IR 05000220/2022004
| ML23020A103 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 01/23/2023 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| References | |
| IR 2022004 | |
| Download: ML23020A103 (1) | |
Text
January 23, 2023
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000220/2022004 AND 05000410/2022004
Dear David Rhoades:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2. On January 20, 2023, the NRC inspectors discussed the results of this inspection with Alexander Sterio, Plant Manager, 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 (10 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:
05000220/2022004 and 05000410/2022004
Enterprise Identifier: I-2022-004-0036
Licensee:
Constellation Energy Generation, LLC
Facility:
Nine Mile Point Nuclear Station
Location:
Oswego, NY
Inspection Dates:
October 1, 2022 to December 31, 2022
Inspectors:
G. Stock, Senior Resident Inspector
C. Kline, Resident Inspector
B. Sienel, Resident Inspector
T. Fish, Senior Operations Engineer
S. Haney, Senior Project Engineer
K. Murphy, Operations Engineer
P. Ott, Operations Engineer
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, 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
Type Issue Number Title Report Section Status LER 05000410/2022-002-00 Reactor Protection System Actuation While Shutdown 71153 Closed LER 05000410/2022-002-01 Reactor Protection System Actuation While Shutdown 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On November 5, 2022, the unit was downpowered to 90 percent to secure reactor recirculation motor-generator set 14 and conduct a load line adjustment. The unit was returned to rated thermal power on November 6, 2022. On November 8, 2022, the unit was downpowered to 70 percent to restore reactor recirculation motor-generator set 14 and conduct a rod pattern adjustment. The unit was returned to rated thermal power on November 9, 2022. On December 2, 2022, the unit was downpowered to 92 percent for a load line adjustment. The unit was returned to rated thermal power on December 3, 2022. On December 20, 2022, the unit was downpowered to 70 percent to conduct a rod pattern and load line adjustment. The unit returned to rated thermal power on December 21, 2022 and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On November 18, 2022, the unit was downpowered to 78 percent for control rod sequence exchange. The unit returned to rated thermal power on November 19, 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, 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
Seasonal Extreme Weather (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:
- Unit 1 125 volts direct current power distribution system on December 5, 2022
- Unit 2 control room ventilation on December 5, 2022
Impending Severe Weather (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather for a lake effect snow warning on November 17, 2022.
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 Division I diesel generator on October 31, 2022
- (2) Unit 1 111 containment spray on November 10, 2022
Complete Walkdown (IP Section 03.02) (1 Sample)
- (1) Unit 1 125 volts direct current power distribution system on October 21, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (IP Section 03.01) (5 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 240 south, fire area 3, on October 5, 2022
- (2) Unit 2 control building 237, Division II cable spreading room, fire area 19, on October 12, 2022
- (3) Unit 2 control building 237, Division I cable spreading room, fire area 17, on October 12, 2022
- (4) Unit 2 diesel generator building 261', high pressure core spray diesel generator room, fire area 30, on November 15 through 18, 2022
- (5) Unit 1 turbine building 261 north center, fire area 9, on December 2, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1 reactor building southeast corner room on December 12, 2022
- (2) Unit 2 reactor building 240' north auxiliary bay on December 12, 2022
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (2 Samples)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the Unit 1 requalification annual operating exams administered October through November 2022.
- (2) The inspectors reviewed and evaluated the Unit 2 licensed operator annual requalification results for the annual operating exams completed on December 2, 2022.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations
The inspectors evaluated the quality of the Unit 1 biennial requalification written examinations administered October through November, 2022.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the Unit 1 annual requalification operating test administered November 14 through 18, 2022.
Administration of an Annual Requalification Operating Test
The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
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 and evaluated licensed operator performance in the control room during a downpower to 90 percent to remove the reactor recirculation motor-generator set 14 from service and perform a control rod pattern adjustment on November 5, 2022.
- (2) The inspectors observed Unit 2 operations personnel during restoration from low pressure core spray maintenance and a standby liquid control surveillance on December 21, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
- (1) The inspectors observed a Unit 1 annual simulator examination that included a control rod drive pump trip, a loss of offsite power, a reactor scram, and a stuck open electromatic relief valve on November 8, 2022.
