IR 05000220/2023003

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Integrated Inspection Report 05000220/2023003 and 05000410/2023003
ML23298A022
Person / Time
Site: Nine Mile Point  Constellation icon.png
Issue date: 10/25/2023
From: Erin Carfang
NRC/RGN-I/DORS
To: Rhoades D
Constellation Energy Generation, Constellation Nuclear
References
IR 2023003
Download: ML23298A022 (1)


Text

October 25, 2023

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000220/2023003 AND 05000410/2023003

Dear David Rhoades:

On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2. On October 19, 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 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:

DPR-63 and NPF-69

Report Numbers:

05000220/2023003 and 05000410/2023003

Enterprise Identifier: I-2023-003-0040

Licensee:

Constellation Energy Generation, LLC

Facility:

Nine Mile Point Nuclear Station

Location:

Oswego, NY

Inspection Dates:

July 1, 2023 to September 30, 2023

Inspectors:

C. Swisher, Senior Resident Inspector

J. England, Resident Inspector

E. Allen, Resident Inspector

C. Kline, Senior Resident Inspector

E. Miller, Reactor Inspector

B. Sienel, Resident Inspector

G. Stock, Reactor Operations Engineer

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.

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. The unit remained at or near rated thermal power for the entire inspection period.

Unit 2 began the inspection period at rated thermal power. On July 24, 2023, the unit was downpowered to 65 percent to secure the 'A' feedwater pump and start the 'C feedwater pump to establish conditions for modifications to the 'A' feedwater level control valve. The unit returned to rated thermal power on July 25, 2023. On July 29, 2023, the unit was downpowered to 62 percent to secure the 'C' feedwater pump and start the 'A' feedwater pump following the modifications on the 'A' feedwater level control valve. The unit returned to rated thermal power on the same day. On September 2, 2023, the unit experienced an automatic reactor scram caused by low reactor water level due to a loss of feedwater that was attributed to stem-to-plug separation on a feedwater level control valve. Startup commenced on September 7, 2023, and rated thermal power was reached September 10, 2023. The unit 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

71111.04 - Equipment Alignment

Complete Walkdown (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 containment spray system during the week of September 11, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection (IP Section 03.01) (7 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 1 offgas building 261', fire area 5, on July 5, 2023
(2) Unit 1 reactor building 261' east, fire area 1, on July 5, 2023
(3) Unit 1 cable spreading room 250', fire area 9, on July 5, 2023
(4) Unit 2 control building Division I vital switchgear and battery room, fire area 17, on July 6, 2023
(5) Unit 2 normal switchgear building, fire area 52, on July 6, 2023
(6) Unit 2 turbine building 277', east switchgear room, fire area 83, on August 22, 2023
(7) Unit 2 turbine building 277', west switchgear room, fire area 84, on August 22, 2023

Fire Brigade Drill Performance (IP Section 03.02) (2 Samples)

(1) The inspectors evaluated the on-site fire brigade training and performance during an unannounced fire drill on August 31, 2023.
(2) The inspectors evaluated the on-site fire brigade training and performance during an announced fire drill on September 14, 2023.

71111.06 - Flood Protection Measures

Flooding (IP Section 03.01) (2 Samples)

(1) The inspectors evaluated internal flooding mitigation protections in the Unit 2 switchgear foundation on July 5, 2023.
(2) The inspectors evaluated internal flooding mitigation protections in the Unit 2 pipe tunnel on July 11, 2023.

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 Unit 2 operations personnel during a downpower to 63 percent to swap the 'A' and 'C' reactor feedwater pumps to establish conditions for modifications to the 'A' feedwater level control valve on July 25, 2023.
(2) The inspectors observed and evaluated Unit 1 licensed operator performance in the control room during restoration and run of emergency diesel generator 103 following a system outage window on September 15, 2023.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed a Unit 1 simulator evaluation that included a seismic event, a failure of both seals in the 12 reactor recirculation pump, a control rod drift out, a loss of powerboard 12, and a large break loss of coolant accident inside containment on July 18, 2023.
(2) The inspectors observed a Unit 2 simulator evaluation that included a control rod drive pump trip, a loss of the Division II safety bus and an emergency diesel generator automatic start failure, a loss of main condenser vacuum, and an anticipated transient without a scram requiring an Alert declaration on August 8, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 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) Unit 1 12 H2O2 containment monitor failure
(2) Unit 1 intermediate range monitors following erratic indications
(3) Unit 1 emergency condenser 11 drain line steam leak

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:

