Text

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)
	v • d • e

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. 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

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 Rise in Differential Pressure Results in Loss of Safety Function 71153 Closed

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.

REACTOR SAFETY

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)

Main article: IP 71111.22

(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,

RADIATION SAFETY

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

OTHER ACTIVITIES - BASELINE

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)

Main article: IP 71153

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===

Main article: IP 60855

(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===

Main article: IP 60857

(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

Procedure

Type

Designation

Description or Title

Revision or

Date

60855

Corrective Action

Documents

CR-CNS-

2017-04504, 2017-04793, 2017-05139, 2017-06746,

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

20-02869, 2020-02882

Corrective Action

Documents

Resulting from

Inspection

CR-CNS-

20-03772

09/10/2020

Miscellaneous

Cooper Nuclear Station Independent Spent Fuel Storage

Installation 10 CFR 72.212 Report

07/24/2020

C/06838/01.01/LTR1

91017-001

CNS Review and Acceptance of ORANO, TN Americas,

Certificate of Conformance, NUHOMS Horizontal Storage

Modules

09/17/2019

NCR 2019-005

Hot Concrete Temperature Oven Testing

01/22/2019

Procedures

0-CNS-LI-102

Corrective Action Process

03/18/2020

Radiation

Surveys

CNS-2007-0002

ISFSI Pad Radiation Survey

07/01/2020

Self-

Assessments

QA Audit 18-05

Radiological Controls

09/23/2018

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

283574

Reactor Building Crane Hoist Maintenance

04/02/2020

60857

Engineering

Changes

EC 09-11

Addition of 22 Model HSM-H Modules within the CSN

ISFSI Area and 2018 Update to ISFSI Offsite Dose

Estimates

Engineering

Evaluations

PAD 121939

Lift of the ISFSI Transfer Cask (TC) Lid from Elevation

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

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

corrections and for addition of 22 model HSM-H modules

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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

CFR 72.212 Update

10/29/2019

Procedures

0-CNS-LI-100

Process Applicability Determination

2/12/2020

0-CNS-LI-101

CFR 50.59 Evaluations

2/12/2020

0-CNS-LI-112

CFR 72.48 Evaluations

2/20/2019

71111.04

Drawings

2077

Flow Diagram - Diesel Gen. Bldg. Service Water, Starting

Air, Fuel Oil, Sump System & Roof Drains

Procedures

2.2.27

Equipment, Floor, and Chemical Drain System

2.2.27A

Equipment, Floor, and Chemical Drain System

Component Checklist

2.2.66A

Reactor Water Cleanup Component Checklist

2.2A.CS.DIV2

Core Spray Component Checklist (DIV 2)

2.2A.DG.DIV2

Standby AC Power System (Diesel Generator)

Component Checklist (DIV 2)

2.2A.RHR.DIV2

Residual Heat Removal System Component Checklist

(DIV 2)

71111.05

Corrective Action

Documents

CR-CNS-

20-02475, 2020-02630, 2020-03545, 2020-03546

Fire Plans

CNS-FP-212

Reactor Building Southeast Quadrant Elevation 991-9

and 859-9

CNS-FP-214

Reactor Building Southwest Quadrant Elevations 881-9

and 859-9

CNS-FP-218

Reactor Building - Second Floor Elevation 931-6

CNS-FP-219

Reactor Building - Third Floor Elevation 958-3

CNS-FP-223

Reactor Building - Refuel Floor Elevation 1001-0

CNS-FP-229

Control Building Cable Spreading Room

CNS-FP-236

Diesel Generator Building Diesel Generator #1 Elevations

917-6 and 903-6

CNS-FP-237

Diesel Generator Building Diesel Generator #2 Elevations

917-6 and 903-6

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CNS-FP-251

Turbine Building Turbine Operating Floor Elevation 932-

CNS-FP-285,

Sheet 1

Fire Barrier Penetration Seal Details

CNS-FP-285,

Sheet 2

Fire Barrier Penetration Seal Details

CNS-FP-285,

Sheet 3

Fire Barrier Penetration Seal Details

CNS-FP-285,

Sheet 4

Fire Barrier Penetration Seal Details

CNS-FP-65

Fire Area Boundary Drawing Cable Spreading Room

South Wall

CNS-FP-69

Fire Area Boundary Drawing South Wall (Office Building

Side)

