IR 05000298/2019003

Integrated Inspection Report 05000298/2019003

ML19303A660
Person / Time
Site:	Cooper
Issue date:	10/30/2019
From:	Christopher Newport NRC/RGN-IV/DRP/RPB-C
To:	Dent J Nebraska Public Power District (NPPD)
References
EPID I-2019-003-0003 IR 2019003
Download: ML19303A660 (40)

Text

ber 30, 2019

SUBJECT:

COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2019003

Dear Mr. Dent:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Cooper Nuclear Station. On October 17, 2019, the NRC inspectors discussed the results of this inspection with Mr. J. Sullivan, General Manager Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.

Two findings of very low safety significance (Green) are documented in this report. These findings involved violations of NRC requirements. 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 significance 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 IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Cooper Nuclear Station.

If you disagree with a cross-cutting aspect assignment 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 IV; and the NRC Resident Inspector at Cooper Nuclear Station.

J. Dent, Jr. 2 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Christopher W. Newport, Acting Chief Reactor Projects Branch C Division of Reactor Projects Docket No. 05000298 License No. DPR-46

Enclosure:

As stated

Inspection Report

Docket Number: 05000298 License Number: DPR-46 Report Number: 05000298/2019003 Enterprise Identifier: I-2019-003-0003 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: Brownville, NE Inspection Dates: July 1, 2019 to September 30, 2019 Inspectors: B. Baca, Health Physicist L. Carson, Senior Health Physicist L. Flores, Project Engineer N. Greene, Senior Health Physicist J. O'Donnell, Health Physicist N. Okonkwo, Reactor Inspector D. Proulx, Senior Project Engineer W. Sifre, Senior Reactor Inspector M. Stafford, Senior Resident Inspector C. Stott, Reactor Inspector P. Vossmar, Senior Resident Inspector Approved By: Christopher W. Newport, Acting 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 Failure to Implement Fire Protection Program Surveillance Requirements for a Fire Barrier Seal Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.1] - 71111.05Q Systems NCV 05000298/2019003-01 Identification Open/Closed The inspectors identified a Green, non-cited violation of License Condition 2.C(4), Fire Protection, for the failure to implement all provisions of the approved fire protection program.

Specifically, prior to July 2, 2019, the licensee failed to implement Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded until it was discovered by the inspectors on July 2, 2019, and subsequently declared nonfunctional by operations personnel.

Failure to Take Required Actions of Technical Specification 3.5.2 for Reactor Pressure Vessel Water Inventory Control During Secondary Containment Work Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.5] - Work 71153 NCV 05000298/2019003-02 Management Open/Closed The inspectors documented a self-revealed, Green, non-cited violation of Technical Specification 3.5.2, Reactor Pressure Vessel Water Inventory Control, for the licensees failure to take technical specification required actions during a reactor pressure vessel water inventory control activity. Specifically, on October 10, 2018, during a planned water inventory control activity, the licensee failed to meet Technical Specification 3.5.2, Condition C, when an unplanned and unrecognized breach of secondary containment occurred, and the licensee did not verify secondary containment could be closed as required until the breach was discovered several hours later. In particular, during residual heat removal service water piping work, the penetration of the same residual heat removal service water piping on both the control building and reactor building sides of the secondary containment boundary was not recognized, and as a result, a containment closure plan was not in place.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000298/2018-002-00 Lack of Procedural Guidance 71153 Closed Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications

PLANT STATUS

Cooper Nuclear Station began the inspection period at rated thermal power. On August 23, 2019, the unit was down powered to 70 percent for a control rod sequence exchange. The plant was returned to rated thermal power on August 24, 2019, and remained at or near rated thermal power for the remainder of the inspection period

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Standby liquid control B on July 8, 2019

(2) Service water booster pump A subsystem on July 16, 2019

(3) Reactor core isolation cooling on September 13, 2019

(4) Core spray B on September 26, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

(1) The inspectors evaluated system configurations during a complete walkdown of the hardened containment vent system installed in accordance with NRC Order EA-13-109 on August 27, 2019. [Completion of this sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in IP

71111.04 - further details are documented in Inspection Report 05000298/2019012, ADAMS

Accession No. ML19266A571.]

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Cable expansion room on July 3, 2019

(2) Reactor building suppression pool 859 feet elevation on July 22, 2019

(3) Southeast quad 859 feet and 881 feet elevations on August 21, 2019

(4) Control cable spreading room on September 17, 2019

(5) Critical switchgear rooms 1F and 1G on September 18, 2019

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Reactor building 931 feet elevation on September 30, 2019 Inspection Activities - Underground Cables (IP Section 02.02c.) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Sump W during sump pump failure and elevated river levels on September 27, 2019

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) The inspectors observed and evaluated licensed operator performance in the control room during a planned quarterly downpower on August 24, 2019.

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

(1) The inspectors observed and evaluated a licensed operator training drill performed as a corrective action for a declining emergency response performance trend on July 30, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Reactor building essential ventilation units on September 30, 2019

Quality Control (IP Section 02.02) (1 Sample)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Reactor core isolation cooling commercially dedicated signal conditioner failure on September 24, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Standby liquid control A pump planned maintenance on July 8, 2019

(2) Unplanned reactor core isolation cooling unavailability on July 24, 2019

(3) Core spray B planned work window on August 13, 2019

(4) Emergency station service transformer planned work window on August 21, 2019

(5) Emergent RF-MO-29 valve packing injection on August 27, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Part 21 for reactor core isolation cooling positioner defect on July 3, 2019

(2) Residual heat removal to radwaste primary containment isolation valve classification/operability on August 15, 2019

(3) Service water check valve 37 past operability on August 19, 2019

(4) Southeast quad fan coil unit failed to meet surveillance acceptance criteria on August 16, 2019

(5) Questionable results during containment isolation valve local leak-rate test on September 19, 2019

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from September 20, 2013, to September 20, 2019:

(1) Evaluation 2013-3, Revision 2, Remove heater bay steam leak detection temperature switches

(2) Evaluation 2015-2, Revision 0, Startup transformer replacement

(3) Evaluation 2015-4, Revision 1, Time critical operator action for suppression pool cooling

(4) Evaluation 2015-5, Revision 1, Reactor containment isolation cooling turbine governor control system replacement

(5) Evaluation 2018-1, Revision 0, Engineering Change (EC) 6038060, Open phase protection system

(6) Evaluation 2018-2, Revision 0, Engineering Evaluation (EE)18-012, Extending inspection duration of underwater torus region

(7) Evaluation 2019-2, Revision 0, Technical Requirements Manual 3.7.1, flooding forecast removed

(8) Screen 71719, 161 kV low voltage limit

(9) Screen 71720, CR-CNS-2016-02270, Standing Order 2016-005

(10) Screen 81728, R3402, sudden pressure relay replacement

(11) Screen 81739, Service water surveillance operation, Division 2

(12) Screen 81731, Use of NSF fuel channels

(13) Screen 81734, Control room air conditioning temporary compressor breaker

(14) Screen 91748, Procedure 6.1EE.306, 4160 V, bus 1F, undervoltage relay channel functional test

(15) Screen 91758, 4160 V, bus 1G, undervoltage relay channel functional test (Division 2)

(16) Screen 91770, Reactor equipment cooling sequential load time delay relay relocation

(17) Screen 91778, Code Case N-513-3 compensatory actions

(18) Screen 91795, Operability Evaluation CR-CNS-2016-05558

(19) Screen 91793, Reclassify MCC-L and MCC-T as nonessential motor control centers

(20) Screen 101794, CR-CNS-2016-05628, CA-001

(21) Screen 111827, High pressure core injection turbine overspeed functional test

(22) Screen 121884, Asea Brown Bovari breaker 145PMB40 BLK limit switch upgrade (1602)

(23) Screen 121895, Service water booster pump oil sight glasses and reservoir

(24) Screen 121898, T2 transformer sudden pressure and seal-in relay replacement

(25) Screen 121948, Replace high pressure core injection flow controller (analog to digital)

(26) Screen 121953, Main generator underfrequency relay replacement

(27) Screen 122011, Residual heat removal service water booster pump system

(28) Screen 122025, Emergency diesel generator indicating light isolation

(29) Screen 122038, Reclassify relays HV-REL-1CFX and HV-REL-1DFX to nonessential

(30) Screen 122067, Various motor operated valve packing load adjustment calculation revisions

(31) Screen 122093, High pressure core injection loss of coolant heat exchanger thermal performance and tube plugging margin

(32) Screen 122143, Residual heat removal and high pressure core injection net positive suction head margins for an anticipated transient without SCRAM event

(33) Screen 142229, Reactor equipment cooling heat exchanger allowable tube plugging increase

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

(1) Hardened containment vent system installed in accordance with NRC Order EA-13-109 on August 29, 2019. [Completion of this permanent modification sample was in accordance with the guidance in Temporary Instruction 2515/193, with credit taken in Inspection Procedure

71111.18 - further details are documented in

Inspection Report 05000298/2019012, ADAMS Accession No. ML19266A571.]

