IR 05000333/2018003
| ML18313A068 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/08/2018 |
| From: | Anthony Dimitriadis NRC/RGN-I/DRP/PB5 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Dimitriadis A | |
| References | |
| IR 2018003 | |
| Download: ML18313A068 (19) | |
Text
(Addressee)
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PA 19406-2713 November 8, 2018 Mr. Bryan Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2018003
Dear Mr. Hanson:
On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the James A. FitzPatrick Nuclear Power Plant. On October 22, 2018, the NRC inspectors discussed the results of this inspection with Mr. Joseph Pacher, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket Number: 50-333 License Number: DPR-59
Enclosure:
Inspection Report 05000333/2018003
Inspection Report
Docket Number: 50-333 License Number: DPR-59 Report Number: 05000333/2018003 Enterprise Identifier: I-2018-003-0065 Licensee: Exelon Generation Company, LLC (Exelon)
Facility: James A. FitzPatrick Nuclear Power Plant Location: Scriba, NY Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: J. Schussler, Acting Senior Resident Inspector G. Stock, Acting Senior Resident Inspector J. Bream, Physical Security Inspector P. Boguszewski, Project Engineer T. Daun, Resident Inspector, Susquehanna Nuclear Power Plant J. DeBoer, Emergency Preparedness Inspector S. Ghrayeb, Acting Resident Inspector E. Miller, Senior Resident Inspector, Nine Mile Point Nuclear Station M. Modes, Senior Reactor Inspector R. Rolph, Health Physicist B. Sienel, Resident Inspector, Nine Mile Point Nuclear Station Approved By: Anthony Dimitriadis, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
FitzPatrick by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
No findings or more-than-minor violations were identified.
PLANT STATUS
FitzPatrick began the inspection period at approximately 98 percent and gradually lowered power as it entered end-of-cycle coastdown operations. On September 10, 2018, operators commenced a shutdown from approximately 80 percent for a planned refueling and maintenance outage (RFO23). The unit remained shutdown for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Exelons performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.04 - Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) A and B emergency service water on July 9, 2018
- (2) Reactor core isolation cooling (RCIC) system on July 12, 2018
- (3) B and D emergency diesel generators (EDGs) on July 25, 2018
- (4) Decay heat removal system on September 27, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the B residual heat removal system on September 12, 2018.
71111.05A/Q - Fire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Screenwell, fire area (FA) SH-1, on July 5, 2018
- (3) Auxiliary boiler room, FA AS-1, on July 9, 2018
- (4) Cable spreading room, FA CS-1, on July 9, 2018
- (5) Standby gas treatment room, FA CS-1, on July 9, 2018
- (7) Outboard main steam isolation valve (MSIV) room and steam tunnel, FA TB-1, on September 20, 2018
- (8) Drywell, FA PC-1, on September 25, 2018
71111.07 - Heat Sink Performance Heat Sink
The inspectors evaluated Exelons monitoring and maintenance of the A residual heat removal heat exchanger performance.
71111.08 - Inservice Inspection Activities
The inspectors evaluated Exelons non-destructive examination and welding activities at FitzPatrick by reviewing the volumetric examination by manual ultrasonic encoded examination of Reactor Nozzle N1 and Reactor Nozzle N2 during the period September 17- 20, 2018, for compliance to the requirements in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable high pressure coolant injection (HPCI) steam leak into the rector building requiring emergency depressurization on July 17, 2018.
Operator Performance (1 Sample)
The inspectors observed operations personnel during downpower to 15 percent after end-of-cycle coastdown to open the unit output breakers for the start of RFO23 on September 9, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Flexible mitigating strategies equipment on August 6, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) B service air compressor out of service for maintenance on July 31, 2018
- (2) B core spray system out of service for maintenance on August 1, 2018
- (3) A core spray system inoperable for hold pump planned maintenance on August 9, 2018
- (4) Differential voltage relay testing on both offsite power lines on August 31, 2018
- (5) Phase 1 outage risk management on September 12, 2018
- (6) Station battery A out of service for maintenance on September 20, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) RCIC operability with condensate storage tank (CST) low-level transmitter 13LS-76B inoperable on August 16, 2018
- (2) Pitting identified on drywell liner on September 24, 2018
- (3) A and C residual heat removal service water pump bolt material type on September 30, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change 620602 - Replace all 11 two-stage safety relief valves with three-stage valves, on September 30, 2018
==71111.20 - Refueling and Other Outage Activities The inspectors evaluated RFO23 activities from September 10, 2018 through September 30, 2018.
