IR 05000220/2022001
| ML22119A018 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/29/2022 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| Carfang E | |
| References | |
| IR 2022001 | |
| Download: ML22119A018 (21) | |
Text
April 29, 2022
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000220/2022001 AND 05000410/2022001
Dear Mr. Rhoades:
On March 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2. On April 21, 2022, the NRC inspectors discussed the results of this inspection with Mr. Peter Orphanos, 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, Erin E. Carfang, Chief Projects Branch 1 Division of Operating Reactor Safety
Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000220 and 05000410
License Numbers:
Report Numbers:
05000220/2022001 and 05000410/2022001
Enterprise Identifier: I-2022-001-0049
Licensee:
Constellation Energy Generation, LLC
Facility:
Nine Mile Point Nuclear Station, Units 1 and 2
Location:
Oswego, NY
Inspection Dates:
January 1, 2022 to March 31, 2022
Inspectors:
G. Stock, Senior Resident Inspector
C. Kline, Resident Inspector
B. Sienel, Resident Inspector
N. Floyd, Senior Reactor Inspector
S. Haney, Senior Project Engineer
C. Hobbs, Reactor Inspector
S. Wilson, Senior Health Physicist
Approved By:
Erin E. Carfang, Chief
Projects Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Nine Mile Point Nuclear Station, Units 1 and 2, 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
Unit 1 operated at or near rated thermal power for the entire inspection period.
Unit 2 began the inspection period at rated thermal power. On January 7, 2022, the unit was downpowered to 78 percent to perform planned control rod channel interference testing and a control rod pattern adjustment, and returned to rated thermal power on January 8, 2022.
On January 28, 2022, the unit began end-of-cycle coastdown. On February 11, 2022, the unit was downpowered to 85 percent to avoid a known oscillation region during end-of-cycle coastdown. On March 7, 2022, the unit was shut down for a planned refueling outage. Startup was commenced on March 25, 2022, and rated thermal power was reached on March 29, 2022. Later that day, the unit was downpowered to 80 percent for a planned rod pattern adjustment. During the downpower, a main turbine control valve malfunction required an additional downpower to 60 percent. The unit returned to rated thermal power on March 31, 2022, and 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 activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk-significant activities, and completed on-site portions of IPs. 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.
On February 1, 2022, the operating license for Nine Mile Point Nuclear Station, held by Exelon Generation Company, LLC, was transferred to Constellation Energy Generation, LLC (Constellation). While some or all of the inspections documented in this report were performed while the license was held by Exelon Generation Company, LLC, this report will refer to the licensee as Constellation throughout.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems due to a winter storm warning on March 11, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 reactor core isolation cooling system on January 26, 2022
- (2) Unit 1 reactor building closed loop cooling system on February 7, 2022
- (3) Unit 2 'C' residual heat removal system on February 7, 2022
- (4) Unit 2 Division II emergency diesel generator on February 22, 2022
- (5) Unit 2 'B' residual heat removal system in shutdown cooling on March 8, 2022
- (6) Unit 2 Division I emergency diesel generator on March 10, 2022
- (7) Unit 2 'A' spent fuel pool cooling system on March 15, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (9 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) Unit 2 radwaste building 261/265, condensate storage building, fire area 55, on February 1, 2022
- (2) Unit 2 reactor building 289, fire areas 34 and 35, on February 10, 2022
- (3) Unit 2 reactor building 240 north, fire area 1, on February 14, 2022
- (4) Unit 1 turbine building 261' west, fire area 5, on February 17, 2022
- (5) Unit 2 reactor building 175' north, fire area 1, on February 28, 2022
- (6) Unit 2 reactor building, primary containment steam tunnel, fire area 50, on March 7, 2022
- (7) Unit 2 turbine building, condenser, fire area 50, on March 7, 2022
- (8) Unit 2 turbine building, feedwater heater bays, fire area 50, on March 9, 2022
- (9) Unit 2 reactor building, drywell, fire area 5, on March 16, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the Unit 1 cable spreading room on February 28, 2022.
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 2 'B' residual heat removal heat exchanger
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 March 7 to March 17, 2022:
- Automated phased array ultrasonic testing of the N1B reactor recirculation nozzle to safe-end dissimilar metal weld, 2RPV-KB02 (NDE Report N2R18-APR-02).
- Automated phased array ultrasonic testing of the N4E reactor feedwater nozzle to safe-end dissimilar metal weld, 2RPV-KB21 (NDE Report N2R18-APR-09).
