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| number = ML18134A214
| number = ML18134A214
| issue date = 05/14/2018
| issue date = 05/14/2018
| title = James A. Fitzpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2018001
| title = Integrated Inspection Report 05000333/2018001
| 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
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:May 14, 2018
[[Issue date::May 14, 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 05000333/2018001
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018001


==Dear Mr. Hanson:==
==Dear Mr. Hanson:==
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 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  
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 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.
 
report.


The NRC inspectors did not identify any finding or violation of more than minor significance.
The NRC inspectors did not identify any finding or violation of more than minor significance.


This letter, its enclosure, and your response (if any) will be made available for public 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 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.


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/  


Sincerely,/RA/
Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects
Anthony Dimitriadis, Chief Reactor Projects Branch 5  


Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59  
Docket Number: 50-333 License Number: DPR-59  


===Enclosure:===
===Enclosure:===
Inspection Report 05000333/2018001  
Inspection Report 05000333/2018001  


cc w/encl: Distribution via ListServ
==Inspection Report==
 
Docket Number:
ML18134A214 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME KKolaczyk/GStock for via email LCline via email ADimitriadis DATE 5/14/18 5/14/18 5/14/18
50-333  
 
1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
 
Docket Number: 50-333  


License Number: DPR-59  
License Number:
DPR-59  


Report Number: 05000333/2018001  
Report Number:
05000333/2018001  


Enterprise Identifier: I-2018-001-0048  
Enterprise Identifier: I-2018-001-0048  


Licensee: Exelon Generation Company, LLC  
Licensee:
Exelon Generation Company, LLC  


Facility: James A. FitzPatrick Nuclear Power Plant  
Facility:
James A. FitzPatrick Nuclear Power Plant  


Location: Scriba, NY  
Location:
Scriba, NY  


Inspection Dates: January 1, 2018 to March 31, 2018  
Inspection Dates:
January 1, 2018 to March 31, 2018  


Inspectors: K. Kolaczyk, Senior Resident Inspector G. Stock, Resident Inspector J. Ambrosini, Senior Emergency Preparedness Inspector T. Dunn, Operations Engineer J. Kulp, Senior Reactor Inspector R. Rolph, Health Physicist C. Safouri, Project Engineer A. Turilin, Resident Inspector  
Inspectors:
K. Kolaczyk, Senior Resident Inspector  


Approved By: A. Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects
G. Stock, Resident Inspector


2 SUMMARY 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
J. Ambrosini, Senior Emergency Preparedness Inspector


https://www.nrc.gov/reactors/operating/oversight.html for more information.
T. Dunn, Operations Engineer


No findings or more-than-minor violations were identified.
J. Kulp, Senior Reactor Inspector


3 PLANT STATUS FitzPatrick began the inspection period at rated thermal power. On February 25, 2018, operators reduced power to 54 percent to perform scram time testing and turbine and main steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the inspection period.
R. Rolph, Health Physicist


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."
C. Safouri, Project Engineer


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.
A. Turilin, Resident Inspector


REACTOR SAFETY 71111.01 - Adverse Weather Protection
Approved By:
A. Dimitriadis, Chief


Impending Severe Weather (1 Sample)
Reactor Projects Branch 5
The inspectors evaluated readiness for impending extreme weather conditions prior to the unseasonably cold weather during the week of January 1, 2018.


71111.04 - Equipment Alignment Partial Walkdown (5 Samples)
Division of Reactor Projects


The inspectors evaluated system configurations during partial walkdowns of the following systems:
=SUMMARY=
(1) Containment air dilution system following completion of maintenance activities conducted the week of January 15, 2018 (2) High pressure coolant injection (HPCI) system on January 18, 2018 (3) Drywell outage cooling system on January 26, 2018 (4) 'A' control room emergency ventilation system with 'B' train inoperable for relay maintenance on March 3, 2018 (5) 'B' spent fuel pool cooling system while the 'A' system was out of service for unplanned maintenance on March 22, 2018
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at


4 Complete Walkdown (1 Sample)
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 inspectors evaluated system configurations during a complete walkdown of the drywell vent and purge and containment pressurization system on March 16, 2018.


71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection (6 Samples)
No findings or more-than-minor violations were identified.
The inspectors evaluated fire protection program implementation in the following selected areas:


(1) North cable tunnel fire zone CT-4 on January 3, 2018 (2) South cable tunnel fire zone CT-3 on January 3, 2018 (3) Relay room fire zone RR-1 on January 3, 2018 (4) East pipe tunnel fire zone RW-1 on January 18, 2018 (5) Battery room 'A' fire zone BR-1 on February 21, 2018 (6) Interim waste storage facility, fire area yard on March 28, 2018 71111.06 - Flood Protection Measures (1 Sample)
=PLANT STATUS=
Internal Flooding The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was removed for west crescent cooler maintenance, on March 9, 2018.


71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification (1 Sample)
FitzPatrick began the inspection period at rated thermal power. On February 25, 2018, operators reduced power to 54 percent to perform scram time testing and turbine and main steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the inspection period.
The inspectors observed and evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level instrumentation on January 25, 2018.


Operator Performance (1 Sample)  
==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.


The inspectors observed 'B' turbine driv en feed pump taken to manual to perform operational decision making issue actions for motor gear unit sticking, and the performance of ST-5BB system 'B' channel function test on March 13, 2018.
==REACTOR SAFETY==
==71111.01 - Adverse Weather Protection==
===Impending Severe Weather (1 Sample)===
The inspectors evaluated readiness for impending extreme weather conditions prior to the unseasonably cold weather during the week of January 1, 2018.


71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness (2 Samples)
==71111.04 - Equipment Alignment==
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:  
===Partial Walkdown (5 Samples)===
(1) Structural monitoring program walkdown of the torus room on March 1, 2018  
The inspectors evaluated system configurations during partial walkdowns of the following systems:
: (1) Containment air dilution system following completion of maintenance activities conducted the week of January 15, 2018
: (2) High pressure coolant injection (HPCI) system on January 18, 2018
: (3) Drywell outage cooling system on January 26, 2018
: (4) A control room emergency ventilation system with B train inoperable for relay maintenance on March 3, 2018
: (5) B spent fuel pool cooling system while the A system was out of service for unplanned maintenance on March 22, 2018  


5 (2) Structural monitoring program walkdown of reactor building refuel floor exterior on March 13, 2018 71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
===Complete Walkdown (1 Sample)===
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
The inspectors evaluated system configurations during a complete walkdown of the drywell vent and purge and containment pressurization system on March 16, 2018.
(1) 'C' battery room ventilation fan maintenance on January 26, 2018 (2) HPCI planned maintenance on February 13, 2018 (3) 'B' station air compressor planned maintenance on February 13, 2018 (4) 'A' and 'C' diesel generators planned maintenance the week of February 19, 2018 (5) Hardened containment vent tie-in to normal ventilation on February 27, 2018  


71111.15 - Operability Determinations and Functionality Assessments (9 Samples)
==71111.05A/Q - Fire Protection Annual/Quarterly==
The inspectors evaluated the following operability determinations and functionality assessments:  
===Quarterly Inspection (6 Samples)===
(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018 (2) Standby gas treatment 'A' after excessive runtime without a charcoal sample on January 31, 2018 (3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018 (4) Bypass valve operability following intermittent partial open indication on February 12, 2018 (5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on February 15, 2018 (6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00 on February 23, 2018 (7) Past operability for the safety pump room with the fire dampers covered with herculite on February 27, 2018 (8) HPCI secured during surveillance test due to high flow on March 9, 2018 (9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018  
The inspectors evaluated fire protection program implementation in the following selected areas:
: (1) North cable tunnel fire zone CT-4 on January 3, 2018
: (2) South cable tunnel fire zone CT-3 on January 3, 2018
: (3) Relay room fire zone RR-1 on January 3, 2018
: (4) East pipe tunnel fire zone RW-1 on January 18, 2018
: (5) Battery room A fire zone BR-1 on February 21, 2018
: (6) Interim waste storage facility, fire area yard on March 28, 2018


71111.17T - Evaluations of Changes, Tests, and Experiments (29 Samples)
==71111.06 - Flood Protection Measures==
The inspectors evaluated the following from March 26, 2018 to March 29, 2018:
{{IP sample|IP=IP 71111.06|count=1}}
10 CFR 50.59 Evaluations (1) JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0 (2) JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0 10 CFR 50.59 Screening/Applicability Determinations (1) 2452, PRCR: AOP-77, Revision 5 (2) 9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0 (3) 9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0 (4) 9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header Pressure, Revision 1 6 (5) 9000067365, 10MOV-89A/B Replacement, Revision 0 (6) 9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0 (7) 9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0 (8) 9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39, Revision 1 (9) AR04078735, Revision 37 of OP-55B, Revision 0 (10) DRN 16-00288, Revision 36 of OP-55B, Revision 0 (11) DRN-00156, OP-65B, Shutdown Operation, Revision 0 (12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0 (13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank Additions, Revision 0 (14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48, 49, 50, and 51 and Retire in Place, Revision 0 (15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position (Open), Revision 0 (16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0 (17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat Removal Service Water for Work on 10MOV-89B, Revision 0 (18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set Overvoltage Relay Setpoint, Revision 0 (19) EC 9000067410, Replace 3-stage Safety Relie f Valves with 2-stage Valves 2RV-71E and 2RV-71F, Revision 0 (20) EC 9000067794, Replacement of 92TIC-101B, Revision 0 (21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0 (22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0 (23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch Calibration, Revision 0 (24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0 (25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision, Revision 0 (26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0 (27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement 3.3.1.1.8 Frequency Change, Revision 0


71111.19 - Post Maintenance Testing (7 Samples)
Internal Flooding
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
(1) 76-P4 run preventive maintenance on February 12, 2018 (2) HPCI system turbine steam supply drain trap replacement on February 13, 2018 (3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018 (4) 'B' turbine driven feed pump motor gear unit replacement and testing on February 28, 2018 (5) 'B' control room emergency ventilation system relay maintenance on March 13, 2018 (6) 'A' residual heat removal maintenance window on March 22, 2018 (7) 'A' emergency diesel generator circulating oil pump coupling replacement and realignment on March 28, 2018


7 71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:
The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was removed for west crescent cooler maintenance, on March 9, 2018.
Routine (3 Samples)
(1) ST-9BA, Emergency Diesel Generator 'A' and 'C' Full Load Test and Emergency Service Water Pump Operability Test, on January 29, 2017 (2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018 (3) ST-9R, Emergency Diesel Generator 'A' and 'C' System Quick-Start Operability Test and Offsite Circuit Verification, on February 5, 2018  


Inservice (2 Samples)
==71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance==
(1) ST-2AL , 'A' Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018 (2) ST-25BB, Containment Atmosphere Dilution System 'B' Quarterly Operability Test (IST),
===Operator Requalification (1 Sample)===
on January 19, 2018 71114.06 - Drill Evaluation Drill/Training Evolution (1 Sample)
The inspectors observed and evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level instrumentation on January 25, 2018.
The inspectors evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel level instrumentation which led to a site area emergency declaration, on January 25,  


2018. RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (1 Sample)
===Operator Performance (1 Sample)===
The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite workers or members of the public. The inspectors evaluated assessments and controls for new radiological hazards.
The inspectors observed B turbine driven feed pump taken to manual to perform operational decision making issue actions for motor gear unit sticking, and the performance of ST-5BB system B channel function test on March 13, 2018.