71111.19 - Post Maintenance Testing
==
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
- (1) Torus leak rate outboard isolation valve testing following unplanned maintenance on July 17, 2018
- (2) Diesel fire pump 76-P1 relief valve replacement on July 19, 2018
- (3) Torus leak rate outboard isolation valve maintenance and testing following unplanned maintenance on August 26, 2018
- (4) RCIC transfer switch from CST suction to Torus suction following unplanned maintenance on September 4, 2018
- (5) Low pressure coolant injection inverter replacement and testing on September 26, 2018
- (6) MSIV 85 percent open position switch replacement on September 28, 2018
- (7) Residual heat removal A containment spray outboard isolation valve 10MOV-26A following planned maintenance on September 30, 2018
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine
- (1) ST-9BA, A and C EDG Full Load Test and Emergency Service Water Pump Operability Test, on July 9, 2018
- (3) ST-9CA, A Division Loss of Offsite Power/Loss of Cooling Accident Test, on
September 29, 2018 Inservice (1 Sample)
- (1) ST-6HB, B Standby Liquid Control Quarterly Operability Test, on July 26, 2018
Containment Isolation Valve (1 Sample)
- (1) ST-39B-X7A, A MSIV As-Found Local Leak Rate Test, on September 14, 2018
71114.02 - Alert and Notification System Testing
The Inspectors evaluated the maintenance and testing of the alert and notification system (ANS) from July 2016 to July 2018.
71114.03 - Emergency Response Organization Staffing and Augmentation System
The inspectors conducted a review of Exelons emergency response organization (ERO)augmentation staffing requirements and the process for notifying and augmenting the ERO.
71114.05 - Maintenance of Emergency Preparedness
The inspectors reviewed a number of activities to evaluate the efficacy of Exelons efforts to maintain FitzPatricks emergency preparedness programs.
71114.06 - Drill Evaluation Emergency Planning Drill
The inspectors evaluated the conduct of a routine emergency planning drill observation on
===August 1, 2018.
Drill/Training Evolution (1 Sample)===
The inspectors evaluated a simulator scenario including a trip of the A core spray loop holding pump, a trip of the A condensate pump, a trip of the A service water pump and failure of the standby pump to auto-start, a loss of control rod drive, and an un-isolable HPCI steam leak into the reactor building which required a site area emergency declaration on July 17,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment
The inspectors reviewed recent plant radiation surveys to ensure radiological hazards to onsite workers and to members of the public were identified. The inspectors evaluated assessments and controls for new radiological hazards.
Instructions to Workers (1 Sample)
The inspectors evaluated instructions provided to workers.
Contamination and Radioactive Material Control (1 Sample)
The inspectors observed the monitoring of potentially contaminated material leaving the radiological control area and evaluated contamination and radioactive material controls.
The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and tested for loose surface contamination.
Radiological Hazards Control and Work Coverage (1 Sample)
The inspectors evaluated in-plant radiological conditions and performed independent radiation measurements during facility walk-downs and observation of radiological work activities. The inspectors assessed posted surveys, radiation work permits, worker radiological briefings, the use of continuous air monitoring, and dosimetry monitoring to determine if they were consistent with the present conditions.
High Radiation Area and Very High Radiation Area Controls (1 Sample)
The inspectors evaluated risk-significant high radiation area and very high radiation area controls including postings and physical barriers.
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician radiological performance.
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Verification of Dose Estimates and Exposure Tracking Systems
===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 Engineering Controls
The inspectors observed the setup and use of ventilation systems and the use of monitoring instrumentation.
71124.04 - Occupational Dose Assessment Source Term Characterization
The inspectors evaluated Exelons source term characterization at FitzPatrick.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated Exelons performance for special dosimetric situations.