- Manual ultrasonic testing of the reactor water cleanup system pipe-to-pipe and valve-to-pipe welds, 2WCS-09-14-FW039 / -FW040 (NDE Reports
==2R18 -ISI-UT-002 / -003).
- ==
Visual examinations of the containment, including accessible portions of the drywell and suppression chamber metal liner (Work Order [WO] C93672957)
- Welding activities associated with the modification of the instrument air check valve, 2IAS*V450, under engineering change ECP-21-000088 (Work Order
[WO] 93782709). This included liquid penetrant testing of two pipe-to-valve welds, FW-03 and FW-04 (NDE Report BOP-PT-22-004).
- Flaw evaluation of the embedded reflector identified during the spring 2020 refueling outage using automated phased array UT on the N2J reactor recirculation nozzle to safe-end dissimilar metal weld (NDE Report N2R17-APR-06). The flaw was determined to be acceptable for continued service.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed Unit 1 operations personnel during control rod exercising operability testing on March 5, 2022.
- (2) The inspectors observed Unit 2 operations personnel during the plant shutdown for refueling outage N2R18 on March 6, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed a Unit 2 simulator evaluation that included an instrument air compressor failure, reactor core isolation cooling system inoperability, and a small loss of coolant accident with additional failures that required the depressurization of the reactor on January 25, 2022.
- (2) The inspectors observed a Unit 1 simulator evaluation that included the inadvertent opening of an electromatic relief valve, a loss of offsite power, an emergency diesel generator failure to start, and a steam leak in the drywell on February 2, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Unit 2 Division I emergency diesel generator jacket water pump
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (9 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) Unit 2 elevated risk during planned 'B' residual heat removal pump maintenance on January 4, 2022
- (2) Unit 2 elevated risk during emergent work on the Division I emergency diesel generator starting air system on January 20, 2022
- (3) Unit 1 elevated risk during emergent work on the 'C' instrument air compressor on February 16, 2022
- (4) Unit 2 elevated risk during planned Division I emergency diesel generator maintenance on February 22, 2022
- (5) Unit 2 elevated risk during emergent work on the 'B' service water pump on March 2, 2022
- (6) Unit 2 elevated risk during a planned 115-kilovolt Line 5 outage on March 6, 2022
- (7) Unit 2 elevated risk during a planned reactor cavity flood-up on March 8, 2022
- (8) Unit 2 elevated risk during planned maintenance on SWP*MOV66B, cooling water to Division II emergency diesel generator, on March 10-12, 2022
- (9) Unit 2 elevated risk during a planned reactor cavity draindown on March 22, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (9 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2 Division I emergency diesel generator slow start on January 3, 2022
- (2) Unit 2 Division I emergency diesel generator starting air compressor 'B' failure on January 18, 2022
- (3) Unit 2 Division I emergency diesel generator emergency start solenoid valve air leaks on January 20, 2022
- (4) Unit 1 safety relief valve elevated discharge temperature indications on February 1, 2022
- (5) Unit 1 emergency diesel generator 103 starting flywheel chipped tooth on February 15, 2022
- (6) Unit 1 containment spray raw water 122 rate set valve unable to operate on February 24, 2022
- (7) Unit 1 core spray topping pump 111 pump-bearing oil leak on March 2, 2022
- (8) Unit 2 Division III diesel under voltage relay failure to reset after testing on March 4, 2022
- (9) Unit 2 main steam isolation valve slow fast closure times on March 7, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent Modification: ECP-21-000437, Unit 2 Division II Emergency Diesel Generator Governor Booster
- (2) Permanent Modification: ECP-21-000454, Unit 2 Digital Electro-Hydraulic Control (DEHC) Low Pass Filter Modification
- (3) Permanent Modification: ECP-21-000088, Unit 2 PCIV [primary containment isolation valve] Supply Nitrogen Line Primary Containment Inboard Isolation Re-Design
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 2 Division I emergency diesel generator jacket water pump following replacement on February 23, 2022
- (2) Unit 2 'B' service water pump following a failure to start on March 2, 2022
- (3) Unit 2 Division II emergency diesel generator following governor oil booster installation on March 21, 2022
