IR 05000220/2023001
ML23125A005 | |
Person / Time | |
---|---|
Site: | Nine Mile Point ![]() |
Issue date: | 05/05/2023 |
From: | Erin Carfang NRC/RGN-I/DORS |
To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
References | |
IR 2023001 | |
Download: ML23125A005 (1) | |
Text
May 5, 2023
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000220/2023001 AND 05000410/2023001
Dear David Rhoades:
On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station. On April 20, 2023, the NRC inspectors discussed the results of this inspection with Peter Orphanos, Site Vice President, and other members of your staff.
The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Nine Mile Point Nuclear Station. 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 (CFR) 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:
05000220/2023001 and 05000410/2023001
Enterprise Identifier: I-2023-001-0045
Licensee:
Constellation Energy Generation, LLC
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
January 1, 2023 to March 31, 2023
Inspectors:
G. Stock, Senior Resident Inspector
C. Kline, Resident Inspector
B. Sienel, Resident Inspector
J. Kulp, Senior Reactor Inspector
S. Veunephachan, 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, 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. A licensee-identified NCV is documented in report section 71111.1
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On January 7, 2023, the unit was downpowered to 88 percent for a control rod pattern adjustment and returned to rated thermal power on January 8, 2023. On January 17, 2023, the unit was downpowered to 93 percent to perform suppression testing following the identification of a leaking fuel assembly. On January 18, 2023, power was raised to 95 percent and the unit began end of cycle coastdown.
On March 12, 2023, the unit was downpowered to enter the Unit 1 refueling outage and the unit was shut down March 13, 2023. The unit remained shut down for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On January 6, 2023, the unit was downpowered to 65 percent for a reactor feedwater pump swap and was returned to rated thermal power on the same day. On March 4, 2023, the unit was downpowered to 62 percent for a reactor feedwater pump swap, scram time testing, turbine valve testing, and a control rod pattern adjustment. The unit was returned to rated thermal power on March 6, 2023 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, 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for impending adverse weather for a wind chill warning on February 3, 2023.
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01) (7 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 'B' residual heat removal system on January 10, 2023
- (2) Unit 2 high pressure core spray system on February 8, 2023
- (3) Unit 2 reactor core isolation cooling (RCIC) on February 21, 2023
- (4) Unit 1 core spray train 121 on March 15, 2023
- (5) Unit 1 shutdown cooling 12 on March 16, 2023
- (6) Unit 1 emergency diesel generator 103 on March 17, 2023
- (7) Unit 1 spent fuel pool cooling 11 on March 28, 2023
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (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 reactor building 175' north, fire area 1, on January 4, 2023
- (2) Unit 1 emergency diesel generator 103 room, fire area 19, on January 13, 2023
- (3) Unit 1 emergency diesel generator 102 room, fire area 22, on January 19, 2023
- (4) Unit 1 turbine building 291' north, fire area 5, on February 14, 2023
- (5) Unit 2 diesel fire pump room, screenwell 261', fire area 71, on February 15, 2023
- (6) Unit 1 main steam line room, fire area T1A, on March 13, 2023
- (7) Unit 1 condenser bay, fire area 5, on March 14, 2023
- (8) Unit 1 heater bay, fire area 5, on March 14, 2023
- (9) Unit 1 drywell, fire area 3, on March 16, 2023
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1 reactor building closed loop cooling 12 heat exchanger
71111.08G - Inservice Inspection Activities (BWR)
BWR Inservice Inspection Activities - 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 May 14, 2023 to April 17, 2023:
- ECP-21-000197-CN-001, Flaw Evaluation of the Unit 1 Recirculation Nozzles (N1C
& N1D) Nozzle to Safe End Axial Indications, Revision 0
- Encoded Phased Array Ultrasonic Examination of the N1A Nozzle to Safe End Weld 32-WD-002, (1R27-ISI-VE-030)
- Encoded Phased Array Ultrasonic Examination of the N1B Nozzle to Safe End Weld 32-WD-045 (1R27-ISI-VE-031)
- Encoded Phased Array Ultrasonic Examination of the N1C Nozzle to Safe End Weld 32-WD-085 (1R27-ISI-VE-021)
- Encoded Phased Array Ultrasonic Examination of the N1D Nozzle to Safe End Weld 32-WD-125 (1R27-ISI-VE-018)
