IR 05000315/2022002

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Integrated Inspection Report 05000315/2022002 and 05000316/2022002
ML22216A258
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 08/08/2022
From: Laura Kozak
Reactor Projects Region 3 Branch 4
To: Lies Q
Indiana Michigan Power Co
References
IR 2022002
Download: ML22216A258 (29)


Text

August 8, 2022

SUBJECT:

DONALD C. COOK NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000315/2022002 AND 05000316/2022002

Dear Mr. Lies:

On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Donald C. Cook Nuclear Plant and 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.

One finding of very low safety significance (Green) is documented in this report. This finding did not involve a violation of NRC requirements.

Licensee-identified violations which were determined to be of very low safety significance 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.

If you disagree with a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Donald C. Cook Nuclear Plant.

Q. 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 Kozak, Laura on 08/08/22 Laura L. Kozak, Acting Chief Branch 4 Division of Reactor Projects 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: 05000315/2022002 and 05000316/2022002 Enterprise Identifier: I-2022-002-0047 Licensee: Indiana Michigan Power Company Facility: Donald C. Cook Nuclear Plant Location: Bridgman, MI Inspection Dates: April 1, 2022 to June 30, 2022 Inspectors: S. Bell, Health Physicist M. Domke, Reactor Inspector M. Garza, Emergency Preparedness Inspector J. Gewargis, Reactor Engineer I. Hafeez, Senior Reactor Inspector J. Mancuso, Resident Inspector R. Ng, Project Engineer J. Reed, Health Physicist R. Wehrmann, Reactor Engineer P. Zurawski, Senior Resident Inspector Approved By: Laura L. Kozak, Chief Branch 4 Division of Reactor Projects 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: 71111.20 and 71124.0

List of Findings and Violations

Spent Fuel Crane Bridge Modification Not Processed Correctly Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green Unable to 71111.18 FIN 05000315,05000316/2022002-01 Identify Open A Green finding was NRC-identified and associated with the licensees failure to process a permanent spent fuel handling crane bridge modification in accordance with licensee procedure IP ENG-001, Standard Design Process, Revision 0. Specifically, a permanent modification to a seismic category I structure, system, or component (SSC) was processed as a commercial change on May 26, 2020, which was prohibited by IP ENG-001.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at 100 percent power and shut down for a refueling outage on April 3, 2022. The unit was returned to rated thermal power on June 2, 2022. Unit 2 began the inspection period at rated thermal power and power was reduced to approximately 92 percent on June 10, 2022, for main feedwater pump and turbine valve functional checks. The unit was returned to full rated power on June 11,

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 summer readiness of offsite and alternate alternating current (AC) power systems prior to the onset of excessive heat and hot weather conditions on June 13, 2022.

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 turbine driven auxiliary feedwater (AFW) Pump on May 21, 2022
(2) Unit 1 north and south safety injection (SI) pumps on May 24, 2022
(3) Unit 1 east and west residual heat removal (RHR) pumps on May 24, 2022

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 Zone 53; Unit 1 Control Room, elevation 633' -0" on April 15, 2022
(2) Fire Zone 56; Unit 1 Auxiliary Cable Vault, elevation 620'-6" on April 29, 2022
(3) Fire Zone 52; Unit 1 and Unit 2 Auxiliary Building, elevation 633' on May 10, 2022
(4) Fire Zone 69; Unit 1 and Unit 2 Auxiliary Building, elevation 650' on May 17, 2022

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 4, 2022 to April 25, 2022:

03.01.a - Nondestructive Examination and Welding Activities.

Volumetric Examination of Component 1-SI-31-26F, ASME Section XI Category R-A/R1.20 Volumetric Examination of Bolts 1-24 in accordance with ASME Section XI Category B-G/B6.180 Volumetric Examination of Component 1-WD-644-03S, ASME Section XI Category R-A/R11.S Surface Examination of ASME Class II Reactor Coolant Pump Seal Injection Lines 1, 2, 3, 4 Pressure Boundary Taper Fillet Welds 1, 4, 5, 8 on Charging Pump Bypass Line per Work Order 5550042-01 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

Visual Examination of Reactor Closure Head and All 58 and 2 Vent Penetrations in accordance with ASME Section XI Category N-729/B4.30 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

Boric Acid Evaluation AR 2020-7358-1, 9/19/2020, 1-SI-153E has a Boric Acid Leak Boric Acid Evaluation AR 2020-7371, 9/19/2020, BA Leak at 1-CS-440-4 Boric Acid Evaluation AR 2020-7379, 9/19/2020, BA Leak at 1-CS-441-4 Boric Acid Correction Action AR 2022-2559, 1-CS-451-3 Flange Leak Boric Acid Correction Action AR 2022-2651, 1-RH-143 Boric Acid Leak Boric Acid Correction Action AR 2022-2587, 1-SI-153W Pipe Cap Leak 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

Steam Generators 11, 12, 13, 14 examined 100 percent tubes by eddy current.

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 Unit 1 startup following refueling outage U1C31 on May 23, 2022.

