IR 05000315/2023001

Integrated Inspection Report 05000315/2023001 and 05000316/2023001

ML23122A100
Person / Time
Site:	Cook
Issue date:	05/03/2023
From:	Nestor Feliz-Adorno NRC/RGN-III/DORS/ERPB
To:	Lies Q Indiana Michigan Power Co
References
IR 2023001
Download: ML23122A100 (1)

Text

May 3, 2023

SUBJECT:

DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2023001 AND 05000316/2023001

Dear Q. Shane Lies:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant. On April 12, 2023, 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 NRC-identified or self-revealing findings were identified during this inspection.

Licensee-identified violations which were determined to be of very low safety significance and Severity Level IV are documented in this report. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Donald C. Cook Nuclear Plant. 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, Signed by Feliz-Adorno, Nestor on 05/03/23 Néstor J. Féliz Adorno, Chief Engineering & Reactor Projects Branch Division of Operating Reactor Safety Docket Nos. 05000315 and 05000316 License Nos. DPR-58 and DPR-74

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000315 and 05000316 License Numbers: DPR-58 and DPR-74 Report Numbers: 05000315/2023001 and 05000316/2023001 Enterprise Identifier: I-2023-001-0056 Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Plant Location: Bridgman, MI Inspection Dates: January 01, 2023 to March 31, 2023 Inspectors: T. Briley, Senior Project Engineer T. Hartman, Senior Project Engineer J. Mancuso, Acting Senior Resident Inspector J. Meszaros, Resident Inspector P. Zurawski, Senior Resident Inspector Approved By: Néstor J. Féliz Adorno, Chief Engineering & Reactor Projects Branch 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 Donald C. Cook Nuclear 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. Licensee-identified non-cited violations are documented in report sections: 71152A and 7115

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 05000315/2022-002-00 LER 2022-002-00 for 71153 Closed Donald C. Cook Nuclear Plant, Unit 1, Ice Condenser Door Inoperable Resulting in a Condition Prohibited by Technical Specifications

PLANT STATUS

Unit 1 and Unit 2 began the inspection period at rated thermal power 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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of a cold weather advisory/alert on January 30, 2023.

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 high winds on February 9, 2023.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 1 south control room air conditioning (CRAC) with north CRAC out of service for maintenance on January 9, 2023

(2) Unit 1 and Unit 2 plant air compressors during Unit 1 control air compressor maintenance on January 30, 2023

(3) Unit 1 west essential service water (ESW) during Unit 1 east ESW maintenance on February 6, 2023

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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 Zones 18 and 115, 2 CD diesel generator room, Unit 2, elevation 587', and essential service water pipe tunnel, Unit 2, elevation 591' on February 9, 2023

(2) Fire Zones 47A, AB 4kv switchgear room and 47B, CD 4kv switchgear room, Unit 2, elevation 690' -6" on February 28, 2023

(3) Fire Zone 17F, turbine auxiliary feedwater pump room, Unit 2, elevation 591' on March 14, 2023

(4) Fire Zone 46D, AB battery room, Unit 2, elevation 609' -6" on March 17, 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)

(1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during high-risk Unit 2 solid state protection system testing on February 22, 2023.

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

(1) The inspectors observed and evaluated RQ-S-4707-U2-T1 Period 4707 Unit 2 Training Scenario 1, "D" Shift, in the facility's simulator on February 1, 2023.

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) Unit 2 electrohydraulic control system on January 23, 2023

(2) Unit 2 steam generator blowdown tripping on February 13, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (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) Action Requests (ARs) 2023-0084 and 2023-0079; Unit 1 East Motor Driven Auxiliary Feedwater Pump Discharge Flow Switch Sticks on January 4, 2023

(2) AR 2023-0471; Unit 2 Right Inner Turbine Control Valve 2-OME-90-RI-H2 Broken Bolt on January 17, 2023

(3) Maintenance Risk Cycle 125, Week 06 with Unit 1 east ESW work window on February 6, 2023

71111.15 - Operability Determinations and Functionality Assessments

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

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

(1) AR 2022-10401; 2-TR-AFWX Transformer Abnormal Fan Noise on January 5, 2023

(2) ARs 2023-0962 and 2023-0965; 1-DR-AUX343 & 2 DR-AUX344 Found with Door Seal Ripped on February 1, 2023

(3) ARs 2023-1415 and 2023-1416; Unit 2 Gas Void at 2-RH-125W and 2-RH-130 on February 16, 2023

(4) Unit 2 east essential service water pump breaker failure past operability on March 5, 2023

