 12RWC-46 and 12MOV-15           AP-18-0541
Surveys
Surveys
Survey   Description   Date/Time 2018-021841 DW 268'    September 10, 2018/2100
Survey               Description                       Date/Time
2018-021911 DW 292' SRV   September 11, 2018/1254
2018-021841         DW 268                           September 10, 2018/2100
2018-022001 Under Reactor Head   September 12, 2018/0052
2018-021911         DW 292 SRV                       September 11, 2018/1254
2018-022623 12RWC-46   September 16, 2018/1058
2018-022001         Under Reactor Head                 September 12, 2018/0052
2018-022711 12RWC-46   September 17, 2018/0837 2018-022565 SRV 71F   September 18, 2018/0116 2018-023578 DW 256'    September 25, 2018/0447  
2018-022623         12RWC-46                           September 16, 2018/1058
 
2018-022711         12RWC-46                           September 17, 2018/0837
2018-022565         SRV 71F                           September 18, 2018/0116
2018-023578         DW 256                           September 25, 2018/0447
Air Sample Results
Air Sample Results
Air Sample Description   Date/Time 18306   DW 12RWC46   September 18, 2018/1220 18320   DW 'B' Recirc Pump Seal September 22, 2018/2300
Air Sample           Description                       Date/Time
18329   DW MSIV 'B' Breach   September 23, 2018/0250
18306               DW 12RWC46                         September 18, 2018/1220
18311   DW 12MOV15 Breach September 23, 2018/1220
18320               DW B Recirc Pump Seal           September 22, 2018/2300
18342   DW 268' General Area September 24, 2018/0640 18343   DW 292' General Area September 24, 2018/0720
18329               DW MSIV B Breach                 September 23, 2018/0250
18345   DW 12MOV15   September 25, 2018/0230
18311               DW 12MOV15 Breach                 September 23, 2018/1220
71124.02 Procedures RP-AA-400, ALARA Program, Revision 15
18342                   DW 268 General Area             September 24, 2018/0640
18343                   DW 292 General Area             September 24, 2018/0720
18345                   DW 12MOV15                       September 25, 2018/0230
71124.02
Procedures
RP-AA-400, ALARA Program, Revision 15
Issue Reports (*initiated in response to inspection)
Issue Reports (*initiated in response to inspection)
04175408 04177200*
04175408
71124.03 Procedures RP-AA-301, Radiological Air Sampling Program, Revision 11 RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 10
04177200*
71124.03
Procedures
RP-AA-301, Radiological Air Sampling Program, Revision 11
RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 10
Issue Reports
Issue Reports
04133415
04133415
Miscellaneous Breathing Air Samples, Report 294228-0 on January 18, 2017; and Report 341956-1 on August 31, 2018
Miscellaneous
71124.04 Procedures RP-AA-12, Internal Dose Control Program Description, Revision 2
Breathing Air Samples, Report 294228-0 on January 18, 2017; and Report 341956-1 on
RP-AA-203-1001, Personnel Exposure Investigations, Revision 10 RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 29
August 31, 2018
71124.04
Procedures
RP-AA-12, Internal Dose Control Program Description, Revision 2
RP-AA-203-1001, Personnel Exposure Investigations, Revision 10
RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 29
RP-AA-220, Bioassay Program, Revision 13
RP-AA-220, Bioassay Program, Revision 13
RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5
RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5
RP-AA-290, Prenatal Radiation Exposure, Revision 8
RP-AA-290, Prenatal Radiation Exposure, Revision 8
Issue Reports
Issue Reports
04102403 04174125
04102403
04174125
04175886
04175886
Miscellaneous Generic Radiation Worker Training Lesson Plan, Revision 11, December 2017 NVLAP Certification for Lab Code 100518-0
Miscellaneous
71124.05 Procedures ISP-95A, Post Accident Containment High Range Radiation Monitor A Functional Test/Calibration, Revision 4  
Generic Radiation Worker Training Lesson Plan, Revision 11, December 2017
 