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

(1) The inspectors observed and evaluated Licensed Operator Requalification RQ-S-4704-U2 on June 8, 2022.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples 1 Partial)

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

(1) Evaluation of 1-HE-15W west component cooling water (CCW) heat exchanger (HX)partial re-tubing on April 25, 2022
(2) Evaluation of 1-HE-15E east CCW HX partial re-tubing on April 15, 2022 (3) (Partial)

Loss of Auxiliary Building integrity on May 4, 2022

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) Unit 1 outage risk due to dual loop essential service water (ESW) outage on April 13, 2022
(2) Hot connection on 2-TR21B transformer on May 2, 2022
(3) Maintenance risk during east CCW/RHR work windows on June 7, 2022

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 2022-2874; Stem Nut Replacement Reduces Anchor-Darling ECCS Valve Stroke Length, on April 8, 2022
(2) AR 2022-2319; Unit 2 Train B CEQ [Containment Equalization] Fan Failed Surveillance Acceptance Criteria, on April 11, 2022
(3) AR 2022-2701; Boric Acid Deposit on U1 Seal Water Injection Piping Suspect Through Wall, on April 11, 2022
(4) AR 2022-3865; Hot Connection on 2-TR21B Transformer, on May 2, 2022
(5) AR 2022-4450; Gas Void at 2-RH-125W, on May 18, 2022
(6) AR 2022-4891; 2-HV-AFP-T2AC Room Cooler Suspected Compressor Issues, on June 7, 2022

71111.18 - Plant Modifications

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

(2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change (EC): 57459; Permanent storage of camera boxes on the Spent Fuel Handling Machine Bridge, on May 17, 2022
(2) EC 54743; Unit 1 Moisture Separator Reheater (MSR) system controls upgrade, on Jun 30, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) U1C31 Containment Penetration 1-CPN-26 VT after Integrated Leak Rate Test (ILRT)on May 13, 2022
(2) Upper Containment Airlock Local Leak Rate Test, 1-AIRLOCK-C650, after ILRT on May 16, 2022
(3) 1-IMO-325 Leak Inspection after stem nut replacement on May 15, 2022
(4) West RHR Pump Leak Test after seal cooler cleaning on May 16, 2022
(5) Main turbine startup after high pressure turbine thrust bearing repairs on May 30, 2022

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage U1C31 activities from April 2 to May 31, 2022.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (6 Samples)

(1) 12-MHP-4030-010-001; Ice Basket Weighing, on April 4, 2022
(2) Unit 2 CD Diesel Generator Slow Start Monthly Surveillance, on April 11, 2022
(3) 12-EHP-4030-051-256; Main Steam Safety Valve Setpoint Verification with Lift Assist Device, on April 11, 2022
(4) 12-MHP-4050-FHP-005; Unit 1 Core Unload/Reload, on April 11, 2022
(5) 12-MHP-4030-031-01; Inspection of the Recirculation Sump, on May 5, 2022
(6) 2-IHP-4030-211-001A; Train A Solid-State Protection System Logic/Reactor Trip

Breakers Surveillance, on May12, 2022 Inservice Testing (IP Section 03.01) (1 Sample)

(1) 1-EHP-4030-134-202; Unit 1 Containment Integrated Leak Rate Test, as documented in Work Order (WO) 5544779 on May 12, 2022

Ice Condenser Testing (IP Section 03.01) (1 Sample)

(1) 12-MHP-4030-010-001; U1C131 Ice Condenser Basket Weighing Surveillance, on April 4, 2022

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the licensees compliance with the requirements specified in the Federal Emergency Management Agency-approved Alert and Notification System Design Report.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program.

71114.06 - Drill Evaluation

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

(1 Sample)

(1) Emergency response facility drill, on June 28,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Workers exiting the radiologically controlled area (RCA) at the Radiation Protection Access Facility during the Unit 1 refueling outage
(2) Workers and equipment exiting the Unit 1 Containment Lower Access Facility during the Unit 1 refueling outage
(3) Workers exiting the RCA at the Turbine Building Access Facility during the Unit 1 refueling outage

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) RWP 221186 U1C31; Radiological Diving to Repair the Upender
(2) RWP 221130 U1C31; Perform Radiography in Auxiliary, Containment & Turbine Buildings & Plant RCA
(3) RWP 221148 U1C31; Steam Generator Primary Activities
(4) RWP 221128 U1C31; Valve Activities in the Auxiliary Building, Containment, and Plant RCA High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Unit 1 587' Auxiliary Building Reactor Coolant Filter Room
(2) Unit 1 Containment Reactor Pit
(3) Unit 1 Containment Steam Generator 1-3 Secondary Side
(4) Unit 1 Accumulator 1-1 Annulus Ladder Entrance
(5) Unit 1 Fuel Transfer Tube Room Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Steam Generator high efficiency particulate air (HEPA) unit #1607, (1600 cubic feet per minute unit)

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

Transportation Radioactive Material Storage (IP Section 03.01) (1 Partial)

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

(1) (Partial)

Material Containers in the Radioactive Materials Building (RMB)

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS07: High Pressure Injection Systems (IP Section 02.06) ===

(1) Unit 1 (April 1, 2021 - March 31, 2022)
(2) Unit 2 (April 1, 2021 - March 31, 2022)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (April 1, 2021 - March 31, 2022)
(2) Unit 2 (April 1, 2021 - March 31, 2022)

EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)

(1) July 1, 2021 through December 31, 2021 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13)

(1 Sample)

(1) July 1, 2021 through December 31, 2021 EP03: Alert and Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
(1) July 1, 2021 through December 31, 2021

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue associated with U1C31 refueling outage main turbine vibrations during the weeks ending June 24 and June 30,

INSPECTION RESULTS

Spent Fuel Crane Bridge Modification Not Processed Correctly Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green Unable to 71111.18 FIN 05000315,05000316/2022002-01 Identify Open/Closed A Green finding was NRC-identified and associated with the licensees failure to process a permanent spent fuel handling crane bridge modification in accordance with licensee procedure IP ENG-001, Standard Design Process, Revision 0. Specifically, a permanent modification to a seismic category I structure, system, or component (SSC) was processed as a commercial change on May 26, 2020, which was prohibited by IP ENG-001.

Description:

On May 17, 2022, during tour of the 650-0 elevation of the Auxiliary Building, the inspectors observed items stored on the spent fuel handling crane bridge. The licensee implemented Permanent Engineering Change, (EC)-0000057459 that authorized storage of up to 8 boxes of camera equipment on the bridge. In addition, storage permit 30105224 was implemented for temporary storage of boxes beyond the EC requirements. Moreover, the inspector observed loose items that did not comply with either the storage permit or the EC.