Instructions to Workers (1 Sample)  
==71111.12 - Maintenance Effectiveness==
===Routine Maintenance Effectiveness (2 Samples)===
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
: (1) Structural monitoring program walkdown of the torus room on March 1, 2018
: (2) Structural monitoring program walkdown of reactor building refuel floor exterior on March 13, 2018


The inspectors evaluated instructions provided to workers.
==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
{{IP sample|IP=IP 71111.13|count=5}}


Contamination and Radioactive Material Control (1 Sample)  
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
: (1) C battery room ventilation fan maintenance on January 26, 2018
: (2) HPCI planned maintenance on February 13, 2018
: (3) B station air compressor planned maintenance on February 13, 2018
: (4) A and C diesel generators planned maintenance the week of February 19, 2018
: (5) Hardened containment vent tie-in to normal ventilation on February 27, 2018


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 were tested for loose surface contamination.
==71111.15 - Operability Determinations and Functionality Assessments==
{{IP sample|IP=IP 71111.15|count=9}}


8 Radiological Hazards Control and Work Coverage (1 Sample)
The inspectors evaluated the following operability determinations and functionality assessments:
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 whether posted surveys, radiation work permits, worker radiological briefings, and the use of continuous air monitoring and dosimetry monitoring were consistent with the present conditions.
: (1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018
: (2) Standby gas treatment A after excessive runtime without a charcoal sample on January 31, 2018
: (3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018
: (4) Bypass valve operability following intermittent partial open indication on February 12, 2018
: (5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on February 15, 2018
: (6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00 on February 23, 2018
: (7) Past operability for the safety pump room with the fire dampers covered with herculite on February 27, 2018
: (8) HPCI secured during surveillance test due to high flow on March 9, 2018
: (9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018


High Radiation Area and Very High Radiation Area Controls (1 Sample)
===71111.17T - Evaluations of Changes, Tests, and Experiments===
{{IP sample|IP=IP 71111.17|count=29}}


The inspectors evaluated risk-significant high radiation area and very high radiation area controls, including postings and physical barriers.
The inspectors evaluated the following from March 26, 2018 to March 29, 2018:


Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)  
10 CFR 50.59 Evaluations
: (1) JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0
: (2) JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0


The inspectors evaluated radiation worker and radiation protection technician radiological
10 CFR 50.59 Screening/Applicability Determinations


performance.
(1)2452, PRCR: AOP-77, Revision 5 (2)


71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)  
===9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0 (3)9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0 (4)9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header Pressure, Revision 1 (5)9000067365, 10MOV-89A/B Replacement, Revision 0 (6)9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0 (7)9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0 (8)9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39, Revision 1
: (9) AR04078735, Revision 37 of OP-55B, Revision 0
: (10) DRN 16-00288, Revision 36 of OP-55B, Revision 0
: (11) DRN-00156, OP-65B, Shutdown Operation, Revision 0
: (12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0
: (13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank Additions, Revision 0
: (14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48, 49, 50, and 51 and Retire in Place, Revision 0
: (15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position (Open), Revision 0
: (16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0
: (17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat Removal Service Water for Work on 10MOV-89B, Revision 0
: (18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set Overvoltage Relay Setpoint, Revision 0
: (19) EC 9000067410, Replace 3-stage Safety Relief Valves with 2-stage Valves 2RV-71E and 2RV-71F, Revision 0
: (20) EC 9000067794, Replacement of 92TIC-101B, Revision 0
: (21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0
: (22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0
: (23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch Calibration, Revision 0
: (24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0
: (25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision, Revision 0
: (26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0
: (27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement 3.3.1.1.8 Frequency Change, Revision 0


The inspectors evaluated dose estimates and exposure tracking.
==71111.19 - Post Maintenance Testing==
{{IP sample|IP=IP 71111.19|count=7}}


Radiation Worker Performance (1 Sample)  
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
: (1) 76-P4 run preventive maintenance on February 12, 2018
: (2) HPCI system turbine steam supply drain trap replacement on February 13, 2018
: (3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018
: (4) B turbine driven feed pump motor gear unit replacement and testing on February 28, 2018
: (5) B control room emergency ventilation system relay maintenance on March 13, 2018
: (6) A residual heat removal maintenance window on March 22, 2018
: (7) A emergency diesel generator circulating oil pump coupling replacement and realignment on March 28, 2018


The inspectors evaluated radiation worker and radiation protection technician performance.
==71111.22 - Surveillance Testing==
The inspectors evaluated the following surveillance tests:


71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Self-Contained Breathing Apparatus for Emergency Use (1 Sample)
===Routine===
The inspectors evaluated Exelon's self-contained breathing apparatus (SCBA) program at FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during emergencies, procedures, maintenance and test records, the refilling and transporting of SCBA air bottles, SCBA mask size availability, and the qualifications of personnel performing service and repair of this equipment.
{{IP sample|IP=IP 71111.22|count=3}}
: (1) ST-9BA, Emergency Diesel Generator A and C Full Load Test and Emergency Service Water Pump Operability Test, on January 29, 2017
: (2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018
: (3) ST-9R, Emergency Diesel Generator A and C System Quick-Start Operability Test and Offsite Circuit Verification, on February 5, 2018


71124.04 - Occupational Dose Assessment
Inservice===
{{IP sample|IP=IP 90000|count=2}}
: (1) ST-2AL, A Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018
: (2) ST-25BB, Containment Atmosphere Dilution System B Quarterly Operability Test (IST),on January 19, 2018


Source Term Characterization (1 Sample)  
==71114.06 - Drill Evaluation==
===Drill/Training Evolution (1 Sample)===
The inspectors evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel level instrumentation which led to a site area emergency declaration, on January 25,


The inspectors evaluated Exelon's s ource term characterization.
==RADIATION SAFETY==
==71124.01 - Radiological Hazard Assessment and Exposure Controls==
===Radiological Hazard Assessment (1 Sample)===
The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite workers or members of the public. The inspectors evaluated assessments and controls for new radiological hazards.


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


The inspectors evaluated Exelon's performance for special dosimetric situations.
===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.


9 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification (2 Samples)
The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination.
The inspectors verified licensee performance indicators submittals listed below for the


period from January 1, 2017 through December 31, 2017:
===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 whether posted surveys, radiation work permits, worker radiological briefings, and the use of continuous air monitoring and dosimetry monitoring were consistent with the present conditions.


(1) MS05, Safety System Functional Failures (2) IE03, Unplanned Power Changes 71152 - Problem Identification and Resolution
===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.


Annual Follow-up of Selected Issues (1 Sample)
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)  
The inspectors reviewed Exelon's implementation of its corrective action program related to the following issues:


(1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level INSPECTION RESULTS Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level
The inspectors evaluated radiation worker and radiation protection technician radiological performance.


On January 23, 2016, during power ascension following a downpower for hydraulic control unit maintenance, the station experienced a reduction in intake level. Operators initially attempted to perform a rapid downpower with the intent of securing two circulating water pumps. After securing the first circulating water pump, intake level momentarily began to rise and then continued to lower. When intake level decreased to the procedurally required minimal intake level, operators inserted a manual scram. Exelon determined the cause of the scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent occurrence, but is expected during winter months during specific meteorological conditions. FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010. However, only in 1996 did the event result in a unit scram, which resulted in a number of corrective actions, including new procedures to combat intake level issues. Since the 2004 -
==71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls==
2010 events did not result in a reactor scram, the evaluations for the events were not as in depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were missed opportunities to not just mitigate the bui ld-up of frazil ice but evaluate and eliminate the potential. Another factor that potentially affected how rapidly the January 2016 progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased the flow rate through the intake, which can expedite frazil ice formation in the intake system.
===Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)===
The inspectors evaluated dose estimates and exposure tracking.


Exelon noted this item in the root cause investigation that was completed following the 2016 scram, and implemented several corrective actions to address this issue.
===Radiation Worker Performance (1 Sample)===
The inspectors evaluated radiation worker and radiation protection technician performance.


The inspectors reviewed the 2016 Exelon root cause analysis documented under IR 03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes were that the procedures for mitigating the impact of frazil ice formation were ineffective, and that station leadership accepted mitigating actions vice elimination for issues that potentially jeopardized safe plant operation. Previous analysis has discovered under certain circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root 10 cause and the contributing causes, Exelon pursued corrective actions to eliminate the possibility of frazil ice build-up which included removing two of the eight bar racks on the intake structure as corrective actions. The removal of the two bar racks will allow for sufficient intake flow should the remaining racks be impeded by frazil ice.
==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation==
===Self-Contained Breathing Apparatus for Emergency Use (1 Sample)===
The inspectors evaluated Exelons self-contained breathing apparatus (SCBA) program at FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during emergencies, procedures, maintenance and test records, the refilling and transporting of SCBA air bottles, SCBA mask size availability, and the qualifications of personnel performing service and repair of this equipment.


The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake level issues which would appear to demonstrate that the removal of the bar racks has improved FitzPatrick's ability to mitigate frazil ice buildup. Further corrective actions include installing an intake level rate of change alarm, revising procedures to increase lake level monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The inspectors concluded that Exelon's response and corrective actions for this event were commensurate with the safety significance, were timely, and included appropriate compensatory measures.
==71124.04 - Occupational Dose Assessment==
===Source Term Characterization (1 Sample)===
The inspectors evaluated Exelons source term characterization.


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


The inspectors verified no proprietary information was retained or documented in this report.
==OTHER ACTIVITIES - BASELINE==
===71151 - Performance Indicator Verification===
{{IP sample|IP=IP 71151|count=2}}


On May 2, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
The inspectors verified licensee performance indicators submittals listed below for the period from January 1, 2017 through December 31, 2017:
: (1) MS05, Safety System Functional Failures
: (2) IE03, Unplanned Power Changes


11 DOCUMENTS REVIEWED
==71152 - Problem Identification and Resolution==
===Annual Follow-up of Selected Issues (1 Sample)===
The inspectors reviewed Exelons implementation of its corrective action program related to the following issues:
: (1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level


71111.01
==INSPECTION RESULTS==
Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level


Issue Report 04087668
On January 23, 2016, during power ascension following a downpower for hydraulic control unit maintenance, the station experienced a reduction in intake level. Operators initially attempted to perform a rapid downpower with the intent of securing two circulating water pumps. After securing the first circulating water pump, intake level momentarily began to rise and then continued to lower. When intake level decreased to the procedurally required minimal intake level, operators inserted a manual scram. Exelon determined the cause of the scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent occurrence, but is expected during winter months during specific meteorological conditions.


71111.04 Procedures CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4 DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4 FB-35E, Flow Diagram Control Room Area Se rvice and Chilled Water System 70, Revision 38 FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70, Revision 42 FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45 OP-13F, RHR- Fuel Pool Cooling Assist, Revision 11 OP-30 Fuel Pool Cooling and Cleanup System, Revision 43
FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010.


Issue Report 04088760
However, only in 1996 did the event result in a unit scram, which resulted in a number of corrective actions, including new procedures to combat intake level issues. Since the 2004 - 2010 events did not result in a reactor scram, the evaluations for the events were not as in depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were missed opportunities to not just mitigate the build-up of frazil ice but evaluate and eliminate the potential. Another factor that potentially affected how rapidly the January 2016 progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased the flow rate through the intake, which can expedite frazil ice formation in the intake system.


Drawings FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65 FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary Cooling System 68, Revision 4 FM-18A, Flow Diagram, Drywell Inerting C.A.D. and Purge System, Revision 57 FM-18B, Flow Diagram, Drywell Inerting C.A.D. Purge and Containment DP System 27, Revision 44 FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75 FM-48A, Flow Diagram Standby Gas Tr eatment System 01-125, Revision 32 71111.05 Procedures JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3 PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0 PFP-PWR04 Battery Room Complex, EL 272', Fire Area/Zone BR-1, Br-2, BR-3, BR-4, Revision 2 PFP-PWR37, East Pipe Tunnel Elevation 258' Fire Area/Zone XIX/RW-1, Revision 002
Exelon noted this item in the root cause investigation that was completed following the 2016 scram, and implemented several corrective actions to address this issue.


71111.06
The inspectors reviewed the 2016 Exelon root cause analysis documented under IR 03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes were that the procedures for mitigating the impact of frazil ice formation were ineffective, and that station leadership accepted mitigating actions vice elimination for issues that potentially jeopardized safe plant operation. Previous analysis has discovered under certain circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root cause and the contributing causes, Exelon pursued corrective actions to eliminate the possibility of frazil ice build-up which included removing two of the eight bar racks on the intake structure as corrective actions. The removal of the two bar racks will allow for sufficient intake flow should the remaining racks be impeded by frazil ice.


Procedures AP-16.14, Hazard Barrier Controls, Revision 7 CC-AA-201, Plant Barrier Control Program, Revision 12
The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake level issues which would appear to demonstrate that the removal of the bar racks has improved FitzPatricks ability to mitigate frazil ice buildup. Further corrective actions include installing an intake level rate of change alarm, revising procedures to increase lake level monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The inspectors concluded that Exelons response and corrective actions for this event were commensurate with the safety significance, were timely, and included appropriate compensatory measures.


71111.12 Procedures ST-5BB, APRM System 'B' Channel Functional Test, Revision 2 12 OP-AA-103-102, Watch-Standing Practices, Revision 18 OP-AA-108-112, Plant Status and Configuration, Revision 10
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.