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Service water check valve 37 leakage post maintenance testing on July 23, 2019

(2) Reactor building outer railroad airlock door seal post maintenance testing on July 25, 2019

(3) Scram discharge volume check valve replacement on August 6, 2019

(4) Core spray B planned work window on August 16, 2019

(5) Southeast quad fan coil unit flow test following coil cleaning on September 5, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) Emergency diesel generator 2 monthly operability test on July 15, 2019

(2) Control room emergency filtration system flow test on July 19, 2019

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Reactor equipment cooling motor operated valve operability inservice test on

July 31, 2019 FLEX Testing (IP Section 03.02) (1 Sample)

(1) Spent fuel pool secondary level instrument functional testing on August 7,

71124.05 - Radiation Monitoring Instrumentation Walk Downs and Observations (IP Section 02.01)

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

(1) The inspectors reviewed the following:

Portable Survey Instruments

• RO-20 RP-11376

• AMS-4 RP-10762

• Model 3 RP-11438

• TelePole RP-11451

• REM 500 RP-11177

• Model 177 RP-11275

• H-809V RP-11469 Source Check Demonstration

• RO-20 RP-11419

• Model 3 RP-11438

• TelePole RP-11451 Area Radiation Monitors and Continuous Air Monitors

• CNS-0-RMA-RA-2

• CNS-0-RMA-RA-6

• CNS-0-RMA-RA-7

• CNS-0-RMA-RA-11

• CNS-0-RMA-RA-16

• CNS-0-RMA-RA-23

• CNS-0-RMA-RA-24 Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

• PCM-2 RP-10571

• PM-12 RP-11178

• SAM-12 RP-11152

Calibration and Testing Program (IP Section 02.02) (1 Sample)

The inspectors evaluated the calibration and testing program implementation.

(1) The inspectors reviewed the following:

Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

• PM-12 RP-11178

• SAM-12 RP-11152 Failure to Meet Calibration or Source Check Acceptance Criteria

• None Available

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment Walk Downs and Observations (IP Section 02.01)

The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:

(1)

• Liquid waste effluent system

• Elevated release point (ERP) system

• Radwaste ventilation

• Reactor building ventilation Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02) (1 Sample)

The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:

(1)

• ERP

• Liquid radwaste

• Reactor building

Sampling and Analysis (IP Section 02.03) (1 Sample)

The inspectors reviewed the following:

(1) Radioactive Effluent Sampling and Analysis Activities

• ERP

• Reactor building

• Radwaste

• Turbine building Effluent Discharges The licensee did not perform a continuous or batch liquid effluent discharge during the inspection for observation. The inspectors reviewed selected discharge permits and the licensee's procedures for performing liquid and gaseous effluent discharges.

Instrumentation and Equipment (IP Section 02.04) (1 Sample)

The inspectors reviewed the following radioactive effluent discharge system surveillance test results:

(1) Air Cleaning System Surveillances

• Standby gas treatment

• Control room envelope filtration system [CREFS]

High-Range Effluent Monitoring Instrumentation Calibrations

• Reactor building

• Radwaste

• ERP

Dose Calculations (IP Section 02.05) (1 Sample)

The inspectors reviewed the following to asses public dose:

(1) Liquid and Gaseous Discharge Permits The inspectors walked through the EFFECTS computer program, which documented the weekly continuous gaseous effluent discharge sample inputs, with a chemistry technician and the associated procedure for selected time periods during the inspection period. In addition, the inspectors reviewed the following liquid batch discharge releases:

• 18-15

• 18-33

• 18-42

• 19-10

• 19-13

• 19-43 Annual Radiological Effluent Release Reports

• 2017 Annual Radioactive Effluent Release Report

• 2018 Annual Radioactive Effluent Release Report Abnormal Gaseous or Liquid Tank Discharges The licensee did not have an abnormal gaseous or liquid tank release during the inspection period. The inspectors reviewed release logs and discharge permits for abnormal discharges. The inspectors verified an infrequent tank discharge was performed according to licensee procedures.

71124.07 - Radiological Environmental Monitoring Program Site Inspection (IP Section 02.01)

The inspectors evaluated the radiological environmental monitoring program implementation.

• Air sampling station No. 1

• Air sampling station No. 2

• Air sampling station No. 6 (aka solar station No. 1)

• Air sampling station No. 7

• Thermo-luminescent dosimeter (TLD) monitoring station No. 2

• TLD monitoring station No. 7

• TLD monitoring station No. 10 Environmental Sample Collections and Preparation Observation 1. Environmental samples: None were available for review and observation during this inspection. The inspectors visited a milk cow collection point and observed the licensees delivery of a milk sampling container in preparation for the next milk sampling. The inspectors observed the collection and replacement of air sample cartridges at the following stations:

• Air sampling station No. 1

• Air sampling station No. 2

• Air sampling station No. 6 (aka solar station No. 1)

• Air sampling station No. 7 Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement 1. CR-CNS-2019-03895: Sampling at positions Nos. 28 and 35 were not available due to flooding July 19, 2019 2. CR-CNS-2019-03596: Suitable broadleaf vegetation unavailable due to flooding July 1, 2019 3. CR-CNS-2018-06283: Air samplers Stations 03, 05, and 08 were inaccessible due to excessive flooding October 10, 2018 4. CR-CNS-2018-08143: 100-meter A channel wind speed excessively high; repair/replace November 30, 2018 5. CR-CNS-2018-02820: 100-meter B channel temperature sensor erroneous/incorrect May 9, 2018 Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02) (1 Sample)

Sampling Program for the Potential of Licensed Material Entering Groundwater Groundwater Monitoring Well (GMW)

• CR-CNS-2019-01891, GMW-15 out of service due to excessive flooding, 03/26/19

• CR-CNS-2019-03553, GMW-12 out of service due to excessive flooding, 06/27/19

• CR-CNS-2019-00355, GMW-10 out of service due to excessive flooding, 06/27/19

• CR-CNS-2018-01877, GMW-06 & GMW out of service due to broken submersible pump, 03/29/19 For the 19 GMWs available for the inspection period, all wells measured less than 3,000 pCi/l H-3. The reporting level for H-3 in groundwater is 20,000 pCi/l.

• GMWs: 1D, 1S, 2, 3, 4D, 4S, 5, 6, 7D, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17

71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Radioactive Material Storage (IP Section 02.01)

The inspectors evaluated radioactive material storage.

(1) The inspectors toured the following areas:

• Low Level Radioactive Waste (LLRW) Storage Pad

• Radioactive Materials Storage Building - Blue Building

• East Warehouse Radioactive Material Storage

• Dry Fuel Storage Pad - ISFSI Horizontal Storage Module (HSM) Pad

• Multipurpose Facility (MPF)

• Spent Fuel Pool Area The inspectors performed a container check (e.g., swelling, leakage and deformation)on the following various containers:

• LSA Boxes in Blue Building

• 55 Gallon Drums

• Sealands with Dry Active Waste

• Used Oil Drums

• Wooden Boxes

• Radioactive Trash Bags Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)

The inspectors evaluated the following radioactive waste processing systems and processes during plant walkdowns:

(1) Liquid or Solid Radioactive Waste Processing Systems

• Floor Drain Filter System

• Reactor Water Cleanup System

• Condensate Waste Storage System

• Low Level Radioactive Waste Processing Radioactive Waste Resin and/or Sludge Discharges Processes

• NUPAC Resin Dewatering System Waste Characterization and Classification (IP Section 02.03) (1 Sample)

The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:

(1)

• RWCU - RWCU Resins, February 28, 2019

• CONDWST - WST RESIN/COND RESIN, March 4, 2019

• DAW - DRY ACTIVE WASTE, March 4, 2019

• SPENT - SPENT BEAD RESIN, March 4, 2019

• SCO - Surface Contaminated Equipment, March 4, 2019

• LAUNDRY - Contaminated Laundry, March 4, 2019

• DAW - Dry Active Waste, April 11, 2019

Shipment Preparation (IP Section 02.04) (1 Sample)

The inspectors evaluated and observed the following radioactive material shipment preparation processes:

(1)

• The inspectors were not able to evaluate and observe actual radioactive material shipment preparation processes as no shipments were in process.

The inspectors observed loads of sampled soil being removed from the site which was appropriately surveyed and analyzed. The inspectors also reviewed several shipment packages that included surveys and assessments in preparation for shipment.