NVLAP Certification for Lab Code 100518-0
ISP-95B, Post Accident Containment High Range Radiation Monitor B Functional Test/Calibration, Revision 4 RP-AA-700-1101, Calibration of the RO-2, RO-2A, RO-20 and RSO-50E Ion Chambers, Revision 1 RP-AA-700-1203, Calibration of the MGP Instruments Telepole, Revision 1
71124.05
Procedures
ISP-95A, Post Accident Containment High Range Radiation Monitor A Functional
Test/Calibration, Revision 4
ISP-95B, Post Accident Containment High Range Radiation Monitor B Functional
Test/Calibration, Revision 4
RP-AA-700-1101, Calibration of the RO-2, RO-2A, RO-20 and RSO-50E Ion Chambers,
Revision 1
RP-AA-700-1203, Calibration of the MGP Instruments Telepole, Revision 1
RP-AA-700-1215, Calibration of Low-Vol Air Samplers, Revision 2
RP-AA-700-1215, Calibration of Low-Vol Air Samplers, Revision 2
RP-AA-700-1216, Calibration of Hi-Vol Air Samplers, Revision 4
RP-AA-700-1216, Calibration of Hi-Vol Air Samplers, Revision 4
RP-AA-700-1235, Operation and Calibration of the PM-12 Gamma Portal Monitor, Revision 5
RP-AA-700-1235, Operation and Calibration of the PM-12 Gamma Portal Monitor, Revision 5
RP-AA-700-1239, Operation and Calibration of the Model SAM-12 Small Articles Monitor, Revision 4 RP-AA-700-1240, Operation and Calibration of the Canberra ARGOS-5 Personnel Contamination Monitor, Revision 6 RP-AA-700-1242, Calibration of Eberline Model 6112B Teletector, Revision 0
RP-AA-700-1239, Operation and Calibration of the Model SAM-12 Small Articles Monitor,
RP-AA-700-1301, Calibration, Source Check, Operation and Set-Up of the Eberline Beta Air Monitor, Model AMS-4, Revision 4 RP-AA-700-1305, Operation and Calibration of the AMP-100/200, Revision 2
Revision 4
RP-AA-700-1240, Operation and Calibration of the Canberra ARGOS-5 Personnel
Contamination Monitor, Revision 6
RP-AA-700-1242, Calibration of Eberline Model 6112B Teletector, Revision 0
RP-AA-700-1301, Calibration, Source Check, Operation and Set-Up of the Eberline Beta Air
Monitor, Model AMS-4, Revision 4
RP-AA-700-1305, Operation and Calibration of the AMP-100/200, Revision 2
RP-AA-700-1312, Calibration of Bicron Micro REM Survey Meter, Revision 1
RP-AA-700-1312, Calibration of Bicron Micro REM Survey Meter, Revision 1
RP-AA-700-1401, Operation and Calibration of Eberline Model PM-7 Personnel Contamination Monitor, Revision 6 RP-INST-02.09, Calibration of Mini-Scaler MS-2 and MS-3, Revision 5 RP-INST-02.15, Calibration of Ludlum L-2000 Scaler, Revision 0
RP-AA-700-1401, Operation and Calibration of Eberline Model PM-7 Personnel Contamination
SP-03.14, Post Accident Sampling, Revision 0  
Monitor, Revision 6
 
RP-INST-02.09, Calibration of Mini-Scaler MS-2 and MS-3, Revision 5
Issue Reports 04095004 04096020 04156340 04162340
RP-INST-02.15, Calibration of Ludlum L-2000 Scaler, Revision 0
Calibration Records 17RM-351, Normal Service Water Monitor, February 16, 2018
SP-03.14, Post Accident Sampling, Revision 0
Issue Reports
04095004               04096020             04156340           04162340
Calibration Records
17RM-351, Normal Service Water Monitor, February 16, 2018
04752950-01, Reactor Building Vent Monitor, June 15, 2018
04752950-01, Reactor Building Vent Monitor, June 15, 2018
04752006-01, Stack Vent Monitor, June 8, 2018 04771225-01, Radwaste Building Vent, July 10, 2018 52606748-01, 27RM-104A Containment High Range Monitor (Source), February 5, 2017
04752006-01, Stack Vent Monitor, June 8, 2018
04771225-01, Radwaste Building Vent, July 10, 2018
2606748-01, 27RM-104A Containment High Range Monitor (Source), February 5, 2017
2606749-01, 27RM-104B Containment High Range Monitor (Source), February 7, 2017
2606749-01, 27RM-104B Containment High Range Monitor (Source), February 7, 2017
2720565-01, 27RM-104A Containment High Range Monitor (Electronics), December 27, 2016
2720565-01, 27RM-104A Containment High Range Monitor (Electronics), December 27, 2016
2714885-01, 27RM-104B Containment High Range Monitor (Electronics), December 27, 2016
2714885-01, 27RM-104B Containment High Range Monitor (Electronics), December 27, 2016
Miscellaneous Mirion Technologies Calibration of the Canberra Fastscan WBC System at the Exelon James  
Miscellaneous
: [[contact::A. FitzPatrick Nuclear Power Plant]], March 28, 2018
Mirion Technologies Calibration of the Canberra Fastscan WBC System at the Exelon James  
71124.06 Procedures CY-AA-130-200, Quality Control, Revision 13
: [[contact::A.
FitzPatrick Nuclear Power Plant]], March 28, 2018
71124.06
Procedures
CY-AA-130-200, Quality Control, Revision 13
CY-AA-130-201, Radiochemistry Quality Control, Revision 5
CY-AA-130-201, Radiochemistry Quality Control, Revision 5
CY-AA-170-2200, RETDAS, Revision 1 EN-AA-408, Radiological Groundwater Protection Program, Revision 0 EN-CY-102, Laboratory Analytical Quality Control, Revision 9
CY-AA-170-2200, RETDAS, Revision 1
EN-AA-408, Radiological Groundwater Protection Program, Revision 0
EN-CY-102, Laboratory Analytical Quality Control, Revision 9
SP-01.06, Gaseous Effluent Sampling and Analysis, Revision 20
SP-01.06, Gaseous Effluent Sampling and Analysis, Revision 20
SP-03.05, Steam Jet Air Ejector and Recombiner Effluent Sampling and Analysis, Revision 13
SP-03.05, Steam Jet Air Ejector and Recombiner Effluent Sampling and Analysis, Revision 13
SP-03.07, Liquid Process Radiation Monitors, Revision 10
SP-03.07, Liquid Process Radiation Monitors, Revision 10
SP-03.08RF, Refuel Floor Gaseous Effluent Monitors, Revision 2a SP-03.08RW, Radwaste Building Gaseous Effluent Monitors, Revision 4a
SP-03.08RF, Refuel Floor Gaseous Effluent Monitors, Revision 2a
SP-03.08RX, Reactor Building Gaseous Effluent Monitors, Revision 1a SP-03.08STK, Stack Effluent Monitors, Revision 6a SP-03.08TB, Turbine Building Gaseous Effluent Monitors, Revision 3  
SP-03.08RW, Radwaste Building Gaseous Effluent Monitors, Revision 4a
 