- (4) Unit 2 'B' residual heat removal system following heat exchanger inspection on March 25, 2022
- (5) Unit 2 drywell nitrogen supply system following solenoid operated valve replacement on March 28, 2022
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 2 refueling outage N2R18 from March 6 to March 27, 2022.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (8 Samples)
- (1) N1-ST-M4A, Emergency Diesel Generator 102 and PB 102 Operability Test, on January 24, 2022
- (2) N2-OSP-CSL-Q@002, LPCS [low pressure core spray] Pump and Valve Operability and System Integrity Test, on February 28, 2022
- (3) N1-ST-Q1A, Core Spray 111 Pump, Valve and Shutdown Cooling Water Seal Check Valve Operability Test, on March 1, 2022
- (4) N2-OSP-MSS-CS001, Main Steam Isolation Valve Operability Test, on March 7, 2022
- (5) N2-OSP-RHS-R001, Division II ECCS [emergency core cooling system] Functional Test, on March 9, 2022
- (6) N2-OSP-SLS-R001, Standby Liquid Control Manual Initiate Actuation and ASME XI Pressure Test, on March 16, 2022
- (7) N2-OSP-ADS-R002, ADS [automatic depressurization system] Functional Test and Remote Shutdown System Test, on March 19, 2022
- (8) N2-OSP-EGS-R001, Diesel Generator ECCS Start and Load Reject Division II, on March 20, 2022
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) N2-OSP-ICS-Q@002, Reactor Core Isolation Cooling Pump and Valve Operability Test and System Integrity Test and ASME XI Functional Test and Analysis, on February 10, 2022
- (2) N2-ISP-RRC-R001, ARI [alternate rod insertion] Function of RRCS [redundant reactivity control system], on March 7, 2022
Containment Isolation Valve Testing (IP Section 03.01) (2 Samples)
- (1) N2-OSP-MSS-003, Unit 2 Main Steam Isolation Valve Leak Rate Test, on March 7, 2022
- (2) N2-OSP-MSS-004, Unit 2 Main Steam Isolation Valve Leak Rate Test (Reactor Vessel Head Removed), on March 25,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how Constellation assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
- (1) Workers exiting the Unit 2 radiologically controlled area during refueling outage N2R18
- (2) Licensee surveys of contaminated equipment on the refuel floor during refueling outage N2R18
Radiological Hazards Control and Work Coverage (IP Section 03.04) (5 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 2 outage refuel floor activities, low power range monitor exchange, and supporting activities
- (2) Unit 2 in-vessel inspection and supporting activities
- (3) Unit 2 refuel floor equipment decontamination activities
- (4) Unit 2 drywell feedwater nozzle inspection activities
- (5) Unit 2 safety relief valve maintenance in the drywell
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) High Radiation Area in the Unit 2 reactor building valve pit, 196' elevation
- (2) Locked High Radiation Areas in the Unit 2 drywell
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2021 through December 31, 2021)
- (2) Unit 2 (January 1, 2021 through December 31, 2021)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2021 through December 31, 2021)
- (2) Unit 2 (January 1, 2021 through December 31, 2021)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2021 through December 31, 2021)
- (2) Unit 2 (January 1, 2021 through December 31, 2021)
===71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03)===
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) IR 04436618 - Nine Mile Point Control Rod Blade Technical Evaluation
INSPECTION RESULTS
Observation: Nine Mile Point Control Rod Blade Technical Evaluation 71152A On November 23, 2020, General Electric Hitachi (GEH) released Safety Communication 20-06 (SC 20-06) Revision 0, describing the discovery that Boron 10 (B-10) depletion had been underpredicted in the top 6-inch node of the neutron absorber section of control rod blades currently in use in boiling water reactors in the United States. Nine Mile Point Nuclear Station was on the list of plants affected by this issue. In Revision 0 of the Safety Communication, the population of control rod blades affected was restricted to Original Equipment Manufacturer (OEM) series D-100 control rod blades, still in operation from the 1970s and 1980s. On February 26, 2021, GEH issued Revision 1 to SC 20-06, in which it was determined that the population of control rod blades affected by the underprediction of B-10 in the tip segment included all control rod blades that did not contain Hafnium (Hf) in the tips, not just OEM D-100 control rod blades. This greatly increased the population of control rod blades affected by this issue.