71124.05 - Radiation Monitoring Instrumentation Walkdowns and Observations
The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.
Calibration and Testing Program (1 Sample)
The inspectors evaluated Exelons calibration and testing program.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walkdowns and Observations
The inspectors walked down the gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design.
Calibration and Testing Program (Process and Effluent Monitors) (1 Sample)
The inspectors evaluated Exelons gaseous and liquid effluent monitor instrument calibration and testing.
Sampling and Analyses (1 Sample)
The inspectors evaluated radioactive effluent sampling and analysis activities.
Instrumentation and Equipment (1 Sample)
The inspectors reviewed radioactive effluent discharge system surveillance test results and reviewed the methodology used to determine the radioactive effluent stack and vent flow rates based on technical specifications/off site dose calculation manual (TS/ODCM)acceptance criteria.
Dose Calculations (1 Sample)
The inspectors reviewed several liquid and gaseous discharges to evaluate public dose calculations (monthly, quarterly, and annual) and the annual radiological effluent release reports for 2017 and
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified Exelon performance indicators submittals listed below for the period from December 2017 through June 2018:
- (1) EP01, Drill and Exercise Performance
- (2) EP02, ERO Drill Participation
- (3) EP03, ANS System Reliability
- (4) IE01, Unplanned Scrams
- (5) IE04, Unplanned Scrams with Complications
- (7) MS07, MSPI High Pressure Injection
- (8) MS08, MSPI Heat Removal Systems
- (9) MS09, MSPI Residual Heat Removal Systems
- (10) MS10, MSPI Cooling Water Systems The inspectors verified Exelon performance indicator submittals listed below for the period from January 2017 through June 2018:
- (11) PR01, RETS/ODCM Radiological Effluent Occurrence The inspectors verified Exelon performance indicator submittals listed below for the period from August 2017 through August 2018:
- (12) OR01, Occupational Exposure Control
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 19, 2018, the inspectors conducted a debrief meeting and presented the baseline radiation protection inspection results to Mr. Chris Adner, Acting Plant Manager, and other members of the Exelon staff.
On July 19, 2018, the inspectors conducted a debrief meeting and presented the preliminary emergency preparedness inspection results to Mr. Chris Adner, Acting Plant Manager, and other members of the Exelon staff.
On August 16, 2018, the inspectors conducted a debrief meeting and presented the baseline radiation protection inspection results to Mr. Timothy Peters, Plant Manager, and other members of the Exelon staff.
On September 27, 2018, the inspectors conducted a debrief meeting and presented the radiation protection inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
On October 22, 2018, the inspectors presented the quarterly resident inspection results to Mr. Joseph Pacher, Site Vice President, and other members of the Exelon staff.
DOCUMENTS REVIEWED
Procedures
AOP-68A, Loss of Decay Heat Removal, Revision 7
FM-133A, Decay Heat Removal Flow Diagram, Revision 9
FM-133B, Decay Heat Removal Flow Diagram, Revision 8
OP-13D, Residual Heat Removal Shutdown Cooling, Revision 31
OP-21, Emergency Service Water, Revision 38
OP-22, Diesel Generator Emergency Power, Revision 62
OP-30B, Decay Heat Removal System, Revision 19
OP-60, Diesel Generator Room Ventilation, Revision 9