SP-03.08RX, Reactor Building Gaseous Effluent Monitors, Revision 1a
Issue Reports 03037511 03847968 03992568 03996675
SP-03.08STK, Stack Effluent Monitors, Revision 6a
04001340 04010103
SP-03.08TB, Turbine Building Gaseous Effluent Monitors, Revision 3
Miscellaneous Radioiodine Penetration/Efficiency Test Report, March 23, 2018
Issue Reports
71151 Procedures EN-LI-114, Performance Indicator Process, Revision 7
03037511             03847968             03992568             03996675
04001340             04010103
Miscellaneous
Radioiodine Penetration/Efficiency Test Report, March 23, 2018
71151
Procedures
EN-LI-114, Performance Indicator Process, Revision 7
NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7
NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7
Miscellaneous JAF-RPT-05-0047, Mitigating Systems Performance Index Basis Document, Revision 5
Miscellaneous
JAF-RPT-05-0047, Mitigating Systems Performance Index Basis Document, Revision 5
}}
}}

Latest revision as of 17:02, 18 December 2019

Integrated Inspection Report 05000333/2018003
ML18313A068
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 11/08/2018
From: Anthony Dimitriadis
NRC/RGN-I/DRP/PB5
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Dimitriadis A
References
IR 2018003
Download: ML18313A068 (19)
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(Addressee)

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 November 8, 2018 Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018003

Dear Mr. Hanson:

On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant. On October 22, 2018, the NRC inspectors discussed the results of this inspection with Mr. Joseph Pacher, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any findings or violations of more than minor significance.

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 Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59

Enclosure:

Inspection Report 05000333/2018003

Inspection Report

Docket Number: 50-333 License Number: DPR-59 Report Number: 05000333/2018003 Enterprise Identifier: I-2018-003-0065 Licensee: Exelon Generation Company, LLC (Exelon)

Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba, NY Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: J. Schussler, Acting Senior Resident Inspector G. Stock, Acting Senior Resident Inspector J. Bream, Physical Security Inspector P. Boguszewski, Project Engineer T. Daun, Resident Inspector, Susquehanna Nuclear Power Plant J. DeBoer, Emergency Preparedness Inspector S. Ghrayeb, Acting Resident Inspector E. Miller, Senior Resident Inspector, Nine Mile Point Nuclear Station M. Modes, Senior Reactor Inspector R. Rolph, Health Physicist B. Sienel, Resident Inspector, Nine Mile Point Nuclear Station Approved By: Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at

FitzPatrick by conducting the baseline inspections described in this report 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.

No findings or more-than-minor violations were identified.