The inspectors reviewed IP ENG-001, Standard Design Process, Revision 0. Section 1.2.6 states in part, any Yes answer to the following questions prohibits the use of Commercial Change for the proposed activity. Question 7 states in part, Are any affected Structure, System, or Component (SSC) seismic category I or required to be seismically mounted. The spent fuel handling crane bridge is a seismic category I SSC and required a yes answer to Question 7, which precluded the use of a Commercial Change for EC-0000057549.

However, the EC was processed as a commercial change on May 26, 2020 and none of the boxes on the crane bridge were seismically mounted.

Corrective Actions: Immediate corrective actions included removal of the loose items as well as reconfiguration of the boxes stored on the bridge.

Corrective Action References: AR 2022-4404

Performance Assessment:

Performance Deficiency: The licensees failure to adequately process EC-0000057549 was contrary to Section 1.2.6 of licensee procedure IP ENG-001, Standard Design Process, Revision 0, and was a performance deficiency. Specifically, the licensee processed the EC as a commercial change, which was prohibited by the IP ENG-001 procedure.

Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to properly implement the engineering change process resulted in lack of updates to design bases documents associated with the spent fuel handling crane bridge and could result in modifications not adequately incorporating prior changes resulting in unanalyzed conditions, or exceeding design limits.

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that the finding had very low safety significance (Green) because each of the questions in Section E of Exhibit 3 was answered NO.

Cross-Cutting Aspect: Unable to Identify. No cross-cutting aspect was assigned to this finding because the inspectors were unable to identify a cross-cutting aspect that represents the cause or most-significant contributor as to why the performance deficiency exists using Inspection Manual Chapter 0310.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding.

Licensee-Identified Non-Cited Violation 71111.20 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: Technical Specification (TS) 5.4.1.a, Procedures requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Appendix A, February 1978. Regulatory Guide 1.33, Appendix A, Section 3.f.(1) recommended Maintaining Containment Integrity as a general plant operating procedure.

Contrary to the above, on May 14, 2022, the licensee failed to implement a written procedure covering a procedure recommended in Regulatory Guide 1.33, Appendix A, February 1978. Specifically, the licensee established procedure 12-MHP-5021-001-189 CPN-71 Service Penetration, Revision 015, to cover the procedure recommended by Section 3.f.(1) of Regulatory Guide 1.33, Appendix A. In part, Steps 3.2 and 3.6 of this procedure required service penetration CPN-71 to be placed in service to provide containment integrity and containment closure capability during Mode 5 and when containment closure was required during service penetration removal, then at least one cover be installed. However, during Mode 5 with containment integrity required, the licensee removed an integrated leak rate test device from the outboard CPN-71 service penetration flange prior to closure of its inboard cover.

Significance/Severity: Green. The inspectors evaluated the significance of this issue using Inspection Manual Chapter 0609, Appendix H, "Containment Integrity Significance Determination Process and screened the issue Green in Step 2.1.

Corrective Action References: AR 2022-4243 Licensee-Identified Non-Cited Violation 71124.08 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: Title 10 CFR 37.45

(d) states, the licensee shall coordinate with the local law enforcement agency (LLEA) at least every 12 months, or when changes to the facility design or operation adversely affect the potential vulnerability of the licensee's material to theft, sabotage, or diversion.

Title 10 CFR 37.55

(a) states, each licensee shall be responsible for the continuing effectiveness of the security program. Each licensee shall ensure that the security program is reviewed to confirm compliance with the requirements of this subpart and that comprehensive actions are taken to correct any noncompliance that is identified. The review must include the radioactive material security program content and implementation. Each licensee shall periodically (at least annually) review the security program content and implementation.

Contrary to the above, from July 30, 2015 to December 22, 2021, the licensee failed to (1)coordinate with the local law enforcement agency (LLEA) at least every 12 months, or when changes to the facility design or operation adversely affect the potential vulnerability of the licensee's material to theft, sabotage, or diversion, and

(2) periodically (at least annually)review the security program content and implementation.

Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 609 Appendix D, Public Radiation Safety SDP. The inspectors evaluated the finding by applying the Part 37 Subpart A, B or C finding branch of the SDP. The finding was determined to be of very low safety significance (i.e., Green) because:

(1) there was no actual loss of material,
(2) access was not granted to an individual who is not trustworthy and reliable,
(3) there was not an ineffective security zone, and
(4) there was not a deficient security zone.

Corrective Action References: AR 2021-9421 and AR 2021-9047

EXIT MEETINGS AND DEBRIEFS

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

On June 30, 2022, the inspectors presented the integrated inspection results to Mr. Q. S. Lies, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.

On April 25, 2022, the inspectors presented the inservice inspection results to Mr. J. Gebbie, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.

On April 28, 2022, the inspectors presented the radiation protection baseline inspection results to Mr. S. Lies, Site Vice President, and other members of the licensee staff.