Issue Report 04114489
On May 2, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
 
Miscellaneous JAF-1-2017-0609, Revision 1
 
71111.12
 
Procedures ER-AA-450, Structures Monitoring, Revision 6 JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 Issue Report 04114448
 
71111.13 Procedures AP-10.10, On-Line Risk Assessment, Revision 9 EN-WM-104, On-Line Risk Assessment, Revision 12 OP-AA-108-117, Protected Equipment Program, Revision 4
 
71111.15 Procedures FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42 OP-AA-108-115, Operability Determinations, Revision 20 RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19 ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66 ST-40D, Daily Surveillance and Channel Check, Revision 112
 
Issue Reports 03992613 04071131 04081869 04088480 04088760 04096823 04097327 04103156 04103690 04112832
 
Work Order 4712278 Drawings Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42 FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75
 
71111.19 Procedures HU-AA-104-101, Procedure Use and Adherence, Revision 5 ST-2AN, RHR Loop A Monthly Operability Test, Revision 16 13 ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33 ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10 WC-AA-111, Surveillance Program Requirements, Revision 5 Issue Reports 04097327 04098786 04103334 04107062 04114905 04119383
 
Work Orders 4691285 4731093 82691241 04765320
 
04666902-32
 
Miscellaneous Engineering Change 50781 71111.22 Procedures MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14 ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37 ST-9BA, EDG 'A' and 'C' Full Load Test and ESW Pump Operability Test, Revision 16 ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9
 
Work Orders 04710258 04733734 71124.01 Procedures EN-RP-105, Radiological Work Permits, Revision 16 EN-RP-106, Radiological Survey Documentation, Revision 7 EN-RP-106-01, Radiological Survey Guidelines, Revision 3 EN-RP-108, Radiation Protection Posting, Revision 18 EN-RP-121, Radioactive Material Control, Revision 13 RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1 RP-AA-300, Radiological Survey Program, Revision 15 RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9 RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30 RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3 RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential or Actual Emergency, Revision 9 RP-AA-504, Unconditional Release Survey Method, Revision 14 RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,
 
Revision 4 Issue Reports 04102384 04096595 04080866 04066877 04063769 04053351
 
14 Miscellaneous Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934, S935, S1018, S1029 71124.02 Procedures EN-RP-110, ALARA Program, Revision 14 EN-RP-110-01, ALARA Initiative Deferrals, Revision 1 EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4 EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7 EN-RP-110-05, ALARA Planning and Controls, Revision 3 RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals, Revision 4 RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9 RP-AA-401, Operational ALARA Planning and Controls, Revision 22 RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8
 
Issue Reports 04053610 04060956
 
04071477 71124.03
 
Procedures EN-RP-131, Air Sampling, Revision 15 EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7 RP-AA-301, Radiological Air Sampling Program, Revision 10 RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8 RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8 RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6


Issue Reports 04061257 04089450
=DOCUMENTS REVIEWED=


Miscellaneous LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel Monitoring Program and Bioassay Program, October 16, 2017 71124.04 Procedures RP-AA-203-1001, Personnel Exposure Investigations, Revision 10 RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28 RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1 RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5 RP-AA-250, External Dose Assessment from Contamination, Revision 7 RP-AA-270, Prenatal Radiation Exposure, Revision 8 15 Miscellaneous NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 71151 Procedure EN-LI-114, Performance Indicator Process, Revision 7 71152 Procedures OP-4, Circulating Water System, Revision 81 AOP-56, Intake Water Level Trouble, Revision 15
71111.01
Issue Report
04087668
71111.04
Procedures
CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4
DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4
FB-35E, Flow Diagram Control Room Area Service and Chilled Water System 70, Revision 38
FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70,
Revision 42
FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45
OP-13F, RHR-Fuel Pool Cooling Assist, Revision 11
OP-30 Fuel Pool Cooling and Cleanup System, Revision 43
Issue Report
04088760
Drawings
FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65
FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary
Cooling System 68, Revision 4
FM-18A, Flow Diagram, Drywell Inerting C.
: [[contact::A.D. and Purge System]], Revision 57
FM-18B, Flow Diagram, Drywell Inerting C.
: [[contact::A.D. Purge and Containment DP System 27]],
Revision 44
FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75
FM-48A, Flow Diagram Standby Gas Treatment System 01-125, Revision 32
71111.05
Procedures
JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3
PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0
PFP-PWR04 Battery Room Complex, EL 272, Fire Area/Zone BR-1, Br-2, BR-3, BR-4,
Revision 2
PFP-PWR37, East Pipe Tunnel Elevation 258 Fire Area/Zone XIX/RW-1, Revision 002
71111.06
Procedures
AP-16.14, Hazard Barrier Controls, Revision 7
CC-AA-201, Plant Barrier Control Program, Revision 12
71111.12
Procedures
ST-5BB, APRM System B Channel Functional Test, Revision 2


Issue Reports 03992624 04087426
OP-AA-103-102, Watch-Standing Practices, Revision 18
OP-AA-108-112, Plant Status and Configuration, Revision 10
Issue Report
04114489
Miscellaneous
JAF-1-2017-0609, Revision 1
71111.12
Procedures
ER-AA-450, Structures Monitoring, Revision 6
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6
Issue Report
04114448
71111.13
Procedures
AP-10.10, On-Line Risk Assessment, Revision 9
EN-WM-104, On-Line Risk Assessment, Revision 12
OP-AA-108-117, Protected Equipment Program, Revision 4
71111.15
Procedures
FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42
OP-AA-108-115, Operability Determinations, Revision 20
RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19
ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66
ST-40D, Daily Surveillance and Channel Check, Revision 112
Issue Reports
03992613
04071131
04081869
04088480
04088760
04096823
04097327
04103156
04103690
04112832
Work Order
4712278
Drawings
Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42
FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75
71111.19
Procedures
HU-AA-104-101, Procedure Use and Adherence, Revision 5
ST-2AN, RHR Loop A Monthly Operability Test, Revision 16


Miscellaneous EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21 Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level
ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33
ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10
WC-AA-111, Surveillance Program Requirements, Revision 5
Issue Reports
04097327
04098786
04103334
04107062
04114905
04119383
Work Orders
4691285
4731093
2691241
04765320
04666902-32
Miscellaneous
Engineering Change 50781
71111.22
Procedures
MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14
ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37
ST-9BA, EDG A and C Full Load Test and ESW Pump Operability Test, Revision 16
ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9
Work Orders
04710258
04733734
71124.01
Procedures
EN-RP-105, Radiological Work Permits, Revision 16
EN-RP-106, Radiological Survey Documentation, Revision 7
EN-RP-106-01, Radiological Survey Guidelines, Revision 3
EN-RP-108, Radiation Protection Posting, Revision 18
EN-RP-121, Radioactive Material Control, Revision 13
RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1
RP-AA-300, Radiological Survey Program, Revision 15
RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9
RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30
RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3
RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential
or Actual Emergency, Revision 9
RP-AA-504, Unconditional Release Survey Method, Revision 14
RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for
Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,
Revision 4
Issue Reports
04102384
04096595
04080866
04066877
04063769
04053351


May 14, 2018
Miscellaneous
Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934,
S935, S1018, S1029
71124.02
Procedures
EN-RP-110, ALARA Program, Revision 14
EN-RP-110-01, ALARA Initiative Deferrals, Revision 1
EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4
EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7
EN-RP-110-05, ALARA Planning and Controls, Revision 3
RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals,
Revision 4
RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9
RP-AA-401, Operational ALARA Planning and Controls, Revision 22
RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8
Issue Reports
04053610
04060956
04071477
71124.03
Procedures
EN-RP-131, Air Sampling, Revision 15
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7
RP-AA-301, Radiological Air Sampling Program, Revision 10
RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8
RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8
RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6
Issue Reports
04061257
04089450
Miscellaneous
LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel
Monitoring Program and Bioassay Program, October 16, 2017
71124.04
Procedures
RP-AA-203-1001, Personnel Exposure Investigations, Revision 10
RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28
RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1
RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5
RP-AA-250, External Dose Assessment from Contamination, Revision 7
RP-AA-270, Prenatal Radiation Exposure, Revision 8


Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
Miscellaneous
NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016
71151
Procedure
EN-LI-114, Performance Indicator Process, Revision 7
71152
Procedures
OP-4, Circulating Water System, Revision 81
AOP-56, Intake Water Level Trouble, Revision 15
Issue Reports
03992624
04087426
Miscellaneous
EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21
Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level


SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018001
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PENNSLYVANIA 19406-2713


==Dear Mr. Hanson:==
May 14, 2018  
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 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


Mr. Bryan C. Hanson
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 05000333/2018001
Dear Mr. Hanson:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at the James
: [[contact::A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2]], 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.
report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
The NRC inspectors did not identify any finding or violation 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,


This letter, its enclosure, and your response (if any) will be made available for public inspection
/RA/
Anthony Dimitriadis, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Docket Number: 50-333
License Number: DPR-59
Enclosure:
Inspection Report 05000333/2018001
cc w/encl: Distribution via ListServ
ML18134A214
SUNSI Review
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
OFFICE
RI/DRP
RI/DRP
RI/DRP


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."
NAME
KKolaczyk/GStock for
via email
LCline via email
ADimitriadis


Sincerely,/RA/
DATE
Anthony Dimitriadis, Chief Reactor Projects Branch 5  
5/14/18
5/14/18
5/14/18


Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report


===Enclosure:===
Docket Number:
Inspection Report 05000333/2018001
50-333


cc w/encl: Distribution via ListServ
License Number:
DPR-59


ML18134A214 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRP RI/DRP RI/DRP NAME KKolaczyk/GStock for via email LCline via email ADimitriadis DATE 5/14/18 5/14/18 5/14/18
Report Number:
05000333/2018001


1 Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report
Enterprise Identifier: I-2018-001-0048


Docket Number: 50-333
Licensee:
Exelon Generation Company, LLC


License Number: DPR-59
Facility:
James A. FitzPatrick Nuclear Power Plant


Report Number: 05000333/2018001
Location:
Scriba, NY


Enterprise Identifier: I-2018-001-0048
Inspection Dates:
January 1, 2018 to March 31, 2018  


Licensee: Exelon Generation Company, LLC
Inspectors:  
: [[contact::K. Kolaczyk]], Senior Resident Inspector
: [[contact::G. Stock]], Resident Inspector
: [[contact::J. Ambrosini]], Senior Emergency Preparedness Inspector
: [[contact::T. Dunn]], Operations Engineer
: [[contact::J. Kulp]], Senior Reactor Inspector
: [[contact::R. Rolph]], Health Physicist
: [[contact::C. Safouri]], Project Engineer
: [[contact::A. Turilin]], Resident Inspector


Facility: James A. FitzPatrick Nuclear Power Plant
Approved By:
: [[contact::A. Dimitriadis]], Chief


Location: Scriba, NY
Reactor Projects Branch 5


Inspection Dates: January 1, 2018 to March 31, 2018
Division of Reactor Projects  
 
Inspectors: K. Kolaczyk, Senior Resident Inspector G. Stock, Resident Inspector J. Ambrosini, Senior Emergency Preparedness Inspector T. Dunn, Operations Engineer J. Kulp, Senior Reactor Inspector R. Rolph, Health Physicist C. Safouri, Project Engineer A. Turilin, Resident Inspector
 
Approved By: A. Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects  
 
2 SUMMARY 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


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.
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.
PLANT STATUS
 
FitzPatrick began the inspection period at rated thermal power. On February 25, 2018,
3 PLANT STATUS FitzPatrick began the inspection period at rated thermal power. On February 25, 2018, operators reduced power to 54 percent to perform scram time testing and turbine and main steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the inspection period.
operators reduced power to 54 percent to perform scram time testing and turbine and main
 
steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power
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."
March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the
 
inspection period.
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.
INSPECTION SCOPES
 
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
REACTOR SAFETY 71111.01 - Adverse Weather Protection  
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
71111.01 - Adverse Weather Protection
Impending Severe Weather (1 Sample)
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending extreme weather conditions prior to the unseasonably cold weather during the week of January 1, 2018.
The inspectors evaluated readiness for impending extreme weather conditions prior to the
 
unseasonably cold weather during the week of January 1, 2018.
71111.04 - Equipment Alignment Partial Walkdown (5 Samples)  
71111.04 - Equipment Alignment
 
Partial Walkdown (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems:  
The inspectors evaluated system configurations during partial walkdowns of the following
(1) Containment air dilution system following completion of maintenance activities conducted the week of January 15, 2018 (2) High pressure coolant injection (HPCI) system on January 18, 2018 (3) Drywell outage cooling system on January 26, 2018 (4) 'A' control room emergency ventilation system with 'B' train inoperable for relay maintenance on March 3, 2018 (5) 'B' spent fuel pool cooling system while the 'A' system was out of service for unplanned maintenance on March 22, 2018  
systems:  
 