Shipping Records (IP Section 02.05) (1 Sample)

The inspectors evaluated the following nonexcepted package shipment records:

(1)

• 17-24, Type A, October 17, 2017

• 17-25, Type A, December 6, 2017

• 17-26, Type A, December 15, 2017

• 18-05, Type A, August 9, 2018

• 18-10, Type A, September 11, 2018

• 18-11, Type A, October 11, 2018

• 18-14, Type A, December 11, 2018

• 19-01, Type B, March 4, 2019

• 19-03, Type B, April 2,

OTHER ACTIVITIES - BASELINE

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

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

(1) July 1, 2018 - June 30, 2019 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample.

(IP Section 02.16) (1 Sample)

(1) October 1, 2018 - June 30, 2019

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in emergency preparedness drill classification that might be indicative of a more significant safety issue on August 2, 2019.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000298/2018-002-00, Lack of Procedural Guidance Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications (ADAMS Accession No. ML18353A278). The circumstances surrounding this LER and an associated non-cited violation are documented in the Inspection Results section of this report.

INSPECTION RESULTS

Failure to Implement Fire Protection Program Surveillance Requirements for a Fire Barrier Seal Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.1] - 71111.05Q Systems NCV 05000298/2019003-01 Identification Open/Closed The inspectors identified a Green, non-cited violation of License Condition 2.C(4), Fire Protection, for the failure to implement all provisions of the approved fire protection program.

Specifically, prior to July 2, 2019, the licensee failed to implement Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded until it was discovered by the inspectors on July 2, 2019, and subsequently declared nonfunctional by operations personnel.

Description:

On July 2, 2019, the inspectors toured the cable expansion room, a risk-significant area where safety-related cables from both divisions are routed. The inspectors observed that a 3-inch cable conduit ran about 8 feet from the west wall of the room and opened near one of the cable trays. The west wall of the cable expansion room was an FP1 Technical Requirements Manual (TRM)-required fire barrier. The open end of the conduit had four cables in it, and the inspectors noted that the conduit seal material was missing from about half of the conduit opening. The inspectors reported the degraded seal, labeled MN 46, to the control room. In response, operations and fire protection personnel walked down the seal. After review of applicable procedures and plant drawings, the licensee determined that the required intact smoke and hot gas seal could not be proven to exist.

Because the deficiency represented an unsealed fire barrier penetration, operations personnel declared the FP1 fire barrier that the conduit penetrated nonfunctional under TRM 3.11.7 and implemented the required hourly fire watch.

The inspectors noted that the seal appeared to have been degrading for some period of time prior to discovery and the inspectors noted that the degraded seal should have been identified during inspections required by TRM 3.11.7, Fire Barrier and Fire Wall Penetration Fire Seals, Technical Surveillance Requirement (TSR) 3.11.7.1. TSR 3.11.7.1 states, visually inspect each side of each fire barrier and penetration fire seal (where possible) on a 24-month frequency. The inspectors reviewed the results of the licensees most recently performed TSR inspection, documented in Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, and performed on August 27, 2018. The inspectors noted that Procedure 6.FP.606 directed plant personnel to inspect the adequacy of the fire barriers and penetration seals via plant drawings and a checklist of the walls in each room. Step 5.1 contained inspection for "all fire barriers" and required verification that there were "no unsealed openings" and "no unsealed penetrations." The inspectors also noted that Fire Protection Program Procedure 3.6.1, "Fire Barrier Control," Revision 21, stated that the internal sealing requirement for a conduit with a diameter of 2-4 inches is a "smoke and hot gas seal within 5 feet of barrier or nearest opening." In addition, Engineering Evaluation (EE)10-055, "Conduit Internal Seals," Revision 0, which was credited in the licensee's NFPA 805 licensing basis contained industry testing data and stated, in part, that larger sized conduits, 3 inches diameter and over, allowed quantities of smoke to pass through the barrier and escape the conduits such that an exposure to sensitive equipment on the non-fire side of the barrier could be postulated. The smoke, if released on the non-fire side, could be expected to affect exposed equipment. The inspectors concluded that the seal contained in conduit MN 46 was a required penetration seal, and the lack of an intact seal should have been identified during performance of Procedure 6.FP.606.

After discussion with fire protection personnel, the inspectors noted that although Surveillance Procedure 6.FP.606 required identification of any unsealed openings and penetrations in fire barriers, the licensee failed to implement the procedure in a manner that ensured unsealed conduit penetrations like MN 46 would be identified. Specifically, although conduit MN 46 penetrated the wall and partially extended out into a room where it opened, plant personnel stated that they only inspected the external seal surrounding the outside of the conduit located at the wall and had not inspected the seal at the opening of the conduit. Fire protection personnel stated that they had determined that this seal was inaccessible and inspection at this location was not possible. After review of Procedure 6.FP.606, the inspectors concluded that the seal in question was accessible. Specifically, Procedure 6.FP.606 defines inaccessible as penetration seals or sections of fire barriers/fire walls that cannot be visually examined due to field configurations, and directs consideration of factors like hazardous material exposures, potential for plant trip or damage to safety equipment, and the need to remove permanent plant equipment to access the seal. The inspectors determined that MN 46 met none of the criteria listed in that it was located in an open area approximately 7 feet from the floor and was easily accessed via normal traversing paths. As a result, the inspectors determined that the licensee had failed to inspect the cable expansion room west wall fire barrier and its associated MN 46 penetration in accordance with TSR 3.11.7.1 and Procedure 6.FP.606.

Corrective Actions: Corrective actions included declaring the fire barrier nonfunctional, implementing TRM requirements for an hourly fire watch, and resealing the degraded penetration seal.

Corrective Action References: Condition Report CR-CNS-2019-03631

Performance Assessment:

Performance Deficiency: The licensees failure to implement fire protection program inspection requirements for an FP1 fire barrier was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Protection Against External Factors attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the performance deficiency resulted in a nonfunctional fire barrier in the cable expansion room, which houses both Division 1 and Division 2 safety-related cabling.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. Because the finding involved the ability to confine a fire, the inspectors applied Inspection Manual Chapter 0609, Appendix F, Fire Protection SDP, to determine the findings significance. The inspectors determined that there was an adequate automatic suppression system on either side of the fire confinement element, and therefore, they concluded that the performance deficiency was of very low safety significance (Green).

Cross-Cutting Aspect: P.1 - Identification: The organization implements a corrective action program with a low threshold for identifying issues. Individuals identify issues completely, accurately, and in a timely manner in accordance with the program. Specifically, fire protection personnel failed to identify the need to inspect the conduit seal at the opening of fire barrier penetration MN 46 during fire barrier surveillance inspections and failed to identify that the seal was degraded during walkdowns.

Enforcement:

Violation: License Condition 2.C(4) requires, in part, that, NPPD shall implement and maintain in effect all provisions of the approved fire protection program. TRM 3.11.7, Fire Barrier and Fire Wall Penetration Fire Seals, TSR 3.11.7.1 states, visually inspect each side of each fire barrier and penetration fire seal (where possible) on a 24-month frequency.

Surveillance Procedure 6.FP.606, Fire Barrier/Penetration Seal Visual Examination, Revision 25, implements this TSR and Step 5.1 states, in part, for all fire barriers, verify no unsealed openings and no unsealed penetrations.

Contrary to the above, prior to July 2, 2019, the licensee failed to verify there were no unsealed openings and no unsealed penetrations for all fire barriers. Specifically, the licensee failed to implement Surveillance Procedure 6.FP.606 for visual inspection of the cable expansion room west wall fire barrier and its associated MN 46 penetration to ensure that an unsealed penetration opening was identified. As a result, the licensee failed to identify that the conduit seal was degraded and nonfunctional until it was discovered by the inspectors on July 2, 2019.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Failure to Take Required Actions of Technical Specification 3.5.2 for Reactor Pressure Vessel Water Inventory Control During Secondary Containment Work Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.5] - Work 71153 NCV 05000298/2019003-02 Management Open/Closed The inspectors documented a self-revealed, Green, non-cited violation of Technical Specification 3.5.2, Reactor Pressure Vessel Water Inventory Control, for the licensees failure to take technical specification required actions during a reactor pressure vessel water inventory control activity. Specifically, on October 10, 2018, during a planned water inventory control activity, the licensee failed to meet Technical Specification 3.5.2, Condition C, when an unplanned and unrecognized breach of secondary containment occurred, and the licensee did not verify secondary containment could be closed as required until the breach was discovered several hours later. In particular, during residual heat removal service water piping work, the penetration of the same residual heat removal service water piping on both the control building and reactor building sides of the secondary containment boundary was not recognized, and as a result, a containment closure plan was not in place.