On May 6, 2022, the inspectors presented the emergency planning program inspection results to Mr. J. Gebbie, Senior VP and Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures PMI-5055 Winterization/Summerization 008

71111.01 Procedures PMP-5055-001- Winterization/Summerization 039

001

71111.04 Corrective Action AR 2022-3787 Repeat Maintenance Preventable Functional Failure 04/29/2022

Documents

71111.04 Corrective Action AR 2022-4269 1-QT-506 not Stroking Properly. 05/16/2022

Documents

71111.04 Drawings OP-1-5106A Flow Diagram Aux-Feedwater Unit 1 068

71111.04 Drawings OP-1-5142 Flow Diagram Emergency Core Cooling (SIS) 52

71111.04 Drawings OP-1-5143 Flow Diagram Emer. Core Cooling (RHR) Unit No. 1 82

71111.04 Miscellaneous GT 2022-3778 Track completion of 156-107T, LU1 TDAFP 05/02/2022

71111.04 Procedures 1-OHP-4021-017- Placing In Service the Residual Heat Removal System 34

2

71111.04 Procedures 1-OHP-4030-108- North Safety Injection Pump System Test 21

051N

71111.04 Procedures 1-OHP-4030-108- South Safety Injection Pump System Test 023

051S

71111.04 Procedures 1-OHP-4030-156- Turbine Driven Auxiliary Feedwater System Test 031

017T

71111.05 Corrective Action AR 2022-3408 Unpermitted combustibles Found in Level B Area 04/20/2022

Documents

71111.05 Corrective Action AR 2022-4139 Unattended Combustibles 05/10/2022

Documents

71111.05 Corrective Action AR 2022-4386 NRC Identified Degraded Fire Hose at FHC 84 05/17/2022

Documents

71111.05 Fire Plans 12-5975 Fire Hazard Analysis Plan EL 601' 609 & 620' 6" to 625' 10" 004

71111.05 Fire Plans 12-5976 Fire Hazard Analysis Turbine Building Main Floor Elevation 014

633'-0" Units 1 & 2

71111.05 Procedures 12-FPP-2270- Fire Detection Instrument Channel Functional Test 09

066-055 (U-1 Zones 7, 16, 22, 24, and Unit 2 Zones 2, 15, 16, 20)

71111.05 Procedures 12-FPP-2270- Fire Detection Instrumentation Channel Functional Test 07

066-057 (U-2 Zones 6, 9, 22, 24, 26, and Shared Zone 4)

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05 Procedures 12-FPP-2270- Fire Detector Instrumentation Channel Functional Test 5

066-058 (U-1 Zones 10, 11, 13[RCT], 14[4kV], 18, 20, 22 and Shared

Zone 5)

71111.05 Procedures 12-FPP-4030- Fire Detection Instrumentation Operational Test (U-1 Zone 14

066-201 16, U-2 Zone 11 and Shared Zone 2)

71111.05 Procedures 12-FPP-4030- Fire Detection Instrumentation Channel Operational Test 18

066-205 (U-1 Zones 6, 8, 9, 12, 13[4kV], 14[RCT], 15[4kV], 17, 19,

21, 23, 24.

71111.05 Procedures PMP-2270-CCM- Control of Combustible Materials 050

001

71111.05 Work Orders 55537568-01 OPFP, 1-EFR-FIREZONE 22, Channel Functional Test 07/08/2020

71111.05 Work Orders WO-55549765-01 1-EFR-FIRE-ZONE-4 OPFP, 1-EFR-FIREZONE-4, Channel 07/29/2021

Functional Test

71111.08P Corrective Action 2011-11547 Step Change in Steam Generator Eddy Current Indication 10/05/2011

Documents Count

71111.08P Corrective Action 2020-7358-1 1-SI-153E has a Boric Acid Leak 09/19/2020

Documents

71111.08P Corrective Action 2020-7371 BA Leak at 1-CS-440-4 09/19/2020

Documents

71111.08P Corrective Action 2020-7379 BA Leak at 1-CS-441-4 09/19/2020

Documents

71111.08P Corrective Action 2020-7699 Improper Evaluation of BMI Inspection Relevant Conditions 09/25/2020

Documents

71111.08P Corrective Action 2020-8218-12 Revise EHI-5054-RHI Revision 2, Reactor Head Inspection 01/28/2021

Documents Program

71111.08P Corrective Action 2022-2559 1-CS-451-3 Flange Leak 04/02/2022

Documents

71111.08P Corrective Action 2022-2587 1-SI-153W Pipe Cap Leak 04/03/2022

Documents

71111.08P Corrective Action 2022-2651 1-RH-143 Boric Acid Leak 04/04/2022

Documents

71111.08P Corrective Action 2022-2744 Limited Coverage Obtained During ISI Examination 04/06/2022

Documents

Resulting from

Inspection Type Designation Description or Title Revision or

Procedure Date

Inspection

71111.08P Engineering 57714 Use 2 to 1 Taper Fillet Welds on Charging Pump Bypass 0

Changes Lines

71111.08P NDE Reports 51-9280743-000 DC Cook Unit 1 Steam Generator Condition Monitoring for 0

Cycles 26 and 27 and Final Operational Assessment for

Cycles 28, 29, and 30.

71111.08P NDE Reports C10013391002 Liquid Penetrant Examination Report 04/08/2022

71111.08P NDE Reports U1-UT-22-005 UT Calibration/Examination 04/05/2022

71111.08P NDE Reports U1-UT-22-008 UT Calibration/Examination 04/06/2022

71111.08P NDE Reports U1-UT-22-035 UT Calibration/Examination 04/20/2022

71111.08P NDE Reports U1-VT-22-016 Visual Examination of Boric Acid (VT-BM) 04/05/2022

71111.08P NDE Reports U1-VT-22-023 Visual Examination of Boric Acid (VT-BM) 04/10/2022

71111.08P Procedures 12-QHP-5050- Liquid Penetrant Examination 11

NDE-001

71111.08P Procedures EHI-5054-RHI Reactor Head Inspection Program 5

71111.08P Procedures MRS-GEN-1240 Positive Verification Procedure 7

71111.08P Procedures SGP-PLG-RIB- Mechanical Ribbed Plugging of Steam Generator Tubes 5.0

FP-GEN

71111.08P Procedures WDI-STD-1186 Generic Ultrasonic Examination Procedure for Austenitic 1

Welds in accordance with PDI-UT-2

71111.08P Work Orders 55550042-01 2 to 1 Fillets 09/30/2020

71111.11Q Miscellaneous DIT-10000-00 Unit 1 Cycle 30 End-of-Cycle (EOC) Time-to-Boil Information 03/02/2022

