IR 05000298/2020003

Integrated Inspection Report 05000298/2020003 and Independent Spent Fuel Storage Installation Inspection Report 07200066/2020001

ML20304A778
Person / Time
Site:	Cooper
Issue date:	11/02/2020
From:	Jason Kozal NRC/RGN-IV/DRP/RPB-C
To:	Dent J Nebraska Public Power District (NPPD)
References
IR 2020001, IR 2020003
Download: ML20304A778 (20)

Text

November 2, 2020

SUBJECT:

COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2020003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200066/2020001

Dear Mr. Dent:

On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 15, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

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

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Jason W. Digitally signed by Jason W. Kozal Kozal Date: 2020.11.02 12:31:56 -06'00'

Jason W. Kozal, Chief Reactor Projects Branch C Division of Reactor Projects Docket No. 05000298 License No. DPR-46

Enclosure:

As stated

Inspection Report

Docket Number: 05000298 and 07200066 License Number: DPR-46 Report Number: 05000298/2020003 and 07200066/2020001 Enterprise Identifier: I-2020-003-0006 and I-2020-001-0097 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: Brownville, NE Inspection Dates: July 1, 2020 to September 30, 2020 Inspectors: B. Baca, Health Physicist B. Bergeon, Operations Engineer L. Brookhart, Senior Spent Fuel Storage Inspector J. O'Donnell, Senior Health Physicist E. Simpson, Health Physicist A. Siwy, Senior Resident Inspector C. Smith, Health Physicist M. Stafford, Resident Inspector C. Young, Senior Project Engineer Approved By: Jason W. Kozal, Chief Reactor Projects Branch C Division of Reactor Projects Enclosure

SUMMARY

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

List of Findings and Violations

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

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000298/2019-002-00 Secondary Containment 71153 Closed Rise in Differential Pressure Results in Loss of Safety Function

PLANT STATUS

Cooper Nuclear Station began the inspection period at rated thermal power. On July 24, 2020, power was lowered to approximately 70 percent for a control rod sequence exchange. The plant was returned to rated thermal power on July 25, 2020. On July 26, 2020, power was lowered to approximately 80 percent for a control rod sequence exchange. The plant was returned to rated thermal power on July 26, 2020. On August 8, 2020, the plant commenced power coastdown. On August 9, 2020, power was lowered to 95 percent due to a single control rod scram. On August 10, 2020, power was lowered to 75 percent for control rod recovery. The plant was returned to rated thermal power on August 10, 2020. On September 8, 2020, power was lowered from 89 percent power to 80 percent power when reactor feed pump A was removed from service due to an issue with its governor valve. The plant was returned to 89 percent power on September 10, 2020. On September 26, 2020, the licensee shut the plant down for a scheduled refueling outage. The unit remained shutdown 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 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

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) Emergency diesel generator 2 starting air while emergency diesel generator 1 was inoperable on July 9, 2020

(2) Residual heat removal system B on July 30, 2020

(3) Reactor building sumps on August 27, 2020

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the core spray B system on July 31, 2020.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 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) Cable spreading room on July 1, 2020

(2) Reactor building southwest quad, Elevation 881 feet and 859 feet, on July 30, 2020

(3) Walkdown fire drill area on August 28, 2020

(4) Reactor building southeast quad, Elevation 859 feet, on September 1, 2020

(5) Reactor building refuel floor, Elevation 1001 feet, on September 28, 2020

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from June 9, 2020, through July 17, 2020.

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 downpower and scram for Refueling Outage RE31 on September 26, 2020.

