IR 05000333/2018001: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION May 14, 2018 | ||
==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, | |||
Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Anthony Dimitriadis, Chief Reactor Projects Branch 5 | Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59 | ||
Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59 | |||
===Enclosure:=== | ===Enclosure:=== | ||
Inspection Report 05000333/2018001 | Inspection Report 05000333/2018001 | ||
==Inspection Report== | ==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 Enclosure | |||
=SUMMARY= | |||
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at | |||
FitzPatrick by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. | |||
No findings or more-than-minor violations were identified. | No findings or more-than-minor violations were identified. | ||
=PLANT STATUS= | =PLANT STATUS= | ||
===March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the inspection period. | ===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== | ==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, | 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess | |||
==REACTOR SAFETY== | ==REACTOR SAFETY== | ||
| Line 103: | Line 72: | ||
: (2) High pressure coolant injection (HPCI) system on January 18, 2018 | : (2) High pressure coolant injection (HPCI) system on January 18, 2018 | ||
: (3) Drywell outage cooling system on January 26, 2018 | : (3) Drywell outage cooling system on January 26, 2018 | ||
: (4) | : (4) A control room emergency ventilation system with B train inoperable for relay maintenance on March 3, 2018 | ||
: (5) | : (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 | The inspectors evaluated system configurations during a complete walkdown of the drywell | ||
=====71111.05A/Q - Fire Protection Annual/Quarterly== | ===vent and purge and containment pressurization system on March 16, 2018. | ||
==71111.05A/Q - Fire Protection Annual/Quarterly== | |||
===Quarterly Inspection=== | ===Quarterly Inspection=== | ||
| Line 117: | Line 88: | ||
: (3) Relay room fire zone RR-1 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 | : (4) East pipe tunnel fire zone RW-1 on January 18, 2018 | ||
: (5) Battery room | : (5) Battery room A fire zone BR-1 on February 21, 2018 | ||
: (6) Interim waste storage facility, fire area yard on March 28, 2018 | : (6) Interim waste storage facility, fire area yard on March 28, 2018 | ||
| Line 134: | Line 105: | ||
Operator Performance (1 Sample)=== | 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== | ==71111.12 - Maintenance Effectiveness== | ||
| Line 151: | Line 123: | ||
The inspectors evaluated the risk assessments for the following planned and emergent work activities: | The inspectors evaluated the risk assessments for the following planned and emergent work activities: | ||
: (1) | : (1) C battery room ventilation fan maintenance on January 26, 2018 | ||
: (2) HPCI planned maintenance on February 13, 2018 | : (2) HPCI planned maintenance on February 13, 2018 | ||
: (3) | : (3) B station air compressor planned maintenance on February 13, 2018 | ||
: (4) | : (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 | : (5) Hardened containment vent tie-in to normal ventilation on February 27, 2018 | ||
| Line 162: | Line 134: | ||
The inspectors evaluated the following operability determinations and functionality assessments: | 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 | : (1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018 | ||
: (2) Standby gas treatment | : (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 | : (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 | : (4) Bypass valve operability following intermittent partial open indication on February 12, 2018 | ||
| Line 169: | Line 141: | ||
: (7) Past operability for the safety pump room with the fire dampers covered with herculite on February 27, 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 | : (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 | : (9) 70MOD-110A indicated dual with control room vent placed in purge on March 29, 2018 | ||
===71111.17T - Evaluations of Changes, Tests, and Experiments=== | ===71111.17T - Evaluations of Changes, Tests, and Experiments=== | ||
| Line 196: | Line 168: | ||
: (17) EC 66088, Provide Isolation Between Secondary Containment and Residual Heat Removal Service Water for Work on 10MOV-89B, 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 | : (18) EC 66125, Evaluate Increasing the Reactor Protection System Motor-Generator Set Overvoltage Relay Setpoint, Revision 0 | ||
: (19) EC 9000067410, Replace 3-stage Safety | : (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 | : (20) EC 9000067794, Replacement of 92TIC-101B, Revision 0 | ||
: (21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0 | : (21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0 | ||
| Line 214: | Line 186: | ||
: (2) HPCI system turbine steam supply drain trap replacement on February 13, 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 | : (3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018 | ||
: (4) | : (4) B turbine driven feed pump motor gear unit replacement and testing on February 28, 2018 | ||
: (5) | : (5) B control room emergency ventilation system relay maintenance on March 13, 2018 | ||
: (6) | : (6) A residual heat removal maintenance window on March 22, 2018 | ||
: (7) | : (7) A emergency diesel generator circulating oil pump coupling replacement and realignment on March 28, 2018 | ||