- (2) The inspectors observed a Unit 2 annual simulator evaluation that included a degrading condenser vacuum, a failure in the digital feedwater level control system, a trip of a reactor building closed loop cooling pump, a reactor core isolation cooling (RCIC) steam leak inside the RCIC pump room, and a high power anticipated transient without scram resulting in an Alert declaration on November 9, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended functions:
- (1) Unit 2 source range monitors
- (2) Unit 2 main steam isolation valves
- (3) Unit 1 average power range monitors
- (4) Unit 2 reactor core isolation cooling
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (3 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 Division I residual heat removal scheduled outage window on October 18, 2022
- (2) Unit 1 elevated risk during planned 11 high pressure coolant injection maintenance window on October 20, 2022
- (3) Unit 2 elevated risk during planned high pressure core spray relay testing on October 24, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 emergency diesel generator 102 following circulating oil pump trip on October 10, 2022
- (2) Unit 2 diesel driven fire pump due to jacket water leak on October 17, 2022
- (3) Unit 2 high pressure core spray pump due to differential pressure below acceptance criteria on November 1, 2022
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Permanent Modification - ECP-19-000052, Unit 2 Standby Liquid Control System Test Flow Indicator
- (2) Permanent Modification - ECP-20-000069, Replace Unit 1 Drywell Continuous Airborne Monitors
71111.19 - Post-Maintenance Testing
Post-Maintenance Test (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 2 'A' residual heat removal following scheduled outage window on October 19, 2022
- (2) Unit 1 core spray 111 following outboard isolation valve breaker replacement on October 21, 2022
- (3) Unit 1 emergency diesel generator 102 following system outage window on October 24, 2022
- (4) Unit 2 high pressure core spray following system outage window on October 27, 2022
- (5) Unit 2 Division II emergency diesel generator following scheduled outage window on November 4, 2022
- (6) Unit 2 reactor coolant system following 'A' recirculation pump seal replacement on November 15, 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) (3 Samples)
- (1) N1-ST-Q3, High Pressure Coolant Injection Pump and Check Valve Operability Test on October 27, 2022
- (2) N2-OSP-EGS-R002, Operating Cycle Diesel Generator 24 Hour Run Division I and Division II, on November 16, 2022
- (3) N1-ISP-036-004, Low-Low Reactor Level Instrument Trip Channel Test/Calibration, on November 30,
RADIATION SAFETY
71124.04 - Occupational Dose Assessment
Internal Dosimetry (IP Section 03.03) (1 Sample)
The inspectors evaluated the following internal dose assessments:
- (1) Internal dose assessment associated with ingestion investigation for individual working on the Unit 2 refuel floor. Investigation commenced on March 13, 2022 (Issue Report (IR) 04484571).
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicator submittals listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (October 1, 2021 through September 30, 2022)
- (2) Unit 2 (October 1, 2021 through September 30, 2022)
OR01: Occupational Exposure Control Effectiveness (IP Section 02.15) (1 Sample)
- (1) July 1, 2021 through September 30, 2022
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences (IP Section 02.16) (1 Sample)
- (1) July 1, 2021 through September 30, 2022
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 04481795 - Unit 2 Service Water Pump 'B' (2SWP*P1B) Failure to Start
- (2) IR 04435353 - Evaluation of Nine Mile Point Operator Work-Around Program
- (3) IR 04520704 - Unit 2 Reactor Pressure Vessel Low Water Level During Plant Cooldown
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue.
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000410/2022-002-00 and LER 05000410/2022-002-01, Reactor Protection System Actuation While Shutdown (ADAMS Accession Nos. ML22312A003 and ML22362A073, respectively). The inspection conclusions associated with these LERs are documented in this report under Inspection Results.