Description:

During the licensees refueling outage, on September 30, 2018, work orders for residual heat removal service water (RHRSW) piping, located in the control building, were added to an originally approved scope on the same line of RHRSW piping located in the reactor building. When the work was added to the original scope, the licensee did not plan for the repairs to be ongoing simultaneously and, therefore, did not identify the need for a contingency plan to be established for a breach of a secondary containment boundary. On October 10, 2018, Day 11 of the refueling outage, control rod drive mechanism (CRDM)maintenance was ongoing during the RHRSW piping repairs. The CRDM maintenance involved some leakage of reactor pressure vessel (RPV) water during the maintenance activity and was considered a planned water inventory control activity (WICA). Technical Specification (TS) 3.5.2, Reactor Pressure Vessel Water Inventory Control, requires that the drain time of the RPV water inventory to the top of active fuel must be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The licensee calculated the drain time to be 21.62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br /> for the CRDM maintenance. As such, entry into TS Limiting Condition for Operation (LCO) 3.5.2, Condition C, was required. One of the requirements of TS 3.5.2, Condition C, is that the licensee must verify that each secondary containment penetration flow path will be capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of LCO entry. Upon entry into the LCO for the CRDM work, at 12:10 a.m. on October 10, 2018, the licensee took action to verify containment closure plans were in place for all secondary containment breaches that plant personnel were aware of.

Containment closure contingency planning is contained in the licensees procedures.

Administrative Procedure 0-CNS-OU-108, Cooper Shutdown Safety Management Program, Revision 6, Section 6.17, contains containment defense in depth considerations that include, in part, maintaining containment closure capability during reduced water inventory operations.

Within that section, Step 6.17.4 references Administrative Procedure 0.50.5, Outage Shutdown Safety, Revision 40, for containment control requirements. Administrative Procedure 0.50.5 states, in part, that during Modes 4 and 5 when containment closure is required, simultaneously breaching both sides of a secondary containment piping penetration requires preplanned means to block off the breach.

On October 10, 2018, at 11:15 a.m., the licensee discovered that both the control building side and the reactor building side of the RHRSW piping were open simultaneously without a preplanned containment closure document (contingency plan) in place and failed to meet the technical specification LCO requirement that was entered for CRDM maintenance. This configuration existed for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> before the breach was secured. The licensee was able to re-establish the boundary in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery and established a containment closure plan for the RHRSW piping work. Had the licensee recognized that the RHRSW piping work was ongoing in both the control building and the reactor building simultaneously during the RPV water inventory control activity, the containment closure plan would have contained these secondary containment penetrations and included them for the verification of flow path isolation capability within the 4-hour time requirement, and the TS violation would not have occurred. However, during the approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> that the condition existed, the licensee was unaware of the breach until discovery at 11:15 a.m., and if containment closure was required during that time, sealing of this breach would not have occurred. This issue was identified through an event reported to the NRC as a condition prohibited by TS in LER 05000298/2018-002-00, Lack of Procedural Guidance Results in Work Scheduling Error Causing Breach of Secondary Containment and Condition Prohibited by Technical Specifications. It was self-revealed in that workers in the vicinity were unable to weld due to the sustained high volume of air flow through the secondary containment breach.

Corrective Actions: The licensee immediately stopped work, re-established the secondary containment boundary within an hour, and established a contingency closure plan for the RHRSW piping repairs.

Corrective Action References: Condition Report CR-CNS-2018-06295

Performance Assessment:

Performance Deficiency: The licensees failure to take actions required by Technical Specification 3.5.2 for reactor pressure vessel water inventory control is a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Configuration Control attribute of the Barrier Integrity Cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee was unaware that there was ongoing work on RHRSW piping in both the control building and reactor building that breached secondary containment. These piping penetrations were not contained in a contingency closure plan and thus not verified to be capable of being isolated within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> required by TS LCO 3.5.2, Condition C, when performing a reactor pressure vessel water inventory control activity.

Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP. The inspectors determined that the performance deficiency degraded the ability to close or isolate the containment, and as a result, Appendix G, 1, Exhibit 4, directed entry into Inspection Manual Chapter 0609, Appendix H, Containment Integrity Significance Determination Process. The inspectors applied Appendix H, Section 07.02, Approach for Assessing Type B Findings at Shutdown, Step 2.1, to the finding. At the time of the event, the plant operating status (POS) was POS 3, which represents the Mode 5 shutdown condition when the RPV water level is the minimum level required for movement of irradiated fuel assemblies within the RPV. The inspectors determined that the finding was of very low safety significance (Green) because it:

(1) did not occur in POS 1 or POS 2;

(2) did not occur in TW-E (Early Time Window); and

(3) it did not occur within 8 days of the start of the outage.

Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, the licensee failed to implement a process of planning, controlling, and executing work, resulting in a breach of secondary containment that was not recognized as a secondary containment penetration that needed to be verified to be capable of isolation by TS 3.5.2, Condition C, for the RPV water inventory control activity.

Enforcement:

Violation: Technical Specification (TS) 3.5.2, RPV Water Inventory Control, requires, in part, that in Modes 4 and 5, drain time of RPV water inventory to the top of active fuel (TAF)shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The TS action statement requires that, with Drain time < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, verify each secondary containment penetration flow path is capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or initiate action to restore drain time to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> immediately.

Contrary to the above, on October 10, 2018, for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, while in Mode 5, the licensee failed to ensure the drain time of RPV water inventory to the TAF was 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or take the required actions. Specifically, with the drain time of < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the licensee failed to verify each secondary containment penetration flow path was capable of being isolated in less than the drain time within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or initiate action to restore drain time to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> immediately. In particular, improperly sequenced RHRSW work created an unplanned and unrecognized breach of secondary containment, which resulted in the licensee failing to identify the need to take the TS required actions.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On August 22, 2019, the inspectors presented the Public Radiation Safety Cornerstone inspection results to Mr. J. Sullivan, General Manager Plant Operations, and other members of the licensee staff.

• On September 19, 2019, the inspectors presented the Evaluations of Changes, Tests, and Experiments inspection results to Mr. J. Sullivan, General Manager of Plant Operations, and other members of the licensee staff.

• On October 17, 2019, the inspectors presented the integrated inspection results to Mr. J. Sullivan, General Manager Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04Q Drawings 2006, Sheet 4 Flow Diagram Control Building Service Water System 61

71111.04Q Drawings 2036, Sheet 1 Flow Diagram Reactor Building Service Water System A6

71111.04Q Drawings 2043 Flow Diagram Reactor Core Isolation Coolant and Reactor 57

Feed Systems

71111.04Q Drawings 2045, Sheet 1 Flow Diagram Core Spray System N58

71111.04Q Procedures 2.2.67 Reactor Core Isolation Cooling System 80

71111.04Q Procedures 2.2.67.1 Reactor Core Isolation Cooling System Operations 45

71111.04Q Procedures 2.2.67A Reactor Core Isolation Cooling System Component Checklist 23

71111.04Q Procedures 2.2.67B Reactor Core Isolation Cooling System Instrument Valve 3

Checklist

71111.04Q Procedures 2.2.74A Standby Liquid Control System Component Checklist 11

71111.04Q Procedures 2.2.74B Standby Liquid Control System Instrument Valve Checklist 1

71111.04Q Procedures 2.2.9 Core Spray System 85

71111.04Q Procedures 2.2A.CS.DIV2 Core Spray Component Checklist (DIV 2) 3

71111.04Q Procedures 2.2A.RHRSW.DIV1 RHR Service Water Booster Pump System Component 10

Checklist

71111.04Q Procedures 2.2B.CS.DIV2 Core Spray System Instrument Valve Checklist (DIV 2) 0

71111.04Q Procedures 2.2B.RHRSW.DIV1 RHR Service Water Booster Pump System Instrument Valve 0

Checklist

71111.04Q Work Orders WO 5211509

71111.05Q Corrective Action CR-CNS- 2019-03631

Documents

71111.05Q Engineering EE 10-055 Conduit Internal Seals 0

Evaluations

71111.05Q Fire Plans CNS-FP-136 Fire Area Boundary Drawing 6

71111.05Q Fire Plans CNS-FP-212 Reactor SE Quad, Elevations 881 and 859 0

71111.05Q Fire Plans CNS-FP-285 Fire Barrier Penetration Seal Details 7

71111.05Q Miscellaneous CNS-FP-234 Office Building Cable Expansion Room Elevation 918 6 4

71111.05Q Miscellaneous CNS-FP-39 Reactor Building Suppression Pool Elevation 859-9 0

71111.05Q Miscellaneous NEDC 10-080 Fundamental Fire Protection Program and Design Elements 4

Review

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05Q Procedures 0-BARRIER-MAPS Barrier Maps 9

71111.05Q Procedures 0-BARRIER-MAPS Barrier Maps 10

71111.05Q Procedures 0-BARRIER- 14

REACTOR

71111.05Q Procedures 0.7.1 Control of Combustibles 40

71111.05Q Procedures 3.6.1 Fire Barrier Control 21

71111.05Q Procedures 6.FP.606 Fire Barrier/Penetration Seal Visual Examination 25