==71111.22 - Surveillance Testing== | ==71111.22 - Surveillance Testing== | ||
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Routine=== | Routine=== | ||
{{IP sample|IP=IP 71111.19|count=3}} | {{IP sample|IP=IP 71111.19|count=3}} | ||
: (1) ST-9BA, Emergency Diesel Generator | : (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 | : (2) MST-071.16, Instrument Battery Quarterly Surveillance Test, on February 8, 2018 | ||
: (3) ST-9R, Emergency Diesel Generator | : (3) ST-9R, Emergency Diesel Generator A and C System Quick-Start Operability Test and Offsite Circuit Verification, on February 5, 2018 Inservice === | ||
Inservice === | |||
{{IP sample|IP=IP 71111.17|count=2}} | {{IP sample|IP=IP 71111.17|count=2}} | ||
: (1) ST-2AL , | : (1) ST-2AL , A Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018 | ||
: (2) ST-25BB, Containment Atmosphere Dilution System | : (2) ST-25BB, Containment Atmosphere Dilution System B Quarterly Operability Test (IST), | ||
on January 19, 2018 | |||
==71114.06 - Drill Evaluation== | ==71114.06 - Drill Evaluation== | ||
| Line 238: | Line 209: | ||
{{IP sample|IP=IP 71114.06|count=1}} | {{IP sample|IP=IP 71114.06|count=1}} | ||
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 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== | ==RADIATION SAFETY== | ||
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Instructions to Workers (1 Sample)=== | Instructions to Workers (1 Sample)=== | ||
The inspectors evaluated instructions provided to workers. | |||
===The inspectors | ===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)=== | Radiological Hazards Control and Work Coverage (1 Sample)=== | ||
The inspectors evaluated in-plant radiological conditions and performed independent | The inspectors evaluated in-plant radiological conditions and performed independent | ||
===radiological briefings, and the use of continuous air monitoring and dosimetry monitoring were consistent with the present conditions. | ===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)=== | 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)=== | 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== | ||
| Line 280: | Line 253: | ||
Radiation Worker Performance (1 Sample)=== | Radiation Worker Performance (1 Sample)=== | ||
The inspectors evaluated radiation worker and radiation protection technician performance. | |||
=== | =====71124.03 - In-Plant Airborne Radioactivity Control and Mitigation== | ||
==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation== | |||
===Self-Contained Breathing Apparatus for Emergency Use=== | ===Self-Contained Breathing Apparatus for Emergency Use=== | ||
{{IP sample|IP=IP 71124.03|count=1}} | {{IP sample|IP=IP 71124.03|count=1}} | ||
The inspectors evaluated | 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== | ==71124.04 - Occupational Dose Assessment== | ||
| Line 295: | Line 267: | ||
{{IP sample|IP=IP 71124.04|count=1}} | {{IP sample|IP=IP 71124.04|count=1}} | ||
The inspectors evaluated | The inspectors evaluated Exelons source term characterization. | ||
Special Dosimetric Situations (1 Sample)=== | Special Dosimetric Situations (1 Sample)=== | ||
The inspectors evaluated Exelons performance for special dosimetric situations. | |||
The inspectors evaluated | |||
==OTHER ACTIVITIES - BASELINE== | ==OTHER ACTIVITIES - BASELINE== | ||
| Line 305: | Line 276: | ||
===71151 - Performance Indicator Verification === | ===71151 - Performance Indicator Verification === | ||
{{IP sample|IP=IP 71151|count=2}} | {{IP sample|IP=IP 71151|count=2}} | ||
The inspectors verified licensee performance indicators submittals listed below for the | 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) MS05, Safety System Functional Failures | : (1) MS05, Safety System Functional Failures | ||
: (2) IE03, Unplanned Power Changes | : (2) IE03, Unplanned Power Changes | ||
| Line 316: | Line 285: | ||
{{IP sample|IP=IP 71152|count=1}} | {{IP sample|IP=IP 71152|count=1}} | ||
The inspectors reviewed | 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 | : (1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level | ||
==INSPECTION RESULTS== | ==INSPECTION RESULTS== | ||
Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level | 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 | 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. | 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. | ||
| Line 329: | Line 300: | ||
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 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 | 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== | ==EXIT MEETINGS AND DEBRIEFS== | ||
| Line 341: | Line 312: | ||
Issue Report | Issue Report | ||
04087668 | 04087668 | ||
71111.04 | 71111.04 | ||
CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4 DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4 | Procedures | ||
FB-35E, Flow Diagram Control Room Area | 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-13F, RHR- Fuel Pool Cooling Assist, Revision 11 | ||
OP-30 Fuel Pool Cooling and Cleanup System, Revision 43 | OP-30 Fuel Pool Cooling and Cleanup System, Revision 43 | ||
Issue Report | Issue Report | ||
04088760 | 04088760 | ||
Drawings FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65 | Drawings | ||
FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary Cooling System 68, Revision 4 FM-18A, Flow Diagram, Drywell Inerting C. | 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 | : [[contact::A.D. and Purge System]], Revision 57 | ||