PLANT STATUS

FitzPatrick began the inspection period at approximately 98 percent and gradually lowered power as it entered end-of-cycle coastdown operations. On September 10, 2018, operators commenced a shutdown from approximately 80 percent for a planned refueling and maintenance outage (RFO23). The unit remained shutdown 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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Exelons performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.04 - Equipment Alignment Partial Walkdown

Main article: IP 71111.04

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

(1) A and B emergency service water on July 9, 2018
(2) Reactor core isolation cooling (RCIC) system on July 12, 2018
(3) B and D emergency diesel generators (EDGs) on July 25, 2018
(4) Decay heat removal system on September 27, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the B residual heat removal system on September 12, 2018.

71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection

Main article: IP 71111.05A/Q

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Screenwell, fire area (FA) SH-1, on July 5, 2018
(2) Safety pump rooms, FA SP-1, FA SP-2, FA FP-1, and FA-FP-3, on July 5, 2018
(3) Auxiliary boiler room, FA AS-1, on July 9, 2018
(4) Cable spreading room, FA CS-1, on July 9, 2018
(5) Standby gas treatment room, FA CS-1, on July 9, 2018
(6) Turbine deck, condenser bay, and feedwater heater bays, FA TB-1, on September 13, 2018
(7) Outboard main steam isolation valve (MSIV) room and steam tunnel, FA TB-1, on September 20, 2018
(8) Drywell, FA PC-1, on September 25, 2018

71111.07 - Heat Sink Performance Heat Sink

Main article: IP 71111.07

The inspectors evaluated Exelons monitoring and maintenance of the A residual heat removal heat exchanger performance.

71111.08 - Inservice Inspection Activities

Main article: IP 71111.08

The inspectors evaluated Exelons non-destructive examination and welding activities at FitzPatrick by reviewing the volumetric examination by manual ultrasonic encoded examination of Reactor Nozzle N1 and Reactor Nozzle N2 during the period September 17- 20, 2018, for compliance to the requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

Main article: IP 71111.11

The inspectors observed and evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable high pressure coolant injection (HPCI) steam leak into the rector building requiring emergency depressurization on July 17, 2018.

Operator Performance (1 Sample)

The inspectors observed operations personnel during downpower to 15 percent after end-of-cycle coastdown to open the unit output breakers for the start of RFO23 on September 9, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

Main article: IP 71111.12

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Flexible mitigating strategies equipment on August 6, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) B service air compressor out of service for maintenance on July 31, 2018
(2) B core spray system out of service for maintenance on August 1, 2018
(3) A core spray system inoperable for hold pump planned maintenance on August 9, 2018
(4) Differential voltage relay testing on both offsite power lines on August 31, 2018
(5) Phase 1 outage risk management on September 12, 2018
(6) Station battery A out of service for maintenance on September 20, 2018

71111.15 - Operability Determinations and Functionality Assessments

Main article: IP 71111.15

The inspectors evaluated the following operability determinations and functionality assessments:

(1) RCIC operability with condensate storage tank (CST) low-level transmitter 13LS-76B inoperable on August 16, 2018
(2) Pitting identified on drywell liner on September 24, 2018
(3) A and C residual heat removal service water pump bolt material type on September 30, 2018

71111.18 - Plant Modifications

Main article: IP 71111.18

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change 620602 - Replace all 11 two-stage safety relief valves with three-stage valves, on September 30, 2018

==71111.20 - Refueling and Other Outage Activities The inspectors evaluated RFO23 activities from September 10, 2018 through September 30, 2018.

71111.19 - Post Maintenance Testing

Main article: IP 71111.20

==

The inspectors evaluated post maintenance testing for the following maintenance/repair activities:

(1) Torus leak rate outboard isolation valve testing following unplanned maintenance on July 17, 2018
(2) Diesel fire pump 76-P1 relief valve replacement on July 19, 2018
(3) Torus leak rate outboard isolation valve maintenance and testing following unplanned maintenance on August 26, 2018
(4) RCIC transfer switch from CST suction to Torus suction following unplanned maintenance on September 4, 2018
(5) Low pressure coolant injection inverter replacement and testing on September 26, 2018
(6) MSIV 85 percent open position switch replacement on September 28, 2018
(7) Residual heat removal A containment spray outboard isolation valve 10MOV-26A following planned maintenance on September 30, 2018

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

Main article: IP 71111.22
(1) ST-9BA, A and C EDG Full Load Test and Emergency Service Water Pump Operability Test, on July 9, 2018
(2) ST-1B, MSIV Fast Closure Test, on September 12, 2018
(3) ST-9CA, A Division Loss of Offsite Power/Loss of Cooling Accident Test, on

September 29, 2018 Inservice (1 Sample)

(1) ST-6HB, B Standby Liquid Control Quarterly Operability Test, on July 26, 2018

Containment Isolation Valve (1 Sample)

(1) ST-39B-X7A, A MSIV As-Found Local Leak Rate Test, on September 14, 2018

71114.02 - Alert and Notification System Testing

Main article: IP 71114.02

The Inspectors evaluated the maintenance and testing of the alert and notification system (ANS) from July 2016 to July 2018.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Main article: IP 71114.03

The inspectors conducted a review of Exelons emergency response organization (ERO)augmentation staffing requirements and the process for notifying and augmenting the ERO.

