IR 05000333/2020003
| ML20315A323 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/10/2020 |
| From: | Erin Carfang Reactor Projects Branch 1 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Carfang E | |
| References | |
| IR 2020003 | |
| Download: ML20315A323 (19) | |
Text
November 10, 2020
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2020003
Dear Mr. Hanson:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant. On October 22, 2020, the NRC inspectors discussed the results of this inspection with Mr. Pat Navin, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this 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 at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, X /RA/
Signed by: Erin E. Carfang
Erin E. Carfang, Chief Reactor Projects Branch 1 Division of Reactor Projects
Docket No. 05000333 License No. DPR-59
Enclosure:
As stated
Inspection Report
Docket Number:
05000333
License Number:
Report Number:
Enterprise Identifier: I-2020-003-0019
Licensee:
Exelon Generation Company, LLC
Facility:
James A. FitzPatrick Nuclear Power Plant
Location:
Oswego, NY
Inspection Dates:
July 1, 2020 to September 30, 2020
Inspectors:
E. Miller, Senior Resident Inspector
J. England, Resident Inspector
H. Anagnostopoulos, Senior Health Physicist
E. Andrews, Health Physicist
M. Henrion, Health Physicist
C. Lally, Senior Project Engineer
M. Patel, Senior Reactor Inspector
R. Rolph, Resident Inspector
J. Rady, Emergency Preparedness Inspector
B. Sienel, Resident Inspector
A. Turilin, Reactor Inspector
Approved By:
Erin E. Carfang, Chief
Reactor Projects Branch 1
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at James A. FitzPatrick Nuclear Power Plant, 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.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
FitzPatrick began the inspection period at rated thermal power. On July 25, 2020, FitzPatrick began end of cycle coastdown. On August 12, 2020, operators reduced reactor power to 85 percent to perform control rod hydraulic control unit maintenance. Following repairs to the control rod hydraulic control unit, operators restored reactor power to maximum achievable thermal power the same day. On September 5, 2020, operators reduced reactor power to 80 percent due to degraded feedwater heater performance. Following removal of a condensate booster pump from service to stabilize feedwater heating, operators maintained power at 80 percent until September 13, 2020. On September 13, 2020, operators removed FitzPatrick from service to commence refueling outage 24 (J1R24). FitzPatrick remained offline 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted. As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D, observed risk significant activities, and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) A emergency diesel generator on July 8, 2020
- (2) A residual heat removal service water loop 'A' on July 23, 2020
- (3) A residual heat removal system in shutdown cooling mode on September 15, 2020
- (4) Decay heat removal standby diesel generator on September 19, 2020
- (5) Decay heat removal system on September 20, 2020
Complete Walkdown Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated system configurations during a complete walkdown of the reactor building closed loop cooling system on August 5, 2020.
- (2) The inspectors evaluated system configurations during a complete walkdown of the standby gas treatment system on August 21, 2020.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) East diesel fire pump room, elevation 255, fire area/zone IB/FP-3, on July 7, 2020
- (2) Reactor building, elevation 344 and 369, fire area/zone IX/RB-1A, on July 15, 2020
- (3) Turbine building south, elevation 252, fire area/zone IE/TB-1 on September 17, 2020
- (4) Reactor building, elevation 242' & 227', fire area/zone XVII/RB-1E, on September 19, 2020
- (5) Drywell, elevation 268, fire area/zone XIV/PC-1 on September 21, 2020
- (6) Turbine building, elevation 252 and 272, fire area/zone IE/TB-1, OR-1 on September 24, 2020
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade performance during an unannounced fire drill in the auxiliary boiler room on August 3, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Reactor building closed loop cooling heat exchanger 'C'
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
Activities (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from September 21, 2020 to October 8, 2020:
- Ultrasonic examination of residual heat removal valve 81A to reducing tee weld overlay on weld 24-10-130 (J1R24-VEN-001)
- Ultrasonic examination of dissimilar metal weld overlay of CRD N-9-C1 nozzle to cap (ISI-UT-20-004)
- Ultrasonic examination of recirculation system valve to elbow weld overlay on weld 28-02-2-92 (ISI-UT-20-015)
- Ultrasonic examination of core spray safe end to nozzle dissimilar metal weld N-5A-SE (APR-R24-02)
- Ultrasonic examination of recirculation system nozzle N-1B-IR inner radius (J1R24-VEN-005)
- Liquid penetrant examination of nuclear boiler instrumentation nozzle N12A-SE (ISI-PT-20-001)
- Liquid penetrant examination of reactor core isolation cooling turbine steam inlet isolation valve 13 MOV-131 welds W2 and W4 (B20PT026)
- Magnetic particle examination of reactor core isolation cooling turbine steam inlet isolation valve 13MOV-131 welds W1 and W5 (B20MT046)
