IR 05000263/2024001

Plan - Integrated Inspection Report 05000263/2024001

ML24117A352
Person / Time
Site:	Monticello
Issue date:	04/29/2024
From:	Richard Skokowski NRC/RGN-III/DORS/RPB3
To:	Hafen S Northern States Power Company, Minnesota
References
IR 2024001
Download: ML24117A352 (1)

Text

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - INTEGRATED INSPECTION REPORT 05000263/2024001

Dear Shawn Hafen:

On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Monticello Nuclear Generating Plant. On April 11, 2024, the NRC inspectors discussed the results of this inspection with you 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, Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket No. 05000263 License No. DPR-22

Enclosure:

As stated

Inspection Report

Docket Number: 05000263

License Number: DPR-22

Report Number: 05000263/2024001

Licensee: Northern States Power Company, Minnesota

Facility: Monticello Nuclear Generating Plant

Location: Monticello, MN

Inspection Dates: January 01, 2024 to March 31, 2024

Inspectors: N. Bolling, Acting Resident Inspector T. McGowan, Resident Inspector C. Norton, Senior Resident Inspector J. Reed, Health Physicist

Approved By: Richard A. Skokowski, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Monticello Nuclear Generating Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000263/2023-002-00 LER 2023-002-00 for 71153 Closed Monticello Nuclear Generating Plant, Reactor Scram and Containment Isolation due to Valve Responses during Main Turbine Control Valve Testing

LER 05000263/2023-003-00 LER 2023-003-00 for 71153 Closed Monticello Nuclear Generating Plant, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch

PLANT STATUS

Monticello began the inspection period at rated thermal power. On February 28, 2024, the unit tripped and entered Mode 4. On March 2, 2024, the licensee commenced a reactor startup, and synced to the grid on March 3, 2024. The unit returned at or near rated thermal power on March 5, 2024. On March 27, 2024, the licensee performed a shutdown to Mode 4 to replace a safety relief valve. On March 30, 2024, the licensee commenced a unit startup, and synced to the grid on March 31, 2024, and ended the inspection period at 31% of rated thermal power.

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.

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 from impending severe weather on January 10, 2024.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Emergency diesel generator (EDG) 11 starting air and fuel oil systems prior to making EDG 12 inoperable for testing on January 30, 2024

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (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) Fire Zone 1-E, high pressure coolant injection (HPCI) room on January 4, 2024

(2) Fire Zone 1-G, control rod drive pump room on January 4, 2024

(3) Fire Zone 14-A, upper 4KV bus area (14 and 16) on January 5, 2024

(4) Fire Zone 12-A, lower 4KV bus area (13 and 15) on January 5, 2024

(5) Fire Zone 1-C, reactor core isolation cooling room on January 10, 2024

(6) Fire Zone 2-H, west shutdown cooling area on January 12, 2024

(7) Fire Zone 33, emergency filtration building third floor on January 12, 2024

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 reactor startup to critical and the point of adding heat on March 2, 2024.

(2) The inspectors observed and evaluated licensed operator performance in the control room during reactor startup on March 31, 2024.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated crew as found simulator exam on January 16, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) P111D, emergency service water (ESW) pump 14

(2) F safety relief valve degrading tailpipe temperature on March 26, 2024

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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) Risk associated with the B feedwater regulating valve lockup on January 16, 2024

(2) Risk associated with clamping C outboard main team isolation valve (MSIV)instrument air line on February 7, 2024

(3) Risk associated with anticipated transient without scram reactor coolant pump trip reactor pressure restoration of setpoint after reactor SCRAM on February 29, 2024

(4) Risk associated with cycling breaker 3A-CB1, reactor manual control system 120 VAC logic power supply on March 7, 2024

(5) Risk associated with HPCI inboard steam isolation valve and failure of leak rate testing isolation valves on March 28, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:

(1) 501000081180, ESW 14 quarterly flow degradation

(2) 501000080744, VD-9175B, B control room pressure control damper failed to open

(3) 501000082034, inadvertent BKR 4300 operation

(4) 501000082532, check valve failed during RHRSW quarterly

(5) 501000082683, reactor pressure vessel bottom head cooldown rate >100 degrees per hour

(6) 501000082407, LS-2-3-680F and LS-2-3-680H reactor feed pump and main turbine trip failure to reset

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) VD-9175A emergency filtration train control room ventilation damper

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)

(1) The inspectors evaluated forced outage MIF 3202 activities from February 28 to March 2, 2024.