71114.05 - Maintenance of Emergency Preparedness

Main article: IP 71114.05

The inspectors reviewed a number of activities to evaluate the efficacy of Exelons efforts to maintain FitzPatricks emergency preparedness programs.

71114.06 - Drill Evaluation Emergency Planning Drill

Main article: IP 71114.06

The inspectors evaluated the conduct of a routine emergency planning drill observation on

===August 1, 2018.

Drill/Training Evolution (1 Sample)===

The inspectors evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable HPCI steam leak into the reactor building which required a site area emergency declaration on July 17,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment

Main article: IP 71124.01

The inspectors reviewed recent plant radiation surveys to ensure radiological hazards to onsite workers and to members of the public were identified. The inspectors evaluated assessments and controls for new radiological hazards.

Instructions to Workers (1 Sample)

The inspectors evaluated instructions provided to workers.

Contamination and Radioactive Material Control (1 Sample)

The inspectors observed the monitoring of potentially contaminated material leaving the radiological control area and evaluated contamination and radioactive material controls.

The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and tested for loose surface contamination.

Radiological Hazards Control and Work Coverage (1 Sample)

The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walk-downs and observation of radiological work activities. The inspectors assessed posted surveys, radiation work permits, worker radiological briefings, the use of continuous air monitoring, and dosimetry monitoring to determine if they were consistent with the present conditions.

High Radiation Area and Very High Radiation Area Controls (1 Sample)

The inspectors evaluated risk-significant high radiation area and very high radiation area controls including postings and physical barriers.

Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician radiological performance.

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Verification of Dose Estimates and Exposure Tracking Systems

Main article: IP 71124.02

===The inspectors evaluated dose estimates and exposure tracking.

Radiation Worker Performance===

Main article: IP 71124.02

The inspectors evaluated radiation worker and radiation protection technician performance.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Engineering Controls

Main article: IP 71124.03

The inspectors observed the setup and use of ventilation systems and the use of monitoring instrumentation.

71124.04 - Occupational Dose Assessment Source Term Characterization

Main article: IP 71124.04

The inspectors evaluated Exelons source term characterization at FitzPatrick.

Special Dosimetric Situations (1 Sample)

The inspectors evaluated Exelons performance for special dosimetric situations.

71124.05 - Radiation Monitoring Instrumentation Walkdowns and Observations

Main article: IP 71124.05

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

Calibration and Testing Program (1 Sample)

The inspectors evaluated Exelons calibration and testing program.

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walkdowns and Observations

Main article: IP 71124.06

The inspectors walked down the gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.

Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)

The inspectors evaluated Exelons gaseous and liquid effluent monitor instrument calibration and testing.

Sampling and Analyses (1 Sample)

The inspectors evaluated radioactive effluent sampling and analysis activities.

Instrumentation and Equipment (1 Sample)

The inspectors reviewed radioactive effluent discharge system surveillance test results and reviewed the methodology used to determine the radioactive effluent stack and vent flow rates based on technical specifications/off site dose calculation manual (TS/ODCM)acceptance criteria.

Dose Calculations (1 Sample)

The inspectors reviewed several liquid and gaseous discharges to evaluate public dose calculations (monthly, quarterly, and annual) and the annual radiological effluent release reports for 2017 and

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

Main article: IP 71151

The inspectors verified Exelon performance indicators submittals listed below for the period from December 2017 through June 2018:

(1) EP01, Drill and Exercise Performance
(2) EP02, ERO Drill Participation
(3) EP03, ANS System Reliability
(4) IE01, Unplanned Scrams
(5) IE04, Unplanned Scrams with Complications
(6) MS06, MSPI Emergency AC Power Systems
(7) MS07, MSPI High Pressure Injection
(8) MS08, MSPI Heat Removal Systems
(9) MS09, MSPI Residual Heat Removal Systems
(10) MS10, MSPI Cooling Water Systems The inspectors verified Exelon performance indicator submittals listed below for the period from January 2017 through June 2018:
(11) PR01, RETS/ODCM Radiological Effluent Occurrence The inspectors verified Exelon performance indicator submittals listed below for the period from August 2017 through August 2018:
(12) OR01, Occupational Exposure Control

EXIT MEETINGS AND DEBRIEFS

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

On July 19, 2018, the inspectors conducted a debrief meeting and presented the baseline radiation protection inspection results to Mr. Chris Adner, Acting Plant Manager, and other members of the Exelon staff.