(1) Unit 1 emergency diesel generator 103 air start tanks

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 scheduled activity to swap the 'A' and 'C' reactor feed pumps due to a feedwater level control valve lockup on July 28, 2023
(2) Unit 1 elevated risk during scheduled work on emergency diesel generator 103 the week of September 11, 2023
(3) Unit 1 elevated risk during scheduled work on the diesel-driven fire pump the week of September 18, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2 'E' service water pump due to seal leak on July 12, 2023
(2) Unit 1 drywell floor drain system due to intermittent increases in drywell floor drain leak rate on July 18, 2023
(3) Unit 2 diesel-driven fire pump due to a delayed start during surveillance testing on July 25, 2023
(4) Unit 1 emergency condenser snubber due to low fluid level on August 4, 2023
(5) Unit 1 seismic qualification of control room 'G' panel due to four average power range monitors' and intermediate range monitors' drawers being withdrawn on August 7, 2023
(6) Unit 1 primary containment due to indications of increased nitrogen makeup on August 8, 2023
(7) Unit 1 average power range monitoring systems due to exceeding 2,200 operating hours between traverse incore probe runs on August 18, 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) (15 Samples)

(1) N2-OSP-RHS-Q@001, Residual Heat Removal (RHR) System Loop A Valve Operability Test and American Society of Mechanical Engineers (ASME) XI Pressure Test Diagnostic Testing of Motor Operated Valves, on July 19, 2023
(2) N1-EPM-UPS-003, Uninterruptible power supply (UPS) Maintenance, on July 24, 2023
(3) N2-EPM-GEN-V582, Molded Case Circuit Breaker and Thermal Overload Relay Testing, 2FWS*LV10A positioner modification, on July 26, 2023
(4) N1-IPM-201-008, H2O2 Analyzers Support Instrumentation, on August 8, 2023
(5) N2-ESP-BYS-W675, 125 Volts direct current (DC) 2VBA*UPS2D Bi-Weekly Battery Surveillance, following oscillator card failure, on August 10, 2023
(6) N1-ISP-092-204, Intermediate Range Monitor 18 Calibration, following amplifier attenuation card replacement, on August 15, 2023
(7) Flex pump P1B following annual preventive maintenance on August 15, 2023
(8) Unit 2 motor operated valve 2GTS*MOV4A diagnostic testing, on August 16, 2023
(9) N2-IPM-NMS-@002, Source Range Monitor (SRM) B High Voltage (HV) Discriminator Testing for New Detector, on September 3, 2023
(10) Unit 2 MA-AA-716-234, FIN Team Process, for 2RCS*HYV17A retest, on September 4, 2023
(11) Unit 2 level control valve LV10A following partial disassembly for extent of condition evaluation, on September 4, 2023
(12) Unit 2 level control valve LV10B following stem and plug replacement, on September 11, 2023
(13) Unit 1 12 reactor water cleanup pump retest after maintenance was performed, on September 12, 2023
(14) N1-EMP-GEN-203, General Small Motor Maintenance, emergency diesel generator 103 fuel oil pump motor test, on September 15, 2023
(15) N1-PM-M9, Operation of Fire Pumps, following diesel fire pump fuel injector replacement, on September 21, 2023

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) N2-OSP-RHS-Q@004, RHR System Loop A Pump and Valve Operability Test and System Integrity Test and ASME XI Pressure Test, on July 19, 2023
(2) N2-ESP-ENS-Q731, Quarterly Channel Functional Test of low pressure core spray (LPCS)/low pressure coolant injection (LPCI) Pumps A, B, and C Auto Start Time Delay Relays Test, on July 20, 2023
(3) N2-OSP-EGS-R005, Diesel Generator ECCS emergency core cooling system (ECCS) Start Division III, on July 26, 2023
(4) N2-RESP-04, local power range monitoring (LPRM) Calibration, on August 24, 2023

Inservice Testing (IP Section 03.01) (1 Sample)

(1) N1-ST-Q6D, Containment Spray System Loop 122 Quarterly Operability Test, on July 11, 2023

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) N2-OSP-LOG-S001, Shift Checks - Mode 1, on July 13, 2023

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) S-PM-003, FLEX 450KW Portable Diesel Generator Test, on July 20, 2023 and September 6,

RADIATION SAFETY

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) RO-2 Ion chamber, S/N: 0025972, Unit 2 count room
(2) Ludlum 3 S/N: 0021702, Unit 2 count room
(3) PING monitor S/N: 225, Unit 1 radwaste building 261
(4) Telepole S/N: 25992, Unit 2 calibration room
(5) Eberline AMS-4, S/N: 0017971, Unit 2 refuel floor
(6) Eberline AMS-4, S/N: 1745/7146-9, Unit 1 turbine building 300'
(7) Ludlum 3030P, S/N: 0027975, Unit 1 reactor building 340'
(8) Ludlum frisker, S/N: 0022692, Unit 1 reactor building 340'