Issue Reports
04092020 04099657 04117175 04117285
04117659
Drawings
FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 072
FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 073
FM-22A, Flow Diagram Reactor Core Isolation Cooling System 13, Revision 57
FM-46B, Flow Diagram Emergency Service Water System 46 and 15, Revision 57
ISI-FM-20A, Flow Diagram Residual Heat Removal System 10, Revision 18
ISI-FM-20B, Flow Diagram Residual Heat Removal System 10, Revision 16
Miscellaneous
Engineering Report No. JAF-RPT-05-AMM02, Aging Management Review of Residual Heat
Removal System, Revision 3
FPSSK-100, Fire Barrier Penetrations Arrangement Plan Below Elevation 272 0, Revision 5
FPSSK-206, Fire Barrier Penetrations Arrangement Fire Area Zone XII/SP-1 Elevation 255 0,
Revision 2
Procedures
PFP-PWR09, Auxiliary Boiler Room, Elevation 272 and 285, Revision 4
PFP-PWR11, Cable Spreading Room, Elevation 272, Revision 3
PFP-PWR18, Drywell Area Elevation 268, Fire Area Zone XIV/PC-1, Revision 0
PFP-PWR19, Drywell Area Elevation 292, Fire Area Zone XIV/PC-1, Revision 0
PFP-PWR22, Standby Gas Filter Room. Elevation 272, Revision 6
PFP-PWR34, Screenwell House and Water Treatment Area, Elevation 235, 255, and 260,
Revision 05
PFP-PWR33, Pump Rooms (Screenwell), Elevation 255, Revision 02
PFP-PWR42, Turbine Building - North / Elev. 252, Revision 03
PFP-PWR43, Turbine Building - South / Elev. 252, Revision 05
PFP-PWR45, Turbine Building - North / Elev. 272, Revision 06
PFP-PWR46, Turbine Building - South / Elev. 272, Revision 04
PFP-PWR48, Turbine Building Elev. 300, Revision 04
Procedures
ST-2YA, Residual Heat Removal Heat Exchanger A Performance Test, Revision 5
Drawings 4.95-5, RHR Heat Exchanger A Tube Plugging Map 10E-2A, Revision 2
Miscellaneous
14620.9033, Total Available Tube Plugging Margin in the RHR Heat Exchanger at Related
Conditions, Revision 0
Procedures
OP-65, Startup and Shutdown Procedures, Revision 123
OP-65B, Shutdown Operations, Revision 7
Issue Reports
04045089 04086665 04087668 04098168
04126033 04149166
Procedures
AP-10.09, Outage Risk Assessment, Revision 37
Procedures
ISP 75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
ER-AA-335-018, Visual Examination of ASME IWE Class MC and Metallic Liners of IWL Class
CC Components, Revision 13
Issue Reports
04164618
04164660
04174135
04178640
Work Orders
C04799709
C04832920
Miscellaneous
Design Equivalent Change Package 625754
DWG 2.28-5, Sectional Allis Chalmers H16 x 12VTMC-3, Revision 003
Engineering Change (EC) 625691
Drawings
DWG 6.32-80, Model 7567F 6 x 10 Relief Valve Alternate Configuration, Revision 4
Miscellaneous
EC 620602, UFSAR Change Request Form per LA-AA-107-1001, Revision 7
EC 620602, Engineering Calculation, Evaluation of SRV QBUBS Load Changes on Torus Shell,
Torus Attached Piping and Internal Structures, Revision 0
EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for ADS Line B, Revision 0
EC 620602, Engineering Calculation, S/RVDL Tailpipe Evaluation for Non-ADS Line L,
Revision 0
ECN 624214, Target Rock ASME Design Report 8692, Revision D
JAF-RPT-11-00003, Operational Leakage Action Levels for Target Rock Three Stages Safety
Relief Valves, Revision 1
JAF-SCN-18-056, 50.59 Screening Form for EC 620602, Revision 0
James
- A. FitzPatrick Nuclear Power Plant, Technical Proposal for 3-Stage Main Steam Safety
Relief Valves
Report No. 8696, Temperature/Seat Leakage Correlation Report for Three Stage Pilot Operated
6x10 Safety Relief Valve SRV, Target Rock Model: 0867F-001, Revision D