FM-18B, Flow Diagram, Drywell Inerting C. | 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 | : [[contact::A.D. Purge and Containment DP System 27]], | ||
Revision 44 | |||
71111.05 | FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75 | ||
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 | 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 | 71111.06 | ||
Procedures AP-16.14, Hazard Barrier Controls, Revision 7 | Procedures | ||
CC-AA-201, Plant Barrier Control Program, Revision 12 | AP-16.14, Hazard Barrier Controls, Revision 7 | ||
CC-AA-201, Plant Barrier Control Program, Revision 12 | |||
71111.12 | 71111.12 | ||
OP-AA-103-102, Watch-Standing Practices, Revision 18 OP-AA-108-112, Plant Status and Configuration, Revision 10 | 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 | Issue Report | ||
04114489 | 04114489 | ||
Miscellaneous | Miscellaneous | ||
JAF-1-2017-0609, Revision 1 | JAF-1-2017-0609, Revision 1 | ||
71111.12 | 71111.12 | ||
Procedures ER-AA-450, Structures Monitoring, Revision 6 | Procedures | ||
ER-AA-450, Structures Monitoring, Revision 6 | |||
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 | JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 | ||
Issue Report | Issue Report | ||
04114448 | 04114448 | ||
71111.13 | 71111.13 | ||
Procedures | |||
AP-10.10, On-Line Risk Assessment, Revision 9 | |||
EN-WM-104, On-Line Risk Assessment, Revision 12 | EN-WM-104, On-Line Risk Assessment, Revision 12 | ||
OP-AA-108-117, Protected Equipment Program, Revision 4 | OP-AA-108-117, Protected Equipment Program, Revision 4 | ||
71111.15 | |||
71111.15 | Procedures | ||
ST-40D, Daily Surveillance and Channel Check, Revision 112 | FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42 | ||
OP-AA-108-115, Operability Determinations, Revision 20 | |||
Issue Reports 03992613 | 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 | Work Order | ||
4712278 | 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 | FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75 | ||
71111.19 | 71111.19 | ||
Procedures | |||
HU-AA-104-101, Procedure Use and Adherence, Revision 5 | HU-AA-104-101, Procedure Use and Adherence, Revision 5 | ||
ST-2AN, RHR Loop A Monthly Operability Test, Revision 16 | 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 | 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 | WC-AA-111, Surveillance Program Requirements, Revision 5 | ||
Issue Reports 04097327 | Issue Reports | ||
04114905 | 04097327 04098786 04103334 04107062 | ||
04114905 04119383 | |||
Work Orders 4691285 | Work Orders | ||
04666902-32 | 4691285 4731093 82691241 04765320 | ||
04666902-32 | |||
Miscellaneous | |||
71111.22 | Engineering Change 50781 | ||
ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9 | 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 | Work Orders | ||
04710258 04733734 | 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-106-01, Radiological Survey Guidelines, Revision 3 | ||
EN-RP-108, Radiation Protection Posting, Revision 18 | EN-RP-108, Radiation Protection Posting, Revision 18 | ||
EN-RP-121, Radioactive Material Control, Revision 13 | 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-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, Controls for High and Locked High Radiation Areas, Revision 30 | ||
RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3 | 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-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential | ||
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, | 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 | Revision 4 | ||
Issue Reports 04102384 | Issue Reports | ||
04102384 04096595 04080866 04066877 | |||
04063769 04053351 | |||
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934, S935, S1018, S1029 | Miscellaneous | ||
71124.02 | 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 | 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-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-401, Operational ALARA Planning and Controls, Revision 22 | ||
RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8 | RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8 | ||
Issue Reports | Issue Reports | ||
04053610 04060956 | 04053610 | ||
04071477 | 04060956 | ||
Procedures EN-RP-131, Air Sampling, Revision 15 | 04071477 | ||
71124.03 | |||
Procedures | |||
EN-RP-131, Air Sampling, Revision 15 | |||
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7 | 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-AA-301, Radiological Air Sampling Program, Revision 10 | ||
RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6 | 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 | Issue Reports | ||
04061257 04089450 | 04061257 | ||
Miscellaneous LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel Monitoring Program and Bioassay Program, October 16, 2017 | 04089450 | ||
71124.04 | 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-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-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-250, External Dose Assessment from Contamination, Revision 7 | ||
RP-AA-270, Prenatal Radiation Exposure, Revision 8 | RP-AA-270, Prenatal Radiation Exposure, Revision 8 | ||
Miscellaneous NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 | Miscellaneous | ||
71151 | NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 | ||
71152 | 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 | AOP-56, Intake Water Level Trouble, Revision 15 | ||