(5) Reactor coolant system increased leakage on March 15, 2023

(6) Unit 2 battery breaker linkages on March 15, 2023

71111.18 - Plant Modifications

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

(1 Partial)

The inspectors evaluated the following temporary or permanent modifications:

(1) (Partial)plastic and rubber blanket covers in Unit 2 AB battery room on March 17, 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 (PMT) (IP Section 03.01)

(1) Unit 1 CD EDG following critical maintenance project on March 5, 2023

(2) Unit 2 steam generator steam flow/feed flow mismatch card after failure on March 15, 2023

(3) Unit 1 turbine driven auxiliary feedwater pump following planned work window on

March 22, 2023 Surveillance Testing (IP Section 03.01) (1 Sample)

(1) 1-IHP-4030-111-001B, Train "B" solid state protection system automatic trip and actuation logic operational test, actuation logic test and master relay test on

February 22, 2023 Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Unit 1 CD EDG 24-hour run on March 2, 2023

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1 Sample)

(1) Emergency Response Organization Training Drill Team #1 on January 10, 2023

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) RQ-S-4707-U2-T1 Period 4707 Unit 2 Training Scenario 1, "C" Shift on January 25,

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) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

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

(2 Samples)

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (January 1, 2022 through December 31, 2022)

(2) Unit 2 (January 1, 2022 through December 31, 2022)

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

(1) AR 2022-8945; Fire Doors with Roton Hinge May Not Meet Design Requirement on January 9, 2023.

(2) AR 2023-1281; Extra Oil Absorbents in U1 AB Diesel on February 10, 2023.

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 2022-002-00 (ADAMS Accession No. ML22263A029). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER therefore no performance deficiency was identified. However, the issue resulted in a violation of NRC requirements, which is documented in the Inspection Results Section of this report. This LER is Closed.

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71152A This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Donald C. Cook Nuclear Plant Renewed Operating License Condition 2.C(4), "Fire Protection Program," for Unit 1 and Condition 2.C(3)(o), "Fire Protection Program," for Unit 2, requires the licensee to implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), National Fire Protection Association (NFPA) Standard 805, as specified in the license amendment requests and as approved in the safety evaluation reports dated October 24, 2013, and July 6, 2018. NFPA 805 Design Element 3.11.3(1) states, in part, that passive fire protection devices such as doors and dampers shall conform with NFPA 80, Standard for Fire Doors and Fire Windows. The licensee's committed Code of Record NFPA 80-1970 Edition states specifically that, Fire door assemblies consist of individually labeled components which are essential to satisfactory performance of the complete assembly, and that, The effectiveness of the entire assembly as a fire barrier may be destroyed if any component is omitted or one of substandard quality is used. To comply with this requirement the licensee intended to install all doors as UL Class A (3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) fire rating or a UL Class B (1-1/2 hour) commensurate with the severity of the hazard as determined by the performance requirements established by Chapter 4 of NFPA 805.

Contrary to the above, as of November 1, 2022, the licensee did not implement and maintain in effect all provisions of the approved fire protection program. Specifically, on November 1, 2022, the licensee identified 29 passive fire protection devices (doors) that did not conform with NFPA 80-1970. The doors did not meet the required fire rating commensurate with the severity of the hazard because the installed hinges either did not meet or could not be verified to meet the required rating of the barrier.

Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Appendix F, "Fire Protection Significance Determination Process," dated May 2, 2018. The inspectors answered NO to question 1.3 as it did not meet the low degradation rating. The inspectors continued to Step 1.4.4 and answered NO to question 1.4.4-A, because six doors had fire scenarios that lasted beyond the 1-5-hour rating of the hinge. The inspectors answered YES to question 1.4.4-B, because the remaining six doors all had adequate automatic suppression on at least one side of the door.