Report TERI 081, Technical Evaluation of 3-Stage 6x10 MS-SRV Upgrade to Address Limited
Flow Test Induced Defect (Model 0867F) Ref: Problem Report 080 and CAR 15-045,
Revision A
Procedures
ISP-75-1, RCIC CST Low Water Level Switch Functional Test/Calibration, Revision 24
MP-200.03, Replacement of NAMCO EA-180 and EA-740 Position Switches, Revision 11
MST-029.02, Main Steam Line Isolation Valve 85 Percent Open (RPS) Position Switch
Calibration Surveillance, Revision 19
ST-1CA, Outside Primary Containment Isolation Valve Exercise Test, Revision 1
ST-2AL, RHR Loop A Quarterly Operability Test (IST), Revision 038
ST-76J23, West Diesel Fire Pump 76P-1 Performance Test, Revision 22
Issue Reports
04109193 04156252 04164618 04164660
04167340 04176976
Work Orders
C04644984 C04732717 C80161193 C80403118
C82503567
Procedures
IMP-71.25, Test Equipment Set Up for 10500 and 10600 Emergency Bus Sequencing Test
ST- C, Revision 10
ST-1B, MSIV Fast Closure Test, Revision 26
ST-6HB, Standby Liquid Control Quarterly Operability Test (IST), Revision 9
ST-9BA, EDG A and C Full Load Test and ESW Pump Operability Test, Revision 16
ST-9CA, EDG A and C Load Sequencing Test and 4kV Emergency Power System Voltage
Relays Instrument Functional Test, Revision 4
ST-39B-X7A, Type C Leak Test Main Steam Line A MSIVs, Revision 16
Issue Reports
04178600
Work Orders
C82606584
Procedures
NISP-RP-004, Radiological Posting and Labeling, Revision 00
NISP-RP-005, Access Controls for High Radiation Areas, Revision 0
RP-AA-18, Radiological Posting and Labeling Program Description, Revision 1
RP-AA-300, Radiological Survey Program, Revision 15
RP-AA-460, Controls for High and Locked High Radiation Areas, Revision 34
RP-AA-503, Unconditional Release Survey Method, Revision 14
Issue Reports
04171228 04174941 04175570 04175765
04176037 04176242
RWPs/ALARA Plans
JF-1-18-00506 DW Scaffold AP-18-0506
JF-1-18-00510 DW SRV Activities AP-18-0510
JF-1-18-00513 DW CRD Drive Exchange AP-18-0513
JF-1-18-00516 DW RW Recirc Pump and Motor AP-18-0516
JF-1-18-00541 DW 12RWC-46 and 12MOV-15 AP-18-0541
Surveys
Survey Description Date/Time
2018-021841 DW 268 September 10, 2018/2100
2018-021911 DW 292 SRV September 11, 2018/1254
2018-022001 Under Reactor Head September 12, 2018/0052
2018-022623 12RWC-46 September 16, 2018/1058
2018-022711 12RWC-46 September 17, 2018/0837
2018-022565 SRV 71F September 18, 2018/0116
2018-023578 DW 256 September 25, 2018/0447
Air Sample Results
Air Sample Description Date/Time
18306 DW 12RWC46 September 18, 2018/1220
18320 DW B Recirc Pump Seal September 22, 2018/2300
18329 DW MSIV B Breach September 23, 2018/0250
18311 DW 12MOV15 Breach September 23, 2018/1220
18342 DW 268 General Area September 24, 2018/0640
18343 DW 292 General Area September 24, 2018/0720
18345 DW 12MOV15 September 25, 2018/0230
Procedures
RP-AA-400, ALARA Program, Revision 15
Issue Reports (*initiated in response to inspection)
04175408
04177200*
Procedures
RP-AA-301, Radiological Air Sampling Program, Revision 11
RP-AA-302, Determination of Alpha Levels and Monitoring, Revision 10
Issue Reports
04133415
Miscellaneous
Breathing Air Samples, Report 294228-0 on January 18, 2017; and Report 341956-1 on
August 31, 2018
Procedures
RP-AA-12, Internal Dose Control Program Description, Revision 2
RP-AA-203-1001, Personnel Exposure Investigations, Revision 10
RP-AA-210, Dosimetry Issue, Usage, and Control, Revision 29
RP-AA-220, Bioassay Program, Revision 13
RP-AA-222, Methods for Estimating Internal Exposure from in VIVO Bioassay Data, Revision 5
RP-AA-290, Prenatal Radiation Exposure, Revision 8