(1) Containment air dilution system following completion of maintenance activities
4 Complete Walkdown (1 Sample)
conducted the week of January 15, 2018  
The inspectors evaluated system configurations during a complete walkdown of the drywell vent and purge and containment pressurization system on March 16, 2018.
(2) High pressure coolant injection (HPCI) system on January 18, 2018  
(3) Drywell outage cooling system on January 26, 2018  
(4) A control room emergency ventilation system with B train inoperable for relay
maintenance on March 3, 2018  
(5) B spent fuel pool cooling system while the A system was out of service for unplanned
maintenance on March 22, 2018  


71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection (6 Samples)
Complete Walkdown (1 Sample)
The inspectors evaluated fire protection program implementation in the following selected areas:  
The inspectors evaluated system configurations during a complete walkdown of the drywell
 
vent and purge and containment pressurization system on March 16, 2018.
(1) North cable tunnel fire zone CT-4 on January 3, 2018 (2) South cable tunnel fire zone CT-3 on January 3, 2018 (3) Relay room fire zone RR-1 on January 3, 2018 (4) East pipe tunnel fire zone RW-1 on January 18, 2018 (5) Battery room 'A' fire zone BR-1 on February 21, 2018 (6) Interim waste storage facility, fire area yard on March 28, 2018 71111.06 - Flood Protection Measures (1 Sample)
71111.05A/Q - Fire Protection Annual/Quarterly
Internal Flooding The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was removed for west crescent cooler maintenance, on March 9, 2018.
Quarterly Inspection (6 Samples)
 
The inspectors evaluated fire protection program implementation in the following selected
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification (1 Sample)
areas:  
The inspectors observed and evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level instrumentation on January 25, 2018.
(1) North cable tunnel fire zone CT-4 on January 3, 2018  
 
(2) South cable tunnel fire zone CT-3 on January 3, 2018  
Operator Performance (1 Sample)  
(3) Relay room fire zone RR-1 on January 3, 2018  
 
(4) East pipe tunnel fire zone RW-1 on January 18, 2018  
The inspectors observed 'B' turbine driv en feed pump taken to manual to perform operational decision making issue actions for motor gear unit sticking, and the performance of ST-5BB system 'B' channel function test on March 13, 2018.
(5) Battery room A fire zone BR-1 on February 21, 2018  
 
(6) Interim waste storage facility, fire area yard on March 28, 2018
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness (2 Samples)
71111.06 - Flood Protection Measures (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:  
Internal Flooding
(1) Structural monitoring program walkdown of the torus room on March 1, 2018
The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was
 
removed for west crescent cooler maintenance, on March 9, 2018.
5 (2) Structural monitoring program walkdown of reactor building refuel floor exterior on March 13, 2018 71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
Operator Requalification (1 Sample)
(1) 'C' battery room ventilation fan maintenance on January 26, 2018 (2) HPCI planned maintenance on February 13, 2018 (3) 'B' station air compressor planned maintenance on February 13, 2018 (4) 'A' and 'C' diesel generators planned maintenance the week of February 19, 2018 (5) Hardened containment vent tie-in to normal ventilation on February 27, 2018  
The inspectors observed and evaluated a simulator scenario including swapping of service
water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring
reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level
instrumentation on January 25, 2018.
Operator Performance (1 Sample)
The inspectors observed B turbine driven feed pump taken to manual to perform
operational decision making issue actions for motor gear unit sticking, and the performance
of ST-5BB system B channel function test on March 13, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated
with the following equipment and/or safety significant functions:  
(1) Structural monitoring program walkdown of the torus room on March 1, 2018  


(2) Structural monitoring program walkdown of reactor building refuel floor exterior on
March 13, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) C battery room ventilation fan maintenance on January 26, 2018
(2) HPCI planned maintenance on February 13, 2018
(3) B station air compressor planned maintenance on February 13, 2018
(4) A and C diesel generators planned maintenance the week of February 19, 2018
(5) Hardened containment vent tie-in to normal ventilation on February 27, 2018
71111.15 - Operability Determinations and Functionality Assessments (9 Samples)
71111.15 - Operability Determinations and Functionality Assessments (9 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:  
The inspectors evaluated the following operability determinations and functionality
(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018 (2) Standby gas treatment 'A' after excessive runtime without a charcoal sample on January 31, 2018 (3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018 (4) Bypass valve operability following intermittent partial open indication on February 12, 2018 (5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on February 15, 2018 (6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00 on February 23, 2018 (7) Past operability for the safety pump room with the fire dampers covered with herculite on February 27, 2018 (8) HPCI secured during surveillance test due to high flow on March 9, 2018 (9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018  
assessments:  
 
(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018  
(2) Standby gas treatment A after excessive runtime without a charcoal sample on
January 31, 2018  
(3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018  
(4) Bypass valve operability following intermittent partial open indication on
February 12, 2018  
(5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on
February 15, 2018  
(6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00
on February 23, 2018  
(7) Past operability for the safety pump room with the fire dampers covered with herculite on
February 27, 2018  
(8) HPCI secured during surveillance test due to high flow on March 9, 2018  
(9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018
71111.17T - Evaluations of Changes, Tests, and Experiments (29 Samples)
71111.17T - Evaluations of Changes, Tests, and Experiments (29 Samples)
The inspectors evaluated the following from March 26, 2018 to March 29, 2018:
The inspectors evaluated the following from March 26, 2018 to March 29, 2018:
10 CFR 50.59 Evaluations (1) JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0 (2) JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0 10 CFR 50.59 Screening/Applicability Determinations (1) 2452, PRCR: AOP-77, Revision 5 (2) 9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0 (3) 9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0 (4) 9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header Pressure, Revision 1 6 (5) 9000067365, 10MOV-89A/B Replacement, Revision 0 (6) 9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0 (7) 9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0 (8) 9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39, Revision 1 (9) AR04078735, Revision 37 of OP-55B, Revision 0 (10) DRN 16-00288, Revision 36 of OP-55B, Revision 0 (11) DRN-00156, OP-65B, Shutdown Operation, Revision 0 (12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0 (13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank Additions, Revision 0 (14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48, 49, 50, and 51 and Retire in Place, Revision 0 (15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position (Open), Revision 0 (16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0 (17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat Removal Service Water for Work on 10MOV-89B, Revision 0 (18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set Overvoltage Relay Setpoint, Revision 0 (19) EC 9000067410, Replace 3-stage Safety Relie f Valves with 2-stage Valves 2RV-71E and 2RV-71F, Revision 0 (20) EC 9000067794, Replacement of 92TIC-101B, Revision 0 (21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0 (22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0 (23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch Calibration, Revision 0 (24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0 (25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision, Revision 0 (26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0 (27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement 3.3.1.1.8 Frequency Change, Revision 0
CFR 50.59 Evaluations  
(1)
JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0  
(2)
JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0
CFR 50.59 Screening/Applicability Determinations  
(1)
2452, PRCR: AOP-77, Revision 5  
(2)
9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0  
(3)
9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0  
(4)
9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header
Pressure, Revision 1  


(5)
9000067365, 10MOV-89A/B Replacement, Revision 0
(6)
9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0
(7)
9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0
(8)
9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39,
Revision 1
(9)
AR04078735, Revision 37 of OP-55B, Revision 0
(10) DRN 16-00288, Revision 36 of OP-55B, Revision 0
(11) DRN-00156, OP-65B, Shutdown Operation, Revision 0
(12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0
(13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank
Additions, Revision 0
(14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48,
49, 50, and 51 and Retire in Place, Revision 0
(15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position
(Open), Revision 0
(16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0
(17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat
Removal Service Water for Work on 10MOV-89B, Revision 0
(18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set
Overvoltage Relay Setpoint, Revision 0
(19) EC 9000067410, Replace 3-stage Safety Relief Valves with 2-stage Valves 2RV-71E
and 2RV-71F, Revision 0
(20) EC 9000067794, Replacement of 92TIC-101B, Revision 0
(21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0
(22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0
(23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch
Calibration, Revision 0
(24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0
(25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision,
Revision 0
(26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0
(27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement
3.3.1.1.8 Frequency Change, Revision 0
71111.19 - Post Maintenance Testing (7 Samples)
71111.19 - Post Maintenance Testing (7 Samples)
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:  
The inspectors evaluated post maintenance testing for the following maintenance/repair
(1) 76-P4 run preventive maintenance on February 12, 2018 (2) HPCI system turbine steam supply drain trap replacement on February 13, 2018 (3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018 (4) 'B' turbine driven feed pump motor gear unit replacement and testing on February 28, 2018 (5) 'B' control room emergency ventilation system relay maintenance on March 13, 2018 (6) 'A' residual heat removal maintenance window on March 22, 2018 (7) 'A' emergency diesel generator circulating oil pump coupling replacement and realignment on March 28, 2018  
activities:  
(1) 76-P4 run preventive maintenance on February 12, 2018  
(2) HPCI system turbine steam supply drain trap replacement on February 13, 2018  
(3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018  
(4) B turbine driven feed pump motor gear unit replacement and testing on February 28,
2018  
(5) B control room emergency ventilation system relay maintenance on March 13, 2018  
(6) A residual heat removal maintenance window on March 22, 2018  
(7) A emergency diesel generator circulating oil pump coupling replacement and
realignment on March 28, 2018  


7 71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (3 Samples)  
Routine (3 Samples)  
(1) ST-9BA, Emergency Diesel Generator 'A' and 'C' Full Load Test and Emergency Service Water Pump Operability Test, on January 29, 2017 (2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018 (3) ST-9R, Emergency Diesel Generator 'A' and 'C' System Quick-Start Operability Test and Offsite Circuit Verification, on February 5, 2018  
(1) ST-9BA, Emergency Diesel Generator A and C Full Load Test and Emergency Service
 
Water Pump Operability Test, on January 29, 2017  
(2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018  
(3) ST-9R, Emergency Diesel Generator A and C System Quick-Start Operability Test and
Offsite Circuit Verification, on February 5, 2018
Inservice (2 Samples)  
Inservice (2 Samples)  
(1) ST-2AL , 'A' Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018 (2) ST-25BB, Containment Atmosphere Dilution System 'B' Quarterly Operability Test (IST),
(1) ST-2AL, A Residual Heat Removal Quarterly Operability Test (IST), on January 2,
on January 19, 2018 71114.06 - Drill Evaluation Drill/Training Evolution (1 Sample)
2018  
The inspectors evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel level instrumentation which led to a site area emergency declaration, on January 25,  
(2) ST-25BB, Containment Atmosphere Dilution System B Quarterly Operability Test (IST),
 
on January 19, 2018
2018. RADIATION SAFETY 71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (1 Sample)
71114.06 - Drill Evaluation
The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite workers or members of the public. The inspectors evaluated assessments and controls for new radiological hazards.
Drill/Training Evolution (1 Sample)
 
The inspectors evaluated a simulator scenario including swapping of service water
Instructions to Workers (1 Sample)  
pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor
 
pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel
level instrumentation which led to a site area emergency declaration, on January 25,
2018.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (1 Sample)
The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite
workers or members of the public. The inspectors evaluated assessments and controls for
new radiological hazards.
Instructions to Workers (1 Sample)
The inspectors evaluated instructions provided to workers.
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 were tested for loose surface contamination.


Contamination and Radioactive Material Control (1 Sample)
Radiological Hazards Control and Work Coverage (1 Sample)
 
The inspectors evaluated in-plant radiological conditions and performed independent
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 were tested for loose surface contamination.
radiation measurements during facility walk-downs and observation of radiological work
 
activities. The inspectors assessed whether posted surveys, radiation work permits, worker
8 Radiological Hazards Control and Work Coverage (1 Sample)
radiological briefings, and the use of continuous air monitoring and dosimetry monitoring
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 whether posted surveys, radiation work permits, worker radiological briefings, and the use of continuous air monitoring and dosimetry monitoring were consistent with the present conditions.
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)
 
The inspectors evaluated radiation worker and radiation protection technician radiological
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)  
 
The inspectors evaluated radiation worker and radiation protection technician radiological  
 
performance.
performance.
 
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)  
Verification of Dose Estimates and Exposure Tracking Systems (1 Sample)
 
The inspectors evaluated dose estimates and exposure tracking.
The inspectors evaluated dose estimates and exposure tracking.
 
