IR 05000315/2023001
| 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
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.
May 3, 2023 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, 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:
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
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 Donald C. Cook Nuclear Plant, Unit 1, Ice Condenser Door Inoperable Resulting in a Condition Prohibited by Technical Specifications 71153 Closed
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.
REACTOR SAFETY
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) (3 Samples)
- (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.
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
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2023-1221
NRC Identified Housekeeping Issue
2/09/2023
Corrective Action
Documents
Resulting from
Inspection
AR 2023-1253
NRC Concern with Metal Wire in Scaffold Cart
2/09/2023
2-OHP-4022-
001-010
Severe Weather
24
2-OHP-5030-
057-001
Screen House Vulnerability Determination
Procedures
PMP=5055-SWM-
001
Severe Weather Guidelines
013
1-OHP-4021-028-
014 - Lineup
Sheet 2
Operation of the Control Room Air Conditioning and
Pressurization/Cleanup Filter Systems
060
1-OHP-4021-064-
001
Operation of Plant and Control Air Systems
057
Procedures
1-OHP-4030-119-
2
ESW Flow Verification
Fire Plans
FIRE-PRE-
PLANS-
VOLUME-1
DC Cook Nuclear Power Plant-Fire Protection
Program-Fire Pre-Plans Volume 1
2
Miscellaneous
2CD Emergency Diesel Generator Room Fire Watch
Records
01/01/2023 -
01/31/2023
Procedures
PMP-2270-CCM-
001
Control of Combustible Materials
Emergency Planning Drill - January 10, 2023
Miscellaneous
RQ-S-4707-U2-
T1
Period 4707 U2 Training Session Scenario 1
23-0471
2-OME-90-RI-H2 Broken Bolt
01/17/2023
AR 2023-0471
2-OME-90-RI-H2 Broken Bolt
01/17/2023
AR 2023-1301
Unexpected Trip of Blowdown in Unit 2
2/12/2023
Corrective Action
Documents
AR 2023-1302
Steam Generator Blowdown Start-Up Flash Tank Level
Control
2/12/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AR 2023-1350
U2 Loop 1 Blowdown Flow Indicates 'Suspect'
2/13/2023
AR 2023-1422
2-DRV-350 Cycling
2/15/2023
GT 2022-9069
Ad Hoc SHOT on EHC Leaks
11/04/2022
Work Orders
C10047530
2-DLC-352 Tune and PMT New Controller
AR 2023-0079
1-FFS-255 Calibration Adjustment
01/03/2023
AR 2023-0084
1-FFS-255 Flow Switch Sticks
01/04/2023
Corrective Action
Documents
AR 2023-0471
2-OME-90-RI-H2 Broken Bolt
01/17/2023
Unit 1 & 2 Online Risk - Cycle 125, Week 06
Unit 1 & 2 Fire Risk Assessment - Cycle 125, Week 06
Unit 1 & 2 Fire Risk Assessment - Cycle 125, Week 06
Miscellaneous
Unit 1 & 2 Online Risk - Cycle 125, Week 06
Work Orders
C10046220
Found a Bolt Laying Under U2 Right Inner Control Valve
01/17/2023
AR 2017-2847
Gas Void Locations Operable but
Degraded / Non-Conforming
03/13/2017
AR 2022-10401
2-TR-AFWX Abnormal Fan Noise
2/28/2022
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
2/15/2023
AR 2023-1416
Gas Void at 2-RH-130
2/15/2023
AR 2023-1862
2-WMO-703 Failed to Auto Open During Pump Start
03/04/2023
Corrective Action
Documents
AR 2023-2109
Tier 1 RCS Leak Rate Calculated in Unit 1
03/14/2023
AR 2023-1916
2-EZC-C-2B Linkage Disassembled
03/06/2023
Corrective Action
Documents
Resulting from
Inspection
AR 2023-1944
2-EZC-C-2B Breaker Linkage Not Engaging Breaker
03/07/2023
Procedures
2-OHP-4021-082-
006
Operation of 2AB & 2CD Battery Chargers
Calculations
1-E-N-ELCP-250-
007
250VDC Battery 1AB System Analysis
11/16/2022
Corrective Action
23-2625
Engineering Direction Not Provided for 2AB Battery Covers
03/30/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
2-MHP-5021-
SCF-001
Scaffolding Procedure
PMI-5041
Temporary Configuration Change Program
Procedures
PMP-5041-TCC-
001
Temporary Configuration Changes
C10006885107
Cover Batteries U2 Battery Room
03/16/2023
Work Orders
C10008148128
Erect Scaffold to W7874 Inside AB Battery Room
03/16/2023
1-IHP-4030-111-
Train 'B' Solid State Protection System (SSPS) Automatic Trip and Actuation Logic Operational Test (TADOT,
Actuation Logic Test and Master Relay Test) and Reactor
Trip Breaker Operational Test (TADOT)
018
1-OHP-4021-032-
001CD
DG1CD Operation
1-OHP-4030-132-
27CD
CD Diesel Generator Operability Test (Train A) - DG1CD
Restart
2/27/2023
1-OHP-4030-132-
27CD
CD Diesel Generator Operability Test (Train A) - DG1CD
Slow Speed Start
2/26/2023
Procedures
1-OHP-4030-156-
017T
Turbine Driven Auxiliary Feedwater System Test
03/23/2023
Miscellaneous
RQ-S-4707-U2-
T1
Period 4707 U2 Training Session (with DEP)
PMP-2350-INS-
001
Inspection Contact and Information Request
Form - 1Q-2023-004
03/16/2023
71151
Miscellaneous
PMP-7110-PIP-
001
Reactor Oversight Program Performance Indicators and
Monthly Operating Report Data Sheets (January 2022
through December 2022)
Corrective Action
Documents
AR 2022-8945
Fire Doors with Roton Hinge May Not Meet Design
Requirement
11/01/2022
Corrective Action
Documents
Resulting from
AR 2023-1281
Extra Oil Absorbents in U-1 AB Diesel
2/10/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Engineering
Evaluations
FPCE-2022-0015
Significance of Fire Protection Program Change Evaluation
11/23/2022
Procedures
2-FPE-2270-
FPCE-001
Fire Protection Program Change Evaluation (FPCE)
AR 2022-5912
Unit 1 IDD 23-H Curtain interference
07/20/2022
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
Corrective Action
Documents
GT 2022-6371
LER 315/2022-002-00 Submittal Tracker
08/09/2022
Miscellaneous
LER 315/2022-
2-00
Unit 1 Ice Condenser Door Inoperable Resulting in a
Condition Prohibited by Technical Specifications
09/19/2022