71111.06 Corrective Action CR-CNS- 2017-00229, 2019-02931, 2019-04268, 2019-05066, 2019-

Documents 05271, 2019-05283

71111.06 Procedures 0-BARRIER Barrier Control Process 29

71111.06 Procedures 0-BARRIER- 14

REACTOR

71111.11Q Miscellaneous RMP 31-013 Quarterly Downpower, 10-EN-RE-215/6CO, Att 2 0

71111.11Q Procedures 10.13 Control Rod Sequence and Movement Control 75

71111.11Q Procedures 10.9 Control Rod Scram Time Evaluation 71

71111.11Q Procedures 2.0.3 Conduct of Operations 102

71111.12 Corrective Action CR-CNS- 2018-07835, 2019-02127, 2019-02581, 2019-03265, 2019-

Documents 03488, 2019-03501, 2019-03934, 2019-03936, 2019-04317,

2019-04336, 2017-04701

71111.12 Engineering EE-PF02F Maintenance Rule Function EE-PF02F Performance Criteria 4

Evaluations Basis

71111.12 Miscellaneous Maintenance Rule (a)(1) Evaluation RCIC-PF01 - RCIC 0, 1

System

71111.12 Miscellaneous 8001553-1 Turbine Control Schematic 1

71111.12 Miscellaneous RCIC-PF01 Maintenance Rule Function RCIC-PF01 Performance Criteria 6

Basis

71111.12 Procedures 3-EN-DC-206 Maintenance Rule (a)(1) Process 3C3

71111.12 Procedures 6.2HV.601 Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2) 7

71111.12 Work Orders WO 5312924

71111.13 Corrective Action CR-CNS- 2019-03936, 2019-03947, 2019-03964, 2019-04218, 2019-

Documents 04347

71111.13 Drawings 18-900# Gate Valve - R.S.-Press Seal Cast STL WCB - 760-3

Stellite Trim - B.W. Ends SMB-2 (60#) Motor Operator

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.13 Miscellaneous Critical Evolutions Meeting Presentation - RF-MOV-29MV

Reactor Feed Pump A Discharge Valve, Packing Gland

Leak Injection

71111.13 Miscellaneous Risk Management Plan - RF-MOV-29MV Reactor Feed

Pump A Discharge Valve, Packing Gland Leak Injection

71111.13 Miscellaneous Protected Equipment Tracking Form - ESST Planned Work 08/21/2019

Window

71111.13 Miscellaneous Protected Equipment Tracking Form - SLC A LCO 07/08/2019

71111.13 Miscellaneous Protected Equipment Tracking Form - Core Spray B 1933 08/13/2019

Maintenance Window

71111.13 Miscellaneous Protected Equipment Tracking Form - RCIC inoperable 07/24/2019

71111.13 Miscellaneous 5284609-03 Work Plan, RF-MOV-29MV

71111.13 Miscellaneous 5284609-05 Work Plan, RF-MOV-29MV

71111.13 Procedures 0-CNS-WM-104 Online Schedule Risk Assessment 9

71111.13 Procedures 0-CNS-WM-104 Attachment 1, Risk Characterization, for WO 5284609-5

71111.13 Procedures 0-PROTECT-EQP Protected Equipment Program 46

71111.13 Work Orders WO 5201509, 5209480, 5211242, 5211244, 5211377, 5211509,

284609-Rev. 3, 5284609-Rev. 5, 5309711

71111.15 Corrective Action CR-CNS- 2017-04701, 2019-02127, 2019-03189, 2019-03478, 2019-

Documents 03860, 2019-03889, 2019-03934, 2019-03936, 2019-04317,

2019-04336

71111.15 Drawings 2040, Sheet 2 Flow Diagram - Residual Heat Removal Sys Loop B 20

71111.15 Engineering EE 10-073 Deletion of Type C Testing of One Barrier due to Closed Loop 0

Evaluations Analysis for 9 Pens

71111.15 Miscellaneous CNS Original Custom Technical Specifications

71111.15 Miscellaneous LO 2019-0045 Part 21 Issue 06/07/2019

71111.15 Miscellaneous USQE-1999 Combine Table V-2-7 and Table VII-3-1 0

71111.15 Procedures 6.2HV.601 Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2) 7

71111.15 Procedures 6.2SW.401 Diesel Generator Service Water Check Valve and Sump Test 3

(IST) (DIV 2)

71111.15 Work Orders WO 5166780, 5196337, 5312924

71111.17T Calculations NEDC 92-064 Transient Temperature Rise in SWBP Room After Loss of 3

Cooling

71111.17T Calculations NEDC 94-034B CNS Containment System Response for NPSH Analysis 2

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations NEDC 97-044A NPSH Margins for the RHR and CS Pumps 4

71111.17T Calculations NEDC 97-044D RHR and HPCI NPSH Margins for ATWS Event 2

71111.17T Corrective Action CR-CNS- 2019-02345, 2019-02364, 2019-03587, 2019-03790, 2019-

Documents 03880, 2019-04668

71111.17T Corrective Action CR-CNS- 2019-04959

Documents

Resulting from

Inspection

71111.17T Drawings CNS-EE-319 SSST OPP Cabinets #1 and #2 Connection Diagram 01

71111.17T Drawings 3001 Main One Line Diagram 30

71111.17T Drawings 3006, Sh. 5 Auxiliary One Line Diagram MCC Z, SWGR Bus 1A, 1B, 1E, 37

& Critical SWGR Bus 1F 1G

71111.17T Drawings 3006, Sh. 5 Auxiliary One Line Diagram Starter Racks LZ and TZ MCCs 90

K, L, LX, RA, RX, S, T, TX, X

71111.17T Drawings 3017, Sh. 1 4160V Switchgear Elementary Diagrams 26

71111.17T Drawings 3020, Sh. 4 4160V Switchgear Elementary Diagrams 27

71111.17T Drawings 3031, Sh. 3 Control Elementary Diagrams Switch Developments 31

71111.17T Drawings 3040, Sh. 9 Control Elementary Diagram 40

71111.17T Drawings 3253, Sh. DT4 460V Motor Control Centers Wiring Details, Connection 21

Wiring Diagram

71111.17T Drawings 3700, Sh. 19 Annunciator Elementary Ladder Diagram N09

71111.17T Drawings 791E271, Sh. 6 HPCI System Elementary Diagram 21

71111.17T Drawings CNS-EE-320 ESST OPP Cabinets #1 and #2 Connection Diagram 01

71111.17T Drawings IL-E-70-3, Sh. Area Temp. Monitoring System for Nuclear Boiler Systems 7

107B Leak Detection

71111.17T Drawings IL-E-70-3, Sh. Area Temperature Monitoring System for Nuclear Boiler 1

107BB Systems Leak Detection

71111.17T Drawings NC 02161 One-line Switching Diagram 345KV/161KV/4160V 34

71111.17T Drawings NC 43456 Cooper 161kV Substation One-line Switching Diagram 13

71111.17T Drawings NC 66688 Cooper 345kV Substation One-line Switching Diagram 24

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Pg. 1 of 18

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Pg. 2 of 18

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 3 of 18

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 4 of 18

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 5

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 6

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 7

71111.17T Drawings OPP-ELE-B101, Open Phase Detection and Protection System 01

Sh. 8 of 18

71111.17T Drawings SKE-EC- HPCI Flow Control Wiring Diagram 5

6016502-3

71111.17T Engineering DEC 5243039 Emergency Diesel Generator Indicating Light Isolation 0

Changes

71111.17T Engineering EC 6016502 HPCI Flow Control 0

Changes

71111.17T Engineering EC 60387820 Main Generator Under Frequency Relay Replacement 0

Changes

71111.17T Engineering EC 6040480 SWBP Oil Sight Glasses and Reservoir 0

Changes

71111.17T Engineering EE 16-021 Engineering Evaluation for 161KV Low Voltage Limit 0

Evaluations

71111.17T Engineering EE 16-048 Engineering Evaluation MCC-L and MCC-T to Non-Essential 0

Evaluations

71111.17T Engineering EE 18-012 Re-Evaluation of Torus Inspection Frequency During Period 0

Evaluations of Extended Operation

71111.17T Engineering EE 18-028 Various MOV Packing Load Adjustment Calculation 0

Evaluations Revisions

71111.17T Engineering EE 18-045 HPCI LOC HX Thermal Performance and Tube Plugging 0

Evaluations Margin

71111.17T Engineering EE 18-046 RHR and HPCI NPSH Margins for ATWS Event 0

Evaluations

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Engineering EE 19-018 REC HX Allowable Tube Plugging Increase 0