(2) The inspectors evaluated forced outage MIF 3203 activities from March 26 to 31, 2024.

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 (PMT) (IP Section 03.01) (10 Samples)

(1) B.05.07-05, local manual control of feedwater regulating valves after repair of programable logic controller on January 20, 2024

(2) Electric fire pump after replacement of the seal water PCV on February 27, 2024

(3) K61D relay replacement, March 1, 2023

(4) Reactor manual control system after power supply breaker exercising on March 7, 2024

(5) HPCI governor actuator remote servo after maintenance on March 22, 2024

(6) HPCI governor after maintenance on March 22, 2024

(7) HPCI gland seal drain pump after maintenance on March 22, 2024

(8) HPCI inlet steam trap drain after maintenance on March 22, 2024

(9) HPCI exhaust pressure root valve after replacement on March 22, 2024

(10) A Inboard MSIV after packing adjustment due to steam leak on March 31, 2024

Surveillance Testing (IP Section 03.01) (4 Samples)

(1) Security system emergency generator operability check and alarm on January 8, 2024

(2) EDG 12 quarterly test on January 29, 2024

(3) Residual heat removal (RHR) pump 11 time delay over current relay calibration on March 5, 2024

(4) 2-of-4 voter average power range monitor channel functional test on March 14, 2024

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) RHR service water B pump testing on January 26, 2024

(2) Division 1 RHR IST flow verification on March 27, 2024

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) Licensed operator requalification including emergency classification and notification on January 16,

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling,

Storage, & Transportation

Radioactive Material Storage (IP Section 03.01)

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

(1) 10 CFR 37 material storage locations

(2) Radioactive materials stored outside the protected area

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) Condensates resin processing system

(2) Reactor water clean-up (RWCU) system

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

The inspectors evaluated the following characterization and classification of radioactive waste:

(1) RWCU

(2) Dry active waste (DAW)

Shipping Records (IP Section 03.05) (4 Samples)

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

(1) Radioactive material shipment 23-57 containing control rod drive mechanisms in a general design package

(2) Radioactive waste shipment 23-99 containing powder resin of class A waste in a general design package

(3) Radioactive material shipment 24-04 containing control rod drive equipment in a general design package

(4) Radioactive waste shipment 23-92 containing powder resin of class A waste in a general design package

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) January 1, 2023, through December 31, 2023

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)

(1) January 1, 2023, through December 31, 2023

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)

(1) January 1, 2023, through December 31, 2023

71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow up (IP Section 03.01)

(1) The inspectors evaluated a reactor SCRAM with recirculation pump trip and licensees response on February 28, 2024.

Event Report (IP Section 03.02) (2 Samples)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000263/2023-002-00, Reactor Scram and Containment Isolation due to Valve Responses during Main Turbine Control Valve Testing (ADAMS Accession No. ML23317A359). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensee's ability to foresee and correct, and therefore was not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. This LER is Closed.

(2) LER 05000263/2023-003-00, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch (ADAMS Accession No. ML23338A184). The inspectors determined that the cause of the condition described in the LER was not reasonably within the licensees ability to foresee and correct, and therefore was not reasonably preventable. The inspection conclusions associated with this LER are documented in this report under Inspection Results Section. This LER is Closed.