INSPECTION RESULTS
Minor Violation 71152A Minor Violation: On September 4, 2022, Unit 2 entered hot shutdown to commence a maintenance outage due to degrading 'A' reactor recirculation pump seal leakage. During the reactor cooldown, reactor water level lowered to Level 3 which actuates the reactor protection system (RPS) and a SCRAM signal. At the time of the actuation and SCRAM signal, all control rods were fully inserted and isolations caused by a SCRAM signal, Groups 4 and 5, were already complete, so no equipment changed state as a result of the SCRAM signal. Constellation initiated Issue Report 04520704 and performed a corrective action program evaluation due to the event. The cause identified was a lack of procedural guidance in N2-SOP-101C, "Reactor SCRAM," in that the procedure did not direct the operator responsible for plant cooldown to the appropriate procedure detail. This resulted in a rapid opening and closure of the bypass valves that complicated level control, resulting in the Level 3 and RPS actuation.
The inspectors reviewed Constellations corrective action program evaluation regarding the Level 3 and RPS actuation. This included the associated procedures, corrective actions, and extent of condition. Constellations failure to provide an adequate procedure for plant cooldown following a SCRAM is a performance deficiency.
This review closes LERs 05000410/2022-002-00 and 05000410/2022-002-01.
Screening: The inspectors determined the performance deficiency was minor. The inspectors evaluated the inadequate procedure for significance in accordance with the guidance in IMC 0612, Appendix B, "Issue Screening" and Appendix E, "Examples of Minor Issues." The performance deficiency was minor because it did not adversely impact a cornerstone objective.
Enforcement:
This failure to comply with 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: IR 04435353 - Evaluation of Nine Mile Point Operator Work-Around Program 71152A In inspection report 05000220/2021002 the inspectors identified a minor performance deficiency associated with Nine Mile Points application of the Operator Work-Around Program. IR 04435353 was originated on July 16, 2021 to document benchmarking the Constellation fleet on the operator work-around classification process based on inspector concerns. The benchmark determined that Nine Mile Points interpretation of the definition of an operator work-around was different than the rest of the Constellation fleet. The benchmark found that peers interpret any deficiency on equipment used in emergency or abnormal operating procedures - no matter how long additional operator actions may take - as an operator work-around. As a result, two conditions were reclassified as an operator work-arounds (IR 04277608 and IR 04409500).
Inspectors reviewed equipment deficiencies that met the criteria for consideration under procedure OP-AA-102-103, Operator Work-Around Program, as an operator work-around or an Operator Challenge. Operator Work-Around Program guidance grants wide latitude in final classification of specific deficiencies as work-arounds or challenges, however one equipment deficiency was identified as likely worth consideration by the Work-Around Board. On April 10, 2022, control rod drive supply header flow controller 2RDS-FC-107 was placed in manual to correct flow oscillations that occurred when the system was placed in automatic (IR 04491945). This flow controller, under normal operations, operates in automatic, however, manual control is a proceduralized mode of operation. This condition is consistent with at least one criterion for consideration as an Operator Challenge in accordance with Section 2.2.1 of OP-AA102-103 and previous benchmark interpretations. Following inspector questioning, Nine Mile Point staff reviewed the issue during the quarterly operator work-around meeting and determined that the condition did not require designation as an Operator Work-Around or Operator Challenge.
Observation: IR 04481795 - Unit 2 Service Water Pump 'B' Failure to Start 71152A The inspectors reviewed Constellations corrective actions regarding the failure of the 'B' service water pump failure to start during performance of N2-OSP-SWP-Q004, "Division II Service Water Operability Test," Section 6.1, on March 2, 2022. Constellation declared the pump inoperable, and removed its circuit breaker from service. The circuit breaker auxiliary switch was identified to have high resistance. Constellation burnished the contacts to reduce the contact resistance, and returned the pump to operable. Constellation generated IR 04481795 and performed a work group evaluation that determined the likely cause of the 2SWP*P1B failure was high contact resistance on an auxiliary switch contact internal to the pump's circuit breaker. The circuit breaker was installed following refurbishment in June 2021 during which a satisfactory resistance check of the auxiliary switch was performed.
The inspectors reviewed Constellations IR, breaker preventive maintenance procedure, work orders, preventive maintenance history, and applicable engineering and corrective action program procedures to assess Constellations conclusions and corrective actions.