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

(1) The inspectors observed and evaluated the licensed operator requalification scenario on August 12, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 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) Emergency core cooling system sumps on August 7, 2020

(2) Heat trace on the condensate storage tank on August 7, 2020

(3) Reactor protection system scram solenoid valve failure on August 23, 2020

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) Residual heat removal heat exchanger B unavailable during service water flow adjustment on July 16, 2020

(2) Division 2, 4160 volt undervoltage relay surveillance on August 18, 2020

(3) High pressure coolant injection auto isolation logic steam line low pressure functional on September 26, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)

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

(1) Reactor equipment cooling increased outflow on July 13, 2020

(2) FLEX haul path functionality during outage preps on September 4, 2020

71111.18 - Plant Modifications

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

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Reactor equipment cooling leakage modification on September 8, 2020

71111.19 - Post-Maintenance Testing

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

The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:

(1) Standby liquid control A post work testing on July 28, 2020

(2) Service water booster pump A post work testing on July 30, 2020

(3) Intermediate-range monitor G post work testing on August 6, 2020

(4) Main steam line process radiation monitor repairs on September 10, 2020

(5) Reactor feed pump A speed demand deviation repairs on September 11, 2020

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Refueling Outage 31 activities from September 26, 2020, to September 30, 2020. The inspectors completed inspection procedure Sections 03.01a and 03.01b.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Emergency diesel generator 1 operability test with isolation switches in isolate on

September 2, 2020 Inservice Testing (IP Section 03.01) (2 Samples)

(1) Service water check valves on the Division 2 diesel generator on July 18, 2020

(2) High pressure coolant injection dripleg drain valve inservice test on August 5, 2020

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Local leak rate testing for primary containment penetrations on September 21,

71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls

Radiological Work Planning (IP Section 03.01) (5 Samples)

The inspectors evaluated the integration of as low as is reasonably achievable planning into the work activities for the following ALARA packages:

(1) 2018-01, "Control Rod Drive Mechanisms (CRDMs)," Revision 0, which involved the replacement of 15 CRDMs including loading into shipping boxes, rod position instrumentation system (RPIS) probe removal and re-installation, and set up and shoot out steel removals and re-installation

(2) 2018-05, "Reactor Disassembly, Refuel, Reassembly and Miscellaneous Repairs,"

Revisions 0 - 2, which involved the removal and re-installation of the reactor pressure vessel head and associated reactor vessel components, defuel and refuel, and the performance of miscellaneous repairs and maintenance

(3) 2018-15, "General Valve Work for Refuel-30 (RE-30)," Revision 0, which involved maintenance and repairs for valves in the reactor building, drywell, steam tunnel and rad waste buildings

(4) 2018-20, "Radiation Protection Support for RE-30," Revisions 0 - 2, which included radiation protection activities in high radiation areas and locked high radiation areas

(5) 2018-34, "High Pressure Core Injection (HPCI) Motor Operated Valve (MOV) MO-15,"

Revision 0 - 2, which involved high radiation area maintenance work and repairs to the HPCI MOV MO-15 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (5 Samples)

The inspectors evaluated dose estimates and exposure tracking in the following ALARA packages:

(1) 2018-01, "CRDMs," Revision 0, which involved the replacement of 15 CRDMs including loading into shipping boxes, rod position information system probe removal and re-installation, and set up and shoot out steel removals and re-installation

(2) 2018-05, "Reactor Disassembly, Refuel, Reassembly and Miscellaneous Repairs,"

Revisions 0 - 2, which involved the removal and re-installation of the reactor pressure vessel head and associated reactor vessel components, defuel and refuel, and perform miscellaneous repairs and maintenance

(3) 2018-15, "General Valve Work for RE-30," Revision 0, which involved maintenance and repairs for valves in the reactor building, drywell, steam tunnel and rad waste building

(4) 2018-20, "Radiation Protection Support for RE-30," Revisions 0 - 2, which included radiation protection activities in high radiation areas and lock high radiation areas

(5) 2018-34, "HPCI MOV MO-15," Revision 0 - 2, which involved high radiation area maintenance work and repairs to the HPCI MOV MO-15 valve

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments for actual internal exposures:

(1) Two radiation protection technicians' potential airborne exposure evaluations, dated October 15, 2019: Evaluation Nos. 29430 and 30360

(2) A radiation worker alarming a personnel contamination monitor exiting the radiologically controlled area on October 11, 2019: Evaluation No. 37397

Special Dosimetric Situations (IP Section 03.04) (3 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Four dose assessments for three declared pregnant workers

(2) Three personnel contamination events (PCEs) which had skin/shallow dose assessments performed: PCE No. 18-12, PCE No. 18-13, and PCE No. 18-19

