IR 05000333/2018001
| 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 (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
The inspectors evaluated a simulator scenario including swapping of service water pumps, a loss of the T-13 transformer, a steam leak inside the drywell requiring reactor pressure vessel blowdown, an alert declaration, and the loss of all reactor pressure vessel level instrumentation which led to a site area emergency declaration, on January 25,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment
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===
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===
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
71152
Procedures
OP-4, Circulating Water System, Revision 81
AOP-56, Intake Water Level Trouble, Revision 15
Issue Reports
03992624
04087426
Miscellaneous
EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21
Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PENNSLYVANIA 19406-2713
May 14, 2018
Mr. Bryan C. Hanson
Senior Vice President, Exelon Generation Company, LLC
President and Chief Nuclear Officer, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED
INSPECTION REPORT 05000333/2018001
Dear Mr. Hanson:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at the James
- A. FitzPatrick Nuclear Power Plant (FitzPatrick). On May 2, 2018, the NRC
inspectors discussed the results of this inspection with Mr. Joseph Pacher, Site Vice President,
and other members of your staff. The results of this inspection are documented in the enclosed
report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room
in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public
Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Anthony Dimitriadis, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Docket Number: 50-333
License Number: DPR-59
Enclosure:
Inspection Report 05000333/2018001
cc w/encl: Distribution via ListServ
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
71152
Procedures
OP-4, Circulating Water System, Revision 81
AOP-56, Intake Water Level Trouble, Revision 15
Issue Reports
03992624
04087426
Miscellaneous
EC 621217 - Removal of Existing Intake Structure Bar-Racks, Revision 21
Root Cause Report - CR-JAF-2016-00243, SCRAM Due to Lowering Screenwell Water Level