- Encoded Phased Array Ultrasonic Examination of the N2E Nozzle to Safe End Weld Overlay, (N2ENMPU1ND1)
- General Visual Examination of the Moisture Barrier Between Concrete Floor and Steel Shell - 90 to 360 degree Azimuth (1R27-IWE-VT-035)
- General Visual Examination of the Moisture Barrier Between Concrete Floor and Steel Shell - 0 to 90 degree Azimuth (1R27-IWE-VT-045)
- In-vessel Visual Examination of Core Spray Sparger Nozzles (N1R27 CSS-S3a-A-23A)
- In-vessel Visual Examination of Tie Rod 166W (N1R27 SHD TR 166 W Dimension 165)
- Manual Ultrasonic Examination of Emergency Condenser Steam Inlet Line Pipe to Elbow Weld (1R27-ISI-UT-033)
- N1R27 Weld Overlay Nozzle N2E (C93903029)
- Ultrasonic Thickness Examination of Internal Ring Header 1 through 20 (1R27-IWE-UT-007)
- Visual Examination (VT1) on Repaired Locations of Drywell Moisture Barrier (1R27-VT-23-039)
- Visual Examination (VT2) on N13B RPV Instrumentation Nozzle, (NMP1-VT-23-014)
- Visual Examination (VT2) on N14B RPV Instrumentation Nozzle, (NMP1-VT-23-017)
- Visual Examination (VT2) on N15B RPV Instrumentation Nozzle, (NMP1-VT-23-018)
- Visual Examination (VT2) on N16B RPV Instrumentation Nozzle, (NMP1-VT-23-019)
- Visual Examination (VT2) on N17B RPV Instrumentation Nozzle, (NMP1-VT-23-020)
- Visual Examination (VT3) of Internal Ring Header, Bays 1 through 20, (1R27-IWE-VT-044)
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 2 operations personnel during a reactor downpower to 62 percent and control rod scram time testing on March 4, 2023.
- (2) The inspectors observed Unit 1 operations personnel during the reactor shutdown for refueling outage N1R27.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed a Unit 2 simulator evaluation that included a reactor coolant leak culminating in the declaration of a Site Area Emergency on January 31, 2023.
- (2) The inspectors observed a Unit 1 simulator evaluation that included a 13 feedwater flow control valve failure, a loss of power board 102, a loss of condenser vacuum, and a large break loss-of-coolant accident with loss of level indication on February 14, 2023.
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 remain capable of performing their intended function:
- (1) Unit 1 emergency diesel generator 103
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (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) Unit 2 Division I air conditioning (A/C) fan failure on January 27, 2023
- (2) Unit 1 elevated risk during 12 reactor building closed loop cooling heat exchanger maintenance on February 6, 2022
- (3) Unit 2 elevated risk during RCIC system outage on February 6, 2023
- (4) Unit 2 elevated risk during emergent work on RCIC keep fill pump discharge line on February 13, 2023
- (5) Unit 1 elevated risk during emergent maintenance on the diesel fire pump on February 15, 2023
- (6) Unit 1 elevated risk during planned reactor cavity floodup on March 14, 2023
- (7) Unit 1 elevated risk during planned reactor cavity draindown on March 28, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 diesel driven fire pump due to coolant leak on January 24, 2023
- (2) Unit 2 high pressure core spray due to surveillance test below specification recirculating flow on January 26, 2023
- (3) Unit 1 emergency diesel generator 103 fuel oil normal level switch degraded identified during surveillance testing on February 27, 2023
- (4) Unit 2 Division II standby diesel generator due to exhaust fan trip after automatic start during a surveillance on March 6, 2023
- (5) Unit 1 diesel generator 103 due to loss of power board 171A on March 10, 2023
- (6) Unit 1 diesel generator 102 due to output breaker failure to close during testing on March 23, 2023
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) Temporary Modification: ECP-23-000038, Division I Control Room A/C Fan Motor Replacement
- (2) Permanent Modification: ECP-22-000042, Replace Obsolete GEMAC Steam Flow Indication with NUS Module
- (3) Permanent Modification: ECP-22-000396, Unit 1 Suppression Chamber (Torus)
Minimum Wall Thickness Optimization
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage (IP Section 03.01) (1 Partial)
- (1) The inspectors evaluated Unit 1 refueling outage N1R27 activities from March 13 through 31, 2023.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (IP Section 03.01) (2 Samples)
- (1) Control room emergency filtration system following A/C fan motor replacement on January 29, 2023
- (2) Unit 1 power board 102 following loss of voltage relay replacement on March 23, 2023
Surveillance Testing (IP Section 03.01) (5 Samples)