INSPECTION RESULTS

Minor Violation 71153 LER 05000263/2023-003-00, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch

Minor Violation: The inspectors reviewed LER 05000263/2023-003-00, Condition Prohibited by Technical Specification (TS) due to Inoperable Main Steam Line Low Pressure Isolation Switch, for the licensees failure to comply with the actions required in TS limiting condition for operation (LCO) 3.3.6.1. Specifically, on October 7, 2023, at 0228 when the reactor entered Mode 1, the licensee failed to enter TS LCO 3.3.6.1 Condition A for One or more required channels inoperable, when the B1 main steam line low pressure isolation switch reset prior to its allowed TS value. This condition existed until it was discovered and corrected on October 10, 2023, at 0901 when the B1 main steam line low pressure isolation switch was recalibrated using TS Surveillance Requirement (SR) 3.3.6.1.4. As a result, the licensee operated in a condition prohibited by TS by failing to place the affected channel in trip within the required time in TS LCO 3.3.6.1 Condition A and subsequently failing to transition to Mode 2 by the required time in TS LCO 3.3.6.1 Condition E.

Screening: The inspectors determined the performance deficiency was minor.

Enforcement:

This failure to comply with Technical Specification 3.3.6.1 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On April 11, 2024, the inspectors presented the integrated inspection results to Shawn Hafen, and other members of the licensee staff.

• On March 7, 2024, the inspectors presented the radiation protection baseline inspection results to K. Lorensen, Director Site Performance and Operations Support, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 1444 Pre and Post Severe Weather Inspection Checklist 84

71111.04 Procedures 2154-14 Fuel Oil System Prestart Valve Checklist 20

2154-28 Diesel Generator Air Start System Prestart Valve Checklist 12

71111.05 Fire Plans Strategy A.13-12- Lower 4 KV Bus Area (13&15) 19

A

Strategy A.3-01-C RCIC Room and Appendix R Cable Enclosure 11

Strategy A.3-01-E HPCI Room - Reactor Building Elevation 896' 9

Strategy A.3-01-G Fire Zone 1-G, CRD Pump Room 5

Strategy A.3-02-H West Shutdown Cooling Area 10

Strategy A.3-14-A Upper 4KV Bus Area (14&16) 18

Strategy A.3-33 EFT Building Third Floor 13

71111.11Q Corrective Action 501000082463 IRM 12 HI HI Light on C-36 During SU 03/03/2024

Documents

Resulting from

Inspection

Miscellaneous RQ-SS-203 Loss of Control Rod Drive, Loss of Load Center 103, Bus 15 0

Lockout, Reactor Water Cleanup Leak Requiring Blowdown

Procedures 1371 Drywell Prestart Inspection 14

2159 Predicted Critical for Plant Startup 13

2167 Plant Startup 110

2167-04 Startup Checklist for Surveillance Requirements 12

2167-05 Startup Checklist for Transition from Mode 2 to Mode 1 5

2300 Reactivity Adjustment 27

253 B Defeat/Reinstall Drywell Personal Airlock Interlocks 11

71111.12 Procedures 0255-11-III-4 ESW 14 Quarterly Pump and Valve Tests 69

71111.13 Corrective Action 501000080923 B FRV Lockup 01/17/2024

Documents 501000080960 CV-6-12B-IL Amber Light Not Lit 01/17/2024

501000080971 PRA Model for Main FRV Configuration 01/17/2024

501000080986 Challenge Board Materials Timeliness 01/18/2024

Engineering 601000004946 Replace HPCI-1 and HPCI-2 0

Evaluations

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous 700136403 Weld Control Record HPCI-1/HPCI-2 03/28/2024