Issue Reports | Issue Reports | ||
03992624 04087426 | 03992624 | ||
Miscellaneous EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21 | 04087426 | ||
Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level | Miscellaneous | ||
EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21 | |||
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSLYVANIA | 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 | May 14, 2018 | ||
Mr. Bryan C. Hanson | Mr. Bryan C. Hanson | ||
Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road | Senior Vice President, Exelon Generation Company, LLC | ||
Warrenville, IL | President and Chief Nuclear Officer, Exelon Nuclear | ||
4300 Winfield Road | |||
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018001 | Warrenville, IL 60555 | ||
Dear Mr. Hanson: | 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 | On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection | ||
at the James | 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 | : [[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 | 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, | and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room | ||
Sincerely, | in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public | ||
Inspections, Exemptions, Requests for Withholding. | |||
Anthony Dimitriadis, Chief Reactor Projects Branch 5 | Sincerely, | ||
/RA/ | |||
Anthony Dimitriadis, Chief | |||
Reactor Projects Branch 5 | |||
Division of Reactor Projects | Division of Reactor Projects | ||
Docket Number: | Docket Number: 50-333 | ||
License Number: | License Number: DPR-59 | ||
Enclosure: | Enclosure: | ||
Inspection Report 05000333/2018001 | Inspection Report 05000333/2018001 | ||
cc w/encl: Distribution via ListServ | |||
cc w/encl: | |||
ML18134A214 | ML18134A214 | ||
Non-Sensitive Publicly Available | |||
SUNSI Review | SUNSI Review | ||
Sensitive Non-Publicly Available | |||
OFFICE RI/DRP RI/DRP RI/DRP | |||
OFFICE RI/DRP RI/DRP RI/DRP | KKolaczyk/GStock for | ||
NAME LCline via email ADimitriadis | |||
via email | |||
DATE 5/14/18 5/14/18 5/14/18 | |||
U.S. NUCLEAR REGULATORY COMMISSION | |||
Inspection Report | 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: | |||
: [[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 | |||
Approved By: | |||
: [[contact::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 | overseeing the safe operation of commercial nuclear power reactors. Refer to | ||
https://www.nrc.gov/reactors/operating/oversight.html | https://www.nrc.gov/reactors/operating/oversight.html for more information. | ||
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, | |||
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 | 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 | March 1, 2018, and the plant remained at or near rated thermal power for the remainder of the | ||
inspection period. | inspection period. | ||
INSPECTION SCOPES | INSPECTION SCOPES | ||
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with | Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in | ||
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, | effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with | ||
Identification and Resolution. | their attached revision histories are located on the public website at http://www.nrc.gov/reading- | ||
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess | 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. | with Commission rules and regulations, license conditions, site procedures, and standards. | ||
REACTOR SAFETY | REACTOR SAFETY | ||
71111.01 - Adverse Weather Protection | 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 | 71111.04 - Equipment Alignment | ||
Partial Walkdown (5 Samples) | 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 | ||
(3) Drywell outage cooling system on January 26, 2018 | systems: | ||
(4) | (1) Containment air dilution system following completion of maintenance activities | ||
maintenance on March 3, 2018 (5) | conducted the week of January 15, 2018 | ||
maintenance on March 22, 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) | 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. | 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 | 71111.05A/Q - Fire Protection Annual/Quarterly | ||
Quarterly Inspection (6 Samples) | Quarterly Inspection (6 Samples) | ||
The inspectors evaluated fire protection program implementation in the following selected | The inspectors evaluated fire protection program implementation in the following selected | ||
areas: | areas: | ||
(1) North cable tunnel fire zone CT-4 on January 3, 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 | (2) South cable tunnel fire zone CT-3 on January 3, 2018 | ||
(5) Battery room | (3) Relay room fire zone RR-1 on January 3, 2018 | ||
(6) Interim waste storage facility, fire area yard on March 28, 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) | 71111.06 - Flood Protection Measures (1 Sample) | ||
Internal Flooding | Internal Flooding | ||
| Line 554: | Line 614: | ||
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance | 71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance | ||
Operator Requalification (1 Sample) | 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 | 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 | reactor pressure vessel blowdown, and the loss of all reactor pressure vessel level | ||
instrumentation on January 25, 2018. | instrumentation on January 25, 2018. | ||