Control rod blades deplete the B-10 isotope as they absorb neutrons when they are inserted into an operating reactor core. Control rod blades are typically fully withdrawn from the core when the reactor is at full power. However, the tips of the control rod blades still experience some thermal neutron flux. The B-10 depletion in the top node of the control rod blade is accounted for in engineering analysis by adding a "tip adder" factor in the B-10 depletion calculation for each control rod blade. Safety Communication SC 20-06 stated that the tip adder factor was much larger than previously calculated, for control rod blades without Hf in the tips. General Electric manufactured control rod blades with Hf tips for a period of time in the 1980s and 1990s that are excluded from the tip adder issue described in SC 20-06. All other control rod blade models, including the OEM blades, are affected by the tip adder issue described in SC 20-06. The higher depletion values in the control rod blade tips for multiple control rod blade types may cause the control rod blade to exceed its effective neutron absorbing capability before the end of the operating fuel cycle. This has the potential to decrease the overall shutdown margin (SDM), which is the ability of all the control rods, except for the most reactive control rod, to shut down the reactor core in all anticipated normal and accident scenarios.
In Revision 1 to SC 20-06, GEH recommended all customers ensure that adequate SDM was available in the current operating fuel cycle until the end of the fuel cycle, once the amount of B-10 depletion was determined in all control rod blade tips. GEH recommended this be done for all General Electric control rod blades that did not contain Hf tips, as well as alternate vendor control rod blades. GEH also recommended all customers assess the impact of control rod blades exceeding their nuclear end of life (NEOL) criteria - the ability of the control rod blade to effectively absorb neutrons - for future fuel cycles beyond the current operating fuel cycle.
Following issuance of GEH SC 20-06, Revision 1, Nine Mile Point Unit 1 entered a refueling outage in March 2021. A control rod blade depletion engineering evaluation was performed, taking into account the new tip adder calculation in SC 20-06. It was determined that two control rod blades that had been located in higher power locations in the previous fuel cycle would be shuffled to two lower power locations in the core for the current Unit 1 operating fuel cycle. No control rod blades in the previous or current fuel cycle have exceeded their NEOL criteria, thus requiring replacement.
In July 2021, Exelon Nuclear Fuels validated that adequate SDM existed for the remainder of the current fuel cycle for Nine Mile Point Unit 2, and that thermal limit margins were not impacted. One control rod blade on the core periphery was predicted to exceed its NEOL criteria due to the tip adder issue described in SC 20-06, before the end of the Unit 2 fuel cycle in March 2022. This blade, along with six other control rod blades, are scheduled for replacement in the upcoming refueling outage. In September 2021, General Electric Global Nuclear Fuels completed an analysis to confirm that SDM would be maintained above the technical specification limit for the remainder of the Unit 2 fuel cycle. Exelon procedure NF-AB-135-1410, "BWR Control Blade Lifetime Management," contains guidance for calculating B-10 depletion in all models of control rod blades currently in operation in the nuclear fleet.
This procedure will require an update to incorporate the new guidance from SC 20-06, for estimating the tip adder factor for non-Hf tipped control rod blades. Issue Report 04242262 is tracking completion of this procedural update.
The inspectors interviewed engineering staff from Exelon Nuclear Fuels and Nine Mile Point Reactor Engineering to discuss corrective actions taken in response to GEH SC 20-06, and reviewed shutdown margin and control rod blade depletion engineering evaluations. The inspectors also reviewed the corrective actions taken and planned for responding to GEH SC 20-06 entered into the corrective action system. No performance deficiencies were identified.
Corrective Action References: 04242262, 04386300,
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 21, 2022, the inspectors presented the integrated inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
- On February 8, 2022, the inspectors presented the control rod blade technical evaluation problem identification and resolution inspection results to Philip Nichols, Manager Reactor Engineering, and other members of the licensee staff.