- (1) N1-ST-M4A, Emergency Diesel Generator 102 and power board (PB) 102 Operability Test, on January 23, 2023
- (2) N1-ST-M4B, Emergency Diesel Generator 103 and PB 103 Operability Test, on February 13, 2022
- (3) N1-ST-V8, Main steam, feedwater/high pressure coolant injection, shutdown cooling, emergency cooling, Reactor Head Vent Valve Cold Shutdown Operability Test, on March 13, 2023
- (4) N1-ST-R9A, Core Spray Loop 11 Operability Test Using Demineralized Water, on March 15, 2023
- (5) N1-ST-C1A, Liquid Poison Functional Test Using Demineralized Water with Squib Valve Plugs Removed, on March 20, 2023
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) N2-OSP-SWP-Q005, Division III Service Water Operability Test, on January 23, 2023
- (2) N2-OSP-ICS-Q@002, RCIC Pump and Valve Operability Test and System Integrity Test, on February 9, 2023
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) N1-ST-TYC-001, Main steam isolation valve Type C Leak Rate Tests, Attachment 16, on March 13, 2023
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated:
- (1) The inspectors evaluated a Unit 1 simulator scenario that included a large break loss-of-coolant accident with loss of level indication requiring a Site Area Emergency declaration on February 14,
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 the licensee 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) Licensee surveys of potentially contaminated material leaving the radiologically controlled area
- (2) Workers exiting the radiologically controlled area at Unit 1 during refueling outage N1R27
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) RWP-23-00805
- (2) VLV-39-50 breach and valve replacement
- (3) RWP 23-00513
- (4) Torus diving and torus vacuuming
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Unit 2 reactor water cleanup phase separator aisle, reactor building, 289' elevation
- (2) Unit 1 cleanup demineralizer 11, reactor building, 261' elevation
- (3) Unit 1 drywell entrance, 237' elevation
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.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, and
Transportation
Shipment Preparation (IP Section 03.04)
- (1) The inspectors observed the preparation and shipment of radioactive waste shipment: 22-2056, LSA-II, Bead Resin Liner. Manifest Number: 1039-C-0068
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours (IP Section 02.01)===
- (1) Unit 1, January 1, 2022 through December 31, 2022
- (2) Unit 2, January 1, 2022 through December 31, 2022
IE03: Unplanned Power Changes per 7000 Critical Hours (IP Section 02.02) (2 Samples)
- (1) Unit 1, January 1, 2022 through December 31, 2022
- (2) Unit 2, January 1, 2022 through December 31, 2022
IE04: Unplanned Scrams with Complications (IP Section 02.03) (2 Samples)
- (1) Unit 1, January 1, 2022 through December 31, 2022
- (2) Unit 2, January 1, 2022 through December 31, 2022
===71153 - Follow-up of Events and Notices of Enforcement Discretion
Event Follow-up (IP Section 03.01)===
- (1) Unit 2 Division I control room A/C fan failure on January 26,
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.12 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy.
Violation: 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems and components. The safety-related Nine Mile Point Unit 2 Division I control room chiller is required to maintain control room habitability during an event. On December 8, 2022, the Division I control room chiller tripped on high motor windings temperature due to a degraded relay.
Contrary to above, on December 8, 2022, Constellation failed to establish measures for the selection of parts that are essential to the safety-related functions of the Division I control room chiller. Specifically, a non-safety-related relay was installed following the identification of a degraded high motor temperature trip module relay. The chiller was restored to operable and during work package review Constellation identified that the incorrect relay was installed. The unit was taken out of service and the relay was replaced with a safety-related relay.
Significance/Severity: Green. The inspectors determined this issue to be Green in accordance with IMC 0609 Appendix A, Exhibit 3 because the finding did not represent a degradation to the radiological barrier function provided for the control room or the barrier function of the control room against smoke or a toxic atmosphere.
Corrective Action References: IR
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 23, 2023, the inspectors presented the radiation hazard assessment and control inspection results to Joseph Garcia, Radiation Protection Manager, and other members of the licensee staff.