On July 19, 2018, the inspectors conducted a debrief meeting and presented the preliminary emergency preparedness inspection results to Mr. Chris Adner, Acting Plant Manager, and other members of the Exelon staff.

On August 16, 2018, the inspectors conducted a debrief meeting and presented the baseline radiation protection inspection results to Mr. Timothy Peters, Plant Manager, and other members of the Exelon staff.

On September 27, 2018, the inspectors conducted a debrief meeting and presented the radiation protection inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.

On October 22, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.

DOCUMENTS REVIEWED

71111.04

Procedures

AOP-68A, Loss of Decay Heat Removal, Revision 7

FM-133A, Decay Heat Removal Flow Diagram, Revision 9

FM-133B, Decay Heat Removal Flow Diagram, Revision 8

OP-13D, Residual Heat Removal Shutdown Cooling, Revision 31

OP-21, Emergency Service Water, Revision 38

OP-22, Diesel Generator Emergency Power, Revision 62

OP-30B, Decay Heat Removal System, Revision 19

OP-60, Diesel Generator Room Ventilation, Revision 9

Issue Reports

04092020 04099657 04117175 04117285

04117659

Drawings

FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 072

FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 073

FM-22A, Flow Diagram Reactor Core Isolation Cooling System 13, Revision 57

FM-46B, Flow Diagram Emergency Service Water System 46 and 15, Revision 57

ISI-FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 18

ISI-FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 16

Miscellaneous

Engineering Report No. JAF-RPT-05-AMM02, Aging Management Review of Residual Heat

Removal System, Revision 3

FPSSK-100, Fire Barrier Penetrations Arrangement Plan Below Elevation 272 0, Revision 5

FPSSK-206, Fire Barrier Penetrations Arrangement Fire Area Zone XII/SP-1 Elevation 255 0,

Revision 2

71111.05

Procedures

PFP-PWR09, Auxiliary Boiler Room, Elevation 272 and 285, Revision 4

PFP-PWR11, Cable Spreading Room, Elevation 272, Revision 3

PFP-PWR18, Drywell Area Elevation 268, Fire Area Zone XIV/PC-1, Revision 0

PFP-PWR19, Drywell Area Elevation 292, Fire Area Zone XIV/PC-1, Revision 0

PFP-PWR22, Standby Gas Filter Room. Elevation 272, Revision 6

PFP-PWR34, Screenwell House and Water Treatment Area, Elevation 235, 255, and 260,

Revision 05

PFP-PWR33, Pump Rooms (Screenwell), Elevation 255, Revision 02

PFP-PWR42, Turbine Building - North / Elev. 252, Revision 03

PFP-PWR43, Turbine Building - South / Elev. 252, Revision 05

PFP-PWR45, Turbine Building - North / Elev. 272, Revision 06

PFP-PWR46, Turbine Building - South / Elev. 272, Revision 04

PFP-PWR48, Turbine Building Elev. 300, Revision 04

71111.07

Procedures

ST-2YA, Residual Heat Removal Heat Exchanger A Performance Test, Revision 5

Drawings 4.95-5, RHR Heat Exchanger A Tube Plugging Map 10E-2A, Revision 2

Miscellaneous

14620.9033, Total Available Tube Plugging Margin in the RHR Heat Exchanger at Related

Conditions, Revision 0

71111.11

Procedures

OP-65, Startup and Shutdown Procedures, Revision 123

OP-65B, Shutdown Operations, Revision 7

71111.12

Issue Reports

04045089 04086665 04087668 04098168

04126033 04149166

71111.13

Procedures

AP-10.09, Outage Risk Assessment, Revision 37

71111.15

Procedures

ISP 75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24

ER-AA-335-018, Visual Examination of ASME IWE Class MC and Metallic Liners of IWL Class

CC Components, Revision 13

Issue Reports

04164618

04164660

04174135

04178640

Work Orders

C04799709

C04832920

Miscellaneous

Design Equivalent Change Package 625754

DWG 2.28-5, Sectional Allis Chalmers H16 x 12VTMC-3, Revision 003

Engineering Change (EC) 625691

71111.18

Drawings

DWG 6.32-80, Model 7567F 6 x 10 Relief Valve Alternate Configuration, Revision 4

Miscellaneous

EC 620602, UFSAR Change Request Form per LA-AA-107-1001, Revision 7

EC 620602, Engineering Calculation, Evaluation of SRV QBUBS Load Changes on Torus Shell,