Radiation Worker Performance (1 Sample)
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
Self-Contained Breathing Apparatus for Emergency Use (1 Sample)
The inspectors evaluated Exelons self-contained breathing apparatus (SCBA) program at
FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during
emergencies, procedures, maintenance and test records, the refilling and transporting of
SCBA air bottles, SCBA mask size availability, and the qualifications of personnel
performing service and repair of this equipment.
71124.04 - Occupational Dose Assessment
Source Term Characterization (1 Sample)
The inspectors evaluated Exelons source term characterization.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated Exelons performance for special dosimetric situations.


71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Self-Contained Breathing Apparatus for Emergency Use (1 Sample)
OTHER ACTIVITIES - BASELINE
The inspectors evaluated Exelon's self-contained breathing apparatus (SCBA) program at FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during emergencies, procedures, maintenance and test records, the refilling and transporting of SCBA air bottles, SCBA mask size availability, and the qualifications of personnel performing service and repair of this equipment.
71151 - Performance Indicator Verification (2 Samples)
 
The inspectors verified licensee performance indicators submittals listed below for the
71124.04 - Occupational Dose Assessment
 
Source Term Characterization (1 Sample)
 
The inspectors evaluated Exelon's s ource term characterization.
 
Special Dosimetric Situations (1 Sample)
 
The inspectors evaluated Exelon's performance for special dosimetric situations.
 
9 OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification (2 Samples)
The inspectors verified licensee performance indicators submittals listed below for the  
 
period from January 1, 2017 through December 31, 2017:  
period from January 1, 2017 through December 31, 2017:  
 
(1)
(1) MS05, Safety System Functional Failures (2) IE03, Unplanned Power Changes 71152 - Problem Identification and Resolution  
MS05, Safety System Functional Failures  
 
(2)
IE03, Unplanned Power Changes
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (1 Sample)
Annual Follow-up of Selected Issues (1 Sample)
The inspectors reviewed Exelon's implementation of its corrective action program related to the following issues:  
The inspectors reviewed Exelons implementation of its corrective action program related to
 
the following issues:  
(1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level INSPECTION RESULTS Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level  
(1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level
 
INSPECTION RESULTS
On January 23, 2016, during power ascension following a downpower for hydraulic control unit maintenance, the station experienced a reduction in intake level. Operators initially attempted to perform a rapid downpower with the intent of securing two circulating water pumps. After securing the first circulating water pump, intake level momentarily began to rise and then continued to lower. When intake level decreased to the procedurally required minimal intake level, operators inserted a manual scram. Exelon determined the cause of the scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent occurrence, but is expected during winter months during specific meteorological conditions. FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010. However, only in 1996 did the event result in a unit scram, which resulted in a number of corrective actions, including new procedures to combat intake level issues. Since the 2004 -
Observations
2010 events did not result in a reactor scram, the evaluations for the events were not as in depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were missed opportunities to not just mitigate the bui ld-up of frazil ice but evaluate and eliminate the potential. Another factor that potentially affected how rapidly the January 2016 progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased the flow rate through the intake, which can expedite frazil ice formation in the intake system.
71152
 
Annual Follow-up of Selected Issues
Exelon noted this item in the root cause investigation that was completed following the 2016 scram, and implemented several corrective actions to address this issue.
Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level
 
On January 23, 2016, during power ascension following a downpower for hydraulic control
The inspectors reviewed the 2016 Exelon root cause analysis documented under IR 03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes were that the procedures for mitigating the impact of frazil ice formation were ineffective, and that station leadership accepted mitigating actions vice elimination for issues that potentially jeopardized safe plant operation. Previous analysis has discovered under certain circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root 10 cause and the contributing causes, Exelon pursued corrective actions to eliminate the possibility of frazil ice build-up which included removing two of the eight bar racks on the intake structure as corrective actions. The removal of the two bar racks will allow for sufficient intake flow should the remaining racks be impeded by frazil ice.
unit maintenance, the station experienced a reduction in intake level. Operators initially
 
attempted to perform a rapid downpower with the intent of securing two circulating water
The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake level issues which would appear to demonstrate that the removal of the bar racks has improved FitzPatrick's ability to mitigate frazil ice buildup. Further corrective actions include installing an intake level rate of change alarm, revising procedures to increase lake level monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The inspectors concluded that Exelon's response and corrective actions for this event were commensurate with the safety significance, were timely, and included appropriate compensatory measures.
pumps. After securing the first circulating water pump, intake level momentarily began to rise
 
and then continued to lower. When intake level decreased to the procedurally required
EXIT MEETINGS AND DEBRIEFS
minimal intake level, operators inserted a manual scram. Exelon determined the cause of the
 
scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent
The inspectors verified no proprietary information was retained or documented in this report.
occurrence, but is expected during winter months during specific meteorological conditions.
 
FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010.
On May 2, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
However, only in 1996 did the event result in a unit scram, which resulted in a number of
 
corrective actions, including new procedures to combat intake level issues. Since the 2004 -
11 DOCUMENTS REVIEWED
2010 events did not result in a reactor scram, the evaluations for the events were not as in
 
depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were
71111.01
missed opportunities to not just mitigate the build-up of frazil ice but evaluate and eliminate
 
the potential. Another factor that potentially affected how rapidly the January 2016
Issue Report 04087668
progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased
 
the flow rate through the intake, which can expedite frazil ice formation in the intake system.
71111.04 Procedures CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4 DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4 FB-35E, Flow Diagram Control Room Area Se rvice and Chilled Water System 70, Revision 38 FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70, Revision 42 FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45 OP-13F, RHR- Fuel Pool Cooling Assist, Revision 11 OP-30 Fuel Pool Cooling and Cleanup System, Revision 43
Exelon noted this item in the root cause investigation that was completed following the 2016
 
scram, and implemented several corrective actions to address this issue.
Issue Report 04088760
The inspectors reviewed the 2016 Exelon root cause analysis documented under IR
 
03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes
Drawings FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65 FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary Cooling System 68, Revision 4 FM-18A, Flow Diagram, Drywell Inerting C.A.D. and Purge System, Revision 57 FM-18B, Flow Diagram, Drywell Inerting C.A.D. Purge and Containment DP System 27, Revision 44 FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75 FM-48A, Flow Diagram Standby Gas Tr eatment System 01-125, Revision 32 71111.05 Procedures JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3 PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0 PFP-PWR04 Battery Room Complex, EL 272', Fire Area/Zone BR-1, Br-2, BR-3, BR-4, Revision 2 PFP-PWR37, East Pipe Tunnel Elevation 258' Fire Area/Zone XIX/RW-1, Revision 002
were that the procedures for mitigating the impact of frazil ice formation were ineffective, and
 
that station leadership accepted mitigating actions vice elimination for issues that potentially
71111.06
jeopardized safe plant operation. Previous analysis has discovered under certain
 
circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root  
Procedures AP-16.14, Hazard Barrier Controls, Revision 7 CC-AA-201, Plant Barrier Control Program, Revision 12
 
71111.12 Procedures ST-5BB, APRM System 'B' Channel Functional Test, Revision 2 12 OP-AA-103-102, Watch-Standing Practices, Revision 18 OP-AA-108-112, Plant Status and Configuration, Revision 10
 
Issue Report 04114489
 
Miscellaneous JAF-1-2017-0609, Revision 1
 
71111.12
 
Procedures ER-AA-450, Structures Monitoring, Revision 6 JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 Issue Report 04114448
 
71111.13 Procedures AP-10.10, On-Line Risk Assessment, Revision 9 EN-WM-104, On-Line Risk Assessment, Revision 12 OP-AA-108-117, Protected Equipment Program, Revision 4
 
71111.15 Procedures FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42 OP-AA-108-115, Operability Determinations, Revision 20 RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19 ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66 ST-40D, Daily Surveillance and Channel Check, Revision 112
 
Issue Reports 03992613 04071131 04081869 04088480 04088760 04096823 04097327 04103156 04103690 04112832
 
Work Order 4712278 Drawings Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42 FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75
 
71111.19 Procedures HU-AA-104-101, Procedure Use and Adherence, Revision 5 ST-2AN, RHR Loop A Monthly Operability Test, Revision 16 13 ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33 ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10 WC-AA-111, Surveillance Program Requirements, Revision 5 Issue Reports 04097327 04098786 04103334 04107062 04114905 04119383
 
Work Orders 4691285 4731093 82691241 04765320
 
04666902-32
 
Miscellaneous Engineering Change 50781 71111.22 Procedures MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14 ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37 ST-9BA, EDG 'A' and 'C' Full Load Test and ESW Pump Operability Test, Revision 16 ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9
 
Work Orders 04710258 04733734 71124.01 Procedures EN-RP-105, Radiological Work Permits, Revision 16 EN-RP-106, Radiological Survey Documentation, Revision 7 EN-RP-106-01, Radiological Survey Guidelines, Revision 3 EN-RP-108, Radiation Protection Posting, Revision 18 EN-RP-121, Radioactive Material Control, Revision 13 RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1 RP-AA-300, Radiological Survey Program, Revision 15 RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9 RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30 RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3 RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential or Actual Emergency, Revision 9 RP-AA-504, Unconditional Release Survey Method, Revision 14 RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,
 
Revision 4 Issue Reports 04102384 04096595 04080866 04066877 04063769 04053351


14 Miscellaneous Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:
cause and the contributing causes, Exelon pursued corrective actions to eliminate the
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934, S935, S1018, S1029 71124.02 Procedures EN-RP-110, ALARA Program, Revision 14 EN-RP-110-01, ALARA Initiative Deferrals, Revision 1 EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4 EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7 EN-RP-110-05, ALARA Planning and Controls, Revision 3 RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals, Revision 4 RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9 RP-AA-401, Operational ALARA Planning and Controls, Revision 22 RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8
possibility of frazil ice build-up which included removing two of the eight bar racks on the
intake structure as corrective actions. The removal of the two bar racks will allow for sufficient
intake flow should the remaining racks be impeded by frazil ice.
The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake
level issues which would appear to demonstrate that the removal of the bar racks has
improved FitzPatricks ability to mitigate frazil ice buildup. Further corrective actions include
installing an intake level rate of change alarm, revising procedures to increase lake level
monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile
Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The
inspectors concluded that Exelons response and corrective actions for this event were
commensurate with the safety significance, were timely, and included appropriate
compensatory measures.


Issue Reports 04053610 04060956
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.


04071477 71124.03
On May 2, 2018, the inspectors presented the quarterly resident inspection results to
Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.  


Procedures EN-RP-131, Air Sampling, Revision 15 EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7 RP-AA-301, Radiological Air Sampling Program, Revision 10 RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8 RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8 RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6
DOCUMENTS REVIEWED
71111.01
Issue Report
04087668
71111.04
Procedures
CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4
DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4
FB-35E, Flow Diagram Control Room Area Service and Chilled Water System 70, Revision 38
FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70,
Revision 42
FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45
OP-13F, RHR-Fuel Pool Cooling Assist, Revision 11
OP-30 Fuel Pool Cooling and Cleanup System, Revision 43
Issue Report
04088760
Drawings
FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65
FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary
Cooling System 68, Revision 4
FM-18A, Flow Diagram, Drywell Inerting C.
: [[contact::A.D. and Purge System]], Revision 57
FM-18B, Flow Diagram, Drywell Inerting C.
: [[contact::A.D. Purge and Containment DP System 27]],
Revision 44
FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75
FM-48A, Flow Diagram Standby Gas Treatment System 01-125, Revision 32
71111.05
Procedures
JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3
PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0
PFP-PWR04 Battery Room Complex, EL 272, Fire Area/Zone BR-1, Br-2, BR-3, BR-4,
Revision 2
PFP-PWR37, East Pipe Tunnel Elevation 258 Fire Area/Zone XIX/RW-1, Revision 002
71111.06
Procedures
AP-16.14, Hazard Barrier Controls, Revision 7
CC-AA-201, Plant Barrier Control Program, Revision 12
71111.12
Procedures
ST-5BB, APRM System B Channel Functional Test, Revision 2