(3) Effective dose equivalent for external exposure (EDEX) evaluations in ALARA Package 2018-05, "Reactor Disassembly, Refuel, Reassembly, and Miscellaneous Repairs," Revisions 0 - 2, for work activities involving entries into the cavity: with the drywell head set and during removal, during and after the reactor vessel head removal, to install and detension/retension the reactor vessel head, and insulation package and associated piping removal

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Packing leak on high pressure coolant injection system valve on September 18, 2020

(2) Reactor core isolation cooling governor 10 CFR Part 21 follow-up on September 24, 2020

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 05000298/2019-002-00, Secondary Containment Rise in Differential Pressure Results in Loss of Safety Function (ADAMS Accession No. ML19295F428). The circumstances surrounding this LER and an associated minor violation are documented in the Inspection Results section of this report.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60855 - Operation of an Independent Spent Fuel Storage Installation (ISFSI) The inspectors verified that the licensee's processes and procedures fulfill the requirements specified in the Updated Final Safety Analysis Report (UFSAR), Safety Evaluation Report (SER), Certificate of Compliance (CoC), 10 CFR Part 72, the site-specific license and technical specifications. Additionally, the inspectors verified, by the review of selected records, that the licensee identified each fuel assembly placed in the ISFSIs, recorded the parameters and characteristics of each fuel assembly, and maintained a record of each fuel assembly as a controlled document.

Operation of An ISFSI ===

(1) The licensee's most current 10 CFR 72.212 Evaluation Report, dated July 24, 2020, was reviewed to verify that site characteristics remained bounded by the design bases of the dry fuel storage systems in use at Cooper Nuclear Station (CNS).

Specifically, CNS utilizes two variations of Transnuclear, Inc. (TN) NUHOMS dry spent fuel storage systems:

(1) the Horizontal Storage Module (HSM) Model 202 HSM system with the 61BT dry shielded canister (DSC), and

(2) the HSM Model H with Type 1 DSC 61BTH DSC.

The CNS ISFSI has a total of 52 HSMs, 30 of which are loaded with spent fuel. In 2019, CNS added an additional 22 HSMs to the existing ISFSI. TN CoC 1004, Amendment 13, Revision 1, and TN UFSAR, Revision 15, are the current revisions used at CNS.

===60857 - Review of 10 CFR 72.48 Evaluations The inspectors reviewed 10 CFR 50.59 and 72.48 evaluations, and 10 CFR 72.212(b)evaluations for general licensed ISFSIs for changes made to the ISFSI programs and procedures since the last inspection to verify that changes made were consistent with the license or CoC and did not reduce the effectiveness of the program.

Review of 10 CFR 72.48 Evaluations ===

(1) The inspectors reviewed a list of 10 CFR 72.48 screenings performed by the licensee since July 2017. During this time period the licensee did not perform any 10 CFR 72.48 evaluations. The inspectors evaluated the following:

• Selected licensee 10 CFR 72.48 screenings for associated changes, tests, and experiments associated with ISFSI operations

• The process by which the licensee evaluates 10 CFR 72.48 screenings and evaluations performed by the CoC holder

• Changes made to the licensees 10 CFR 72.212 report since July 2017 (adding additional HSMs)

INSPECTION RESULTS

Minor Violation 71153 Minor Violation: On August 8, 2019, secondary containment vacuum was reduced below the limit of 0.25 inches of vacuum water gauge, which is required by Technical Specification (TS)

Surveillance Requirement (SR) 3.6.4.1.1. This condition existed for 7 minutes and was identified by operations personnel approximately 97 minutes after it had occurred through a review of control room panel indications. This condition was a result of changes in reactor building ventilation flow caused by operations personnel in the field having taken actions to advance the filter media for the reactor building ventilation supply filters. This activity was performed without pre-planning, without informing control room personnel of the activity, and without any documented work instructions, due to it being classified as a skill of the craft activity in accordance with the licensees maintenance program procedures. This issue was entered into the licensees corrective action program as Condition Report CR-CNS-2019-04194.

