IR 05000263/2024001

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Plan - Integrated Inspection Report 05000263/2024001
ML24117A352
Person / Time
Site: Monticello Xcel Energy icon.png
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

Enterprise Identifier:

I-2024-001-0075

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

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 Monticello Nuclear Generating Plant, Reactor Scram and Containment Isolation due to Valve Responses during Main Turbine Control Valve Testing 71153 Closed LER 05000263/2023-003-00 LER 2023-003-00 for Monticello Nuclear Generating Plant, Condition Prohibited by Technical Specifications due to Inoperable Main Steam Line Low Pressure Isolation Switch 71153 Closed

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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems 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)

=

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,

RADIATION SAFETY

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Procedures

1444

Pre and Post Severe Weather Inspection Checklist

2154-14

Fuel Oil System Prestart Valve Checklist

71111.04

Procedures

2154-28

Diesel Generator Air Start System Prestart Valve Checklist

Strategy A.13-12-

A

Lower 4 KV Bus Area (13&15)

Strategy A.3-01-C

RCIC Room and Appendix R Cable Enclosure

Strategy A.3-01-E

HPCI Room - Reactor Building Elevation 896'

Strategy A.3-01-G

Fire Zone 1-G, CRD Pump Room

Strategy A.3-02-H

West Shutdown Cooling Area

Strategy A.3-14-A

Upper 4KV Bus Area (14&16)

71111.05

Fire Plans

Strategy A.3-33

EFT Building Third Floor

Corrective Action

Documents

Resulting from

Inspection

501000082463

IRM 12 HI HI Light on C-36 During SU

03/03/2024

Miscellaneous

RQ-SS-203

Loss of Control Rod Drive, Loss of Load Center 103, Bus 15

Lockout, Reactor Water Cleanup Leak Requiring Blowdown

1371

Drywell Prestart Inspection

2159

Predicted Critical for Plant Startup

2167

Plant Startup

110

2167-04

Startup Checklist for Surveillance Requirements

2167-05

Startup Checklist for Transition from Mode 2 to Mode 1

2300

Reactivity Adjustment

71111.11Q

Procedures

253 B

Defeat/Reinstall Drywell Personal Airlock Interlocks

71111.12

Procedures

255-11-III-4

ESW 14 Quarterly Pump and Valve Tests

501000080923

B FRV Lockup

01/17/2024

501000080960

CV-6-12B-IL Amber Light Not Lit

01/17/2024

501000080971

PRA Model for Main FRV Configuration

01/17/2024

Corrective Action

Documents

501000080986

Challenge Board Materials Timeliness

01/18/2024

71111.13

Engineering

Evaluations

601000004946

Replace HPCI-1 and HPCI-2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

700136403

Weld Control Record HPCI-1/HPCI-2

03/28/2024

FP-PA-HU-05

Type 2-Operational Decision Making Issue

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

2/06/2024

Miscellaneous

FP-WM-IRM-01

Planning and Approval of High Risk or Scheduled Risk

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

2/29/2024

B.05.07-03

Local Manual Control of Main FW Reg Valves

Procedures

C.6-005-B-40

FW Control Valve Locked

7000091883

3A-CB1-Cycle Breaker

700130106-0020

ATWS RCP Trip Reactor Pressure

Work Orders

700136403-0030

M-2035 Upstream Test/Drain

Calculations16-062

Development of Test Acceptance Criteria Basis for Monticello

FSW Pumps

0A

501000058253

V-D-9175A Failed to Open

05/19/2022

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

255-11-III-4 Flow Less Than 71.0 gpm

10/30/2024

501000080176

VD-9175B Failed to Open

2/20/2023

501000080744

VD-9175B Failed to Open

01/10/2024

501000081180

ESW Quarterly Flow Degradation

01/23/2024

501000082034

Inadvertent BKR 4300 Operation

2/18/2024

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

Corrective Action

Documents

501000082684

Further Evaluation Needed for 501000082683

03/09/2024

Drawings

NH-170037

Main Control Room CRV/EFT System

Engineering

Evaluations

2400420.401

Initial Operability Summary for the MNGP Reactor Pressure

Vessel Bottom Head

03/08/2024

255-05-IA-1-1

A RHRSW Quarterly Pump and Valve Tests

255-11-III-4

ESW Quarterly Pump and Valve Tests

B.09.07-05

Operations Manual Section: 480 Volt Station Auxiliary

71111.15

Procedures

EC 13410

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

3/4 Inch Keep Fill Lines

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ECR4849-NX-

20010-29

Control Panel C243A Wiring Diagram

0-76

ECR4849-NX-

20010-32

Control Panel C243A Wiring Diagram

0-E

NE-93503-18

Damper VD-9175A Control Scheme V211 Channel 1

Drawings

NE-93527

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

71111.18

Engineering

Changes

ECR

601000004849

Modify EFT Hydramotor Damper Logic

2140

Deinerting Primary Containment

2167

Plant Startup

110

2167-03

Startup Transition from Mode 4 to Mode 2

204

Plant Shutdown

2300

Reactivity Maneuvering Steps

2404-03

Shutdown Checklist Transition from Mode 3 to Mode 4

B.03.04-05 D.1.