Issue Reports 04061257 04089450
OP-AA-103-102, Watch-Standing Practices, Revision 18
OP-AA-108-112, Plant Status and Configuration, Revision 10
Issue Report
04114489
Miscellaneous
JAF-1-2017-0609, Revision 1
71111.12
Procedures
ER-AA-450, Structures Monitoring, Revision 6
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6
Issue Report
04114448
71111.13
Procedures
AP-10.10, On-Line Risk Assessment, Revision 9
EN-WM-104, On-Line Risk Assessment, Revision 12
OP-AA-108-117, Protected Equipment Program, Revision 4
71111.15
Procedures
FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42
OP-AA-108-115, Operability Determinations, Revision 20
RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19
ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66
ST-40D, Daily Surveillance and Channel Check, Revision 112
Issue Reports
03992613
04071131
04081869
04088480
04088760
04096823
04097327
04103156
04103690
04112832
Work Order
4712278
Drawings
Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42
FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75
71111.19
Procedures
HU-AA-104-101, Procedure Use and Adherence, Revision 5
ST-2AN, RHR Loop A Monthly Operability Test, Revision 16


Miscellaneous LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel Monitoring Program and Bioassay Program, October 16, 2017 71124.04 Procedures RP-AA-203-1001, Personnel Exposure Investigations, Revision 10 RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28 RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1 RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5 RP-AA-250, External Dose Assessment from Contamination, Revision 7 RP-AA-270, Prenatal Radiation Exposure, Revision 8 15 Miscellaneous NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 71151 Procedure EN-LI-114, Performance Indicator Process, Revision 7 71152 Procedures OP-4, Circulating Water System, Revision 81 AOP-56, Intake Water Level Trouble, Revision 15
ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33
ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10
WC-AA-111, Surveillance Program Requirements, Revision 5
Issue Reports
04097327
04098786
04103334
04107062
04114905
04119383
Work Orders
4691285
4731093
2691241
04765320
04666902-32
Miscellaneous
Engineering Change 50781
71111.22
Procedures
MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14
ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37
ST-9BA, EDG A and C Full Load Test and ESW Pump Operability Test, Revision 16
ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9
Work Orders
04710258
04733734
71124.01
Procedures
EN-RP-105, Radiological Work Permits, Revision 16
EN-RP-106, Radiological Survey Documentation, Revision 7
EN-RP-106-01, Radiological Survey Guidelines, Revision 3
EN-RP-108, Radiation Protection Posting, Revision 18
EN-RP-121, Radioactive Material Control, Revision 13
RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1
RP-AA-300, Radiological Survey Program, Revision 15
RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9
RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30
RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3
RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential
or Actual Emergency, Revision 9
RP-AA-504, Unconditional Release Survey Method, Revision 14
RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for
Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,
Revision 4
Issue Reports
04102384
04096595
04080866
04066877
04063769
04053351


Issue Reports 03992624 04087426
Miscellaneous
Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934,
S935, S1018, S1029
71124.02
Procedures
EN-RP-110, ALARA Program, Revision 14
EN-RP-110-01, ALARA Initiative Deferrals, Revision 1
EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4
EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7
EN-RP-110-05, ALARA Planning and Controls, Revision 3
RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals,
Revision 4
RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9
RP-AA-401, Operational ALARA Planning and Controls, Revision 22
RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8
Issue Reports
04053610
04060956
04071477
71124.03
Procedures
EN-RP-131, Air Sampling, Revision 15
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7
RP-AA-301, Radiological Air Sampling Program, Revision 10
RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8
RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8
RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6
Issue Reports
04061257
04089450
Miscellaneous
LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel
Monitoring Program and Bioassay Program, October 16, 2017
71124.04
Procedures
RP-AA-203-1001, Personnel Exposure Investigations, Revision 10
RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28
RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1
RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5
RP-AA-250, External Dose Assessment from Contamination, Revision 7
RP-AA-270, Prenatal Radiation Exposure, Revision 8


Miscellaneous EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21 Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level
Miscellaneous
NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016
71151
Procedure
EN-LI-114, Performance Indicator Process, Revision 7
71152
Procedures
OP-4, Circulating Water System, Revision 81
AOP-56, Intake Water Level Trouble, Revision 15
Issue Reports
03992624
04087426
Miscellaneous
EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21
Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level
}}
}}

Latest revision as of 21:54, 5 January 2025

Integrated Inspection Report 05000333/2018001
ML18134A214
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 05/14/2018
From: Anthony Dimitriadis
NRC/RGN-I/DRP/PB5
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
Dimitriadis A
References
IR 2018001
Download: ML18134A214 (17)
v • d • e


Text

May 14, 2018

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018001

Dear Mr. Hanson:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 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 finding or violation 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 05000333/2018001

Inspection Report

Docket Number:

50-333

License Number:

DPR-59

Report Number:

05000333/2018001

Enterprise Identifier: I-2018-001-0048

Licensee:

Exelon Generation Company, LLC

Facility:

James A. FitzPatrick Nuclear Power Plant

Location:

Scriba, NY

Inspection Dates:

January 1, 2018 to March 31, 2018

Inspectors:

K. Kolaczyk, Senior Resident Inspector

G. Stock, Resident Inspector

J. Ambrosini, Senior Emergency Preparedness Inspector

T. Dunn, Operations Engineer

J. Kulp, Senior Reactor Inspector

R. Rolph, Health Physicist

C. Safouri, Project Engineer

A. Turilin, Resident Inspector

Approved By:

A. Dimitriadis, Chief

Reactor Projects Branch 5

Division of Reactor Projects

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 rated thermal power. On February 25, 2018, operators reduced power to 54 percent to perform scram time testing and turbine and main steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power March 1, 2018, and the plant 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 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

71111.01 - Adverse Weather Protection

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending extreme weather conditions prior to the unseasonably cold weather during the week of January 1, 2018.

71111.04 - Equipment Alignment

Partial Walkdown (5 Samples)

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

(1) Containment air dilution system following completion of maintenance activities conducted the week of January 15, 2018
(2) High pressure coolant injection (HPCI) system on January 18, 2018
(3) Drywell outage cooling system on January 26, 2018
(4) A control room emergency ventilation system with B train inoperable for relay maintenance on March 3, 2018
(5) B spent fuel pool cooling system while the A system was out of service for unplanned maintenance on March 22, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the drywell vent and purge and containment pressurization system on March 16, 2018.

71111.05A/Q - Fire Protection Annual/Quarterly

Quarterly Inspection (6 Samples)

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

(1) North cable tunnel fire zone CT-4 on January 3, 2018
(2) South cable tunnel fire zone CT-3 on January 3, 2018
(3) Relay room fire zone RR-1 on January 3, 2018
(4) East pipe tunnel fire zone RW-1 on January 18, 2018
(5) Battery room A fire zone BR-1 on February 21, 2018
(6) Interim waste storage facility, fire area yard on March 28, 2018

71111.06 - Flood Protection Measures

Main article: IP 71111.06

Internal Flooding

The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was removed for west crescent cooler maintenance, on March 9, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level instrumentation on January 25, 2018.

Operator Performance (1 Sample)

The inspectors observed B turbine driven feed pump taken to manual to perform operational decision making issue actions for motor gear unit sticking, and the performance of ST-5BB system B channel function test on March 13, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (2 Samples)

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

(1) Structural monitoring program walkdown of the torus room on March 1, 2018
(2) Structural monitoring program walkdown of reactor building refuel floor exterior on March 13, 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) C battery room ventilation fan maintenance on January 26, 2018
(2) HPCI planned maintenance on February 13, 2018
(3) B station air compressor planned maintenance on February 13, 2018
(4) A and C diesel generators planned maintenance the week of February 19, 2018
(5) Hardened containment vent tie-in to normal ventilation on February 27, 2018

71111.15 - Operability Determinations and Functionality Assessments

Main article: IP 71111.15

The inspectors evaluated the following operability determinations and functionality assessments:

(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018
(2) Standby gas treatment A after excessive runtime without a charcoal sample on January 31, 2018
(3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018
(4) Bypass valve operability following intermittent partial open indication on February 12, 2018
(5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on February 15, 2018
(6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00 on February 23, 2018
(7) Past operability for the safety pump room with the fire dampers covered with herculite on February 27, 2018
(8) HPCI secured during surveillance test due to high flow on March 9, 2018
(9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018

71111.17T - Evaluations of Changes, Tests, and Experiments

Main article: IP 71111.17

The inspectors evaluated the following from March 26, 2018 to March 29, 2018:

10 CFR 50.59 Evaluations

(1) JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0
(2) JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0

10 CFR 50.59 Screening/Applicability Determinations

(1)2452, PRCR: AOP-77, Revision 5 (2)

===9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0 (3)9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0 (4)9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header Pressure, Revision 1 (5)9000067365, 10MOV-89A/B Replacement, Revision 0 (6)9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0 (7)9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0 (8)9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39, Revision 1

(9) AR04078735, Revision 37 of OP-55B, Revision 0
(10) DRN 16-00288, Revision 36 of OP-55B, Revision 0
(11) DRN-00156, OP-65B, Shutdown Operation, Revision 0
(12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0
(13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank Additions, Revision 0
(14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48, 49, 50, and 51 and Retire in Place, Revision 0
(15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position (Open), Revision 0
(16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0
(17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat Removal Service Water for Work on 10MOV-89B, Revision 0
(18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set Overvoltage Relay Setpoint, Revision 0
(19) EC 9000067410, Replace 3-stage Safety Relief Valves with 2-stage Valves 2RV-71E and 2RV-71F, Revision 0
(20) EC 9000067794, Replacement of 92TIC-101B, Revision 0
(21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0
(22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0
(23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch Calibration, Revision 0
(24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0
(25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision, Revision 0
(26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0
(27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement 3.3.1.1.8 Frequency Change, Revision 0

71111.19 - Post Maintenance Testing

Main article: IP 71111.19

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

(1) 76-P4 run preventive maintenance on February 12, 2018
(2) HPCI system turbine steam supply drain trap replacement on February 13, 2018
(3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018
(4) B turbine driven feed pump motor gear unit replacement and testing on February 28, 2018
(5) B control room emergency ventilation system relay maintenance on March 13, 2018
(6) A residual heat removal maintenance window on March 22, 2018
(7) A emergency diesel generator circulating oil pump coupling replacement and realignment on March 28, 2018

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine

Main article: IP 71111.22
(1) ST-9BA, Emergency Diesel Generator A and C Full Load Test and Emergency Service Water Pump Operability Test, on January 29, 2017
(2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018
(3) ST-9R, Emergency Diesel Generator A and C System Quick-Start Operability Test and Offsite Circuit Verification, on February 5, 2018

Inservice===

Main article: IP 90000
(1) ST-2AL, A Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018
(2) ST-25BB, Containment Atmosphere Dilution System B Quarterly Operability Test (IST),on January 19, 2018

71114.06 - Drill Evaluation

Drill/Training Evolution (1 Sample)

The inspectors evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel level instrumentation which led to a site area emergency declaration, on January 25,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (1 Sample)

The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite workers or members of the public. 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 were 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 whether posted surveys, radiation work permits, worker radiological briefings, and the use of continuous air monitoring and dosimetry monitoring 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 (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.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

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

The inspectors evaluated Exelons self-contained breathing apparatus (SCBA) program at FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during emergencies, procedures, maintenance and test records, the refilling and transporting of SCBA air bottles, SCBA mask size availability, and the qualifications of personnel performing service and repair of this equipment.

71124.04 - Occupational Dose Assessment

Source Term Characterization (1 Sample)

The inspectors evaluated Exelons source term characterization.

Special Dosimetric Situations (1 Sample)

The inspectors evaluated Exelons performance for special dosimetric situations.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification

Main article: IP 71151

The inspectors verified licensee performance indicators submittals listed below for the period from January 1, 2017 through December 31, 2017:

(1) MS05, Safety System Functional Failures
(2) IE03, Unplanned Power Changes

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (1 Sample)

The inspectors reviewed Exelons implementation of its corrective action program related to the following issues:

(1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level

INSPECTION RESULTS

Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level

On January 23, 2016, during power ascension following a downpower for hydraulic control unit maintenance, the station experienced a reduction in intake level. Operators initially attempted to perform a rapid downpower with the intent of securing two circulating water pumps. After securing the first circulating water pump, intake level momentarily began to rise and then continued to lower. When intake level decreased to the procedurally required minimal intake level, operators inserted a manual scram. Exelon determined the cause of the scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent occurrence, but is expected during winter months during specific meteorological conditions.

FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010.

However, only in 1996 did the event result in a unit scram, which resulted in a number of corrective actions, including new procedures to combat intake level issues. Since the 2004 - 2010 events did not result in a reactor scram, the evaluations for the events were not as in depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were missed opportunities to not just mitigate the build-up of frazil ice but evaluate and eliminate the potential. Another factor that potentially affected how rapidly the January 2016 progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased the flow rate through the intake, which can expedite frazil ice formation in the intake system.