- Welding activities associated with the replacement of reactor core isolation cooling turbine steam inlet isolation valve 13MOV-131 welds W1, W2, W4 and W5 (4937146)
- Visual examination (VT-G) of ASME Section XI IWE accessible containment surfaces including general exam of torus interior, reactor building, drywell dome interior, drywell head bolting and drywell dome flange surface (CISI-VT-20-001 to CISI-VT-20-008, CISI-VT-20-013, CISI-VT-20-015)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during a power reduction to begin refueling and maintenance outage J1R24 on September 13, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed a simulator evaluation that involved implementation of digital feedwater level control during reactor startup and during transients on September 3, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Torus internal structural monitoring on September 18, 2020
- (2) Drywell internal structural monitoring on September 22, 2020
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Commercial dedication of emergency diesel fuel oil and breaker component on September 9, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed;
- (1) Elevated risk during residual heat removal service water heat exchanger outlet isolation valve,10MOV-89B, repair on July 29, 2020
- (2) B reactor feedwater pump motor gear unit failure on July 29, 2020
- (3) Emergent repair of hydraulic control unit associated with control rod 14-27 on August 12, 2020
- (4) Elevated risk while placing shutdown cooling in service on September 14, 2020
- (5) Elevated risk during reactor cavity flood-up on September 15, 2020
- (6) Elevated risk during planned B 125 volts direct current battery maintenance on September 18, 2020
- (7) Elevated risk during reactor cavity draindown on September 28, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)
'A emergency service water supply piping line 46-10-WES-151-37 through-wall leak on July 21, 2020
- (2) A emergency service water supply piping line 46-10-WES-151-37 through-wall leak flaw extent of condition evaluation on July 30, 2020
- (3) A residual heat removal system snubber support failure on August 11, 2020
- (4) P4 test port leak on hydraulic control unit 14-27 on August 11, 2020
- (5) Reactor core isolation cooling condensate storage tank 'B' logic level switch on September 2, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent Modification: Engineering Change 629806, 10700 Bus Trip on Loss of Coolant Accident Project to Support Replacement of Normal Station Service Transformer 71T-4, on September 15, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
(1)88CR-2, post maintenance test review for the reactor building crane following removal of the trolley festoon cable tray on July 15, 2020 (2)10MOV-89B, residual heat removal service water heat exchanger outlet isolation valve following packing replacement on August 11, 2020 (3)23MOV-15, high pressure coolant injection inboard steam isolation valve following diagnostic testing on September 23, 2020
- (4) ST-22J, safety relief valve electric lift logic system functional and simulated actuation test following main valve replacement on September 25, 2020 (5)12MOV-69, reactor water cleanup outboard isolation valve following stem nut cleaning and repacking on September 25, 2020
- (6) High pressure coolant injection system turbine overspeed trip test following preventative maintenance overhaul on September 27, 2020 and September 29, 2020
- (7) ST-39H, reactor pressure vessel leakage test following refueling on September 30, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
- (1) The inspectors evaluated refueling outage J1R24 activities from September 13, 2020 through September 30, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (2) ST-39B-X7A, B, C, D Type C Leak Test Main Steam Line MSIV on September 15, 2020
- (4) ST-9CB, Emergency Diesel Generator (EDG) B and D Load Sequencing Test and 4KV Emergency Power System Voltage Relays Instrument Functional Test on September 27, 2020
- (5) ST-6M, Standby Liquid Control Recirculation, Injection Test (IST, ISI) on September 29, 2020
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) ST-1B, Main Steam Isolation Valve Fast Closure Test on September 14, 2020
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated Exelon's maintenance and testing of the FitzPatrick alert and notification system on July 13-16, 2020, for the period of July 2018 through June 2020
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of FitzPatrick's emergency preparedness organization on July 13-16, 2020
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes onsite on July 13-16, 2020:
- Evaluation No. 19-54, EP-AA-121-F-11, James A. FitzPatrick Equipment Matrix, Revision 3
- Evaluation No. 19-62, EAP-44, Core Damage Estimation, Revision 9
- Evaluation No. 20-03, EP-AA-111-F-15, FitzPatrick PAR Flowchart, Revision B
This evaluation does not constitute NRC approval
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program on July 13-16, 2020, for the period of July 2018 through June 2020
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the conduct of a routine emergency planning drill on August 13,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Partial)
- (1) The inspectors reviewed logs and discussed the conduct of radiologically significant work via telephone. Comprehensive documents for two jobs were requested. This was done remotely due to the COVID-19 public health emergency.