Torus Attached Piping and Internal Structures, Revision 0

EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for ADS Line B, Revision 0

EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for Non-ADS Line L,

Revision 0

ECN 624214, Target Rock ASME Design Report 8692, Revision D

JAF-RPT-11-00003, Operational Leakage Action Levels for Target Rock Three Stages Safety

Relief Valves, Revision 1

JAF-SCN-18-056, 50.59 Screening Form for EC 620602, Revision 0

James

A. FitzPatrick Nuclear Power Plant, Technical Proposal for 3-Stage Main Steam Safety

Relief Valves

Report No. 8696, Temperature/Seat Leakage Correlation Report for Three Stage Pilot Operated

6x10 Safety Relief Valve SRV, Target Rock Model: 0867F-001, Revision D

Report TERI 081, Technical Evaluation of 3-Stage 6x10 MS-SRV Upgrade to Address Limited

Flow Test Induced Defect (Model 0867F) Ref: Problem Report 080 and CAR 15-045,

Revision A

71111.19

Procedures

ISP-75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24

MP-200.03, Replacement of NAMCO EA-180 and EA-740 Position Switches, Revision 11

MST-029.02, Main Steam Line Isolation Valve 85 Percent Open (RPS) Position Switch

Calibration Surveillance, Revision 19

ST-1CA, Outside Primary Containment Isolation Valve Exercise Test, Revision 1

ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 038

ST-76J23, West Diesel Fire Pump 76P-1 Performance Test, Revision 22

Issue Reports

04109193 04156252 04164618 04164660

04167340 04176976

Work Orders

C04644984 C04732717 C80161193 C80403118

C82503567

71111.22

Procedures

IMP-71.25, Test Equipment Set Up for 10500 and 10600 Emergency Bus Sequencing Test

ST- C, Revision 10

ST-1B, MSIV Fast Closure Test, Revision 26

ST-6HB, Standby Liquid Control Quarterly Operability Test (IST), Revision 9

ST-9BA, EDG A and C Full Load Test and ESW Pump Operability Test, Revision 16

ST-9CA, EDG A and C Load Sequencing Test and 4kV Emergency Power System Voltage

Relays Instrument Functional Test, Revision 4

ST-39B-X7A, Type C Leak Test Main Steam Line A MSIVs, Revision 16

Issue Reports

04178600

Work Orders

C82606584

71124.01

Procedures

NISP-RP-004, Radiological Posting and Labeling, Revision 00

NISP-RP-005, Access Controls for High Radiation Areas, Revision 0

RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1

RP-AA-300, Radiological Survey Program, Revision 15

RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 34

RP-AA-503, Unconditional Release Survey Method, Revision 14

Issue Reports

04171228 04174941 04175570 04175765

04176037 04176242

RWPs/ALARA Plans

RWP Description ALARA Plan

JF-1-18-00506 DW Scaffold AP-18-0506

JF-1-18-00510 DW SRV Activities AP-18-0510

JF-1-18-00513 DW CRD Drive Exchange AP-18-0513

JF-1-18-00516 DW RW Recirc Pump and Motor AP-18-0516

JF-1-18-00541 DW 12RWC-46 and 12MOV-15 AP-18-0541

Surveys

Survey Description Date/Time

2018-021841 DW 268 September 10, 2018/2100

2018-021911 DW 292 SRV September 11, 2018/1254

2018-022001 Under Reactor Head September 12, 2018/0052

2018-022623 12RWC-46 September 16, 2018/1058

2018-022711 12RWC-46 September 17, 2018/0837

2018-022565 SRV 71F September 18, 2018/0116

2018-023578 DW 256 September 25, 2018/0447

Air Sample Results

Air Sample Description Date/Time

18306 DW 12RWC46 September 18, 2018/1220

18320 DW B Recirc Pump Seal September 22, 2018/2300

18329 DW MSIV B Breach September 23, 2018/0250

18311 DW 12MOV15 Breach September 23, 2018/1220

18342 DW 268 General Area September 24, 2018/0640

18343 DW 292 General Area September 24, 2018/0720

18345 DW 12MOV15 September 25, 2018/0230

71124.02

Procedures

RP-AA-400, ALARA Program, Revision 15

Issue Reports (*initiated in response to inspection)

04175408

04177200*

71124.03

Procedures

RP-AA-301, Radiological Air Sampling Program, Revision 11

RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 10

Issue Reports

04133415

Miscellaneous

Breathing Air Samples, Report 294228-0 on January 18, 2017; and Report 341956-1 on