Exelon noted this item in the root cause investigation that was completed following the 2016 scram, and implemented several corrective actions to address this issue.

The inspectors reviewed the 2016 Exelon root cause analysis documented under IR 03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes were that the procedures for mitigating the impact of frazil ice formation were ineffective, and that station leadership accepted mitigating actions vice elimination for issues that potentially jeopardized safe plant operation. Previous analysis has discovered under certain circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root cause and the contributing causes, Exelon pursued corrective actions to eliminate the possibility of frazil ice build-up which included removing two of the eight bar racks on the intake structure as corrective actions. The removal of the two bar racks will allow for sufficient intake flow should the remaining racks be impeded by frazil ice.

The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake level issues which would appear to demonstrate that the removal of the bar racks has improved FitzPatricks ability to mitigate frazil ice buildup. Further corrective actions include installing an intake level rate of change alarm, revising procedures to increase lake level monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The inspectors concluded that Exelons response and corrective actions for this event were commensurate with the safety significance, were timely, and included appropriate compensatory measures.

EXIT MEETINGS AND DEBRIEFS

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

On May 2, 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

71111.01

Issue Report

04087668

71111.04

Procedures

CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4

DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4

FB-35E, Flow Diagram Control Room Area Service and Chilled Water System 70, Revision 38

FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70,

Revision 42

FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45

OP-13F, RHR-Fuel Pool Cooling Assist, Revision 11

OP-30 Fuel Pool Cooling and Cleanup System, Revision 43

Issue Report

04088760

Drawings

FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65

FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary

Cooling System 68, Revision 4

FM-18A, Flow Diagram, Drywell Inerting C.

A.D. and Purge System, Revision 57

FM-18B, Flow Diagram, Drywell Inerting C.

A.D. Purge and Containment DP System 27,

Revision 44

FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75

FM-48A, Flow Diagram Standby Gas Treatment System 01-125, Revision 32

71111.05

Procedures

JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3

PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0

PFP-PWR04 Battery Room Complex, EL 272, Fire Area/Zone BR-1, Br-2, BR-3, BR-4,

Revision 2

PFP-PWR37, East Pipe Tunnel Elevation 258 Fire Area/Zone XIX/RW-1, Revision 002

71111.06

Procedures

AP-16.14, Hazard Barrier Controls, Revision 7

CC-AA-201, Plant Barrier Control Program, Revision 12

71111.12

Procedures

ST-5BB, APRM System B Channel Functional Test, Revision 2

OP-AA-103-102, Watch-Standing Practices, Revision 18

OP-AA-108-112, Plant Status and Configuration, Revision 10

Issue Report

04114489

Miscellaneous

JAF-1-2017-0609, Revision 1

71111.12

Procedures

ER-AA-450, Structures Monitoring, Revision 6

JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6

Issue Report

04114448

71111.13

Procedures

AP-10.10, On-Line Risk Assessment, Revision 9

EN-WM-104, On-Line Risk Assessment, Revision 12

OP-AA-108-117, Protected Equipment Program, Revision 4

71111.15

Procedures

FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42

OP-AA-108-115, Operability Determinations, Revision 20

RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19

ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66

ST-40D, Daily Surveillance and Channel Check, Revision 112

Issue Reports

03992613

04071131

04081869

04088480

04088760

04096823

04097327

04103156

04103690

04112832

Work Order 4712278

Drawings

Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42

FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75

71111.19

Procedures

HU-AA-104-101, Procedure Use and Adherence, Revision 5

ST-2AN, RHR Loop A Monthly Operability Test, Revision 16

ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33

ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10

WC-AA-111, Surveillance Program Requirements, Revision 5

Issue Reports

04097327

04098786

04103334

04107062

04114905

04119383

Work Orders

4691285

4731093

2691241

04765320

04666902-32

Miscellaneous

Engineering Change 50781

71111.22

Procedures

MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14

ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37

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

ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9

Work Orders

04710258

04733734

71124.01

Procedures

EN-RP-105, Radiological Work Permits, Revision 16

EN-RP-106, Radiological Survey Documentation, Revision 7

EN-RP-106-01, Radiological Survey Guidelines, Revision 3

EN-RP-108, Radiation Protection Posting, Revision 18

EN-RP-121, Radioactive Material Control, Revision 13

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

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

RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9

RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30

RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3

RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential

or Actual Emergency, Revision 9

RP-AA-504, Unconditional Release Survey Method, Revision 14

RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for

Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,

Revision 4

Issue Reports

04102384

04096595

04080866

04066877

04063769

04053351

Miscellaneous

Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:

S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934,

S935, S1018, S1029

71124.02

Procedures

EN-RP-110, ALARA Program, Revision 14

EN-RP-110-01, ALARA Initiative Deferrals, Revision 1

EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4

EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7

EN-RP-110-05, ALARA Planning and Controls, Revision 3

RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals,

Revision 4

RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9

RP-AA-401, Operational ALARA Planning and Controls, Revision 22

RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8

Issue Reports

04053610

04060956

04071477

71124.03

Procedures

EN-RP-131, Air Sampling, Revision 15

EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7

RP-AA-301, Radiological Air Sampling Program, Revision 10

RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8

RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8

RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6

Issue Reports

04061257

04089450

Miscellaneous

LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel

Monitoring Program and Bioassay Program, October 16, 2017

71124.04

Procedures

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

RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28

RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1

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

RP-AA-250, External Dose Assessment from Contamination, Revision 7

RP-AA-270, Prenatal Radiation Exposure, Revision 8

Miscellaneous

NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016

71151

Procedure

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

71152

Procedures

OP-4, Circulating Water System, Revision 81

AOP-56, Intake Water Level Trouble, Revision 15

Issue Reports

03992624

04087426

Miscellaneous

EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21

Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BOULEVARD, SUITE 100

KING OF PRUSSIA, PENNSLYVANIA 19406-2713

May 14, 2018

Mr. Bryan C. Hanson

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 05000333/2018001

Dear Mr. Hanson:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection

at the James

A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 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 finding or violation 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 05000333/2018001

cc w/encl: Distribution via ListServ

ML18134A214

SUNSI Review

Non-Sensitive

Sensitive

Publicly Available

Non-Publicly Available

OFFICE

RI/DRP

RI/DRP

RI/DRP

NAME

KKolaczyk/GStock for

via email

LCline via email

ADimitriadis

DATE

5/14/18

5/14/18

5/14/18

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Number:

50-333

License Number:

DPR-59

Report Number:

05000333/2018001

Enterprise Identifier: I-2018-001-0048

Licensee:

Exelon Generation Company, LLC

Facility:

James A. FitzPatrick Nuclear Power Plant

Location:

Scriba, NY

Inspection Dates:

January 1, 2018 to March 31, 2018

Inspectors:

K. Kolaczyk, Senior Resident Inspector
G. Stock, Resident Inspector
J. Ambrosini, Senior Emergency Preparedness Inspector
T. Dunn, Operations Engineer
J. Kulp, Senior Reactor Inspector
R. Rolph, Health Physicist
C. Safouri, Project Engineer
A. Turilin, Resident Inspector

Approved By:

A. Dimitriadis, Chief

Reactor Projects Branch 5

Division of Reactor Projects

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 rated thermal power. On February 25, 2018,

operators reduced power to 54 percent to perform scram time testing and turbine and main

steam isolation valve stroke time testing. Operators returned FitzPatrick to rated thermal power

March 1, 2018, and the plant 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 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

71111.01 - Adverse Weather Protection

Impending Severe Weather (1 Sample)

The inspectors evaluated readiness for impending extreme weather conditions prior to the

unseasonably cold weather during the week of January 1, 2018.

71111.04 - Equipment Alignment

Partial Walkdown (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following

systems:

(1) Containment air dilution system following completion of maintenance activities

conducted the week of January 15, 2018

(2) High pressure coolant injection (HPCI) system on January 18, 2018

(3) Drywell outage cooling system on January 26, 2018

(4) A control room emergency ventilation system with B train inoperable for relay

maintenance on March 3, 2018

(5) B spent fuel pool cooling system while the A system was out of service for unplanned

maintenance on March 22, 2018

Complete Walkdown (1 Sample)

The inspectors evaluated system configurations during a complete walkdown of the drywell

vent and purge and containment pressurization system on March 16, 2018.

71111.05A/Q - Fire Protection Annual/Quarterly

Quarterly Inspection (6 Samples)

The inspectors evaluated fire protection program implementation in the following selected

areas:

(1) North cable tunnel fire zone CT-4 on January 3, 2018

(2) South cable tunnel fire zone CT-3 on January 3, 2018

(3) Relay room fire zone RR-1 on January 3, 2018

(4) East pipe tunnel fire zone RW-1 on January 18, 2018

(5) Battery room A fire zone BR-1 on February 21, 2018

(6) Interim waste storage facility, fire area yard on March 28, 2018

71111.06 - Flood Protection Measures (1 Sample)

Internal Flooding

The inspectors evaluated internal flooding mitigation protections on floor plug 4, which was

removed for west crescent cooler maintenance, on March 9, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance

Operator Requalification (1 Sample)

The inspectors observed and evaluated a simulator scenario including swapping of service

water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring

reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level

instrumentation on January 25, 2018.

Operator Performance (1 Sample)

The inspectors observed B turbine driven feed pump taken to manual to perform

operational decision making issue actions for motor gear unit sticking, and the performance

of ST-5BB system B channel function test on March 13, 2018.

71111.12 - Maintenance Effectiveness

Routine Maintenance Effectiveness (2 Samples)

The inspectors evaluated the effectiveness of routine maintenance activities associated

with the following equipment and/or safety significant functions:

(1) Structural monitoring program walkdown of the torus room on March 1, 2018

(2) Structural monitoring program walkdown of reactor building refuel floor exterior on

March 13, 2018

71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)

The inspectors evaluated the risk assessments for the following planned and emergent

work activities:

(1) C battery room ventilation fan maintenance on January 26, 2018

(2) HPCI planned maintenance on February 13, 2018

(3) B station air compressor planned maintenance on February 13, 2018

(4) A and C diesel generators planned maintenance the week of February 19, 2018

(5) Hardened containment vent tie-in to normal ventilation on February 27, 2018

71111.15 - Operability Determinations and Functionality Assessments (9 Samples)

The inspectors evaluated the following operability determinations and functionality

assessments:

(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018

(2) Standby gas treatment A after excessive runtime without a charcoal sample on

January 31, 2018

(3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018

(4) Bypass valve operability following intermittent partial open indication on

February 12, 2018

(5) 70MOD-108A control room vent exhaust fan 4A outlet isolation damper not closed on

February 15, 2018

(6) Alternate shutdown panel isolation switches due to Part 21 notification NRC-21-2016-00

on February 23, 2018

(7) Past operability for the safety pump room with the fire dampers covered with herculite on

February 27, 2018

(8) HPCI secured during surveillance test due to high flow on March 9, 2018

(9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018

71111.17T - Evaluations of Changes, Tests, and Experiments (29 Samples)

The inspectors evaluated the following from March 26, 2018 to March 29, 2018:

CFR 50.59 Evaluations

(1)

JAF-SE-17-01, Main Turbine Steam Valve Testing Periodicity Change, Revision 0

(2)

JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0

CFR 50.59 Screening/Applicability Determinations

(1)

2452, PRCR: AOP-77, Revision 5

(2)

9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0

(3)

9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0

(4)

9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header

Pressure, Revision 1

(5)

9000067365, 10MOV-89A/B Replacement, Revision 0

(6)

9000068099, Modify DHR Fan Control Circuits For Reverse Operation, Revision 0

(7)

9000068175, 92MOD-150A(OP) Replacement with New Model Operator, Revision 0

(8)

9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39,

Revision 1

(9)

AR04078735, Revision 37 of OP-55B, Revision 0

(10) DRN 16-00288, Revision 36 of OP-55B, Revision 0

(11) DRN-00156, OP-65B, Shutdown Operation, Revision 0

(12) EC 50942, Install Fuses in Remote DC Ammeter Circuits from 71BCB-2A, Revision 0

(13) EC 57625, Changes to the JAF Facility to Support the NYPSA 345kV Capacitor Bank

Additions, Revision 0

(14) EC 61046, Disconnect Power and Communication to Smoke Detection Zones 47, 48,

49, 50, and 51 and Retire in Place, Revision 0

(15) EC 61755, Lift Lead for TCV-121B to Ensure Valve Remains in the Fail-Safe Position