71111.11Q Miscellaneous DIT-10001-00 Unit 1 Cycle 31 Beginning-of-Cycle (BOC) Time-to-Boil 03/07/2022

Information

71111.11Q Miscellaneous PMP-4015-RMP- Reactivity Management Program, Data Sheet 1; Unit 1 Cycle 03/15/2022

001 30 TREVI Testing Downpower and Shutdown

71111.11Q Miscellaneous RQ-S-4702-U2- Period 4702 U2 Training Scenario T1 0

T1

71111.11Q Procedures 1-OHP-4021-001- Reactor Startup 069

2

71111.11Q Procedures 1-OHP-4021-001- Power Reduction 65

003

71111.11Q Procedures 1-OHP-4021-001- Power Escalation 086

006

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11Q Radiation 1-OHP-4023 E-0 Reactor Trip or Safety Injection 46

Surveys

71111.12 Corrective Action AR 2022-3902 Aux Building Bent on 650' Elevation Opened During 05/03/2022

Documents Refueling

71111.12 Work Orders C10007737002 1-HE-15W, Perform Tube Plug, Without Tube 05/15/2022

71111.12 Work Orders WO 55531595-09 MTM, 1-HE-15E, Perform Inprocess Test/Check For Tube 04/15/2022

Leaks

71111.12 Work Orders WO 5553159501 1-HE-15E, Perform Partial Retube of CCE Heat Exchanger 05/18/2022

71111.12 Work Orders WO 5553159516 MTM, 1-HE-15E, Disassemble/Reassemble ESW Side of 05/15/2022

E CCW HX

71111.12 Work Orders WO 55532623-24 MTM, 1-HE-15W, Inspect for Tube Leaks (As-Left Test) 05/15/2022

71111.12 Work Orders WO 5553262301 Vendor, 1-HE-15W, Perform Partial Tube Replacement 05/15/2022

71111.12 Work Orders WO 5553262306 Vendor 1-HE-15W, Re-install Channel Head 05/15/2022

71111.12 Work Orders WO-55557144-01 West ESW Train Flow Verification 05/06/2022

71111.12 Work Orders WO-55557248-01 East ESW Train Flow Verification 04/20/2022

71111.13 Corrective Action AR 2022-3865 Hot Connection on 2-TR21B Transformer 05/02/2022

Documents

71111.13 Miscellaneous Unit 1 and 2 Cycle 122, Work Week 10 Risk 0

71111.13 Procedures 2-OHP-4021-082- Removal and Restoration of Power to 600V Bus 21B and 43

21 Associated Motor Control Center

71111.13 Procedures 2-OHP-4022-082- Loss of Power to a 600V Emergency Bus 001

005

71111.13 Work Orders C10023002 2-TTR21B Hot Connection 05/02/2022

71111.15 Calculations NEID-2DCP650- 2-DCP-650, CEQ Fan Timing Relay Setpoint Calculation 0

2

71111.15 Corrective Action AR 2022-2319 Unit 2 CEQ Fan Quarterly Surveillance Failed 03/24/2022

Documents

71111.15 Corrective Action AR 2022-2701 Boric Acid Deposit on U1 SWI Piping Suspect Through Wall 04/05/2022

Documents

71111.15 Corrective Action AR 2022-2874 Anchor-Darling Valve Stem Nuts Replacement 04/08/2022

Documents

71111.15 Corrective Action AR 2022-3865 Hot Connection on 2-TR21B Transformer 05/02/2022

Documents

71111.15 Corrective Action AR 2022-4450 Gas Void at 2-RH-125W 05/12/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

71111.15 Corrective Action AR 2022-4891 2-HV-AFP-T2AC Room Cooler Suspected Compressor 06/03/2022

Documents Issues

71111.15 NDE Reports 12-QHP-5050- Liquid Penetrant Examination 12

NDE-001

71111.15 Operability AR 2022-2874 Stem Nut Replacement Reduces Anchor-Darling ECCS 0

Evaluations Valve Stroke Length

71111.15 Procedures 2-IHP-4030-228- Train B CEQ Fan Surveillance and ESF Response Time 5

005B Test

71111.15 Work Orders 55448317 2-IMO-350-ACT, Perform As-Found/As-Left Diagnostic Test 04/26/2021

71111.15 Work Orders 55448318 2-IMO-340-ACT, Perform As-Found/As-Left Diagnostic Test 04/26/2021

71111.15 Work Orders 55527055 2-ICM-306-ACT, Perform As-Found/As-Left Diagnostic 04/09/2021

71111.15 Work Orders 55530574 As-Left Diagnostic Test 09/26/2020

71111.15 Work Orders WO 55527054-14 2-ICM-305-ACT, Perform As-found/As-Left Diagnostic 04/19/2021

71111.18 Corrective Action AR 2022-4044 EC-0000057459 Not Properly Implemented 05/17/2022

Documents

71111.18 Engineering EC-0000054743 Unit 1 Moisture Separator Reheater (MSR) System Controls 0

Changes Upgrade

71111.18 Engineering EC-0000057459 Storage of Camera Boxes on Spent Fuel Handling Machine 001

Changes Bridge

71111.18 Procedures IP ENG-001 Standard Design Process 001

71111.18 Work Orders WO-5554330834 TPG, R01, PMT of Components Relocated in Panel 1-C 05/17/2022

71111.18 Work Orders WO-5554330864 TPG, R01, Control Room, Demo Panel 1-C and Rack 1-CR 04/10/2022

71111.18 Work Orders WO- TPG, MSR, Repair Fire Seal F6163 04/01/2022

C10001471063

71111.18 Work Orders WO- TPG, MSR, Repair Fire Seal F6123 04/01/2022

C10001471065

71111.18 Work Orders WO- TPG, R1P, MSR, EC-54743, Install Cables, Control Room 03/21/2022

C10001471066

71111.18 Work Orders WO- TPO, U1, MSR, EC-54743, Install & Terminate Panel T 04/27/2022

C10001471078 1-SG-21

71111.18 Work Orders WO- TPG, MSR, Repair Fire Seal F6163 (FCR-54743-010) 04/12/2022

C10001471080

71111.18 Work Orders WO- TPG, MSR, Repair Fire Seal F6167 (FCR-54743-010) 04/23/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