Calibration and Testing Program (IP Section 03.02) (13 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) RO-2, S/N: 2431 source check, Unit 2
(2) Ludlum model 177, S/N: 23379, Unit 2
(3) Small article monitor, S/N: 12252, Unit 2
(4) ARGOS-5AB, S/N: 1012-318, Unit 2
(5) BC-4, S/N: 580, Unit 2
(6) REM Ball, S/N: 22723, Unit 2
(7) Telepole, S/N: 0025993, Unit 2
(8) BC-4, S/N: 79, Unit 1
(9) Eberline AMS-4, S/N 1746/1741, Unit 1 RSSB 261
(10) Ludlum 3030P sample counter, S/N: 0015888, Unit 1
(11) Unit 2 wide-range gas monitor calibration (12)2022 Fastscan whole body count calibration report (13)2021 Fastscan whole body count calibration report Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Unit 2 Vent RM-200 wide-range gas monitor
(2) Unit 2 RE-146A service water liquid effluent monitor

71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,

and Transportation

Radioactive Material Storage (IP Section 03.01)

The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:

(1) Radioactive materials containers in the Unit 1 and Unit 2 radwaste building and cold storage building
(2) Part 37 radioactive materials and selected sealed sources

Radioactive Waste System Walkdown (IP Section 03.02) (2 Samples)

The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:

(1) Unit 1 and Unit 2 solid radioactive waste systems
(2) Unit 1 and Unit 2 radioactive liquid processing systems

Waste Characterization and Classification (IP Section 03.03) (2 Samples)

(1)2022 Part 61 Unit 2 condensate bead resin waste stream characterization and analysis

(2) 2022 Part 61 Unit 1 dry active waste stream characterization and analysis

Shipping Records (IP Section 03.05) (4 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) Shipment number 17-1231, UN 2916, Type B(U), Yellow-III, Class B mixed bed resin
(2) Shipment number 19-1103, UN 2916, Type B(U), Yellow-III, Class B filter sludge resin liner
(3) Shipment number 20-1114, UN 2916, Type B(U), Yellow-III, Class B mixed bed resin liner
(4) Shipment number 1039-C-0065, UN 3321, LSA-II, Class AU mixed bed resin liner

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (IP Section 02.04)===

(1) Unit 1 for the period of July 1, 2022 through June 30, 2023
(2) Unit 2 for the period of July 1, 2022 through June 30, 2023

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 for the period of July 1, 2022 through June 30, 2023
(2) Unit 2 for the period of July 1, 2022 through June 30, 2023

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 for the period of July 1, 2022 through June 30, 2023
(2) Unit 2 for the period of July 1, 2022 through June 30, 2023

===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) Issue Report (IR) 04490223 - Unit 2 Reactor Scram Due to Low Reactor Water Level
(2) IR 04525848 - GNF3 fuel bundle raised water rod
(3) IR 04520600 - Degrading Trend in 'A' Reactor Recirculation System Motor Upper Seal Pressure

INSPECTION RESULTS

Observation: GNF3 Fuel Bundle Raised Water Rod 71152A A Title 10 of the Code of Federal Regulations (10 CFR) Part 21 notification was issued to Nine Mile Point Nuclear Station for a raised water rod identified on a General Electric Global Nuclear Fuel GNF3 fuel bundle that was located at another nuclear site. This is the same fuel bundle design utilized at Nine Mile Point's Unit 2. The water rod is located in the center of the GNF3 fuel bundles and might not be attached properly to the bundle if not correctly oriented. This could result in the water rod being pressed upward and becoming lodged against the upper tie plate handle, which is utilized during fuel moves. The fuel bundles that are potentially affected by this issue were newly added to the Unit 2 core during the 2022 refueling outage. The analysis provided by the vendor supports the use of fuel bundles through their first cycle of operation, however, if any raised water rods are identified during the first refueling outage, then the bundle must be removed and cannot be utilized for another cycle of operation.

Constellation captured the 10 CFR Part 21 notification in IR 04525848, identified actions to identify any issues at Nine Mile Point during the next refueling outage, performed an analysis to validate the vendors analysis, and created a procedure change to independently verify correct orientation prior to transferring the fuel bundle to the fuel handler. Constellation will be performing an inspection of all the new fuel bundles prior to fuel moves during the 2024 refueling outage and will be redesigning the core as necessary to support the removal of any affected bundles from the core.