Observation: Semi-Annual Trend Review 71152S The inspectors evaluated a sample of issues and events that occurred from July 2022 through December 2022 to determine whether issues were appropriately considered as emerging or adverse trends. The inspectors verified issues were appropriately evaluated by Constellation staff for potential trends and addressed within the scope of the corrective action program or through department review.
The inspectors did not identify any new trends that could indicate a more significant safety issue. Constellation noted a decreasing trend in the Unit 2 'A' recirculating pump upper seal pressure as documented in Issue Reports 04509732 and 04520600. A maintenance outage was subsequently conducted to replace the seal in September 2022. The inspectors also noted other minor potential adverse trends identified by Constellation including Unit 1 card reader errors, Unit 2 instrument air line breaks in feedwater and condensate systems, and Unit 1 intermediate range monitor undervessel connection issues.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On December 8, 2022, the inspectors presented the radiation protection performance indicator verification inspection results to Joseph Garcia, Senior Manager, Site Radiation Protection, and other members of the licensee staff.
- On January 20, 2023, the inspectors presented the integrated inspection results to Alexander Sterio, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
04540975
Procedures
N1-OP-64
Meteorological Monitoring
2100
Procedures
N2-OP-102
Meteorological Monitoring
2800
Procedures
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
Work Orders
C92028587
Work Orders
C92028834
Work Orders
C93797410
Work Orders
C93801639
Corrective Action
Documents
04370026
Corrective Action
Documents
04413071
Corrective Action
Documents
04427094
Corrective Action
Documents
04434108
Corrective Action
Documents
04442230
Corrective Action
Documents
Resulting from
Inspection
04531279
Drawings
C-18012-C-001
Reactor Containment Spray Raw Water System P & I
Diagram
Drawings
C-18012-C-002
Reactor Containment Spray System P & I Diagram
Drawings
C-19839-C
One line diagram 125 VDC Control Bus
Miscellaneous
25 VDC Electrical Distribution System
Procedures
N1-EPM-SB-
A264
24/48 VDC and 125 VDC Battery Cell Visual Inspection and
Rack Integrity Check
00401
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N1-ESP-SB-275
25 VDC Battery Cell Surveillance
01500
Procedures
N1-OP-47A
25 VDC Power System
200
Procedures
N1-PM-S1
Operator's Rounds Guide
03800
Procedures
N2-OP-100A-
Lineups
Standby Diesel Generators - Lineups
00600
Work Orders
C9362607
Work Orders
C93777231
Drawings
PID-43B
Piping and Instrumentation Diagram Fire Protection - Water
Drawings
PID-43E
Piping and Instrumentation Diagram Fire Protection - Water
Drawings
PID-43F
Piping and Instrumentation Diagram Fire Protection - Water
Fire Plans
N1-PFP-0101
Unit 1 Pre-Fire Plans
00700
Fire Plans
N2-FPI-PFP-0201 Unit 2 Pre-Fire Plans
00700
Drawings
PID-63 A-E
Reactor Building Equipment and Floor Drains
Miscellaneous
Nine Mile Point Unit 1 Individual Plant Evaluation
07/1993
Procedures
N2-OP-63
Reactor Building Drains
71111.11Q Procedures
N2-OSP-CSL-
Q@002
LPCS Pump and Valve Operability and System Integrity Test
01500
71111.11Q Procedures
N2-OSP-SLS-
Q001
Standby Liquid Control Pump, Check Valve, Relief Valve
Operability Test and ASME XI Pressure Test
2400
Corrective Action
Documents
04447270
Corrective Action
Documents
04459510
Corrective Action
Documents
04466406
Corrective Action
Documents
04483059
Corrective Action
Documents
04487461
Corrective Action
Documents
04522580
Miscellaneous