Technical Specification 5.4.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Section 9.a of Appendix A to Regulatory Guide 1.33 requires that maintenance that can affect the performance of safety-related equipment should be properly pre-planned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.

Contrary to the above, on August 8, 2019, the licensee failed to properly pre-plan and performed maintenance that can affect the performance of safety-related equipment in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. Specifically, operations personnel performed a maintenance activity without pre-planning or documented work instructions to advance the filter media for the reactor building ventilation supply filters, which resulted in a condition that caused secondary containment vacuum to fall below the limit required by technical specification surveillance requirements.

Screening: The inspectors determined the performance deficiency was minor. The performance deficiency associated with this violation was determined to be minor because:

it could not be reasonably viewed as a precursor to a significant event; if left uncorrected, it would not have the potential to lead to a more significant safety concern; and it did not adversely affect the Barrier Integrity cornerstone objective to provide reasonable assurance that physical design barriers (containment) protect the public from radionuclide releases caused by accidents or events. Specifically, the performance deficiency did not affect the integrity of the secondary containment structure, nor did it affect the ability of the safety-related standby gas treatment system to perform its required safety function.

Enforcement:

The licensee has taken actions to restore compliance. This failure to comply with Technical Specification 5.4 constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On July 23, 2020, the inspectors presented the 71124.02 and 71124.04 occupational radiation safety inspection results to Mr. J. Dent, Jr., Site Vice President, and other members of the licensee staff.

• On September 10, 2020, the inspectors presented the independent spent fuel storage installation inspection results to Mr. T. Barker, Director of Engineering, and other members of the licensee staff.

• On October 1, 2020, the inspectors presented the annual licensed operator requalification inspection results to Mr. J. Florence, Superintendent, Simulator & Training Support, and other members of the licensee staff.

• On October 15, 2020, the inspectors presented the integrated inspection results to Mr. J. Dent, Jr., Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60855 Corrective Action CR-CNS- 2017-04504, 2017-04793, 2017-05139, 2017-06746,

Documents 2018-01495, 2018-04248, 2018-05679, 2019-01072,

20-02869, 2020-02882

Corrective Action CR-CNS- 2020-03772 09/10/2020

Documents

Resulting from

Inspection

Miscellaneous Cooper Nuclear Station Independent Spent Fuel Storage 07/24/2020

Installation 10 CFR 72.212 Report

C/06838/01.01/LTR1 CNS Review and Acceptance of ORANO, TN Americas, 09/17/2019

91017-001 Certificate of Conformance, NUHOMS Horizontal Storage

Modules

NCR 2019-005 Hot Concrete Temperature Oven Testing 01/22/2019

Procedures 0-CNS-LI-102 Corrective Action Process 03/18/2020

Radiation CNS-2007-0002 ISFSI Pad Radiation Survey 07/01/2020

Surveys

Self- QA Audit 18-05 Radiological Controls 09/23/2018

Assessments QS-2018-CNS-002 ISFSI Campaign #3 QA Surveillance Report 01/04/2018

QS-2019-CNS-020 ISFSI HSM Construction QA Surveillance 08/21/2019

Work Orders 5283574 Reactor Building Crane Hoist Maintenance 04/02/2020

60857 Engineering EC 09-11 Addition of 22 Model HSM-H Modules within the CSN 06

Changes ISFSI Area and 2018 Update to ISFSI Offsite Dose

Estimates

Engineering PAD 121939 Lift of the ISFSI Transfer Cask (TC) Lid from Elevation 14

Evaluations 903 Train Bay to Elevation 1001 Spent Fuel Pool using

the TC Lift Yoke as a Strong Back

PAD 122165 Modify 72.212 report for renewal of CoC 1004, add 0

technical specification for aging management, add NPPD

compliance with neutron shield in transfer cask, revise

training program description

PAD 142221 Revise EE 09-011 and the CNS 72.212 Report for minor 0

corrections and for addition of 22 model HSM-H modules

Inspection Type Designation Description or Title Revision or

Procedure Date

within the existing CNS ISFSI area. In addition, the ISFSI

offsite dose estimates from "Evaluation of ISFSI

Radioactive Effluents and Radiation" in accordance with

CFR 72.104, tables are updated for calendar years

2016 through 2018.