FP-PA-HU-05 Type 2- Operational Decision Making Issue 02/06/2024

Evaluation - AO-2-86C (13 OTBD MSIV) Pilot Air Line

FP-WM-IRM-01 Planning and Approval of High Risk or Scheduled Risk 02/29/2024

Work - Restore Set-Point PIS-2-3-678C

Procedures B.05.07-03 Local Manual Control of Main FW Reg Valves 29

C.6-005-B-40 FW Control Valve Locked 4

Work Orders 7000091883 3A-CB1-Cycle Breaker 0

700130106-0020 ATWS RCP Trip Reactor Pressure 1

700136403-0030 M-2035 Upstream Test/Drain 0

71111.15 Calculations16-062 Development of Test Acceptance Criteria Basis for Monticello 0A

FSW Pumps

Corrective Action 501000058253 V-D-9175A Failed to Open 05/19/2022

Documents 501000068971 V-EAC-14A Tripped During CRV Swap 01/09/2023

501000075980 VD-9175B Didnt Open When B CRV Placed in Service 08/13/2023

501000077303 VD-9175B Does Not Open 10/02/2023

501000078405 0255-11-III-4 Flow Less Than 71.0 gpm 10/30/2024

501000080176 VD-9175B Failed to Open 12/20/2023

501000080744 VD-9175B Failed to Open 01/10/2024

501000081180 14 ESW Quarterly Flow Degradation 01/23/2024

501000082034 Inadvertent BKR 4300 Operation 02/18/2024

501000082407 High Level Trips Not Clearing 03/01/2024

501000082532 Check Valve Failed During RHRSW Quarterly 03/05/2024

501000082683 RPV Bottom Head Cooldown Rate>100/hr 03/08/2024

501000082684 Further Evaluation Needed for 501000082683 03/09/2024

Drawings NH-170037 Main Control Room CRV/EFT System 84

Engineering 2400420.401 Initial Operability Summary for the MNGP Reactor Pressure 03/08/2024

Evaluations Vessel Bottom Head

Procedures 0255-05-IA-1-1 A RHRSW Quarterly Pump and Valve Tests 93

255-11-III-4 14 ESW Quarterly Pump and Valve Tests 69

B.09.07-05 Operations Manual Section: 480 Volt Station Auxiliary 65

EC 13410 Evaluate Failure of SW-21-1, 21-2, 22-1, and 22-2 through 0

3/4 Inch Keep Fill Lines

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.18 Drawings ECR4849-NX- Control Panel C243A Wiring Diagram 0-76