- On March 17, 2022, the inspectors presented the Unit 2 inservice inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
- On March 17, 2022, the inspectors presented the radiological hazard assessment and exposure controls inspection results to Mr. Peter Orphanos, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N1-OP-64
Meteorological Monitoring
2100
N2-OP-102
Meteorological Monitoring
2800
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
Drawings
C-18022-C
Piping & Instrumentation Diagram, Reactor Building Closed
Loop Cooling System
PID-031A, B, E
Piping & Instrumentation Diagram Residual Heat Removal
System
PID-31G
Piping & Instrumentation Diagram Residual Heat Removal
PID-35A
Piping & Instrumentation Diagram Reactor Core Isolation
Cooling
PID-35B
Piping & Instrumentation Diagram Reactor Core Isolation
Cooling
PID-38B
Piping & Instrumentation Diagram Fuel Pool Cooling &
Cleanup
PID-38C
Piping & Instrumentation Diagram Fuel Pool Cooling &
Cleanup
Procedures
N1-OP-11
Reactor Building Closed Loop Cooling System
03400
N2-OP-100A
Standby Diesel Generators
200
N2-OP-100A-
LINEUPS
Standby Diesel Generators - LINEUPS
00500
N2-OP-31
Residual Heat Removal System
03700
N2-OP-31-
LINEUPS
Residual Heat Removal System
003
N2-OP-38
Spent Fuel Cooling and Cleanup System
2700
Corrective Action
Documents
04477281
Drawings
B-40143-C
Fire Zones Reactor Building - Fl. El. 261' Turbine Building -
Fl. El. 261' Fire Rated Walls and Slabs
Fire Plans
N2-FPI-PFP-0201
Unit 2 Pre-Fire Plans
Corrective Action
Documents
04416206
04477927
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04661043
71111.07A Corrective Action
Documents
04484882
04486864
Procedures
Service Water Heat Exchanger Inspection Guide
S-TDP-REL-0102
Service Water Heat Exchanger and Component Inspection
Guide
Work Orders
C93738267
71111.08G Corrective Action
Documents
04327298
Corrective Action
Documents
Resulting from
Inspection
04484400
Engineering
Evaluations
ECP-20-000224
Recirculation Inlet Nozzle DMW No. 2RPV-KB11 (N2J) Flaw
Evaluation
03/25/2020
Miscellaneous
ER-NM-330-2001
ISI Program Plan Fourth Ten-Year Inspection Interval
Revision 3
ER-NM-330-2004
Risk Informed Inservice Inspection Program Fourth Ten-
Year Inspection Interval
Revision 0
Procedures
Visual Examination of ASME IWE Class MC and Metallic
Liners of Class CC Components
Revision 15
Ultrasonic Examination of Ferritic Piping Welds
Revision 5
Nondestructive Examination (NDE)
Revision 16
GEH-UT-254
Automated Phased Array Ultrasonic Examination of
Dissimilar Metal Welds with the TOPAZ
Version 1
WPS 8-8-GTSM
Welding Procedure Specification Record for Manual GTAW
and SMAW of P-Number 8 to P-Number 8 Base Metal
Revision 7
71111.11Q Procedures
N1-ST-W1
Control Rod Exercising Operability Test
2300
N2-OP-101C
Plant Shutdown
04100
N2-OP-29
Reactor Recirculation System
03400
N2-OP-31
Residual Heat Removal System
03700
Procedures
N2-MSP-EGS-
R001
Diesel Generator Inspection Division 1 and 2
25
Work Orders
C938144677
Corrective Action
04481795
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Procedures
N2-OP-19-
Lineups
Instrument and Service Air Systems
N2-OP-70
Station Electrical Feed and 115KV Switchyard
2800
N2-PM-082
RPV [reactor pressure vessel] Flood-Up/Draindown
01900
OP-NM-108-117
Protected Equipment Program at Nine Mile Point
OP-NM-108-117
Protected Equipment Program at Nine Mile Point
00500
OU-NM-103-101
Shutdown Safety Management Program
0700
Calculations
2N3714
Nine Mile Point Nuclear Station Unit 1 TRACG-LOCA
Analysis for GNF2 Fuel
Corrective Action
Documents
04061889
04470659
04475343
04476776
04481649
04482642
04483059
04488015
Drawings
0001040209048
Control Diagram Shutdown System
13.00
Engineering
Changes
ECP-22-000147
Technical Evaluation for MSIV Failed Stroke Time Extent of
Condition
0000
Miscellaneous
NEI 06-09-A
Risk-Informed Technical Specifications Initiative 4b: Risk-
Managed Technical Specifications (RMTS) Guidelines
Purchase Order
00802656
Service, Repair, Refurbishment of MSIV Actuator Air Pack
RICT Record for
March 28, 2022
04/06/2022