Operator Performance (1 Sample) | Operator Performance (1 Sample) | ||
The inspectors observed | 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 | of ST-5BB system B channel function test on March 13, 2018. | ||
71111.12 - Maintenance Effectiveness | 71111.12 - Maintenance Effectiveness | ||
Routine Maintenance Effectiveness | Routine Maintenance Effectiveness (2 Samples) | ||
(2 Samples) | The inspectors evaluated the effectiveness of routine maintenance activities associated | ||
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions: | 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 | March 13, 2018 | ||
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples) | 71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples) | ||
The inspectors evaluated the risk assessments for the following planned and emergent | The inspectors evaluated the risk assessments for the following planned and emergent | ||
work activities: | work activities: | ||
(1) C battery room ventilation fan maintenance on January 26, 2018 | |||
(2) HPCI planned maintenance on February 13, 2018 (3) | (2) HPCI planned maintenance on February 13, 2018 | ||
(5) Hardened containment vent tie-in to normal ventilation on February 27, 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 | The inspectors evaluated the following operability determinations and functionality | ||
assessments: | assessments: | ||
(1) HPCI system with steam trap T-3 allowing steam downstream on January 18, 2018 | |||
January 31, 2018 (3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018 | (2) Standby gas treatment A after excessive runtime without a charcoal sample on | ||
(4) Bypass valve operability following intermittent partial open indication on | January 31, 2018 | ||
February 12, 2018 | (3) HPCI foam actuation valve 76-SOV-132 failure to close on February 8, 2018 | ||
February 15, 2018 | (4) Bypass valve operability following intermittent partial open indication on | ||
on February 23, 2018 (7) Past operability for the safety pump room with the fire dampers covered with herculite on | February 12, 2018 | ||
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 | (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: | ||
CFR 50.59 Evaluations | 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 | (2) JAF-SE-17-02, Removal of Existing Intake Structure Bar-Racks, Revision 0 | ||
CFR 50.59 Screening/Applicability Determinations | 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 | (2) 9000051059, Replace Obsolete 06FM-100 Flow Monitor, Revision 0 | ||
Pressure, Revision 1 | (3) 9000052728, Fukushima-Spent Fuel Pool Level Instrumentation, Revision 0 | ||
(4) 9000063007, Install Temporary Pump to Maintain Fire Protection Fire Header | |||
(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 | Pressure, Revision 1 | ||
(10) DRN 16-00288, Revision 36 of OP-55B, Revision 0 | (5) 9000067365, 10MOV-89A/B Replacement, Revision 0 | ||
(11) DRN-00156, OP-65B, Shutdown Operation, Revision 0 | (6) 9000068099, Modify DHR Fan Control Circuits For Reverse 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 | (7) 9000068175, 92MOD-150A(OP) Replacement with New Model Operator, 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 | (8) 9000069558, Enlarge Alignment Slot on Fuel Support Casting for Location 38-39, | ||
Revision 1 | |||
and 2RV-71F, Revision 0 (20) EC 9000067794, Replacement of 92TIC-101B, Revision 0 | (9) AR04078735, Revision 37 of OP-55B, Revision 0 | ||
(21) EC 9000069344, 12MOV-15 and 12MOV-18 Throttle Capability, Revision 0 | (10) DRN 16-00288, Revision 36 of OP-55B, 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 | (11) DRN-00156, OP-65B, Shutdown Operation, 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 | (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 | The inspectors evaluated post maintenance testing for the following maintenance/repair | ||
activities: | 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) | (2) HPCI system turbine steam supply drain trap replacement on February 13, 2018 | ||
(6) | (3) Installation of Fukushima nitrogen supply line 27AOV-117 on February 28, 2018 | ||
(7) | (4) B turbine driven feed pump motor gear unit replacement and testing on February 28, | ||
realignment on March 28, 2018 | 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 | 71111.22 - Surveillance Testing | ||
The inspectors evaluated the following surveillance tests: | 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 | |||
Inservice (2 Samples) | 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 | 71114.06 - Drill Evaluation | ||
Drill/Training Evolution (1 Sample) | 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 | 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 | 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, | level instrumentation which led to a site area emergency declaration, on January 25, | ||
2018. RADIATION SAFETY | 2018. | ||
RADIATION SAFETY | |||
71124.01 - Radiological Hazard Assessment and Exposure Controls | 71124.01 - Radiological Hazard Assessment and Exposure Controls | ||
Radiological Hazard Assessment (1 Sample) | 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 | The inspectors reviewed recent plant radiation surveys and for radiological hazards to onsite | ||
new radiological hazards. | workers or members of the public. The inspectors evaluated assessments and controls for | ||
new radiological hazards. | |||
Instructions to Workers (1 Sample) | Instructions to Workers (1 Sample) | ||