20010-29

ECR4849-NX- Control Panel C243A Wiring Diagram 0-E

20010-32

NE-93503-18 Damper VD-9175A Control Scheme V211 Channel 1 8

NE-93527 Loop Diagram Outlet Flow From V-ERF-14-A/B Flow Control 76

Engineering ECR Modify EFT Hydramotor Damper Logic 0

Changes 601000004849

71111.20 Procedures 2140 Deinerting Primary Containment 36

2167 Plant Startup 110

2167-03 Startup Transition from Mode 4 to Mode 2 23

204 Plant Shutdown 83

2300 Reactivity Maneuvering Steps 0

2404-03 Shutdown Checklist Transition from Mode 3 to Mode 4 7

B.03.04-05 D.1. Shutdown Cooling Mode-Loop A Startup 96

OSP-CRD-0539- Control Rod Testing 6

A

OSP-NIS-0042 IRM Functional Test 3

OSP-NIS-0047 SRM Functional Test 5

71111.24 Corrective Action 501000080637 Over Crank Alarm Received 01/08/2024

Documents

Procedures 0187-02 Emergency Diesel Generator 12/Emergency Service Water 111

Quarterly Pump and Valve Tests

255-04-IA-2 RHR System Cold Shutdown Valve Operability Tests 36

255-05-IA-1-2 B RHRSW Quarterly Pump and Valve Tests 93

255-06-IA-1 HPCI Quarterly Pump and Valve Tests 113

255-06-IA-1 HPCI Quarterly Pump and Valve Tests 113

298-02 Security System Emergency Generator Operability 32

Check & Alarm

1069 HPCI Flow Control System Dynamic Test Procedure 29

4850-504-PM 152-504, 11 RHR Pump Relay Maintenance, Calibration and 14

Trip Testing

B.08.05-05 Start P-110 Electric Fire Pump 52

Inspection Type Designation Description or Title Revision or

Procedure Date

ISP-NIP-0586 2-of-4 Voter Channel Functional Check 8

OPS MAN Main Steam 44

B.02.04-05

OPs Man Rod Worth Minimizer 24

B.05.02-05

OPS Man Startup of RHRSW Pump 50

B.08.01.03-05

OSP-MSC-0542- Breaker Alignment and Indicating Power Availability 1

Verification of Required Offsite Circuits

PCV-3163 Seal Water PCV to Electric Fire Pump (P-110) 0

PMT/RTS

Work Orders 700080595-0020 Replace Relay K61D 5

700091883 PMT/RTS Instructions After RMCS 120 Control Power Breaker 03/07/2024

Cycling

700112498-0010 Security System EDG - Annual Check 01/08/2024

700133351-0070 MT:1CFW:CV-6-12B, B Main Feed Water Regulation Valve 1

700136470-0010 11 INBD MSIV AO-2-80-A Adjust Packing 2

71114.06 Procedures FP-EP-EPIP-01 ERO Position Checklist 0

71124.08 Corrective Action 501000073443 Class B RW Shipment to Non-QSL Location 05/09/2023

Documents 501000078865 NOS: Issues in Rad Waste Shipment Record 11/09/2023

501000079937 Rad Waste Drumming Aisle 12/11/2023

501000081633 Lost Part 61 Paperwork 02/04/2024

Corrective Action 501000082538 Storage of RAM Outside PA 03/05/2024

Documents 501000082591 Records Legibility Issues 03/05/2024

Resulting from 501000082605 Shipment 23-92 Documentation 03/06/2024

Inspection 501000082628 Accurate Records Submission 06/06/2024

Engineering ECR RDS-1000 Replacement 03/23/2023

Changes 601000003555

Engineering 20-002 Evaluation of Used Oil for Radiological Contamination 00

Evaluations

Procedures 5863 Dewatering Resins in Waste Liners 31

FP-RP-RW-001 Additional Security Measures for Transportation of Radioactive 09

Material Part 37 Category 1 Quantities

Inspection Type Designation Description or Title Revision or

Procedure Date

FP-RP-RW-02 Radioactive Shipping Procedure 25

FP-RP-RW-03 10CFR37 Material Accountability 04

FP-RP-RW-09 Rad Waste Streams and Scaling Factors 00

PCP-01 Process Control Program for Wet Radioactive Wastes 02

R.06.09 Storage and Inventory of Radioactive Material Outside the 26

Power Block

Self-Assessments 600001146487 NRC Inspection Activities for IP71124.08. 12/15/2023

606000002023 71124.08 Radioactive Solid Waste Processing and 12/05/2023

Radioactive Material Handling, Storage, and Transportation

Shipping Records 2022 RWCU 10CFR61 Analysis for Reactor Water Clean-Up 08/08/2022

50/50 Mix

23-57 Shipping Papers for Twelve Control Rod Drive Mechanisms 05/09/2023

23-92 Shipping Papers for Dewatered Powder Resin 08/18/2023

23-99 Shipping Papers for Dewatered Powder Resin 09/22/2023

24-04 Shipping Papers for CRD Handling System Tooling 01/16/2024

L101029 10CFR61 Analysis for Secondary Resin Waste Stream 02/05/2024

L101029-3 10CFR61 Analysis for Dry Active Waste (DAW) 02/05/2024

Work Orders 700120331-0010 Semiannual Source Inventory and Smear Test 12/13/2023

71151 Miscellaneous QF0445 Monthly Operating Report - Generation Occurrences, 18

January 2023 - December 2023

71153 Drawings NF-36790 Reactor Vessel Thermocouple Locations & Expansion Lead 77

Miscellaneous FP-E-TS-01 Troubleshooting Plan PCIS - Group 1 Isolation 9

FP-PA-CSE-01 Cause Evaluation Template Reactor Scram Number 141 21

FP-PA-CSE-01 Equipment Cause Evaluation PS-2-134B Out of As-Found 12

FP-PA-HU-05 Type 2 - Operational Decision Making Issue Evaluation Group 11

Isolation on Main Steam Line High Flow

Operability FP-OP-OL-01 Past Operability Review PS-2-134B 5

Evaluations

Procedures 0058-B Main Steam Line Low Pressure Group 1 Isolation Instrument 17

Test and Calibration (RX in Run)

0118 Reactor Vessel Temperature Monitoring 23

B.01.04-05 Reactor Recirculation System H.6 Stratification Recovery 61

FP-OP-REP-01 Event Reporting and Notification Process 13

14