Miscellaneous LBDCR 2019-001 10 CFR 72.212 Update 10/29/2019

Procedures 0-CNS-LI-100 Process Applicability Determination 02/12/2020

0-CNS-LI-101 10 CFR 50.59 Evaluations 02/12/2020

0-CNS-LI-112 10 CFR 72.48 Evaluations 02/20/2019

71111.04 Drawings 2077 Flow Diagram - Diesel Gen. Bldg. Service Water, Starting 80

Air, Fuel Oil, Sump System & Roof Drains

Procedures 2.2.27 Equipment, Floor, and Chemical Drain System 61

2.2.27A Equipment, Floor, and Chemical Drain System 28

Component Checklist

2.2.66A Reactor Water Cleanup Component Checklist 22

2.2A.CS.DIV2 Core Spray Component Checklist (DIV 2) 4

2.2A.DG.DIV2 Standby AC Power System (Diesel Generator) 8

Component Checklist (DIV 2)

2.2A.RHR.DIV2 Residual Heat Removal System Component Checklist 14

(DIV 2)

71111.05 Corrective Action CR-CNS- 2020-02475, 2020-02630, 2020-03545, 2020-03546

Documents

Fire Plans CNS-FP-212 Reactor Building Southeast Quadrant Elevation 991-9 6

and 859-9

CNS-FP-214 Reactor Building Southwest Quadrant Elevations 881-9 6

and 859-9

CNS-FP-218 Reactor Building - Second Floor Elevation 931-6 11

CNS-FP-219 Reactor Building - Third Floor Elevation 958-3 14

CNS-FP-223 Reactor Building - Refuel Floor Elevation 1001-0 6

CNS-FP-229 Control Building Cable Spreading Room 6

CNS-FP-236 Diesel Generator Building Diesel Generator #1 Elevations 7

917-6 and 903-6

CNS-FP-237 Diesel Generator Building Diesel Generator #2 Elevations 5

917-6 and 903-6

Inspection Type Designation Description or Title Revision or

Procedure Date

CNS-FP-251 Turbine Building Turbine Operating Floor Elevation 932- 11

CNS-FP-285, Fire Barrier Penetration Seal Details 7

Sheet 1

CNS-FP-285, Fire Barrier Penetration Seal Details 5

Sheet 2

CNS-FP-285, Fire Barrier Penetration Seal Details 8

Sheet 3

CNS-FP-285, Fire Barrier Penetration Seal Details 1

Sheet 4

CNS-FP-65 Fire Area Boundary Drawing Cable Spreading Room 3

South Wall

CNS-FP-69 Fire Area Boundary Drawing South Wall (Office Building 4

Side)

Miscellaneous NEDC 10-041 Recovery Action Feasibility Assessment Report Review 1

EPM Report R1006-004-005

Procedures 0-BARRIER Barrier Control Process 31

0-BARRIER-MAPS Barrier Maps 11

15.EE.302 Emergency Lighting and SBO Lighting Functional Test 27

3.6.1 Fire Barrier Control 22

5.1INCIDENT Site Emergency Incident 41

6.FP.606 Fire Barrier/Penetration Seal Visual Examination 25

7.3.12.1 BBESI Emergency Lighting Unit Examination and 24

Maintenance

CNS-EE-178 Safe Shutdown Component Locations & Emerg Route 7

Lighting 903-6: Reactor Building

CNS-EE-180 Safe Shutdown Component Locations & Emerg Route 4

Lighting 859-0 Reactor Building

71111.11Q Procedures 2.0.3 Conduct of Operations 104

2.1.10 Station Power Changes 119

2.1.4 Normal Shutdown 175

2.1.5 Reactor Scram 77

2.2.18.1 4160V Auxiliary Power Distribution System 2

2.2.77 Main Turbine 121

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Corrective Action CR-CNS- 2019-00129, 2019-02921, 2019-02931, 2019-03061,