The inspectors evaluated instructions provided to workers. | The inspectors evaluated instructions provided to workers. | ||
Contamination and Radioactive Material Control (1 Sample) | 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 | The inspectors observed the monitoring of potentially contaminated material leaving the | ||
sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination. | 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) | 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 | 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 | 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 | The inspectors evaluated risk-significant high radiation area and very high radiation area | ||
controls, including postings and physical barriers. | controls, including postings and physical barriers. | ||
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample) | Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample) | ||
The inspectors evaluated radiation worker and radiation protection technician radiological | The inspectors evaluated radiation worker and radiation protection technician radiological | ||
| Line 653: | Line 757: | ||
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 | 71124.03 - In-Plant Airborne Radioactivity Control and Mitigation | ||
Self-Contained Breathing Apparatus for Emergency Use (1 Sample) | Self-Contained Breathing Apparatus for Emergency Use (1 Sample) | ||
The inspectors evaluated | 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 | 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 | 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. | SCBA air bottles, SCBA mask size availability, and the qualifications of personnel | ||
performing service and repair of this equipment. | |||
71124.04 - Occupational Dose Assessment | 71124.04 - Occupational Dose Assessment | ||
Source Term Characterization (1 Sample) | Source Term Characterization (1 Sample) | ||
The inspectors evaluated | The inspectors evaluated Exelons source term characterization. | ||
Special Dosimetric Situations (1 Sample) | Special Dosimetric Situations (1 Sample) | ||
The inspectors evaluated | The inspectors evaluated Exelons performance for special dosimetric situations. | ||
OTHER ACTIVITIES - BASELINE | OTHER ACTIVITIES - BASELINE | ||
71151 - Performance Indicator Verification (2 Samples) | 71151 - Performance Indicator Verification (2 Samples) | ||
The inspectors verified licensee performance indicators submittals listed below for the | The inspectors verified licensee performance indicators submittals listed below for the | ||
period from January 1, 2017 | period from January 1, 2017 through December 31, 2017: | ||
through December 31, 2017: | (1) MS05, Safety System Functional Failures | ||
(1) MS05, Safety System Functional Failures | (2) IE03, Unplanned Power Changes | ||
(2) IE03, Unplanned Power Changes | |||
71152 - Problem Identification and Resolution | 71152 - Problem Identification and Resolution | ||
Annual Follow-up of Selected Issues (1 Sample) | Annual Follow-up of Selected Issues (1 Sample) | ||
The inspectors reviewed | 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 | (1) Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level | ||
INSPECTION RESULTS | INSPECTION RESULTS | ||
Observations 71152 Annual Follow-up of Selected Issues Reactor Scram Due to Frazil Ice Build-up and Subsequent Lowering Intake Level | 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 | 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 | 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 | 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 | 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 | 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 - | 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 | 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 | depth or as scrutinizing as the 1996 event. Exelon recognized that these prior events were | ||
missed opportunities to not just mitigate the | 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. | 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 | 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. | 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 | The inspectors reviewed the 2016 Exelon root cause analysis documented under IR | ||
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 | 03992624. Exelon concluded the event was casued by frazil ice buildup. Contributing causes | ||
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 | 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 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. | 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 | The inspectors noted this winter FitzPatrick had no indications of frazil ice build-up or intake | ||
improved | 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 | 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 | 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 | commensurate with the safety significance, were timely, and included appropriate | ||
compensatory measures. | compensatory measures. | ||
EXIT MEETINGS AND DEBRIEFS | EXIT MEETINGS AND DEBRIEFS | ||
The inspectors verified no proprietary information was retained or documented in this report. | 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. | 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 | DOCUMENTS REVIEWED | ||
71111.01 | 71111.01 | ||
Issue Report | Issue Report | ||
04087668 | 04087668 | ||
71111.04 | 71111.04 | ||