Shutdown Cooling Mode-Loop A Startup

OSP-CRD-0539-

A

Control Rod Testing

OSP-NIS-0042

IRM Functional Test

71111.20

Procedures

OSP-NIS-0047

SRM Functional Test

Corrective Action

Documents

501000080637

Over Crank Alarm Received

01/08/2024

0187-02

Emergency Diesel Generator 12/Emergency Service Water

Quarterly Pump and Valve Tests

111

255-04-IA-2

RHR System Cold Shutdown Valve Operability Tests

255-05-IA-1-2

B RHRSW Quarterly Pump and Valve Tests

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

Check & Alarm

1069

HPCI Flow Control System Dynamic Test Procedure

4850-504-PM

2-504, 11 RHR Pump Relay Maintenance, Calibration and

Trip Testing

71111.24

Procedures

B.08.05-05

Start P-110 Electric Fire Pump

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ISP-NIP-0586

2-of-4 Voter Channel Functional Check

OPS MAN

B.02.04-05

Main Steam

OPs Man

B.05.02-05 Rod Worth Minimizer

OPS Man

B.08.01.03-05

Startup of RHRSW Pump

OSP-MSC-0542-

Breaker Alignment and Indicating Power Availability

Verification of Required Offsite Circuits

PCV-3163

PMT/RTS

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

700080595-0020

Replace Relay K61D

700091883

PMT/RTS Instructions After RMCS 120 Control Power Breaker

Cycling

03/07/2024

700112498-0010

Security System EDG - Annual Check

01/08/2024

700133351-0070

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

Work Orders

700136470-0010

INBD MSIV AO-2-80-A Adjust Packing

71114.06

Procedures

FP-EP-EPIP-01

ERO Position Checklist

501000073443

Class B RW Shipment to Non-QSL Location

05/09/2023

501000078865

NOS: Issues in Rad Waste Shipment Record

11/09/2023

501000079937

Rad Waste Drumming Aisle

2/11/2023

Corrective Action

Documents

501000081633

Lost Part 61 Paperwork

2/04/2024

501000082538

Storage of RAM Outside PA

03/05/2024

501000082591

Records Legibility Issues

03/05/2024

501000082605

Shipment 23-92 Documentation

03/06/2024

Corrective Action

Documents

Resulting from

Inspection

501000082628

Accurate Records Submission

06/06/2024

Engineering

Changes

ECR

601000003555

RDS-1000 Replacement

03/23/2023

Engineering

Evaluations20-002

Evaluation of Used Oil for Radiological Contamination

5863

Dewatering Resins in Waste Liners

71124.08

Procedures

FP-RP-RW-001

Additional Security Measures for Transportation of Radioactive

Material Part 37 Category 1 Quantities

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

FP-RP-RW-02

Radioactive Shipping Procedure

FP-RP-RW-03

10CFR37 Material Accountability

FP-RP-RW-09

Rad Waste Streams and Scaling Factors

PCP-01

Process Control Program for Wet Radioactive Wastes

R.06.09

Storage and Inventory of Radioactive Material Outside the

Power Block

600001146487

NRC Inspection Activities for IP71124.08.

2/15/2023

Self-Assessments

606000002023

71124.08 Radioactive Solid Waste Processing and

Radioactive Material Handling, Storage, and Transportation

2/05/2023

22 RWCU

50/50 Mix

10CFR61 Analysis for Reactor Water Clean-Up

08/08/2022

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

2/05/2024

Shipping Records

L101029-3

10CFR61 Analysis for Dry Active Waste (DAW)

2/05/2024

Work Orders

700120331-0010

Semiannual Source Inventory and Smear Test

2/13/2023

71151

Miscellaneous

QF0445

Monthly Operating Report - Generation Occurrences,

January 2023 - December 2023

Drawings

NF-36790

Reactor Vessel Thermocouple Locations & Expansion Lead

FP-E-TS-01

Troubleshooting Plan PCIS - Group 1 Isolation

FP-PA-CSE-01

Cause Evaluation Template Reactor Scram Number 141

FP-PA-CSE-01

Equipment Cause Evaluation PS-2-134B Out of As-Found

Miscellaneous

FP-PA-HU-05

Type 2 - Operational Decision Making Issue Evaluation Group

Isolation on Main Steam Line High Flow

Operability

Evaluations

FP-OP-OL-01

Past Operability Review PS-2-134B

0058-B

Main Steam Line Low Pressure Group 1 Isolation Instrument

Test and Calibration (RX in Run)

0118

Reactor Vessel Temperature Monitoring

B.01.04-05

Reactor Recirculation System H.6 Stratification Recovery

71153

Procedures

FP-OP-REP-01

Event Reporting and Notification Process

13