August 31, 2018

71124.04

Procedures

RP-AA-12, Internal Dose Control Program Description, Revision 2

RP-AA-203-1001, Personnel Exposure Investigations, Revision 10

RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 29

RP-AA-220, Bioassay Program, Revision 13

RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5

RP-AA-290, Prenatal Radiation Exposure, Revision 8

Issue Reports

04102403

04174125

04175886

Miscellaneous

Generic Radiation Worker Training Lesson Plan, Revision 11, December 2017

NVLAP Certification for Lab Code 100518-0

71124.05

Procedures

ISP-95A, Post Accident Containment High Range Radiation Monitor A Functional

Test/Calibration, Revision 4

ISP-95B, Post Accident Containment High Range Radiation Monitor B Functional

Test/Calibration, Revision 4

RP-AA-700-1101, Calibration of the RO-2, RO-2A, RO-20 and RSO-50E Ion Chambers,

Revision 1

RP-AA-700-1203, Calibration of the MGP Instruments Telepole, Revision 1

RP-AA-700-1215, Calibration of Low-Vol Air Samplers, Revision 2

RP-AA-700-1216, Calibration of Hi-Vol Air Samplers, Revision 4

RP-AA-700-1235, Operation and Calibration of the PM-12 Gamma Portal Monitor, Revision 5

RP-AA-700-1239, Operation and Calibration of the Model SAM-12 Small Articles Monitor,

Revision 4

RP-AA-700-1240, Operation and Calibration of the Canberra ARGOS-5 Personnel

Contamination Monitor, Revision 6

RP-AA-700-1242, Calibration of Eberline Model 6112B Teletector, Revision 0

RP-AA-700-1301, Calibration, Source Check, Operation and Set-Up of the Eberline Beta Air

Monitor, Model AMS-4, Revision 4

RP-AA-700-1305, Operation and Calibration of the AMP-100/200, Revision 2

RP-AA-700-1312, Calibration of Bicron Micro REM Survey Meter, Revision 1

RP-AA-700-1401, Operation and Calibration of Eberline Model PM-7 Personnel Contamination

Monitor, Revision 6

RP-INST-02.09, Calibration of Mini-Scaler MS-2 and MS-3, Revision 5

RP-INST-02.15, Calibration of Ludlum L-2000 Scaler, Revision 0

SP-03.14, Post Accident Sampling, Revision 0

Issue Reports

04095004 04096020 04156340 04162340

Calibration Records

17RM-351, Normal Service Water Monitor, February 16, 2018

04752950-01, Reactor Building Vent Monitor, June 15, 2018

04752006-01, Stack Vent Monitor, June 8, 2018

04771225-01, Radwaste Building Vent, July 10, 2018

2606748-01, 27RM-104A Containment High Range Monitor (Source), February 5, 2017

2606749-01, 27RM-104B Containment High Range Monitor (Source), February 7, 2017

2720565-01, 27RM-104A Containment High Range Monitor (Electronics), December 27, 2016

2714885-01, 27RM-104B Containment High Range Monitor (Electronics), December 27, 2016

Miscellaneous

Mirion Technologies Calibration of the Canberra Fastscan WBC System at the Exelon James

A.

FitzPatrick Nuclear Power Plant, March 28, 2018

71124.06

Procedures

CY-AA-130-200, Quality Control, Revision 13

CY-AA-130-201, Radiochemistry Quality Control, Revision 5

CY-AA-170-2200, RETDAS, Revision 1

EN-AA-408, Radiological Groundwater Protection Program, Revision 0

EN-CY-102, Laboratory Analytical Quality Control, Revision 9

SP-01.06, Gaseous Effluent Sampling and Analysis, Revision 20

SP-03.05, Steam Jet Air Ejector and Recombiner Effluent Sampling and Analysis, Revision 13

SP-03.07, Liquid Process Radiation Monitors, Revision 10

SP-03.08RF, Refuel Floor Gaseous Effluent Monitors, Revision 2a

SP-03.08RW, Radwaste Building Gaseous Effluent Monitors, Revision 4a

SP-03.08RX, Reactor Building Gaseous Effluent Monitors, Revision 1a

SP-03.08STK, Stack Effluent Monitors, Revision 6a

SP-03.08TB, Turbine Building Gaseous Effluent Monitors, Revision 3

Issue Reports

03037511 03847968 03992568 03996675

04001340 04010103

Miscellaneous

Radioiodine Penetration/Efficiency Test Report, March 23, 2018

71151

Procedures

EN-LI-114, Performance Indicator Process, Revision 7

NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7

Miscellaneous

JAF-RPT-05-0047, Mitigating Systems Performance Index Basis Document, Revision 5

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