CAD System B Quarterly Operability Test (IST) ST-25BB, Revision 4 DBD-070, Control Room and Relay Room Ventilation and Cooling Systems, Revision 4 | Procedures | ||
FB-35E, Flow Diagram Control Room Area | 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-13F, RHR- Fuel Pool Cooling Assist, Revision 11 | ||
OP-30 Fuel Pool Cooling and Cleanup System, Revision 43 | OP-30 Fuel Pool Cooling and Cleanup System, Revision 43 | ||
Issue Report | Issue Report | ||
04088760 | 04088760 | ||
Drawings FM-15A, Flow Diagram Reactor Bldg Cooling Water System 15, Revision 65 | Drawings | ||
FM-132A, Temporary Drywell Cooling System 68, Revision 5MSK-1652, Drywell Temporary Cooling System 68, Revision 4 FM-18A, Flow Diagram, Drywell Inerting C. | 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 | : [[contact::A.D. and Purge System]], Revision 57 | ||
FM-18B, Flow Diagram, Drywell Inerting C. | 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 | : [[contact::A.D. Purge and Containment DP System 27]], | ||
Revision 44 | |||
71111.05 | FM-25A, Flow Diagram High Pressure Coolant Injection System 23, Revision 75 | ||
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 | 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 | 71111.06 | ||
Procedures AP-16.14, Hazard Barrier Controls, Revision 7 | Procedures | ||
CC-AA-201, Plant Barrier Control Program, Revision 12 | AP-16.14, Hazard Barrier Controls, Revision 7 | ||
CC-AA-201, Plant Barrier Control Program, Revision 12 | |||
71111.12 | 71111.12 | ||
OP-AA-103-102, Watch-Standing Practices, Revision 18 OP-AA-108-112, Plant Status and Configuration, Revision 10 | 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 | Issue Report | ||
04114489 | 04114489 | ||
Miscellaneous | Miscellaneous | ||
JAF-1-2017-0609, Revision 1 | JAF-1-2017-0609, Revision 1 | ||
71111.12 | 71111.12 | ||
Procedures ER-AA-450, Structures Monitoring, Revision 6 | Procedures | ||
ER-AA-450, Structures Monitoring, Revision 6 | |||
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 | JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6 | ||
Issue Report | Issue Report | ||
04114448 | 04114448 | ||
71111.13 | 71111.13 | ||
Procedures | |||
AP-10.10, On-Line Risk Assessment, Revision 9 | |||
EN-WM-104, On-Line Risk Assessment, Revision 12 | EN-WM-104, On-Line Risk Assessment, Revision 12 | ||
OP-AA-108-117, Protected Equipment Program, Revision 4 | OP-AA-108-117, Protected Equipment Program, Revision 4 | ||
71111.15 | |||
71111.15 | Procedures | ||
ST-40D, Daily Surveillance and Channel Check, Revision 112 | FB-45A, Control and Relay Rooms Heating and Ventilation System 70, Revision 42 | ||
OP-AA-108-115, Operability Determinations, Revision 20 | |||
Issue Reports 03992613 | 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 | Work Order | ||
4712278 | 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 | FM-25A, Flow Diagram High Pressure Injection System 23, Revision 75 | ||
71111.19 | 71111.19 | ||
Procedures | |||
HU-AA-104-101, Procedure Use and Adherence, Revision 5 | HU-AA-104-101, Procedure Use and Adherence, Revision 5 | ||
ST-2AN, RHR Loop A Monthly Operability Test, Revision 16 | 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 | 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 | WC-AA-111, Surveillance Program Requirements, Revision 5 | ||
Issue Reports 04097327 | Issue Reports | ||
04114905 | 04097327 04098786 04103334 04107062 | ||
04114905 04119383 | |||
Work Orders 4691285 | Work Orders | ||
04666902-32 | 4691285 4731093 82691241 04765320 | ||
04666902-32 | |||
Miscellaneous | |||
71111.22 | Engineering Change 50781 | ||
ST-9R, EDG System Quick-Start Operability Test and Offsite Circuit Verification, Revision 9 | 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 | Work Orders | ||
04710258 04733734 | 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-106-01, Radiological Survey Guidelines, Revision 3 | ||
EN-RP-108, Radiation Protection Posting, Revision 18 | EN-RP-108, Radiation Protection Posting, Revision 18 | ||
EN-RP-121, Radioactive Material Control, Revision 13 | 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-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, Controls for High and Locked High Radiation Areas, Revision 30 | ||
RP-AA-460-002, Additional High Radiation Exposure Control, Revision 3 | 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-460-003, Access to HRAS/LHRAS and Contaminated Areas in Response to a Potential | ||
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, | 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 | Revision 4 | ||
Issue Reports 04102384 | Issue Reports | ||
04102384 04096595 04080866 04066877 | |||
04063769 04053351 | |||
S008, S009, S014, S021, S126, S146, S388, S390, S391, S392, S395, S396, S576, S934, S935, S1018, S1029 | Miscellaneous | ||
71124.02 | 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 | 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-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-401, Operational ALARA Planning and Controls, Revision 22 | ||
RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8 | RP-AA-441, Total Effective Dose Equivalent (EDE) ALARA Evaluation, Revision 8 | ||
Issue Reports | Issue Reports | ||
04053610 04060956 | 04053610 | ||
04071477 | 04060956 | ||
Procedures EN-RP-131, Air Sampling, Revision 15 | 04071477 | ||
71124.03 | |||
Procedures | |||
EN-RP-131, Air Sampling, Revision 15 | |||
EN-RP-503, Selection, Issue and Use of Respiratory Protection Equipment, Revision 7 | 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-AA-301, Radiological Air Sampling Program, Revision 10 | ||