Documents 2019-03256, 2019-04359, 2019-04905, 2019-05350,

2019-05903, 2019-06032, 2020-03256, 2020-03279,

20-03282, 2020-03340

Miscellaneous Maintenance Rule Function RW-F03 Performance Criteria 6

Basis

Maintenance Rule Function CRD-F03A Performance 5

Criteria Basis

Maintenance Rule Function CRD-F03B Performance 5

Criteria Basis

Maintenance Rule Function CRD-F02B Performance 3

Criteria Basis

Procedures 3-EN-DC-204 Maintenance Rule Scope and Basis 4C0

3-EN-DC-205 Maintenance Rule Monitoring 7C0

71111.13 Corrective Action CR-CNS- 2020-03992, 2020-03993

Documents

Work Orders WO 5282141, 5337256

71111.15 Corrective Action CR-CNS- 2020-02917, 2020-03601

Documents

Procedures 0-CNS-62 Control of Temporary Facilities 33

5.10FLEX.10 ECST Makeup from North Well 3

5.10FLEX.20 Debris Removal in Support of FLEX Operations 3

5.3SBO Station Blackout 6

FLOWCHART

71111.18 Corrective Action CR-CNS- 2020-02891, 2020-02913, 2020-02917, 2020-02946,

Documents 2020-03188

71111.19 Corrective Action CR-CNS- 2020-02757, 2020-02770, 2020-02775, 2020-02862,

Documents 2020-02881, 2020-03679, 2020-03736, 2020-03764

Procedures 2.2.74 Standby Liquid Control System 56

6.1IRM.304 IRM Channel Calibration (Mode Switch in Run) 28

6.1SWBP.101 RHR Service Water Booster Pump Flow Test and Valve 31

Operability Test

6.PRM.324 Main Steam Line Process Radiation Monitor Channel 29

Calibration, Source Test, and Setpoint Determination

Inspection Type Designation Description or Title Revision or

Procedure Date

6.SLC.101 SLC Pump Operability Test 27

7.0.9 Control of Lubricants 15

7.2.26.2 Bolted or Screwed Bonnet Check Valve Maintenance 18

7.2.4 SLC Pump Maintenance 18

Work Orders WO 5209175, 5209254, 5216093, 5312971, 5335029,

5355837, 5357100, 5363228, 5363300

71111.20 Corrective Action CR-CNS- 2020-04025, 2020-04026, 2020-04030, 2020-04038,

Documents 2020-04053

Procedures 2.1.10 Station Power Changes 119

2.1.4 Normal Shutdown 175

2.1.5 Reactor Scram 77

2.2.18.1 4160V Auxiliary Power Distribution System 2

2.2.77 Main Turbine 121

6.RCS.601 Technical Specification Monitoring of RCS 26

Heatup/Cooldown Rate

7.4DISASSEMBLY Reactor Vessel Disassembly 20

71111.22 Corrective Action CR-CNS- 2020-03592

Documents

Procedures 6.1DG.104 Diesel Operability Test with Isolation Switches in Isolate 23

6.2SW.401 Diesel Generator Service Water Check Valve and Sump 4

Test (IST) (DIV 2)

6.HPCI.204 HPCI-SOV-SSV64 and HPCI-SOV-SSV87 IST Closure 15

Test

6.PC.502 Primary Containment Instrumentation Local Leak Rate 24

Tests

Work Orders WO 5088032, 5100584, 5116747, 5129867, 5209525,

209750, 5259394

71124.02 ALARA Plans 2018-07 Refueling Outage (RE) 30 Scaffolds 12/06/2018

2018-32 RWCU-AOV-13/14A & 13/14B Replacements 12/06/2018

2018-33 Refueling Outage (RE) 30 In Vessel Visual Inspection 11/09/2018

(IVVI)

2018-35 Refueling Outage (RE) 30 MSIV Repairs 10/07/2018

Corrective Action CR-CNS- 2018-04073, 2018-05864, 2018-08076, 2018-08202,

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 2018-08665, 2019-01411, 2019-04073, 2020-00661,