The inspectors did not identify any violations or performance deficiencies.

Observation: Degrading Trend in 'A' Reactor Recirculation System Pump Upper Seal Pressure 71152A The inspectors reviewed Constellations evaluation and corrective actions associated with the degradation and failure of the 'A' reactor recirculation pump upper seal on September 2, 2022. The failure of the pump seal required Unit 2 to initially downpower to 40 percent to investigate the seal and ultimately enter a maintenance outage for seal replacement.

In June 2022, Unit 2 operations personnel identified a degrading trend in 'A' reactor recirculation pump upper seal pressure. A maintenance outage was planned for September 9, 2022 to replace the seal. An adverse condition monitoring plan (ACMP) was established which defined upper seal pressures for operators to take action. On September 2, 2022, upper seal pressure began to degrade more rapidly coincident with a rise in drywell floor drain leakage from 0.22 gpm to 0.49 gpm. These conditions met the threshold in the ACMP for Unit 2 power to be lowered to 40 percent for a drywell entry to investigate the seal. The investigation found the seal was severely degraded and Unit 2 was shut down to replace the seal. During disassembly of the seal, lockwire that had broken free from the seal fasteners was found in the vicinity of the seal. Therefore, the assumed cause of the failure was foreign material intrusion. The recirculation pump seal was replaced, and Unit 2 was started up and no seal degradation was identified. Constellation generated IR 04520600 for the rapid degradation on the recirculation pump seal, and a corrective action program evaluation was performed to evaluate the failure. Many actions were initiated to address the lockwire that had become foreign material. Ultimately, the corrective action was to replace the recirculation pump seal, which was completed, and no further degradation was identified.

The degraded recirculation seal was sent to Constellation Powerlabs for failure analysis. While foreign material was identified near the seal upon disassembly, the failure analysis found the failure was likely caused by seal face delamination from nickel leaching. Both the seal manufacturer, Sultzer, and licensee subject matter experts found that the degradation on the seal face was not indicative of failure from foreign material intrusion. Furthermore, Powerlabs recovered material on the seal face during the analysis and the material identified was from the seal face itself and not the lockwire. Based on this information, additional actions were initiated to address the material condition of seals used for replacement. A number of Constellation sites have recently had recirculation seal challenges, so actions were initiated to establish fleet actions to improve seal reliability. This included additional actions during the procurement of seals and receipt inspection, updates to procedures for building seals, and visits to manufacturer facilities, including Sultzer, to ensure quality assurance standards were being met.

As part of the review, inspectors determined that no performance deficiencies exist as a result of the monitoring or the failure of the 'A' recirculation pump seal on September 2, 2022.

Inspectors did provide Constellation with an observation associated with the actions in response to the seal failure. Specifically, the actions associated with the material condition of the degraded seal are for a fleet initiative to be established to address seal failures at a number of Constellation sites. Inspectors determined that this was within Constellations process, however the observation was that Nine Mile Point is ultimately responsible for their structures, systems and components, not the Constellation fleet and a broad action from a fleet perspective, however comprehensive, could miss specific Nine Mile Point issues.

Observation: Unit 2 Reactor Scram Due to Low Reactor Water Level 71152A On April 5, 2022, Unit 2 received an automatic scram when the B feedwater flow control valve unexpectedly closed, and the subsequent lowering of reactor water level caused a low-level reactor scram to be generated. The inspectors reviewed a corrective action program root cause investigation report and associated corrective actions for a trend in incorrect procedure guidance during maintenance on a feedwater flow control valve.

Constellation captured the root cause investigation report in IR 04490223. Constellation determined as part of their investigation that a newly replaced primary feedback position potentiometer was placed into service with an unintentional position mismatch from the demand, resulting in an unexpected closure of the B feedwater flow control valve. The cause of the position mismatch was determined to be incorrect procedure guidance.

The inspectors reviewed the corrective action program products and did not identify any violations or performance deficiencies.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On October 19, 2023, the inspectors presented the integrated inspection results to Peter Orphanos, Site Vice President, and other members of the licensee staff.