Evaluations

71111.17T Engineering EE-18-021 Engineering Evaluation for Reclassifying Relays 15C11

Evaluations HV-REL-1CFX and HV-REL-1DFX to Non-Essential

71111.17T Engineering MDE-270-1285 Evaluation of ATWS Performance at Cooper Nuclear Station December

Evaluations 1985

71111.17T Miscellaneous CDA-EE-001-C1 Control Group Assessment - Open Phase Protection System 1

Controller (CRIO-9068)

71111.17T Miscellaneous CDA-EE-001-ES Control Group Assessment - Open Phase Protection System 0

Injection Source

71111.17T Miscellaneous CDA-EE-001-ES1 Control Group Assessment - Open Phase Protection System 0

DC Power Supply

71111.17T Miscellaneous CDA-EE-001-KP Control Group Assessment - Open Phase Protection System 0

Keypad

71111.17T Miscellaneous CDA-EE-001-R Control Group Assessment - Open Phase Protection System 0

Recorder

71111.17T Miscellaneous CDA-EE-001-REL Control Group Assessment - Open Phase Protection System 0

Current Switch

71111.17T Miscellaneous CDA-EE-001-UPS Control Group Assessment - Open Phase Protection System 0

UPS

71111.17T Miscellaneous CDA-EE-0013 Functional Description and Consequence Analysis 3

71111.17T Miscellaneous IEGR-MN-699 Vendor Manual Open Phase Protection (OPP) System 1.03

Operating and Maintenance Manual

71111.17T Miscellaneous NLS2018053 l0 CFR 50.59(dX2) and 10 CFR 72.48(dX2) Summary Report 10/08/2018

Cooper Nuclear Station, Docket No. 50-298, License

No. DPR-46

71111.17T Miscellaneous RCE 2017-07513 Both EDGs Declared Inoperable Due to Test Failure of Spare 1

Indicating Light

71111.17T Procedures 0-CNS-LI-100 Process Applicability Determination 26

71111.17T Procedures 0-CNS-LI-101 10 CFR 50.59 Evaluations 19

71111.17T Procedures 0-CNS-LI-112 10 CFR 72.48 Evaluations 13

71111.17T Procedures 0-EN-HU-106 Procedure and Work Instruction Use and Adherence 3C2

71111.17T Procedures 2.0.1.3 Time Critical Operator Action Control and Maintenance 7

71111.17T Procedures 2.1.11.1 Turbine Building Data 178

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Procedures 2.2.70 RHR Service Water Booster Pump System 90

71111.17T Procedures 2.3_R-1 Alarm Procedure for Panel R - Annunciator R-1 19

71111.17T Procedures 2.4HVAC Computer Room Ventilation Failure/Temperature High 24

71111.17T Procedures 3-ED-DC-167 Classification of Structure, Systems, and Component 4C2

71111.17T Procedures 3-EN-DC-115 Engineering Change Process 15C14

71111.17T Procedures 6.1EE.302 4160V Bus 1F Undervoltage Relay and Relay Timer 45

Functional Test (DIV 1)

71111.17T Procedures 6.1EE.306 4160V Bus 1F Undervoltage Relay Channel Functional Test 04

(DIV 1)

71111.17T Procedures 7.2.14 RHR SWBP Overhaul and Replacement 45

71111.17T Procedures 7.3.41 Examination, Repair, High Pot Testing of Non-Segregated 16

Buses and Associated Equipment

71111.17T Procedures IP-ENG-001 Standard Design Process 0C0

71111.17T Self-Assessments 2019-0098 50.59 Pre-Inspection Focused Self-Assessment 1

71111.17T Self-Assessments QAD 2018-008 QA Audit 18-02, "Engineering" 03/27/2018

71111.19 Corrective Action CR-CNS- 2017-04701, 2019-03889, 2019-04141, 2019-04142, 2019-

Documents 04209, 2019-04222, 2019-04317, 2019-04336

71111.19 Miscellaneous SW-CV-37 Leakage Troubleshooting Plan 0

71111.19 Miscellaneous 11628207 Notification

71111.19 Procedures 2.2.8 Control Rod Drive System 106

71111.19 Procedures 6.2CS.101 Core Spray Test Mode Surveillance Operation (IST) (DIV 2) 32

71111.19 Procedures 6.2CS.201 CS Motor Operated Valve Operability Test (IST) (DIV 2) 22

71111.19 Procedures 6.2HV.601 Air Flow Test of Fan Coil Unit FC-R-1E (DIV 2) 7

71111.19 Procedures 6.2SW.401 Diesel Generator Service Water Check Valve and Sump Test 3

(IST) (DIV 2)

71111.19 Procedures 6.CRD.201 North and South SDV Vent and Drain Valve Cycling, Open 27

Verification, and Timing Test

71111.19 Procedures 6.SC.501 Secondary Containment Leak Test 28

71111.19 Procedures 6.SC.502 Secondary Containment Penetration Examination 19

71111.19 Procedures 7.0.10 Railroad Airlock Door Operations 26

71111.19 Procedures 7.0.5 Post-Maintenance Testing 59

71111.19 Work Orders WO 5201509, 5209480, 5210423, 5211242, 5211244, 5211377,

265105, 5309143, 5312924

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Corrective Action CR-CNS- 2019-23824

Documents

71111.22 Miscellaneous 2174 Vendor Manual - Mohr SFP-1 Level Prove Assembly 02/13/2015

Technical Manual

71111.22 Procedures 14.41.1.2 FPC-LIT-2 Testing 4

71111.22 Procedures 2.2.32 Fuel Pool Cooling and Demineralizer System 105

71111.22 Procedures 2.2.84 HVAC Main Control Room and Cable Spreading Room 59

71111.22 Procedures 6.2DG.101 Diesel Generator 31 Day Operability Test (IST) (DIV 2) 86

71111.22 Procedures 6.HV.105 Control Room Envelope Pressurization and CREFS Flow 20

Test

71111.22 Procedures 6.REC.201 REC Motor Operated Valve Operability Test (IST) 31

71111.22 Work Orders WO 5195163, 5234083

71114.06 Miscellaneous Drill Scenario Guide 07/30/2019

71124.05 Calibration 5149599 Area Radiation Monitors Calibration and Functional Test 09/20/2018

Records

71124.05 Calibration 5156820 SW Radiation Monitor - B Calibration Check and Instrument 05/16/2018

Records Channel Test - RMP-RM-332B

71124.05 Calibration 5166729 High Range Containment Monitor Victoreen Model 875 10/03/2018

Records Source Calibration Check

71124.05 Calibration 5166732 Containment High Range Monitors A/R/H Determination 10/03/2018

Records

71124.05 Calibration 5166734 Main Steam Line Process Radiation Monitor Channel 10/04/2018

Records Calibration, Source Test, and Setpoint Determination

RMP-RM-251A/B/C/D Data Sheets

71124.05 Calibration 5167782 Containment High Range Area Monitor Channel Calibration 08/29/2018

Records RMA-RM-40 A/B

71124.05 Calibration 5167787 Main Steam Line Process Radiation Monitor Channel 09/11/2018

Records Calibration, Source Test, and Setpoint Determination

RMP-RM-251A/B/C/D Data Sheets

71124.05 Calibration 5186806 REC Radiation Monitor Calibration Check and Instrument 05/01/2019

Records Channel Test

71124.05 Calibration Detector 1 2 Inch Particulate Filter at 5 cm 05/03/2017

Records

71124.05 Calibration Detector 1 2000 ml Marinelli with 1.5 Density 05/17/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

Records

71124.05 Calibration Detector 1 500 cc Charcoal Marinelli 10/05/2018

Records

71124.05 Calibration Detector 1 Charcoal Cartridge at 5 cm 05/05/2017

Records

71124.05 Calibration DG11095729 Tri-Carb 2910TR Efficiency Calibration 02/28/2019

Records

71124.05 Calibration RP-10571 Instrument Calibration Sheet (PCM-2) S/N 401 07/03/2019

Records

71124.05 Calibration RP-10588 RMV-CAM-20 Particulate & Iodine Calibration Sheets 03/27/2019

Records

71124.05 Calibration RP-10765/11497 Instrument Calibration Data Sheet - AMS-4 01/19/2019

Records

71124.05 Calibration RP-10848 XLB Calibration Data Sheet - Unit 1 01/23/2019

Records

71124.05 Calibration RP-11152 Instrument Calibration Sheet Thermo Eberline SAM 05/22/2019

Records Contamination Monitor

71124.05 Calibration RP-11178 PM-12 Calibration Data Sheet S/N 0902PM1207 06/11/2018

Records

71124.05 Calibration RP-11241 Instrument Calibration Data Sheet - DRM-1 or DRM-2 06/25/2019

Records

71124.05 Calibration RP-11376 Instrument Calibration Data Sheet - RO-20 02/14/2019

Records

71124.05 Calibration RP-11724 Instrument Calibration Data Sheet - H-809V1 06/10/2019

Records

71124.05 Corrective Action CR-CNS- 2017-06407, 2017-06689, 2018-03723, 2018-05687, 2018-

Documents 06543, 2018-08139, 2019-00818, 2019-00866, 2019-00880,

2019-01310, 2019-01442, 2019-02130, 2019-02362, 2019-

2669

71124.05 Miscellaneous PCM-2 Weekly Source Checks 08/18/2019

71124.05 Miscellaneous PM-7/PM-12 Daily/Weekly Source Checks 08/20/2019

71124.05 Miscellaneous SAM-11 / SAM-12 Weekly Functional Checks 08/18/2019

71124.05 Miscellaneous CNS System Health Report - RM 06/2019

71124.05 Miscellaneous Results of Radiochemistry Cross Check Program (Quarterly 12/13/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