C10001471082

71111.18 Work Orders WO- TPG, P1P, MSR, EC-54743, Install Cables, Control Room 04/13/2022

C10001471084

71111.18 Work Orders WO- TPG, U1, MSR, Incorporation of RFI-54743-054 05/09/2022

C10001471096

71111.18 Work Orders WO- U1, MSR Re-Install Temp Removed Components Panel 1-C 04/19/2022

C10001858020

71111.18 Work Orders WO- U1, MSR, Temp Remove Components 1-C 04/14/2022

C1000858019

71111.19 Drawings DC-03871 Personnel Airlock (Upper) General Arrangement and 02

Drawing Index

71111.19 Drawings OP-1-5143 Flow Diagram Emergency Core Cooling (RHR) 82

71111.19 Engineering EC-0000057371 Removal of Bellows, Protective Cover, and Weld Build Up 0

Changes for Containment Penetration 1-CPN-26

71111.19 Procedures 1-OHP-4021-050- Turbine Generator Normal Startup and Operation 05/30/2022

001

71111.19 Procedures 12-QHP-5070- Visual Examinations: Metallic Containment Pressure 007

NDE-005 Retaining Components and Their Integral Attachments.

71111.19 Work Orders WO 5545322311 OPS: 1-IMO-325; Perform PMT Leak Inspection 06/02/2022

71111.19 Work Orders WO C10007271- U1C31 Containment Penetration CPN-26 VT after ILRT 05/13/2022

013

71111.19 Work Orders WO-55557265-01 West RHR Leak Rate Test 05/16/2022

71111.19 Work Orders WO- MTI, 1-AIRLOCK-C650, Perform 12-IHP-4030-046-002 Seal 05/17/2022

C10012372001 LRT

71111.20 Calibration AR 2022-2559 1-CS-451-3 Flange Leak 04/02/2022

Records

71111.20 Calibration AR 2022-2574 Evidence of Prior Leak on Reactor Pit Wall 04/02/2022

Records

71111.20 Corrective Action AR 2022-2501 1-SI-167-2 Downstream Cap Is Leaking onto Carbon Steel 03/31/2022

Documents

71111.20 Corrective Action AR 2022-2503 Boric Acid Leaking from Pipe Cap 1-SI-159E 03/31/2022

Documents

71111.20 Corrective Action AR 2022-2504 1-NS-622 Boric Acid Leak 03/31/2022

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.20 Corrective Action AR 2022-2506 1-NLP-151-1E Boric Acid Leak 03/31/2022

Documents

71111.20 Corrective Action AR 2022-2551 Boric Acid Leaking from Packing on 1-IRV-147 04/02/2022

Documents

71111.20 Corrective Action AR 2022-2560 1-SI-169-L1 Boric Acid Leak 04/02/2022

Documents

71111.20 Corrective Action AR 2022-2561 1-QRV-114 Boric Acid Leak 04/02/2022

Documents

71111.20 Corrective Action AR 2022-2571 #14 RCP Excessive Leakage 04/02/2022

Documents

71111.20 Corrective Action AR 2022-2587 1-SI-153W Pipe Cap Leak 04/03/2022

Documents

71111.20 Corrective Action AR 2022-2604 1-CS-119N 80 DPM Leak 04/03/2022

Documents

71111.20 Corrective Action AR 2022-2646 12 RCP Shaft Seal is Overflowing Down the Side of the 04/04/2022

Documents Pump

71111.20 Corrective Action AR 2022-3333 Two Positive WBCs from Changing Steam Generator HEPA 04/18/2022

Documents Filters

71111.20 Corrective Action AR 2022-3363 Two Divers with Positive Whole-Body Counts 04/19/2022

Documents

71111.20 Corrective Action AR 2022-4240 Potential Uptakes during Vertical Missile Block Installation 05/13/2022

Documents

71111.20 Miscellaneous Operational Narrative Logs (April 01-04, 2022) 0

71111.20 Miscellaneous GT 2020-7120-50 SU1C31 Refueling Outage Shutdown Safety Plan Report 0

(Outage Milestone 21B, GT 2020-7120-50)

71111.20 Miscellaneous U1C31 Refueling The Shutdown Safety Plan Report 02/25/2022

Outage Shutdown

Safety Plan

71111.20 Procedures 1-OHP-4030-001- Containment Inspection Tours 51

2

71111.20 Procedures 12-MHP-4050- Reactor Vessel Head Removal with Fuel in The Vessel 2

FHP-023

71111.20 Procedures PMP-2060-WHL- Work Hour Limitation and Fatigue Management 13

001

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Corrective Action AR 2021-9935 One Cup of Oil Discharged from DG2CD 2R Bank during 12/08/2021

Documents Blowdown.