Issue Reports
04102403
04174125
04175886
Miscellaneous
Generic Radiation Worker Training Lesson Plan, Revision 11, December 2017
NVLAP Certification for Lab Code 100518-0
Procedures
ISP-95A, Post Accident Containment High Range Radiation Monitor A Functional
Test/Calibration, Revision 4
ISP-95B, Post Accident Containment High Range Radiation Monitor B Functional
Test/Calibration, Revision 4
RP-AA-700-1101, Calibration of the RO-2, RO-2A, RO-20 and RSO-50E Ion Chambers,
Revision 1
RP-AA-700-1203, Calibration of the MGP Instruments Telepole, Revision 1
RP-AA-700-1215, Calibration of Low-Vol Air Samplers, Revision 2
RP-AA-700-1216, Calibration of Hi-Vol Air Samplers, Revision 4
RP-AA-700-1235, Operation and Calibration of the PM-12 Gamma Portal Monitor, Revision 5
RP-AA-700-1239, Operation and Calibration of the Model SAM-12 Small Articles Monitor,
Revision 4
RP-AA-700-1240, Operation and Calibration of the Canberra ARGOS-5 Personnel
Contamination Monitor, Revision 6
RP-AA-700-1242, Calibration of Eberline Model 6112B Teletector, Revision 0
RP-AA-700-1301, Calibration, Source Check, Operation and Set-Up of the Eberline Beta Air
Monitor, Model AMS-4, Revision 4
RP-AA-700-1305, Operation and Calibration of the AMP-100/200, Revision 2
RP-AA-700-1312, Calibration of Bicron Micro REM Survey Meter, Revision 1
RP-AA-700-1401, Operation and Calibration of Eberline Model PM-7 Personnel Contamination
Monitor, Revision 6
RP-INST-02.09, Calibration of Mini-Scaler MS-2 and MS-3, Revision 5
RP-INST-02.15, Calibration of Ludlum L-2000 Scaler, Revision 0
SP-03.14, Post Accident Sampling, Revision 0
Issue Reports
04095004 04096020 04156340 04162340
Calibration Records
17RM-351, Normal Service Water Monitor, February 16, 2018
04752950-01, Reactor Building Vent Monitor, June 15, 2018
04752006-01, Stack Vent Monitor, June 8, 2018
04771225-01, Radwaste Building Vent, July 10, 2018
2606748-01, 27RM-104A Containment High Range Monitor (Source), February 5, 2017
2606749-01, 27RM-104B Containment High Range Monitor (Source), February 7, 2017
2720565-01, 27RM-104A Containment High Range Monitor (Electronics), December 27, 2016
2714885-01, 27RM-104B Containment High Range Monitor (Electronics), December 27, 2016
Miscellaneous
Mirion Technologies Calibration of the Canberra Fastscan WBC System at the Exelon James
- A.
FitzPatrick Nuclear Power Plant, March 28, 2018
Procedures
CY-AA-130-200, Quality Control, Revision 13
CY-AA-130-201, Radiochemistry Quality Control, Revision 5
CY-AA-170-2200, RETDAS, Revision 1
EN-AA-408, Radiological Groundwater Protection Program, Revision 0
EN-CY-102, Laboratory Analytical Quality Control, Revision 9
SP-01.06, Gaseous Effluent Sampling and Analysis, Revision 20
SP-03.05, Steam Jet Air Ejector and Recombiner Effluent Sampling and Analysis, Revision 13
SP-03.07, Liquid Process Radiation Monitors, Revision 10
SP-03.08RF, Refuel Floor Gaseous Effluent Monitors, Revision 2a
SP-03.08RW, Radwaste Building Gaseous Effluent Monitors, Revision 4a
SP-03.08RX, Reactor Building Gaseous Effluent Monitors, Revision 1a
SP-03.08STK, Stack Effluent Monitors, Revision 6a
SP-03.08TB, Turbine Building Gaseous Effluent Monitors, Revision 3
Issue Reports
03037511 03847968 03992568 03996675
04001340 04010103
Miscellaneous
Radioiodine Penetration/Efficiency Test Report, March 23, 2018
71151
Procedures
EN-LI-114, Performance Indicator Process, Revision 7
NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7
Miscellaneous
JAF-RPT-05-0047, Mitigating Systems Performance Index Basis Document, Revision 5