Results) through

06/05/2019

71124.05 Miscellaneous 878-10 Source Calibration Certificate (S/N 135) 06/26/2003

71124.05 Miscellaneous 878-10A Source Calibration Certificate (S/N 126) 09/24/2003

71124.05 Miscellaneous 878-10B Source Calibration Certificate (S/N 121) 09/18/2003

71124.05 Procedures 15.ARM.302 Area Radiation Monitors Calibration and Functional Test 19

71124.05 Procedures 6.PRM.322 Containment High Range Area Monitor Channel Calibration 21

71124.05 Procedures 6.PRM.323 High Range Containment Monitor Victoreen Model 875 9

Source Calibration Check

71124.05 Procedures 6.PRM.324 Main Steam Line Process Radiation Monitor Channel 29

Calibration, Source Test and Setpoint Determination

71124.05 Procedures 6.PRM.326 Drywell Air Sampling System Known Source Calibration and 17

Functional Test

71124.05 Procedures 6.PRM.329 Containment High Range Monitors A/R/H Determination 5

71124.05 Procedures 6.PRM.331 SW Radiation Monitor A Calibration Check and Instrument 15

Channel Test

71124.05 Procedures 8-CNS-CY-102 Laboratory Analytical Quality Control 2

71124.05 Procedures 8-CNS-CY-110 Canberra APEX Gamma Spectroscopy System Operation 2

71124.05 Procedures 8.5.2.4 Tri-Carb 2910TR Liquid Scintillation System 2

71124.05 Procedures 9.INST.15 Rem 500 Neutron Survey Meter 1

71124.05 Procedures 9.INST.53 Ion Chamber Survey Instrument Eberline Model RO-20 7

71124.05 Procedures 9.INST.57 Friskers 6

71124.05 Procedures 9.INST.64 Thermo Electron Corporation Small Articles Monitor (SAM) 4

71124.05 Procedures 9.INST.68 WR Telepole GM Survey Instrument 4

71124.05 Self-Assessments LO 2018-0186-04 Radiological Monitoring Instrumentation and Radioactive 05/17/2019

Solid Waste Processing and Radioactive Material Handling,

Storage, and Transport

71124.05 Self-Assessments QAD 2018-019 QA Audit 18-05, "Radiological Controls" 08/23/2018

71124.06 Corrective Action CR-CNS- 2017-04647, 2017-05654, 2017-05888, 2017-06574, 2018-

Documents 00199, 2018-02613, 2018-03046, 2018-03588, 2018-04125,

2018-04354, 2018-04569, 2018-04936, 2018-05167, 2018-

07906, 2018-07922, 2019-01916, 2019-02850, 2019-02904,

2019-03082, 2019-03460, 2019-03497, 2019-03946

71124.06 Miscellaneous Teledyne Brown Engineering Environmental Services 07/20/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Laboratory Quality Control Program: 2nd Quarter 2019

Quality Assurance Report

71124.06 Miscellaneous Teledyne Brown Engineering Environmental Services 02/04/2019

Laboratory Quality Control Program: 4th Quarter 2018 Quality

Assurance Report

71124.06 Miscellaneous 20-AUG-19- Gama Spectrum Analysis: ERP Particulate 08/20/2019

210006

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 08/17/2018

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 11/17/2018

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 12/31/2018

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 03/27/2019

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 04/02/2019

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 05/25/2019

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous Liquid Radioactive Liquid Radioactive Waste Discharge Form: Floor Drain 07/03/2019

Waste Discharge Sample Tank (FDST)

Form

71124.06 Miscellaneous LO-2018-0186-008 Liquid and Gaseous Effluents Focused Self-Assessment 06/05/2019

Report

71124.06 Miscellaneous NUPIC Audit NUPIC Audit/Survey: Teledyne Brown Engineering- 05/09/2019

24791 Environmental Services

71124.06 Miscellaneous NUPIC Audit: NUPIC Audit/Survey: NCS Corporation 03/30/2017

24391

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.06 Miscellaneous ODAM Cooper Nuclear Station Offsite Dose Assessment Manual for 10/03/2018

Gaseous and Liquid Effluents

71124.06 Miscellaneous ODAM 2018 Annual Land Use Census 07/16/2018

71124.06 Miscellaneous QAD 2017-0031 Quality Assurance (QA) Audit 17-07: "Chemistry and 10/11/2017

Radiological Effluent and Environmental Monitoring Program"

71124.06 Procedures 6.1SGT.501 SGT A Carbon Sample, Carbon Absorber and HEPA Filter In- 18

Place Leak Test, and Components Leak Test (DIV 1)

71124.06 Procedures 6.2SGT.501 SGT B Carbon Sample, Carbon Absorber and HEPA Filter In- 20

Place Leak Test, and Components Leak Test (DIV 2)

71124.06 Procedures 6.HV.104 Control Room Emergency Filter System Flow Test, Charcoal 19

and HEPA Filter Leak Test, Filter DP Test, and Charcoal

Sample Analysis

71124.06 Procedures 6.PRM.306 Liquid Radwaste Effluent Flow Monitor Channel Calibration 8

71124.06 Procedures 6.PRM.308 Liquid Radwaste Effluent System Channel Calibration 15

71124.06 Procedures 6.PRM.310 ERP Kaman Monitor Channel Calibration 28

71124.06 Procedures 6.PRM.313 Reactor Building Kaman Monitor Channel Calibration 18

71124.06 Procedures 6.PRM.320 Radwaste Building Kaman Monitor Channel Calibration 28

71124.06 Procedures 6.PRM.328 Kaman Sample Flow System Channel Calibration 13

71124.06 Procedures 8-CNS-CY-102 Laboratory Analytical Quality Control 2

71124.06 Procedures 8.11.1 EFFECTS Program 21

71124.06 Procedures 8.8.1.19 Effluent Composite Sample Preparation and Analysis 0

71124.06 Procedures 8.8.11 Liquid Radioactive Waste Discharge Authorization 34

71124.06 Procedures 8.8.ERP Particulate and Iodine Sample Collection for ERP Effluent 18

71124.06 Procedures 8.8.RW Particulate and Iodine Sample Collection for Radwaste 13

Building Effluent

71124.06 Procedures 8.8.RX Particulate and Iodine Sample Collection for Reactor Building 16

Effluent

71124.06 Procedures 8.8.TB Particulate and Iodine Sample Collection for Turbine Building 13

Effluent

71124.06 Work Orders WO 5028538, 5034888, 5043642, 5078036, 5078037, 5080852,

5094262, 5114291, 5119827, 5123375, 5132845, 5147008,

5149663, 5166229, 5166230, 5180017, 5183064, 5189063,

5191559, 5202504, 5226340, 5285586

71124.07 Calibration 7318 Sample Station No. 7 Pump 04/10/19

Inspection Type Designation Description or Title Revision or

Procedure Date

Records

71124.07 Calibration 7319 Sample Station No. 2 Pump 04/23/19

Records

71124.07 Calibration 7321 Sample Station No. 111 04/10/19

Records

71124.07 Calibration 7453 Sample Station No. 8

Records

71124.07 Calibration 7454 Sample Station No. 10 04/10/19

Records

71124.07 Calibration 7455 Sample Station No. 1 Pump 04/10/19

Records

71124.07 Calibration 7539 Sample Station No. 9 04/10/19

Records

71124.07 Corrective Action CR-CNS- 2017-06303, 2017-06091, 2017-06726, 2018-00145, 2018-

Documents 00508, 2018-00643, 2018-01230, 2018-01646, 2018-02826,

2018-03600, 2018-04300, 2018-07515, 2019-01684, 2019-

2054, 2019-02653, 2019-02693, 2019-02772, 2019-02966,

2019-03245

71124.07 Miscellaneous 2018 Land Use Census 07/11/18

71124.07 Miscellaneous 2018 Cooper Nuclear Station Radioactive Effluent Release 2018

Report

71124.07 Miscellaneous 2017 Cooper Nuclear Station Radioactive Effluent Release 2017

Report

71124.07 Miscellaneous Cooper Radiological Environmental Monitoring Program 12/31/17

2017 Annual Report

71124.07 Miscellaneous Cooper Radiological Environmental Monitoring Program 12/31/18

2017 Annual Report

71124.07 Miscellaneous 2019 Land Use Census 07/15/19

71124.07 Procedures 8.ENV.1 CNS Radiological Environmental Monitoring Program 4

Administration

71124.07 Procedures 8.ENV.4 CNS Environmental Air Pump Calibration and Maintenance 0

71124.07 Procedures 8.ENV.5 Annual Review of Broadleaf Vegetation Sample Locations 0

Procedure

71124.07 Procedures 8.ENV.8 Administering the CNS Meteorological Program (CNS MET) 3

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.07 Procedures 8.ENV.9 Ground Water Monitoring Program Sampling, Monitoring, and 11