71111.22 Miscellaneous 2CD EDG DG2CD System Engineer's Leak Tracking Log. 04/11/2022

71111.22 Procedures 1-EHP-4030-134- Integrated Leak Rate Test 014

2

71111.22 Procedures 12-EHP-4030- Main Steam Safety Valve Setpoint Verification with Lift 03/31/2022

051-256 Assist Device

71111.22 Procedures 12-MHP-4030- Ice Condenser Basket Weighing Surveillance 27

010-001

71111.22 Procedures 12-MHP-4030- Inspection of the Recirculation Sump 21

031-001

71111.22 Procedures 12-MHP-4050- Core Unload/Reload and Incore Shuffle 10

FHP-005

71111.22 Procedures 2-OHP-4030-232- CD Diesel Generator Operability Test (Train A) Attachment 1 068

27CD DG2CD Slow Speed Start

71111.22 Procedures 55260934-01 Perform Recirculation Sump Inspection 0

71111.22 Work Orders 55557124-02 MTM, 1-STN-320 Recirculation Sump Inspection 05/18/2021

71111.22 Work Orders C10004756001 MTI, 2-IHP-4030-211-001A, TR A SSPS LOGIC/RX TRIP 05/12/2022

BKRS SURV

71111.22 Work Orders WO 555547801 1-OME-ICE-COND Ice Basket Weighing Surveillance 04/21/2022

71114.02 Corrective Action AR 2020-4409 Prompt NRC Notification 4-hour Report for EP Sirens 05/27/2020

Documents

71114.02 Miscellaneous Alert and Notification System Evaluation Report 2

71114.03 Corrective Action AR 2020-4343 ERO Shift Staffing Requirements Were Not Met 05/23/2020

Documents

71114.03 Corrective Action AR 2020-9382 Revise EPP-100 with New ERONS Instruction 02/03/2021

Documents

71114.03 Corrective Action AR 20202-5493 First Half 2020 Unannounced Drill Was 8 Days Late 07/09/2020

Documents

71114.03 Corrective Action AR 2021-10362 Everbridge System Down 12/22/2021

Documents

71114.03 Corrective Action AR 2021-1871 ERO Use of Procedure Was Not Up to Standards 02/23/2021

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.03 Corrective Action AR 2021-7359 EOF Activation Time During Drill Exceeded CEP 08/26/2021

Documents Requirements

71114.03 Corrective Action AR 2021-7950 ERO Notification System ERONS/Everbridge 09/22/2021

Documents

71114.03 Corrective Action AR 2021-7980 ERO Exercise Result 09/21/2021

Documents

71114.03 Corrective Action AR 2022-0327 EOF Full Staffing Level Not Met Within 1 Hour Expectation 01/12/2022

Documents

71114.05 Corrective Action AR 2020-3833 U1 Red NRC Phone Did Not Ring When NRC Called 05/06/2020

Documents

71114.05 Corrective Action AR 2020-5910 NRC Red Phone Not Functioning 07/24/2020

Documents

71114.05 Corrective Action AR 2020-6553 Emergency Plan SCBA's in the Control Room 08/20/2020

Documents

71114.05 Corrective Action AR 2020-7626 NRC Red Phone Not Functioning 09/24/2020

Documents

71114.05 Corrective Action AR 2020-9382 Converting 2020 Unannounced Drive-In Drill to Call-Only 11/10/2020

Documents

71114.05 Corrective Action AR 2021-10289 Berrien County EOC Ringdown Phone Inoperable 12/18/2021

Documents

71114.05 Corrective Action AR 2021-1870 Review/Correct MIDAS Issues During ERO Drill 02/25/2021

Documents

71114.05 Corrective Action AR 2021-2965 Poor Procedure Change Review and 50.54q Screening by 04/12/2021

Documents EP

71114.05 Corrective Action AR 2021-4717 NRC Red Phone Issues 05/21/2021

Documents

71114.05 Corrective Action AR 2021-4818 NRC HPN Phone Issues 05/25/2021

Documents

71114.05 Corrective Action AR 2021-4910 10CFR50.54q Screenings 05/27/2021

Documents

71114.05 Corrective Action AR 2021-5056 NRC Phone System Wide Failure 06/02/2021

Documents

71114.05 Corrective Action AR 2021-5149 TSC NRC RSCL Inoperable 06/07/2021

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Corrective Action AR 2021-5654 Control Room NRC Red Phones Not Working 06/24/2021

Documents

71114.05 Corrective Action AR 2021-6449 EOC Phones Failed Daily Testing in SAS and CAS 07/26/2021

Documents

71114.05 Corrective Action AR 2021-7980 ERO Exercise Result 09/21/2021

Documents

71114.05 Corrective Action AR 2021-7982 ERO Exercise Result 09/23/2021

Documents

71114.05 Corrective Action AR 2021-8901 BCSD Ringdown Phone Not Working as Designed 10/29/2021

Documents

71114.05 Corrective Action AR 2021-9059 ERO Drill PAR Result 09/21/2021

Documents

71114.05 Corrective Action AR 2021-9069 OSC Facility was Declared to be Minimum Staff 11/04/2021

Documents

71114.05 Corrective Action AR 2022-0343 Backup Method Required to Notify MSP During ERO Drill 01/12/2022

Documents

71114.05 Corrective Action AR 2022-1277 RMT-2080-PPA-001 Data Sheet Document Incorrect 02/15/2022

Documents

71114.05 Corrective Action AR 2022-1317 TPD-600-EPT Silent on Implementation of Planning 02/16/2022

Documents Standard

71114.05 Corrective Action AR 2022-1455 Conduct of HP Drills 02/22/2022

Documents

71114.05 Corrective Action GT 2021-1685 Document Items from the ERO Drill 02/22/2021

Documents

71114.05 Miscellaneous D.C. Cook Nuclear Plant Emergency Plan 46

71114.05 Miscellaneous D.C. Cook Nuclear Power Plant Unusual Event (HU4.1) 02/15/2022

Declaration Evaluation Report

71114.05 Miscellaneous Emergency Response Resource Readiness Sample

From 2020-

21

71114.05 Miscellaneous DC Cook Nuclear Power Plant August 25, 2020, Training 09/24/2020

Drill

71114.05 Miscellaneous DC Cook Nuclear Power Plant Health Physics Drill 01/26/2021

71114.05 Miscellaneous DC Cook Nuclear Power Plant June 2, 2021, Training Drill 09/02/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Miscellaneous DC Cook Nuclear Power Plant NRC Evaluated Exercise 10/25/2021