Instructions to Workers (IP Section 03.02) (1 Partial)
- (1) Comprehensive documents for two radiologically significant jobs were requested. This was done remotely due to the COVID-19 public health emergency.
Contamination and Radioactive Material Control (IP Section 03.03) (1 Partial)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors reviewed logs and discussed controls via telephone. This was done remotely due to the COVID-19 public health emergency.
Radiological Hazards Control and Work Coverage (IP Section 03.04) (1 Partial)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors reviewed initial radiological surveys of the drywell and the turbine stop valves. The inspector requested comprehensive documents for two radiologically significant jobs. This was done remotely due to the COVID-19 public health emergency.
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (1 Partial)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) The inspectors reviewed licensee procedures for high and very high radiation area controls and reviewed the results of any events that were documented in Exelon's issue reporting system Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Partial)
- (1) The inspectors reviewed logs and discussed the conduct of radiologically significant work via telephone
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (8 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Area radiation monitors in the reactor building, turbine building, and radioactive waste building
- (2) Ion chambers in use in the reactor building, turbine building, and radioactive waste building
- (3) Portable ion chambers and telepoles stored ready for use
- (4) Portable friskers used at the exit to the radiologically controlled area
- (5) Post-accident liquid sampling station
- (6) Process radiation monitors in the control room
- (7) Remote gaseous and particulate air monitoring for the drywell
- (8) Whole body counter
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Eberline RO20AA, SN 12532
- (2) Eberline MS-2, SN 1623
- (3) Eberline MS-3, SN 1036
- (4) Ludlum-3, SN 313206
- (5) Ludlum-177, SN 323559
- (6) Ludlum L-2000, SN 302439
- (7) Mirion BAK-4280, SN 427017-131
- (8) Mirion RDS-31ITX, SN 712470
- (9) Mirion RDS-31ITXSD, SN 720241
- (10) Thermo Fisher AMS-4, SN 13067
- (11) Thermo Fisher AMS-4, SN 13070
- (12) Radeco AVS, SN 14613
- (13) Radeco AVS Gooseneck, SN 1011330082
Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (2) Reactor building closed loop cooling process radiation monitor 17RM-352
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12)===
- (1) April 1, 2019 - March 31, 2020
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) April 1, 2019 - March 31, 2020
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) April 1, 2019 - March 31, 2020
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2019 - March 31, 2020
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) April 1, 2019 - March 31,
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public disclosure.
- On October 22, 2020, the inspectors presented the integrated inspection results to Mr. Pat Navin, Site Vice President, and other members of the licensee staff.
- On July 16, 2020, the inspectors presented the emergency preparedness program inspection results to Mr. Pat Navin, Site Vice President, and other members of the licensee staff.
- On July 23, 2020, the inspectors presented the radiation monitoring instrumentation inspection results to Mr. Timothy Peter, Plant Manager, and other members of the licensee staff.