Corrective Action References: AR 2022-8945 Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Donald C. Cook Technical Specifications Limiting Condition for Operation (LCO)3.6.12, "Ice Condenser Doors," requires the Ice Condenser Inlet Doors, Intermediate Deck Doors (IDD), and Top Deck Doors to be OPERABLE and closed in Modes 1-4. The doors need to be free of any obstructions that would limit their opening to satisfy this LCO. If an IDD is determined to be inoperable, the required action, per LCO 3.6.12 is to verify maximum ice bed temperature is 27°F every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and restore the IDD to operable status and closed within 14 days. If the IDD is not restored to operable status within 14 days, an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allotted to restore the IDD to an operable status, after which the unit is required to be shutdown to Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Contrary to the above, from June 1 to July 20, 2022, the licensee did not have all ice condenser doors operable in Mode 1 and failed to satisfy the associated required actions within their allowable time. Specifically, the licensee entered Mode 4 on May 18 with a bracket which holds the vent curtain in place preventing IDD 23-H from opening completely rendering the door inoperable. The licensee did not restore the door to an operable status within 14 days (i.e., June 1) and the additional 48-hour allowable time. Additionally, the licensee did not place Unit 1 in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> following their failure to restore the door to operable status within the allowable times. The licensee restored compliance on July 20, at 19:52, when the door interference was removed, and the door was successfully tested. This issue is associated with LER 315/2022-002-00, "Unit 1 Ice Condenser Door Inoperable Resulting in a Condition Prohibited by Technical Specifications."

Significance/Severity: No Performance Deficiency. Severity Level IV. Traditional Enforcement is being used to disposition this violation with no associated Reactor Oversight Process (ROP) performance deficiency, per NRC Enforcement Policy Sections 2.2.4.d and 3.10. The inspectors concluded this violation was not associated with an ROP performance deficiency because it was not within the licensee's ability to foresee and correct. Specifically, the licensee had utilized a procedure (i.e., 12-MHP-4030-004, "Ice Condenser Intermediate Deck Door Surveillance") that directed individuals to check the deck doors for known potential impairments that prevent opening of the doors. However, the procedure did not include the obstruction experienced in 2022 because it was not foreseen as a potential impairment. The procedure has since been updated to include checks that address the newly discovered potential impairment.

Corrective Action References: AR 2022-5912

EXIT MEETINGS AND DEBRIEFS

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

On April 12, 2023, the inspectors presented the integrated inspection results to Q. S. Lies and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action AR 2023-1221 NRC Identified Housekeeping Issue 02/09/2023

Documents AR 2023-1253 NRC Concern with Metal Wire in Scaffold Cart 02/09/2023

Resulting from

Inspection

Procedures 12-OHP-4022- Severe Weather 024

001-010

2-OHP-5030- Screen House Vulnerability Determination 40

057-001

PMP=5055-SWM- Severe Weather Guidelines 013

001

71111.04 Procedures 1-OHP-4021-028- Operation of the Control Room Air Conditioning and 060

014 - Lineup Pressurization/Cleanup Filter Systems

Sheet 2

1-OHP-4021-064- Operation of Plant and Control Air Systems 057

001

1-OHP-4030-119- ESW Flow Verification 29

2

71111.05 Fire Plans FIRE-PRE- DC Cook Nuclear Power Plant- Fire Protection 042

PLANS- Program- Fire Pre-Plans Volume 1

VOLUME-1

Miscellaneous 2CD Emergency Diesel Generator Room Fire Watch 01/01/2023 -

Records 01/31/2023

Procedures PMP-2270-CCM- Control of Combustible Materials 53

001

71111.11Q Miscellaneous Emergency Planning Drill - January 10, 2023 0

RQ-S-4707-U2- Period 4707 U2 Training Session Scenario 1 0

T1

71111.12 Corrective Action 2023-0471 2-OME-90-RI-H2 Broken Bolt 01/17/2023

Documents AR 2023-0471 2-OME-90-RI-H2 Broken Bolt 01/17/2023

AR 2023-1301 Unexpected Trip of Blowdown in Unit 2 02/12/2023

AR 2023-1302 Steam Generator Blowdown Start-Up Flash Tank Level 02/12/2023

Control

Inspection Type Designation Description or Title Revision or

Procedure Date

AR 2023-1350 U2 Loop 1 Blowdown Flow Indicates 'Suspect' 02/13/2023

AR 2023-1422 2-DRV-350 Cycling 02/15/2023

GT 2022-9069 Ad Hoc SHOT on EHC Leaks 11/04/2022

Work Orders C10047530 2-DLC-352 Tune and PMT New Controller 0

71111.13 Corrective Action AR 2023-0079 1-FFS-255 Calibration Adjustment 01/03/2023

Documents AR 2023-0084 1-FFS-255 Flow Switch Sticks 01/04/2023

AR 2023-0471 2-OME-90-RI-H2 Broken Bolt 01/17/2023

Miscellaneous Unit 1 & 2 Online Risk - Cycle 125, Week 06 0

Unit 1 & 2 Fire Risk Assessment - Cycle 125, Week 06 0

Unit 1 & 2 Fire Risk Assessment - Cycle 125, Week 06 1

Unit 1 & 2 Online Risk - Cycle 125, Week 06 1

Work Orders C10046220 Found a Bolt Laying Under U2 Right Inner Control Valve 01/17/2023