71114.05 Miscellaneous AR 2021-1936 2/23 Training Drill EAL Classification Different than Manual 02/23/2021

71114.05 Miscellaneous PMP-2080-EPP- Emergency Classification 27

101

71114.06 Miscellaneous Emergency Response Facility Drill Scenario (June 28, 2022) 0

71124.01 Corrective Action AR 2022-2860 Posting of 609' Demin During Resin Sluice 04/07/2022

Documents

71124.01 Corrective Action AR 2022-3456 Alpha Surveys and Smears not Consistent 04/21/2022

Documents

Resulting from

Inspection

71124.01 Engineering RP-07-02 Technical Basis for D. C. Cook's Alpha Program 5

Evaluations

71124.01 Miscellaneous Reactor Cavity Upender Dive Repair Sentinel Dosimetry 04/09/2022

Records

71124.01 Miscellaneous LHRA and VHRA Door Verification 03/23/2022

71124.01 Miscellaneous Radiography Shot Plan - Unit 1 RHR 04/20/2022

71124.01 Miscellaneous Historical Alpha Historical Alpha Data Characterization Data Various

Data

Characterization

Data

71124.01 Procedures 12-THP-6010- Locked High Radiation Area and Very High Radiation Area 5

RPP-019 Verification

71124.01 Procedures 12-THP-6010- Radiation Protection Actions for Radiological Controlled 22

RPP-301 Area Material Control

71124.01 Procedures 12-THP-6010- Performance of Radiation and Contamination Surveys 48

RPP-401

71124.01 Procedures 12-THP-6010- Special Radiological Evolutions 41

RPP-407

71124.01 Procedures 12-THP-6010- Radiological Controls for Nuclear Diving Operations 11

RPP-413

71124.01 Procedures 12-THP-6010- Radiological Postings 40

RPP-418

71124.01 Procedures PMP-6010-RPP- Radiation Work Permit Program 29

Inspection Type Designation Description or Title Revision or

Procedure Date

006

71124.01 Radiation U1C31 Refueling Outage Air Sample Data Various

Surveys

71124.01 Radiation CNP 2204-00323 U1 U/C Lower Cavity Upender Repair Dive 04/09/2022

Surveys

71124.01 Radiation CNP-2204-00508 Unit 1 591' RHR Vestibule Internals of ICM Valves 04/15/2022

Surveys

71124.01 Radiation CNP-2204-00535 Unit 1 Lower Containment Steam Generator Platforms 1 and 04/18/2022

Surveys 4

71124.01 Radiation CNP-2204-00562 U1 C31 591' RHR Vestibule Reassembly of 1-ICM-305 04/17/2022

Surveys

71124.01 Radiation CNP-2204-00587 Unit 1 Lower Containment 615' Initial Breach of SI-158-L2 04/18/2022

Surveys

71124.01 Radiation CNP-2204-00592 Unit 1 Lower Containment Steam Generator Platforms 2 and 04/18/2022

Surveys 3

71124.01 Radiation CNP-2204-00598 Unit 1 591' RHR Vestibule Breach of 1 DCR-205 04/18/2022

Surveys

71124.01 Radiation CNP-2204-00660 Unit 1 Lower Containment 598' Initial Breach of 1-SI-170-L3 04/21/2022

Surveys

71124.01 Radiation Work 221128 U1C31 - Valve Activities in the Auxiliary, Containment, & 2

Permits (RWPs) Turbine Buildings & Plant Radiologically Controlled Areas

(RCAs)

71124.01 Radiation Work 221130 U1C31- Perform Radiography in Auxiliary, Containment, & 0

Permits (RWPs) Turbine Buildings & Plant Radiologically Controlled Areas

(RCAs)

71124.01 Radiation Work 221148 U1C31 - Steam Generator Primary Activities 2

Permits (RWPs)

71124.01 Radiation Work 221186 U1C31 - Support Work for Diving Activities 0

Permits (RWPs)

71124.03 Miscellaneous Total Effective Dose Evaluation (TEDE) for SI-170-L3 04/20/2022

71124.03 Procedures 12-THP-6010- HEPA Equipment Issue, Control, and Maintenance 28

RPP-315

71124.03 Procedures 12-THP-6010- Portable Air Sampling 27

RPP-403

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.03 Procedures 12-THP-6010- Analysis of Airborne Radioactivity 26

RPP-405

71124.08 Corrective Action AR 2021-7962 RMB Roll Up Door Left Open 09/22/2021

Documents

71124.08 Corrective Action AR 2021-9047 No Objective Evidence Identified for 10 CFR 37.55 11/04/2021

Documents

71124.08 Corrective Action AR 2021-9421 Reporting Category 1 and Category 2 Quantities to LLEA 11/17/2021

Documents

71151 Miscellaneous NRC Performance Indicator Data; Emergency 3rd Quarter

Preparedness - ERO Participation Drill 2021

through 4th

Quarter

21

71151 Miscellaneous NRC Performance Indicator Data; Emergency 3rd Quarter

Preparedness - Drill/Exercise Performance 2021

through 4th

Quarter

21

71151 Miscellaneous MSPI Deviation Report MSPI High Pressure Systems 0

(10/01/2021 - 03/31/2022) Unit 1

71151 Miscellaneous MSPI Deviation Report MSPI High Pressure Systems 0

(10/01/2021 - 03/31/2022) Unit 2

71151 Miscellaneous MSPI Deviation Report MSPI Cooling Water Systems 0

(10/01/2021 - 03/31/2022) Unit 1

71151 Miscellaneous Operational Narrative Logs (October 2021 - March 2022) 0

71151 Miscellaneous MSPI Deviation Report MSPI Cooling Water Systems 0

(10/01/2021 - 03/31/2022) Unit 2

26