- On October 8, 2020, the inspectors presented the inservice inspection activities inspection results to Mr. Pat Navin, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
Flow Diagram Reactor Building Closed Loop Cooling
Flow Diagram Residual Heat Removal System 10
Flow Diagram Residual Heat Removal System 10
Flow Diagram Standby Gas Treatment System 01-125
Flow Diagram Fuel Oil Line Emergency Diesel Generators
System 93
Flow Diagram Air Start-Up Lines Emergency Diesel
Generators System 93
Flow Diagram Air Start-up Lines Emergency Diesel
Generators
Procedures
Residual Heat Removal System
Residual Heat Removal System
Diesel Generator Emergency Power
Decay Heat Removal System
Reactor Building Closed Loop Cooling
Operation of the Decay Heat Removal Standby Diesel
Generator
Corrective Action
Documents
04371127
Fire Plans
PFP-PWR 33
Pump Rooms (Screenwell)/Elevation 255 Fire Area/Zone
XII/SP-1, XIII/SP-2, IB/FP-1, FP-3
Crescent Area-East/Elev.227', 242' Fire Area/Zone XVII/RB-
1E
Drywell Elevation 268 Fire Area/Zone XIV/PC-1
Reactor Building / Elevation 344 Fire Area/Zone IX/RB-1A
Reactor Building / Elevation 369, Fire Area/Zone IX/RB-1A
Turbine Building North/Elev. 252' Fire Area/Zone IE/TB-1
Turbine Building-South Elev. 252' Fire Area/Zone IE/TB-1
Turbine Building-North/Elev. 272' Fire Area/Zone IE/TB-1
Turbine Building-South/Elev. 272' Fire Area/Zone IE/TB-1,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OR-2
Procedures
Fire Drill Performance
Heat Exchanger Plugging Map 15E-1C RBCLC
Procedures
Reactor Building Closed Loop Cooling Sampling and Analysis
Service and Circulating water Systems Chemical Treatment
Work Orders
04682358
71111.08G Corrective Action
Documents
09/23/2008
4138318
Through Wall Leak on ESW Line 3-WES-151-136
05/16/18
NDE Reports
APR-R24-02
Safe End to Nozzle
09/21/2020
B20MT046
3" Pipe / Valve
10/01/2020
B20PT026
Valve to Elbow W2 and Elbow to Pipe W4
10/01/2020
CISI-VT-20-001
IWE General Exam Torus interior RB 227 to 272
09/24/2020
CISI-VT-20-002
IWE General Exam RF Cavity 340-369
09/21/2020
CISI-VT-20-003
IWE General Exam Torus supports RB 227
09/21/2020
CISI-VT-20-004
09/24/2020
CISI-VT-20-005
09/21/2020
CISI-VT-20-006
09/20/2020
CISI-VT-20-007
09/24/2020
CISI-VT-20-008
09/24/2020
CISI-VT-20-013
IWE General Exam Drywell Dome RF 369
09/24/2020
CISI-VT-20-015
Drywell Head Bolting
09/24/2020
ISI-PT-20-001
Instrumentation Nozzle Weld
09/18/2020
ISI-UT-20-004
Nozzle to Cap Overlay
09/22/2020
ISI-UT-20-015
Valve to Elbow
09/24/2020
Valve to Tee Weld Overlay
09/22/2020
Nozzle Inner Radius
09/22/2020
Work Orders
04937146
Replace 13MOV-131 in R24
07/21/2020
71111.11Q Miscellaneous
N-JF-OPS-LORT-
DFWLC-2005
Requalification Guide for DFWLC Mod 20-05
Miscellaneous
Purchase Order
0714821
EDG A & C Fuel Oil Receipt 34461
Purchase Order
25006
EDG B & D Fuel Oil Receipt 35606
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Purchase Order
26089
EDG A & C Fuel Oil Receipt 35610
Procedures
Receiving Inspection for Dedication of No. 2 Diesel Fuel Oil
Structures Monitoring
Independent Inspection Process Description
Suppression Chamber and Drywell Deterioration Inspection
Corrective Action
Documents
04359266
04361956
RFP Turbine Control Diagram
C
Flow Diagram Control Rod Drive System 03
Miscellaneous
G080-0056
Hydraulic Control Unit Part Nos 729E950 G1 thru G6
Procedures
Control Rod Malfunction
Disassembly of Reactor Vessel for Refueling (ISI)
Control Rod Drive Hydraulic System
093
Refueling Water Level Control
25 VDC Power System
Startup and Shutdown Procedures
27
Work Orders
05068725