- On April 20, 2023, the inspectors presented the integrated inspection results to 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
Corrective Action
Documents
04562615
Drawings
C-18007-C
Reactor Core Spray P&ID
C-18008-C
Spent Fuel Storage Pool Filtering and Cooling System P & I
Diagram
C-18018-C
Reactor Shutdown Cooling P & I Diagram
PID-31B
Piping & Instrumentation Diagram Residual Heat Removal
PID-31E
Piping & Instrumentation Diagram Residual Heat Removal
PID-31F
Piping & Instrumentation Diagram Residual Heat Removal
PID-33A
Piping & Instrumentation Diagram High Pressure Core Spray
System
PID-33B
Piping & Instrumentation Diagram High Pressure Core Spray
System
Procedures
N1-OP-2
Core Spray System
03900
N1-OP-45
05100
N1-OP-6
Fuel Pool Filtering and Cooling System
03100
N2-OP-31
Residual Heat Removal System - Lineups
03900
N2-OP-31-
Lineups
Residual Heat Removal System - Lineups
00300
N2-OP-33
High Pressure Core Spray System
01900
N2-OP-33-
Lineups
High Pressure Core Spray System - Lineups
00100
N2-OP-35
Reactor Core Isolation Cooling
01800
N2-OP-35-
Lineups
Reactor Core Isolation Cooling - Lineups
200
N2-OSP-RHS-
R@005
RHS Pressure Isolation Valve Leakage Test
00501
Fire Plans
N1-PFP-0101
Unit 1 Pre-Fire Plans
00700
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N2-FPI-PFP-0201 Unit 2 Pre-Fire Plans
Miscellaneous
DCD-805
Nine Mile Point Unit 1 NFPA 805 Design Criteria
Procedures
Service Water Heat Exchanger Inspection Guide
GAP-HSC-02
System Aging Inspection and Cleanliness Controls
2100
Work Orders
C93804532
71111.08G Corrective Action
Documents
04412326
04412423
04565322
04565598
Miscellaneous
Submittal of Emergency Relief Request I5R-11 Concerning
the Installation of a Weld Overlay on Reactor Pressure
Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle
Dissimilar Metal Weld (32-WD-208) (ML23083B991)
Verbal Authorization for NMP1 Proposed Alternative Weld
Overlay N2E Safe End to Nozzle DM Weld (EPID L-2023-
LLR-0011) (ML23090A130)
Verbal Authorization for NMP1 Relief Request I5R-14
Proposed Alternative Associated with N2E Safe End to
Nozzle DM Weld Repair with a Laminar Indication (EPID L-
23-LLR-0017) (ML23104A347)
Work Orders
C93802542
71111.11Q Procedures
N1-OP-43C
Plant Shutdown
030
N2-OSP-RMC-
@001
Control Rod Drive Scram Insertion Time Testing
2700
Corrective Action
Documents
04542590
04543095
04544400
04544741
Miscellaneous
Maintenance Rule System Basis Document for Unit 1
01/24/2023
Work Orders
C93765330
C93893496
Corrective Action
Documents
04450549
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N1-PM-34B
Reactor Cavity Draindown
001
N2-OP-35
Reactor Core Isolation Cooling
01800
Protected Equipment Program
Corrective Action
Documents
04549902
04549997
04557550
04559843
04564239
04564525
Procedures
N1-OP-45
05100
N1-ST-M4A
Emergency Diesel Generator 102 and PB 102 Operability
Test
03100
N2-OP-100A
Standby Diesel Generators
03300
N2-OP-57
Diesel Generator Building Ventilation System
01100
N2-OSP-CSH-
Q@002
HPCS Pump and Valve Operability Test
01100
Work Orders
C93903401
Corrective Action
Documents
04550549
04550876
Engineering
Changes
ECP-22-000396
Unit 1 Suppression Chamber (Torus) Minimum Wall
Thickness Optimization
ECP-23-000038
2HVC*ACU1A Motor Replacement
Miscellaneous
NER-1I-003
Nuclear Engineering Report
Work Orders
C93896666
Procedures
N1-PM-34A
Reactor Cavity Flood Up
N1-PM-34B
Reactor Cavity Drain Down
OU-NM-103-101
Shutdown Safety Management Program
00800
Corrective Action
Documents
04540322
04553684
04561743
Procedures
N1-RCSP-GEN-
334
Operating Cycle Calibration for Loss and Degraded Voltage
Relays on Emergency Switchgear
00700
N1-RCSP-GEN-
Functional Test of 4.16KV Emergency Bus Loss and
00100
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
335
Degraded Voltage Relays
N1-ST-C1A
Liquid Poison Functional Test Using Demineralized Water
with Squib Valve Plugs Removed
N1-ST-M4A
Emergency Diesel Generator 102 and PB 102 Operability
Test
03100
N1-ST-R9A
Core Spray Loop 11 Operability Test Using Demineralized
Water
001
N1-ST-TYC-001
MSIV [main steam isolation valve] Type C Leak Rate Tests
00300
N1-ST-V8
MS, FW/HPCI, SDC,EC, RX Head Vent Valve Cold S/D
Operability Test
200
N1-STM4B
Emergency Diesel Generator 103 and PB 103 Operability
Test
2700
N2-OSP-HVC-
M001
Control Room Emergency Filtration (CREF) System
00500
N2-OSP-ICS-
Q@002
RCIC Pump and Valve Operability Test and System Integrity
Test and ASME XI Functional Test and Analysis
01800
N2-OSP-SWP-
Q005
Division III Service Water Operability Test
00500
Work Orders
C93684058
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
Corrective Action
Documents
04550549