Miscellaneous

NEDC 10-041

Recovery Action Feasibility Assessment Report Review

EPM Report R1006-004-005

Procedures

0-BARRIER

Barrier Control Process

0-BARRIER-MAPS

Barrier Maps

15.EE.302

Emergency Lighting and SBO Lighting Functional Test

3.6.1

Fire Barrier Control

5.1INCIDENT

Site Emergency Incident

6.FP.606

Fire Barrier/Penetration Seal Visual Examination

7.3.12.1

BBESI Emergency Lighting Unit Examination and

Maintenance

CNS-EE-178

Safe Shutdown Component Locations & Emerg Route

Lighting 903-6: Reactor Building

CNS-EE-180

Safe Shutdown Component Locations & Emerg Route

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

2.2.18.1

4160V Auxiliary Power Distribution System

2.2.77

Main Turbine

21

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.12

Corrective Action

Documents

CR-CNS-

2019-00129, 2019-02921, 2019-02931, 2019-03061,

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

Basis

Maintenance Rule Function CRD-F03A Performance

Criteria Basis

Maintenance Rule Function CRD-F03B Performance

Criteria Basis

Maintenance Rule Function CRD-F02B Performance

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

Documents

CR-CNS-

20-03992, 2020-03993

Work Orders

WO 282141, 5337256

71111.15

Corrective Action

Documents

CR-CNS-

20-02917, 2020-03601

Procedures

0-CNS-62

Control of Temporary Facilities

5.10FLEX.10

ECST Makeup from North Well

5.10FLEX.20

Debris Removal in Support of FLEX Operations

5.3SBO

FLOWCHART

Station Blackout

71111.18

Corrective Action

Documents

CR-CNS-

20-02891, 2020-02913, 2020-02917, 2020-02946,

20-03188

71111.19

Corrective Action

Documents

CR-CNS-

20-02757, 2020-02770, 2020-02775, 2020-02862,

20-02881, 2020-03679, 2020-03736, 2020-03764

Procedures

2.2.74

Standby Liquid Control System

6.1IRM.304

IRM Channel Calibration (Mode Switch in Run)

6.1SWBP.101

RHR Service Water Booster Pump Flow Test and Valve

Operability Test

6.PRM.324

Main Steam Line Process Radiation Monitor Channel

Calibration, Source Test, and Setpoint Determination

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

6.SLC.101

SLC Pump Operability Test

7.0.9

Control of Lubricants

7.2.26.2

Bolted or Screwed Bonnet Check Valve Maintenance

7.2.4

SLC Pump Maintenance

Work Orders

WO 209175, 5209254, 5216093, 5312971, 5335029,

5355837, 5357100, 5363228, 5363300

71111.20

Corrective Action

Documents

CR-CNS-

20-04025, 2020-04026, 2020-04030, 2020-04038,

20-04053

Procedures

2.1.10

Station Power Changes

119

2.1.4

Normal Shutdown

175

2.1.5

Reactor Scram

2.2.18.1

4160V Auxiliary Power Distribution System

2.2.77

Main Turbine

21

6.RCS.601

Technical Specification Monitoring of RCS

Heatup/Cooldown Rate

7.4DISASSEMBLY

Reactor Vessel Disassembly

71111.22

Corrective Action

Documents

CR-CNS-

20-03592

Procedures

6.1DG.104

Diesel Operability Test with Isolation Switches in Isolate

6.2SW.401

Diesel Generator Service Water Check Valve and Sump

Test (IST) (DIV 2)

6.HPCI.204

HPCI-SOV-SSV64 and HPCI-SOV-SSV87 IST Closure

Test

6.PC.502

Primary Containment Instrumentation Local Leak Rate

Tests

Work Orders

WO 5088032, 5100584, 5116747, 5129867, 5209525,

209750, 5259394

71124.02

ALARA Plans

2018-07

Refueling Outage (RE) 30 Scaffolds

2/06/2018

2018-32

RWCU-AOV-13/14A & 13/14B Replacements

2/06/2018

2018-33

Refueling Outage (RE) 30 In Vessel Visual Inspection

(IVVI)

11/09/2018

2018-35

Refueling Outage (RE) 30 MSIV Repairs

10/07/2018

Corrective Action

CR-CNS-

2018-04073, 2018-05864, 2018-08076, 2018-08202,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

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-

71124.02) and "Occupational Dose Assessment" (IP-

71124.04)

01/24/2020

Procedures

9.ALARA.1

Dosimetry Administration

9.ALARA.4

Radiation Work Permits

9.EN-RP-109

Hot Spot Program

9.EN-RP-110

ALARA Program

9.EN-RP-110-04

Risk Assessment Process

9.EN-RP-110-05

ALARA Planning and Controls

9.EN-RP-110-06

Outage Dose Estimating and Tracking

Radiation

Surveys

CNS-1809-0092

Unit 1, Reactor Building 1001': Cavity with Reactor Head

09/30/2018

CNS-1810-0008

Unit 1, Reactor Building 1001': RE-30 Survey performed

after drywell head removed from the cavity

10/01/2018

CNS-1810-0012

Unit 1, Reactor Building 1001': Cavity Survey following

insulation package removal

10/01/2018

CNS-1810-0026

Unit 1, Reactor Building 1001': Survey of cavity following

removal of reactor pressure vessel (RPV) head

10/02/2018

CNS-1811-0005

Unit 1, Reactor Building 1001': Remote survey prior to

initial cavity survey following drain down

11/01/2018

CNS-1811-0007

Unit 1, Reactor Building 1001': Pre-decontamination RPV

head not installed during survey; Survey of cavity

following drain down

11/01/2018

CNS-1811-0010

Unit 1, Reactor Building 1001': Survey performed after

final pass on cavity decontamination

11/01/2018

CNS-1811-0033

Unit 1, Reactor Building 1001': RE-30 Performed dose

rate gradient survey after setting drywell head during

reassembly

11/06/2018

71124.04

Calculations

21585

Dose Equivalent Calculation Worksheet

10/28/2018

34677

Dose Equivalent Calculation Worksheet

10/15/2018

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

37436

Dose Equivalent Calculation Worksheet

10/15/2018

Corrective Action

Documents

CR-CNS-

2018-00935, 2018-03373, 2018-03990, 2018-07086,

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

20-01075

Miscellaneous

2018-05

QA Audit "Radiological Controls"

07/24/2018

31937