Procedures
N1-OP-1
Nuclear Steam Supply System
07700
N2-OP-100A
Standby Diesel Generators
03100
N2-OSP-EGS-
M@001
Diesel Generator and Diesel Air Start Valve Operability Test-
Division I and II
24T1
Risk Informed Completion Time
Corrective Action
2547530
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
2689624
04359704
04365824
04428910
04482114
Engineering
Changes
ECP-21-000088
PCIV Supply Nitrogen Line Primary Containment Inboard
Isolation Re-Design
0000
ECP-21-000437
EDG Governor Booster
0000
ECP-21-000454
Digital Electro-Hydraulic Control (DEHC) Low Pass Filter
Modification
Miscellaneous
FAT/SAT Testing for DEHC Low Pass Filter Mod
0000
Procedures
N2-OSP-EGS-
M@0001
Diesel Generator and Diesel Air Start Valve Operability Test
- Division I and II
24T1
Work Orders
C93782709
C93809087
C93813137
Corrective Action
Documents
04480094
04481795
04484882
04486059
Corrective Action
Documents
Resulting from
Inspection
04486063
Procedures
GAP-HSC-09
System Aging Inspection and Cleanliness Controls
2000
N2-MSP-EGS-
R001
Diesel Generator Inspection Division I and II
2400
N2-OSP-EGS-
M@0001
Diesel Generator and Diesel Air Start Valve Operability Test
- Division I and II
2400.01
N2-OSP-RHS-
Q@005
RHR System Loop B Pump and Valve Operability Test,
System Integrity Test and ASME XI Pressure Test
01500
N2-OSP-RHS-
R001
Division II ECCS Functional Test
00900
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
S-EPM-GEN-004
Insulation of Power, Control, and Instrument Cable
Connections
00700
Work Orders
C93738267
C93782709
C93814677
C93825512
Corrective Action
Documents
04482986
04482995
04483785
04484026
04484553
04485270
Corrective Action
Documents
Resulting from
Inspection
04484400
04486063
Miscellaneous
NM2C19-SU
Reactivity Maneuver Plan
Procedures
Fatigue Management and Work Hour Limits
N2-FHP-13.3
Core Shuffle
200
N2-OP-101A
Plant Start-up
05400
N2-OP-38
Spent Fuel Cooling and Cleanup System
2700
N2-OSP-NMS-
@002
Source Range Monitor Check During Core Offload/Reload
201
Personnel and Equipment Tagout Process
Reactivity Management
Reactivity Management - Fuel Handling, Storage and
Refueling
OU-NM-103-101
Shutdown Safety Management Program
00700
OU-NM-4001
Refueling Operations
00800
Corrective Action
Documents
04481649
04482027
04483059
04483200
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
04483399
04485322
Miscellaneous
Technical
Evaluation N2R18
MSIV Leak Rate Tests
Approved
03/17/2022
Procedures
N1-ST-M4A
Emergency Diesel Generator 102 and PB 102 Operability
Test
03000
N1-ST-Q1A
CS 111 Pump, Valve and SDC Water Seal Check Valve
Operability Test
200
N2-ISP-RRC-
R001
ARI [alternate rod insertion] function of RRCS [redundant
reactivity control system]
00700
N2-OSP-ADS-
R002
ADS System Functional Test and Remote Shutdown System
Test
009
N2-OSP-CSL-
Q@002
LPCS Pump and Valve Operability and System Integrity
Test
01500
N2-OSP-EGS-
R001
Diesel Generator ECCS Start and Load Reject Division II
N2-OSP-ICS-
Q@002
RCIC Pump and Valve Operability Test and System Integrity
Test and ASME XI Functional Test and Analysis
01600
N2-OSP-MSS-
003
Main Steam Isolation Valve Leak Rate Test
00300
N2-OSP-MSS-
004
Main Steam Isolation Valve Leak Rate Test (Reactor Vessel
Head Removed)
200
N2-OSP-MSS-
CS001
Main Steam Isolation Valve Operability Test
01000 and
01100
N2-OSP-SLS-
R001
Standby Liquid Control Manual Initiate Actuation and ASME
XI Pressure Test
01100
71151
Procedures
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
242262
04386300
04436618
Engineering
Evaluations
ECP-20-000291
Control Blade Replacement Strategy for Nine Mile Point Unit
Cycle 25 (Reload 26)
ECP-21-000248
Control Blade Replacement Strategy for Nine Mile Point Unit
(Reload 18)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
ECP-21-000380
SC 20-06: Nine Mile Point Unit 2 Cycle 18 SDM and
MSBWP Evaluation
Miscellaneous
Hitachi Safety
Communication
20-06, Rev. 1
Impact of Ex-core Flux on Control Rod Lifetime Limits
2/26/2021
Procedures
Maximum Subcritical Banked Withdrawal Position
BWR Control Blade Lifetime Management
16