THIRD PARTY REVIEWS

Inspectors reviewed Institute on Nuclear Power Operations reports that were issued during the inspection period for the evaluation conducted in July 2023.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Drawings

C-18012-C

Reactor Containment Spray System P & I Diagram Sheet 1

C-18012-C

Reactor Containment Spray System P & I Diagram Sheet 2

Procedures

N1-OP-14

Containment Spray System

04800

71111.05

Fire Plans

N1-PFP-0101

Unit 1 Pre-Fire Plans

00700

N2-FPI-PFP-0201 Unit 2 Pre-Fire Plans

Miscellaneous

DCD-80

Nine Mile Point Unit 1 NFPA 805 Design Criteria

Procedures

OP-AA-201-003

Fire Drill Performance

71111.11Q Corrective Action

Documents

04692308

04694012

Procedures

N2-OP-101D

Power Changes

03700

N2-SOP-06

Feedwater Failures

016

71111.12

Corrective Action

Documents

04068720

04421562

04422454

04543991

04690159

04694768

04697626

Procedures

N1-OP-9

N2 Inerting and H2O2 Monitoring System

05600

NMP-22-0029

Unit 1 102 EDG Air Start Tanks Long-Term Condition

Monitoring Plan

Work Orders

C93910105

71111.13

Corrective Action

Documents

04693370

Procedures

N2-OP-101D

Power Changes

03700

N2-SOP-06

Feedwater Failures

016

OP-AA-108-117

Protected Equipment Program

007

WC-AA-101-1006

On-line Risk Management and Assessment

004

71111.15

Corrective Action

Documents

04689471

04689809

04691678

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

04693080

04693318

04694029

04694596

04695094

04700633

Procedures

N2-OP-11

Service Water System

01500

N2-OSP-FOF-

M001

Engine Driven Fire Pump Operability and Storage Tank

Level Test

00600

N2-OSP-LOG-

S001

Shift Checks - Mode 1

03900

71111.24

Corrective Action

Documents

04693942

04689890

04704143

04704144

04704331

Procedures

MA-AA-716-234

FIN Team Process

MA-AA-723-300

Diagnostic Testing of Motor Operated Valves

014

N1-EMP-GEN-

203

General Small Motor Maintenance

00900

N1-EPM-UPS-

003

UPS Maintenance

006

N1-IPM-201-008

H2O2 Analyzers Support Instrumentation

00700

N1-ISP-092-204

Intermediate Range Monitor Calibration

01300

N1-OP-3

Reactor Water Cleanup Operation

05000

N1-PM-M9

Operation of Fire Pumps

01800

N1-ST-Q6D

Containment Spray System Loop 122 Quarterly Operability

Test

2

N2-EPM-GEN-

V582

Molded Case Circuit Breaker and Thermal Overload Relay

Testing

2600

N2-ESP-BYS-

W675

25 Volts DC Bi-Weekly Battery Surveillance

2000

N2-ESP-ENS-

Quarterly Channel Functional Test of LPCS/LPCI Pumps A,

00900

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Q731

B, and C Auto Start Time Delay Relays

N2-IPM-NMS-

@002

SRM B HV Discriminator Testing for New Detector

00400

N2-MPM-FWS-

6Y001

Level Control Valve Feedwater Flow PM

00100

N2-OSP-EGS-

R005

Diesel Generator ECCS Start Division III

00600

N2-OSP-LOG-

S001

Shift Checks - Mode 1

03900

N2-OSP-RHS-

Q@001

RHR System Loop A Valve Operability Test and ASME XI

Pressure Test

01000

N2-OSP-RHS-

Q@004

RHR System Loop A Pump and Valve Operability Test and

System Integrity Test and ASME XI Pressure Test

01300

N2-OSP-RHS-

R004

A Residual Heat Removal Valve Position Indication

Operability Test

01900

N2-RESP-04

LPRM Calibration

01100

S-EMP-GEN-007

Wiring Verification

00700

S-PM-001

FLEX 3419MX Water Pump Test

00300

S-PM-003

FLEX 450KW Portable Diesel Generator Test

00700

Work Orders

C93808196

C93822711

C93851989

C93897160

C93910430

C93912128

C93937425

C93940475

C93940477

C93940577

71151

Miscellaneous

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71152A

Corrective Action

Documents

04520600

04521714

04525848

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

04540162

04541135

04564318

Miscellaneous

ECP-22-000329

Lost Parts Evaluation - A Recirc Pump Upper Seal Failure

GNF-GEN-2022-

003

SC 22-04 Rev 2 - GNF3 Raised Water Rod - Final

Notification

11/30/2022

PRC 22-04

Raised Water Rod Evaluation

PRC-22-02809

Procedure Change Request for S-MMP-FHP-100

Procedures

NF-AB-120-2200

Reference Loading Pattern Generation

QCII-00008

Enhanced Inspection of the GNF New Fuel Bundles

S-MMP-FHP-100

Receiving, Inspection, and Storage of New Fuel

Work Orders

C93807915