Unit 2 Main Steam Maintenance Rule Basis Document
Miscellaneous
Unit 2 Main Steam Health Group Issue Action Plan for IR
04483059
07/19/2022
Procedures
N1-ISP-092-348
Local Power Range Monitoring (LPRM) Calibration Channel
00500
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N2-OSP-ICS-
Q@002
RCIC Pump and Valve Operability Test and System Integrity
Test and ASME XI Functional Test
01700
Procedures
Protected Equipment Program
007
Procedures
OP-NM-108-117
Protected Equipment Program at Nine Mile Point
00500
Corrective Action
Documents
04529415
Corrective Action
Documents
04532840
Procedures
M2-0006
Inservice Testing Program Plan, Pump Curves and
Acceptance Criteria
Procedures
N1-OP-45
05100
Procedures
N2-OSP-CSH-
Q@002
HPCS Pump and Valve Operability and System Integrity
Test
01100
Procedures
N2-OSP-FOF-
M001
Engine Driven Fire Pump Operability & Storage Tank Level
Test
00600
Engineering
Changes
ECP-19-000052
Unit 2 Standby Liquid Control (SLS) Permanently Installed
Flow Metering
Engineering
Changes
ECP-19-000052-
001-CN-002
Update to Calculation Z400-8LPA-0479 Due to New Flow
Meter 2SLS-FE114 and Valve 2SLS*V171
Engineering
Changes
ECP-19-000052-
CN-005
Small Bore Piping and Instrument Tubing Support
Qualification for Support No. 2-SLS-15-PSR-02-C-2, 2-SLS-
19-PSR-01-C-4, 2-SLS-17-PSR-04-C-2
Engineering
Changes
ECP-20-000069
NMP Unit 1 Drywell Continuous Airborne Monitor (DW CAM)
Procedures
N1-OP-9
N2 Inerting and H2O2 Monitoring Systems
05600
Corrective Action
Documents
04532853
Procedures
N1-EPM-GEN-
2
Motor Control Center (7700 Line) Inspection
2300
Procedures
N1-EPM-GEN-
183
Molded Case Circuit Breaker Inspection
00800
Procedures
N1-ST-M4A
Emergency Diesel Generator 102 and PB 102 Operability
Test
030100
Procedures
N2-OSP-CSH-
HPCS Pump and Valve Operability and System Integrity
01100
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Q@002
Test
Procedures
N2-OSP-EGS-
M@001
Diesel Generator and Diesel Air Start Valve Operability Test
- Div I and II
2500
Procedures
N2-OSP-EGS-
R002
Operating Cycle Diesel Generator 24 Hour Run Division 1
and 2
01100
Procedures
N2-OSP-RCS-
@001
RCS Pressure/Temperature Verification
01100
Procedures
N2-OSP-RHS-
Q@004
RHR System Loop A Pump & Valve Operability Test and
System Integrity Test and ASME XI Pressure Test
01300
Procedures
N2-OSP-RPV-
@003
Reactor Pressure Vessel and All Class I System Leakage
Test with the RPV Solid
01400
Work Orders
C93635398
Work Orders
C93766808
Work Orders
C93802378
Work Orders
C93803590
Corrective Action
Documents
04539889
Procedures
N1-ISP-036-004
Low-Low Reactor Level Instrument Trip Channel
Test/Calibration
01500
Procedures
N1-ST-Q3
High Pressure Coolant Injection Pump and Check Valve
Operability Test
2000
Procedures
N2-OSP-EGS-
M@001
Diesel Generator Air Start Valve Operability Test-Division I
and II
2500
Procedures
N2-OSP-EGS-
R002
Operating Cycle Diesel Generator 24 Hour Run Division I
and II
01100
71151
Miscellaneous
Regulatory Assessment Performance Indicator Guideline
71151
Procedures
N1-MSPI-001
Nine Mile Point 1 MSPI Basis Document
71151
Procedures
N2-MSPI-001
Nine Mile Point 2 MSPI Basis Document
Corrective Action
Documents
04329282
Corrective Action
Documents
04413822
Corrective Action
Documents
04481795
Procedures
N2-OP-11
Service Water System
01500
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
N2-OSP-SWP-
Q004
Division II Service Water Operability Test
001100
Work Orders
C92707902
Work Orders
C92765737
Work Orders
C92863165
Work Orders
C93825512
Corrective Action
Documents
04509732
Corrective Action
Documents
04520600
Corrective Action
Documents
04524844
Corrective Action
Documents
04541104
Corrective Action
Documents
04545161