Corrective Action
Documents
04109193
04164618
04344822
04361956
4351640-09
Drawings
1.61.152
Elem Diag RCIC System
Flow Diagram Emergency Service Water System 46 & 15
Engineering
Changes
631938
ESW N-513 Thru-Wall Leak Evaluation 46-10-WES-151-37
OP Eval
Miscellaneous
4351640
Operability Evaluation
Procedures
Corrective Action
Documents
04369111
JAF-LO-2012-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
00004
Engineering
Changes
29806
10700 Bus Trip on Loss of Coolant Accident Project to Support
Replacement of Normal Station Service Transformer 71T-4
Corrective Action
Documents
04371087
CR-JAF-2013-
218
Valve Outline Drawing, 23MOV-15
C
Flow Diagram Reactor Water Cleanup System 12
Miscellaneous
A391-0057F(A10)
Installation Operation and Maintenance Manual Double Disc
Gate Valve
Recommendations to Resolve Flowserve 10CFR Part 21
Notification Affecting Anchor Darling Double Disc Gate Valve
Wedge Pin Failures
(Proprietary)
Procedures
Diagnostic Testing of Motor Operated Valves
Installation and Checkout of Quick Stem Sensor (QSS) on
Valve Stems
Anchor Darling Pressure Seal Gate and Globe Valve (ISI)
Disconnecting Leads for MOV Maintenance/Testing
HPCI Turbine Overspeed Trip Test and Calibration
SRV Electric Lift Logic System Functional and Simulated
Automatic Actuation Test
SRV Electric Lift Logic System Functional and Simulated
Automatic Actuation Test
9A
Electric Lift Logic System Functional and Simulated Automatic
Actuation Test
Work Orders
0339333
05061232
Procedures
Startup and Shutdown Procedure
28
Work Orders
04738808
Corrective Action
Documents
04369251
04369253
04369255
04369727
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04369728
Auto Depressurization System
1.83-38
Elem Diagram - Auto Depressurization System
Q
1.83-39
Elem Drawing - Auto Depressurization Sys
M
Elementary Diagram 09-ECCS1-EP and 09-ECCS2-EP
Flow Diagram Standby Liquid Control System 11
Flow Diagram Core Spray System 14
Flow Diagram Main Steam System 29
Procedures
Main Steam Isolation Valve Fast Closure Test
ADS Simulated Automatic Actuation Test
RCIC Flow Rate and Inservice Test (IST)
Type C Leak Test Main Steam Line A MSIVs (IST)
Type C Leak Test Main Steam Line B MSIVs (IST)
Type C Leak Test Main Steam Line C MSIVs (IST)
Type C Leak Test Main Steam Line D MSIVs (IST)
Standby Liquid Control Recirculation, Injection Test (IST, ISI)
Emergency Diesel Generator (EDG) B and D Load
Sequencing Test and 4KV Emergency Power System Voltage
Relays Instrument Functional Test
Work Orders
04877902
04878371
04878373
04878375
04878383
04878410
05024253
Miscellaneous
Design Report
Nine Mile Point Nuclear Generating Station and James A.
FitzPatrick Nuclear Power Plant Public Alert and Notification
System
Miscellaneous
Radiological Emergency Plan Annex for James A. FitzPatrick
Station
Addendum 1
James A. FitzPatrick Nuclear Power Plant On-Shift Technical
Basis
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
CFR 50.54(q) Change Evaluation
Corrective Action
Documents
04170901
227133
271107
04302779
04303614
04323222
Miscellaneous
Nine Mile Point Nuclear Station and James A. FitzPatrick
Nuclear Power Plant 2019 Population Update Analysis
Procedures
EP-AA-121-F-11
James A. FitzPatrick Equipment Matrix
Procedures
EP-AA-112-100-
F-01
Shift Emergency Director Checklist
EP-AA-112-F-01
Command and Control Turnover Briefing Form
H
EP-AA-122-300-
F-04
Drill & Exercise Post-Event Critique & Report Development
Guidance
C
Corrective Action
Documents
268293
269079
277823
Procedures
Controls for Radiation Protection Instrumentation
8