RP-RESP-08.02, Air Compressor, Bauer Unicus III, Revision 6 | 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 | Issue Reports | ||
04061257 04089450 | 04061257 | ||
Miscellaneous LO Number A/R 04001198, Airborne Radioactivity Program, Respiratory Program, Personnel Monitoring Program and Bioassay Program, October 16, 2017 | 04089450 | ||
71124.04 | 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-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-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-250, External Dose Assessment from Contamination, Revision 7 | ||
RP-AA-270, Prenatal Radiation Exposure, Revision 8 | RP-AA-270, Prenatal Radiation Exposure, Revision 8 | ||
Miscellaneous NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 | Miscellaneous | ||
71151 | NUPIC Audit No. 24229/Duke Audit No. VA16087, GEL Laboratories, October 17-21, 2016 | ||
71152 | 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 | AOP-56, Intake Water Level Trouble, Revision 15 | ||
Issue Reports | Issue Reports | ||
03992624 04087426 | 03992624 | ||
Miscellaneous EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21 | 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 | Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level | ||
}} | }} | ||
Revision as of 03:25, 21 October 2019
| ML18134A214 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| 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) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION 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 Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
FitzPatrick by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
No findings or more-than-minor violations were identified.
PLANT STATUS
===FitzPatrick began the inspection period at 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
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
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
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
===
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===
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
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
===
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
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
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
- (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
===
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
- (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===
- (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 ===
- (1) ST-2AL , A Residual Heat Removal Quarterly Operability Test (IST), on January 2, 2018
on January 19, 2018
71114.06 - Drill Evaluation
Drill/Training Evolution
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
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
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
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
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
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
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
Issue Report
04087668
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.
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
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
Procedures
AP-16.14, Hazard Barrier Controls, Revision 7
CC-AA-201, Plant Barrier Control Program, Revision 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
Procedures
ER-AA-450, Structures Monitoring, Revision 6
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6
Issue Report
04114448
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
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
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
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 82691241 04765320
04666902-32
Miscellaneous
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
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
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
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
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
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
Non-Sensitive Publicly Available
SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
KKolaczyk/GStock for
NAME LCline via email ADimitriadis
via email
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)
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
Issue Report
04087668
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.
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
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
Procedures
AP-16.14, Hazard Barrier Controls, Revision 7
CC-AA-201, Plant Barrier Control Program, Revision 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
Procedures
ER-AA-450, Structures Monitoring, Revision 6
JAF-RPT-07-00006, Maintenance Rule Structural Monitoring Report, Revision 6
Issue Report
04114448
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
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
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
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 82691241 04765320
04666902-32
Miscellaneous
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
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
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
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
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
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