71111.15 Corrective Action AR 2017-2847 Gas Void Locations Operable but 03/13/2017

Documents Degraded / Non-Conforming

AR 2022-10401 2-TR-AFWX Abnormal Fan Noise 12/28/2022

AR 2022-9421 Void Near 2-RH-130 11/16/2022

AR 2022-9422 Void Near 2-RH-125W 11/16/2022

AR 2023-0866 U2 Right Inner Stop Valve 2 Nuts Loose 01/28/2023

AR 2023-0962 1-DR-AUX343 Was Found with the Door Seal Ripped 01/31/2023

AR 2023-0965 2-DR-Aux344 Was Found with the Door Seal Ripped 01/31/2023

AR 2023-1415 Gas Void at 2-RH-125W 02/15/2023

AR 2023-1416 Gas Void at 2-RH-130 02/15/2023

AR 2023-1862 2-WMO-703 Failed to Auto Open During Pump Start 03/04/2023

AR 2023-2109 Tier 1 RCS Leak Rate Calculated in Unit 1 03/14/2023

Corrective Action AR 2023-1916 2-EZC-C-2B Linkage Disassembled 03/06/2023

Documents AR 2023-1944 2-EZC-C-2B Breaker Linkage Not Engaging Breaker 03/07/2023

Resulting from

Inspection

Procedures 2-OHP-4021-082- Operation of 2AB & 2CD Battery Chargers 13

006

71111.18 Calculations 1-E-N-ELCP-250- 250VDC Battery 1AB System Analysis 11/16/2022

007

Corrective Action 2023-2625 Engineering Direction Not Provided for 2AB Battery Covers 03/30/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

Resulting from

Inspection

Procedures 12-MHP-5021- Scaffolding Procedure 40

SCF-001

PMI-5041 Temporary Configuration Change Program 5

PMP-5041-TCC- Temporary Configuration Changes 12

001

Work Orders C10006885107 Cover Batteries U2 Battery Room 03/16/2023

C10008148128 Erect Scaffold to W7874 Inside AB Battery Room 03/16/2023

71111.24 Procedures 1-IHP-4030-111- Train 'B' Solid State Protection System (SSPS) Automatic 018

001B-018 Trip and Actuation Logic Operational Test (TADOT,

Actuation Logic Test and Master Relay Test) and Reactor

Trip Breaker Operational Test (TADOT)

1-OHP-4021-032- DG1CD Operation 52

001CD

1-OHP-4030-132- CD Diesel Generator Operability Test (Train A) - DG1CD 02/27/2023

27CD Restart

1-OHP-4030-132- CD Diesel Generator Operability Test (Train A) - DG1CD 02/26/2023

27CD Slow Speed Start

1-OHP-4030-156- Turbine Driven Auxiliary Feedwater System Test 03/23/2023

017T

71114.06 Miscellaneous RQ-S-4707-U2- Period 4707 U2 Training Session (with DEP) 0

T1

71151 Miscellaneous PMP-2350-INS- Inspection Contact and Information Request 03/16/2023

001 Form - 1Q-2023-004

PMP-7110-PIP- Reactor Oversight Program Performance Indicators and 21

001 Monthly Operating Report Data Sheets (January 2022

through December 2022)

71152A Corrective Action AR 2022-8945 Fire Doors with Roton Hinge May Not Meet Design 11/01/2022

Documents Requirement

Corrective Action AR 2023-1281 Extra Oil Absorbents in U-1 AB Diesel 02/10/2023

Documents

Resulting from

Inspection Type Designation Description or Title Revision or

Procedure Date

Inspection

Engineering FPCE-2022-0015 Significance of Fire Protection Program Change Evaluation 11/23/2022

Evaluations

Procedures 12-FPE-2270- Fire Protection Program Change Evaluation (FPCE) 10

FPCE-001

71153 Corrective Action AR 2022-5912 Unit 1 IDD 23-H Curtain interference 07/20/2022

Documents AR 2022-5912 Unit 1 IDD 23-H Curtain Interference 07/20/2022

AR 2022-6828 Unit 1 Reactor Trip - RCP 13 Trip 08/28/2022

GT 2022-6371 LER 315/2022-002-00 Submittal Tracker 08/09/2022

Miscellaneous LER 315/2022- Unit 1 Ice Condenser Door Inoperable Resulting in a 09/19/2022

2-00 Condition Prohibited by Technical Specifications

2