Administrative Requirements

71124.07 Procedures 14.MET.304 Meteorological Maintenance Procedure for New 100-Meter

Tower - System A

71124.07 Procedures 14.MET.305 Meteorological Maintenance Procedure for New 100-Meter

Tower - System B

71124.07 Procedures 8.ENV.2 REMP Sampling 4

71124.07 Procedures 8.ENV.3 Action Levels for Environmental Samples 3

71124.07 Self-Assessments CNS Environmental Program Self-Assessment Support in 07/24/19

Advance of NRC Inspection

71124.07 Self-Assessments Cooper Nuclear Station 2018 Environmental Assessment 07/26/18

71124.07 Self-Assessments LO Number: 2018- Radiological Environmental Monitoring Program Focused 06/06/19

0186-008 - Self-Assessment Report

Assessment

Report

71124.07 Self-Assessments NUPIC Duke Energy / NUPIC QA Audit of GEL Laboratories - 11/01/16

Audit/Survey October 2016

Number: 24229

71124.07 Self-Assessments NUPIC Radioanalytical Laboratory Audit Report: Teledyne Brown 04/19/19

Audit/Survey Engineering-Environmental Services

Number: 24791

71124.07 Self-Assessments SS17-009 4500187675 "2016-2018 Environmental TLD Service" 11/06/17

71124.08 Corrective Action CR-CNS- 2017-02377; 2017-06224; 2017-06352; 2018-00572; 2019-

Documents 01039; 2019-02631

71124.08 Corrective Action CR-CNS- 2019-04451; 2019-04462

Documents

Resulting from

Inspection

71124.08 Miscellaneous Gamma Spectrum Analysis of ERP Tower Silt 07/31/2019

71124.08 Miscellaneous 2017 Cooper Nuclear Station Radioactive Effluent Release 2017

Report

71124.08 Miscellaneous 2018 Cooper Nuclear Station Radioactive Effluent Release 2018

Report

71124.08 Miscellaneous Onsite Radioactive Material Storage Areas 08/05/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.08 Miscellaneous Offsite Radioactive Material Storage Inventory 05/20/2019

71124.08 Miscellaneous Radioactive Material Storage Building Inventory 08/06/2019

71124.08 Miscellaneous Top Ten Equipment Reliability Action Plan - Radwaste 08/05/2019

System Reliability

71124.08 Miscellaneous 469062001 Waste Stream Analysis for Dry Active Waste 11/14/2018

71124.08 Miscellaneous CNS-RP-602 CNS Radioactive Material Shipment Log - 2017 2017

71124.08 Miscellaneous CNS-RP-602 CNS Radioactive Material Shipment Log - 2018 2018

71124.08 Miscellaneous CNS-RP-602 CNS Radioactive Material Shipment Log - 2019 2019

71124.08 Procedures 0.PCP.1 Process Control Program 0

71124.08 Procedures 2.5.4.4 NUPAC Dewatering System 16

71124.08 Procedures 59.RW.10 Physical Protection of Category I Quantities of Radioactive 9

Material in Transit

71124.08 Procedures 9.ENN-RP-106-1 Radiation and Contamination Surveys 22

71124.08 Procedures 9.RADOP.10 Radioactive Source Control and Accountability 23

71124.08 Procedures 9.RADOP.14 Off-Site Radioactive Material Storage 5

71124.08 Procedures 9.RW.1 Radioactive Shipments 39

71124.08 Procedures 9.RW.3 Dry Radioactive Waste Classification/Listing and Radioactive 4

Material Shipments

71124.08 Procedures 9.RW.5 Control of On-Site Storage of RWCU and Condensate Resins 4

and Wastes (Transfer Out of Storage)

71124.08 Procedures 9.RW.6 Control of On-Site Dry Active Waste Storage 4

71124.08 Procedures 9.RW.7 Waste Stream Sampling 19

71124.08 Procedures 9.RW.9 Filling Containers with Waste/Radioactive Material 18

71124.08 Radiation CNS-1904-0013 Underwater Survey of Spent Fuel Pool 04/11/2019

Surveys

71124.08 Radiation CNS-1906-0000 OCA 903' - Rad Material Storage Building 06/04/2019

Surveys

71124.08 Radiation CNS-1906-0013 Multipurpose Facility (MPF) 903' 06/25/2019

Surveys

71124.08 Radiation CNS-1907-0006 Horizontal Storage Module (HSM) ISFSI Pad 07/08/2019

Surveys

71124.08 Radiation CNS-1907-0007 Horizontal Storage Module (HSM) ISFSI Pad Top View 07/08/2019

Surveys

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.08 Radiation CNS-RP-138 Alpha/Beta Smear Count Quarterly Survey of Offsite RAM 05/08/2019

Surveys Storage

71124.08 Radiation CNS-RP-508 Low Level Radwaste Storage Building 03/20/2019

Surveys

71124.08 Self-Assessments Annual Review of 10 CFR Part 37 Transportation Security 07/23/2018

Plan, Hittman Transport, 2018

71124.08 Self-Assessments LO-2018-0186-04 Self-Assessment: Radiological Monitoring Instrumentation 04/17/2019

and Radioactive Solid Waste Processing and Radioactive

Material Handling, Storage, and Transport

71124.08 Self-Assessments QA 18-05 Radiological Controls Quality Assurance Audit 08/23/2018

71124.08 Shipping Records 17-24 UN3321 RAM - LSA II, Fissile-Excepted, 7, RQ, Spent Resin 10/17/2017

71124.08 Shipping Records 17-25 UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste 12/06/2017

71124.08 Shipping Records 17-26 UN2912 RAM - LSA I, Fissile-Excepted, 7, RQ, Dry Active 12/15/2017

Waste

71124.08 Shipping Records 18-05 UN2912 RAM - LSA I, Fissile-Excepted, 7, RQ, Dry Active 08/09/2018

Waste

71124.08 Shipping Records 18-10 UN3321 RAM - LSA II, Fissile-Excepted, 7, Spent Resin 09/11/2018

71124.08 Shipping Records 18-11 UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste 10/11/2018

71124.08 Shipping Records 18-14 UN3321 RAM - LSA II, Fissile-Excepted, 7, Dry Active Waste 12/11/2018

71124.08 Shipping Records 19-01 UN2916 RAM - Type B(U), Fissile-Excepted, 7, RQ, Spent 03/04/2019

Resin

71124.08 Shipping Records 19-03 UN2916 RAM - Type B(U), Fissile-Excepted, 7, RQ, Spent 04/02/2019

Resin

71151 Miscellaneous 3Q18 thru 4Q19 PI Verification Package - Complicated

SCRAMS

71152 Corrective Action CR-CNS- 2018-08615, 2019-00171, 2019-01287, 2019-02281, 2019-

Documents 02371, 2019-02739, 2019-02791, 2019-02798, 2019-02842,

2019-02875, 2019-04219

71153 Corrective Action CR-CNS- 2018-06295

Documents

71153 Miscellaneous CNS Operations Log 10/09/2018

71153 Miscellaneous CNS Operations Log 10/10/2018

71153 Miscellaneous LER 2018-002-00 Lack of Procedural Guidance Results in Work Scheduling

Error Causing Breach of Secondary Containment and

Inspection Type Designation Description or Title Revision or

Procedure Date

Condition Prohibited by Technical Specifications

71153 Procedures 0-CNS-OU-108 Cooper Shutdown Safety Management Program 6

71153 Procedures 0-CNS-WM-102 Work Implementation and Closeout 10, 11

71153 Procedures 0.50.5 Outage Shutdown Safety 40

71153 Procedures 0.Barrier Barrier Control Process 29

71153 Work Orders WO 5267091, 5267093

37