(Open), Revision 0

(16) EC 620605, Hardened Containment Vent System Phase 2, Revision 0

(17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat

Removal Service Water for Work on 10MOV-89B, Revision 0

(18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set

Overvoltage Relay Setpoint, Revision 0

(19) EC 9000067410, Replace 3-stage Safety Relief Valves with 2-stage Valves 2RV-71E

and 2RV-71F, Revision 0

(20) EC 9000067794, Replacement of 92TIC-101B, Revision 0

(21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0

(22) JAF-SCN-18-008, 125 Vdc Station Battery and Charger Surveillance Test, Revision 0

(23) JAF-SCN-18-021, IMP-93.1, Emergency Diesel Generator Pressure Switch

Calibration, Revision 0

(24) JAF-SCN-18-026, Cut and Cap Body Drain Lines, Revision 0

(25) JAF-SCR-18-017, AOP-56, Intake Water Level Trouble Procedure Revision,

Revision 0

(26) OP-22, Diesel Generator Emergency Power, Revision 62, Revision 0

(27) TRM 17-003, Technical Requirements Manual, Appendix I, Surveillance Requirement 3.3.1.1.8 Frequency Change, Revision 0

71111.19 - Post Maintenance Testing (7 Samples)

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

activities:

(1) 76-P4 run preventive maintenance on February 12, 2018

(2) HPCI system turbine steam supply drain trap replacement on February 13, 2018

(3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018

(4) B turbine driven feed pump motor gear unit replacement and testing on February 28,

2018

(5) B control room emergency ventilation system relay maintenance on March 13, 2018

(6) A residual heat removal maintenance window on March 22, 2018

(7) A emergency diesel generator circulating oil pump coupling replacement and

realignment on March 28, 2018

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Routine (3 Samples)

(1) ST-9BA, Emergency Diesel Generator A and C Full Load Test and Emergency Service

Water Pump Operability Test, on January 29, 2017

(2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018

(3) ST-9R, Emergency Diesel Generator A and C System Quick-Start Operability Test and

Offsite Circuit Verification, on February 5, 2018

Inservice (2 Samples)

(1) ST-2AL, A Residual Heat Removal Quarterly Operability Test (IST), on January 2,

2018

(2) ST-25BB, Containment Atmosphere Dilution System B Quarterly Operability Test (IST),

on January 19, 2018

71114.06 - Drill Evaluation

Drill/Training Evolution (1 Sample)

The inspectors evaluated a simulator scenario including swapping of service water

pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor

pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel

level instrumentation which led to a site area emergency declaration, on January 25,

2018.

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (1 Sample)

The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite

workers or members of the public. 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 were 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 whether posted surveys, radiation work permits, worker

radiological briefings, and the use of continuous air monitoring and dosimetry monitoring

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 (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.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

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

The inspectors evaluated Exelons self-contained breathing apparatus (SCBA) program at

FitzPatrick to include surveillance records for three SCBAs staged in-plant for use during

emergencies, procedures, maintenance and test records, the refilling and transporting of

SCBA air bottles, SCBA mask size availability, and the qualifications of personnel

performing service and repair of this equipment.

71124.04 - Occupational Dose Assessment

Source Term Characterization (1 Sample)

The inspectors evaluated Exelons source term characterization.

Special Dosimetric Situations (1 Sample)

The inspectors evaluated Exelons performance for special dosimetric situations.

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification (2 Samples)

The inspectors verified licensee performance indicators submittals listed below for the

period from January 1, 2017 through December 31, 2017:

(1)

MS05, Safety System Functional Failures

(2)

IE03, Unplanned Power Changes

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (1 Sample)

The inspectors reviewed Exelons implementation of its corrective action program related to

the following issues:

(1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level

INSPECTION RESULTS

Observations

71152

Annual Follow-up of Selected Issues

Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level

On January 23, 2016, during power ascension following a downpower for hydraulic control

unit maintenance, the station experienced a reduction in intake level. Operators initially

attempted to perform a rapid downpower with the intent of securing two circulating water

pumps. After securing the first circulating water pump, intake level momentarily began to rise

and then continued to lower. When intake level decreased to the procedurally required

minimal intake level, operators inserted a manual scram. Exelon determined the cause of the

scram was frazil ice build-up on the bar racks at the intake structure, which is an infrequent

occurrence, but is expected during winter months during specific meteorological conditions.

FitzPatrick has experienced frazil ice build-up previously in 1996, 2004, 2008, and 2010.

However, only in 1996 did the event result in a unit scram, which resulted in a number of

corrective actions, including new procedures to combat intake level issues. Since the 2004 -

2010 events did not result in a reactor scram, the evaluations for the events were not as in

depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were

missed opportunities to not just mitigate the build-up of frazil ice but evaluate and eliminate

the potential. Another factor that potentially affected how rapidly the January 2016

progressed, was the re-tubing of the FitzPatrick main condensers in 2015, which increased

the flow rate through the intake, which can expedite frazil ice formation in the intake system.

Exelon noted this item in the root cause investigation that was completed following the 2016

scram, and implemented several corrective actions to address this issue.

The inspectors reviewed the 2016 Exelon root cause analysis documented under IR

03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes

were that the procedures for mitigating the impact of frazil ice formation were ineffective, and

that station leadership accepted mitigating actions vice elimination for issues that potentially

jeopardized safe plant operation. Previous analysis has discovered under certain

circumstances that the bar rack heaters were incapable of preventing frazil ice. Given the root

cause and the contributing causes, Exelon pursued corrective actions to eliminate the

possibility of frazil ice build-up which included removing two of the eight bar racks on the

intake structure as corrective actions. The removal of the two bar racks will allow for sufficient

intake flow should the remaining racks be impeded by frazil ice.

The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake

level issues which would appear to demonstrate that the removal of the bar racks has

improved FitzPatricks ability to mitigate frazil ice buildup. Further corrective actions include

installing an intake level rate of change alarm, revising procedures to increase lake level

monitoring during high frazil ice likelihood conditions, and to communicate with Nine Mile

Point Unit 1 and 2 and take action if either plant experiences indications of intake icing. The

inspectors concluded that Exelons response and corrective actions for this event were

commensurate with the safety significance, were timely, and included appropriate

compensatory measures.

EXIT MEETINGS AND DEBRIEFS

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

On May 2, 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

71111.01

Issue Report

04087668

71111.04

Procedures

CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4

DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4

FB-35E, Flow Diagram Control Room Area Service and Chilled Water System 70, Revision 38

FB-45A, Flow Diagram Control and Relay Rooms Heating and Ventilation System 70,

Revision 42

FM-19B Flow Diagram Fuel Pool Cleanup and Cooling System, Revision 45

OP-13F, RHR-Fuel Pool Cooling Assist, Revision 11

OP-30 Fuel Pool Cooling and Cleanup System, Revision 43

Issue Report

04088760

Drawings

FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65

FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary

Cooling System 68, Revision 4

FM-18A, Flow Diagram, Drywell Inerting C.

A.D. and Purge System, Revision 57

FM-18B, Flow Diagram, Drywell Inerting C.

A.D. Purge and Containment DP System 27,

Revision 44

FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75

FM-48A, Flow Diagram Standby Gas Treatment System 01-125, Revision 32

71111.05

Procedures

JAF Fire Hazards Analysis JAF-RPT-04-00478, Revision 3

PFP-OUT25, Interim Waste Storage Facility Fire Area/Yard, Revision 0

PFP-PWR04 Battery Room Complex, EL 272, Fire Area/Zone BR-1, Br-2, BR-3, BR-4,

Revision 2

PFP-PWR37, East Pipe Tunnel Elevation 258 Fire Area/Zone XIX/RW-1, Revision 002

71111.06

Procedures

AP-16.14, Hazard Barrier Controls, Revision 7

CC-AA-201, Plant Barrier Control Program, Revision 12

71111.12

Procedures

ST-5BB, APRM System B Channel Functional Test, Revision 2

OP-AA-103-102, Watch-Standing Practices, Revision 18

OP-AA-108-112, Plant Status and Configuration, Revision 10

Issue Report

04114489

Miscellaneous

JAF-1-2017-0609, Revision 1

71111.12

Procedures

ER-AA-450, Structures Monitoring, Revision 6

JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6

Issue Report

04114448

71111.13

Procedures

AP-10.10, On-Line Risk Assessment, Revision 9

EN-WM-104, On-Line Risk Assessment, Revision 12

OP-AA-108-117, Protected Equipment Program, Revision 4

71111.15

Procedures

FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42

OP-AA-108-115, Operability Determinations, Revision 20

RP-RESP-03.02, SGTS, CREVAS, and TSCVASS Testing, Revision 19

ST-4N, HPCI Quick-Start, Inservice, and Transient Monitoring Test (IST), Revision 66

ST-40D, Daily Surveillance and Channel Check, Revision 112

Issue Reports

03992613

04071131

04081869

04088480

04088760

04096823

04097327

04103156

04103690

04112832

Work Order 4712278

Drawings

Control and Relay Rooms Hearing and Ventilation System Flow Diagram 70, Revision 42

FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75

71111.19

Procedures

HU-AA-104-101, Procedure Use and Adherence, Revision 5

ST-2AN, RHR Loop A Monthly Operability Test, Revision 16

ST-18, Main Control Room Emergency Fan and Damper Operability Test, Revision 33

ST-76AD, East Diesel Fire Pump 76-P4 Performance Test, Revision 10

WC-AA-111, Surveillance Program Requirements, Revision 5

Issue Reports

04097327

04098786

04103334

04107062

04114905

04119383

Work Orders

4691285

4731093

2691241

04765320

04666902-32

Miscellaneous

Engineering Change 50781

71111.22

Procedures

MST-071.16, 24V Instrument Battery Quarterly Surveillance Test, Revision 14

ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 37

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

ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9

Work Orders

04710258

04733734

71124.01

Procedures

EN-RP-105, Radiological Work Permits, Revision 16

EN-RP-106, Radiological Survey Documentation, Revision 7

EN-RP-106-01, Radiological Survey Guidelines, Revision 3

EN-RP-108, Radiation Protection Posting, Revision 18

EN-RP-121, Radioactive Material Control, Revision 13

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

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

RP-AA-376, Radiological Posting, Labeling, and Markings, Revision 9

RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 30

RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3

RP-AA-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential

or Actual Emergency, Revision 9

RP-AA-504, Unconditional Release Survey Method, Revision 14

RP-AA-503-F-01, Unconditional Release Instructions Using the Small Articles Monitor for

Personal Items Used in the Radiologically Controlled Area and in a Contaminated Area,

Revision 4

Issue Reports

04102384

04096595

04080866

04066877

04063769

04053351

Miscellaneous

Source leak tests on April 10, 2017 and October 5, 2017 for the following sources:

S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934,

S935, S1018, S1029

71124.02

Procedures

EN-RP-110, ALARA Program, Revision 14

EN-RP-110-01, ALARA Initiative Deferrals, Revision 1

EN-RP-110-03, Collective Radiation Exposure Reduction Guidelines, Revision 4

EN-RP-110-04, Radiation Protection Risk Assessment Process, Revision 7

EN-RP-110-05, ALARA Planning and Controls, Revision 3

RP-AA-400-1001, Establishing Collective Radiation Exposure Annual Business Plan Goals,

Revision 4

RP-AA-400-1004, Emergent Dose Control and Authorization, Revision 9

RP-AA-401, Operational ALARA Planning and Controls, Revision 22

RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8

Issue Reports

04053610

04060956

04071477

71124.03

Procedures

EN-RP-131, Air Sampling, Revision 15

EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7

RP-AA-301, Radiological Air Sampling Program, Revision 10

RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 8

RP-AA-825, Maintenance, Care and Inspection of Respiratory Protective Equipment, Revision 8

RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6

Issue Reports

04061257

04089450

Miscellaneous

LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel

Monitoring Program and Bioassay Program, October 16, 2017

71124.04

Procedures

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

RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 28

RP-AA-215, Calculating and Crediting Dose from Noble Gas Exposure, Revision 1

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

RP-AA-250, External Dose Assessment from Contamination, Revision 7

RP-AA-270, Prenatal Radiation Exposure, Revision 8

Miscellaneous

NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016

71151

Procedure

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

71152

Procedures

OP-4, Circulating Water System, Revision 81

AOP-56, Intake Water Level Trouble, Revision 15

Issue Reports

03992624

04087426

Miscellaneous

EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21

Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level

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