20-02536, 2020-02828

Miscellaneous Radiation Protection Program Annual Report 2018 05/29/2019

Radiation Protection Program Annual Report 2019 05/27/2020

2018-05 QA Audit "Radiological Controls" 07/24/2018

LO 2019-0202 Occupational ALARA Planning and Controls" (IP- 01/24/2020

71124.02) and "Occupational Dose Assessment" (IP-

71124.04)

Procedures 9.ALARA.1 Dosimetry Administration 48

9.ALARA.4 Radiation Work Permits 24

9.EN-RP-109 Hot Spot Program 7

9.EN-RP-110 ALARA Program 11

9.EN-RP-110-04 Risk Assessment Process 14

9.EN-RP-110-05 ALARA Planning and Controls 7

9.EN-RP-110-06 Outage Dose Estimating and Tracking 0

Radiation CNS-1809-0092 Unit 1, Reactor Building 1001': Cavity with Reactor Head 09/30/2018

Surveys CNS-1810-0008 Unit 1, Reactor Building 1001': RE-30 Survey performed 10/01/2018

after drywell head removed from the cavity

CNS-1810-0012 Unit 1, Reactor Building 1001': Cavity Survey following 10/01/2018

insulation package removal

CNS-1810-0026 Unit 1, Reactor Building 1001': Survey of cavity following 10/02/2018

removal of reactor pressure vessel (RPV) head

CNS-1811-0005 Unit 1, Reactor Building 1001': Remote survey prior to 11/01/2018

initial cavity survey following drain down

CNS-1811-0007 Unit 1, Reactor Building 1001': Pre-decontamination RPV 11/01/2018

head not installed during survey; Survey of cavity

following drain down

CNS-1811-0010 Unit 1, Reactor Building 1001': Survey performed after 11/01/2018

final pass on cavity decontamination

CNS-1811-0033 Unit 1, Reactor Building 1001': RE-30 Performed dose 11/06/2018

rate gradient survey after setting drywell head during

reassembly

71124.04 Calculations 21585 Dose Equivalent Calculation Worksheet 10/28/2018

34677 Dose Equivalent Calculation Worksheet 10/15/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

37436 Dose Equivalent Calculation Worksheet 10/15/2018

Corrective Action CR-CNS- 2018-00935, 2018-03373, 2018-03990, 2018-07086,

Documents 2019-00972, 2020-00506, 2020-00784, 2020-00900,

20-01075

Miscellaneous 2018-05 QA Audit "Radiological Controls" 07/24/2018

31937 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

34830 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

35936 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

37440 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

37474 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

37616 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

37626 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

37637 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2016

Evaluation

37964 CNS Personnel TLD Vs DRD Discrepancy Dose 02/18/2019

Evaluation

LO 2019-0202 Occupational ALARA Planning and Controls" (IP- 01/24/2020

71124.02) and "Occupational Dose Assessment" (IP-

71124.04)

Procedures 9.EN-RP-110-04 Risk Assessment Process 14

9.EN-RP-122 Alpha Monitoring 4

9.EN-RP-203 Dose Assessment 10

9.EN-RP-205 Prenatal Monitoring 1

9.EN-RP-206 Dosimeter of Legal Record Quality Assurance 5

9.EN-RP-208 Whole Body Counting and In-Vitro Bioassay 4

9.EN-RP-210 Area Monitoring Program 2

9.ENN-RP-102 Radiological Control 3

Inspection Type Designation Description or Title Revision or

Procedure Date

9.RADOP.1 Radiation Protection at CNS 15

9.RADOP.5 Airborne Radioactivity Sampling 32

71152 Corrective Action CR-CNS- 2018-01346, 2019-03189, 2019-03478, 2019-03936,

Documents 2019-03940, 2019-04045, 2019-05331, 2019-05388,

2019-05870, 2019-05923

Procedures 0-CNS-LI-108 10 CFR 21 Evaluations and Reporting 1

6.RCIC.102 RCIC IST and 92 Day Test 40

Work Orders WO 5263795, 5272231

71153 Corrective Action CR-CNS- 2019-04194, 2019-04215, 2019-04217, 2019-04816,

Documents 2019-04827, 2020-02088

Procedures 2.0.3 Conduct of Operations 102, 103

7.0.4 Conduct of Maintenance 41, 42

18