IR 05000298/2019002

Integrated Inspection Report 05000298/2019002

ML19219A801
Person / Time
Site:	Cooper
Issue date:	08/05/2019
From:	Cale Young Division of Nuclear Materials Safety IV
To:	Dent J Nebraska Public Power District (NPPD)
Cale Young
References
IR 2019002
Download: ML19219A801 (35)

Text

ust 5, 2019

SUBJECT:

COOPER NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000298/2019002

Dear Mr. Dent,

Jr.:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Cooper Nuclear Station. On July 16, 2019, the NRC inspectors discussed the results of this inspection with Mr. D. Buman, Director of Nuclear Safety Assurance and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the violation 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/

Cale H. Young, Acting Chief Reactor Project Branch C Docket No.: 05000298 License No.: DPR-46

Enclosure:

As stated

Inspection Report

Docket Number: 05000298 License Number: DPR-46 Report Number: 05000298/2019002 Enterprise Identifier: I-2019-002-0003 Licensee: Nebraska Public Power District Facility: Cooper Nuclear Station Location: Brownville, Nebraska Inspection Dates: April 1, 2019 to June 30, 2019 Inspectors: J. Cassidy, Senior Health Physicist P. Elkmann, Senior Emergency Preparedness Inspector J. Rivera, Health Physicist M. Stafford, Resident Inspector P. Vossmar, Senior Resident Inspector Approved By: Cale H. Young, Acting Chief Reactor Project Branch C Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a 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. An NRC finding, violation, and an additional item are summarized in the tables below.

List of Findings and Violations Failure to Evaluate Operability in Accordance with Procedures for a High Pressure Coolant Injection System Degraded Condition Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.7] - 71111.15 Systems NCV 05000298/2019002-01 Documentation Open/Closed The inspectors identified a finding of very low safety significance and an associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, for the licensees failure to evaluate operability of the high pressure coolant injection system in accordance with Procedure 0.5.OPS, Operations Review of Condition Reports / Operability Determination,

Revision 62. Specifically, on January 25, 2019, when the high pressure coolant injection pump low discharge flow instrument failed to generate the required minimum flow valve closure signal during surveillance testing, the licensee failed to recognize that high pressure coolant injection surveillance requirements for pump flow could not be met. As a result, the instrument was inoperable, and although it was repaired within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of discovery, the inoperability was not recognized until inspectors challenged the initial determination.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000298/2017-004-01 Torus to Drywall Vacuum 71153 Closed Breaker Failure to Indicate Full Closed Causes Loss of Safety Function.

PLANT STATUS

Cooper Nuclear Station began the inspection period at rated thermal power. On May 17, 2019, the unit was down powered to 65 percent for a control rod sequence exchange. The plant was returned to rated thermal power on May 18, 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.

71111.01 - Adverse Weather Protection Summer Readiness Sample (IP Section 03.01)

The inspectors evaluated summer readiness of offsite and alternate alternating current (AC)power systems on June 20, 2019.

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

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

(1) Reactor core isolation cooling while high pressure coolant injection out of service on April 18, 2019;

(2) Residual heat removal B during residual heat removal A work week on May 3, 2019;

(3) Service water during service water pump D replacement on May 17, 2019;

(4) Standby gas treatment A during standby gas treatment B maintenance on June 11, 2019.

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

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

(1) Northwest quad 859 feet and 881 feet elevations, Division 1 residual heat removal on April 3, 2019;

(2) Cable expansion room on April 15, 2019;

(3) Alternate shutdown panel area on May 1, 2019;

(4) Southwest quad 859 feet and 881 feel elevations, Division 2 residual heat removal on May 2, 2019;

(5) Reactor building 976 standby liquid control area on June 10, 2019.

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

The inspectors evaluated internal flooding mitigation protections in the:

Core spray A and reactor core isolation cooling area on June 3, 2019.

71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)

The inspectors evaluated readiness and performance of:

Residual heat removal A heat exchanger inspection and maintenance on May 2, 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)

The inspectors observed and evaluated licensed operator performance in the control room during control rod drive exercising, standby gas treatment troubleshooting, and emergency diesel generator 1 service water inservice testing on June 8, 2019.

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

The inspectors observed and evaluated the licensed operator qualification simulator scenario on April 23, 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 quad sumps on June 18, 2019;

(2) Turbine system on June 25, 2019;

(3) Reactor recirculation system on June 27, 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) Emergent reactor feed vent line leak on April 5, 2019;

(2) Emergency diesel generator 2 jacket water heat exchanger flange service water leak repair on April 12, 2019;

(3) High pressure coolant injection planned maintenance work week on April 18, 2019;

(4) Residual heat removal B and residual heat removal service water B work week on April 24, 2019;

(5) Residual heat removal A planned maintenance work week on May 3, 2019;

(6) Main generator reactive load verification on June 21, 2019;

(7) Recirculation motor generator set B potentiometer replacement on June 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) Reactor equipment cooling C operability on April 25, 2019;

(2) Condition Report CR-CNS-2018-02061 battery results operability evaluation on April 29, 2019;

(3) Inadequate station battery technical specification on April 30, 2019;

(4) FP2 barriers found with combustible sealant on May 1, 2019;

(5) High pressure coolant injection minimum flow valve instrumentation failed testing and calibration on June 19, 2019.

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

The inspectors evaluated the following post maintenance tests:

(1) High pressure coolant injection control system card replacement post maintenance test on April 19, 2019;

(2) Residual heat removal pump B post maintenance test following planned system maintenance on April 24, 2019;

(3) Residual heat removal service water pump B leakage testing following maintenance April 24, 2019;

(4) Reactor equipment cooling pump C post maintenance test following pump replacement on April 25, 2019;

(5) Residual heat removal pump A post maintenance test following planned system maintenance on May 3, 2019;

(6) SGT-AO-271 standby gas treatment B dilution air valve post maintenance test on June 12, 2019.

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

Elevated release point sump pump functional test on April 17, 2019.

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

Particulate and iodine sample collection for drywell atmosphere monitor and increased drywell unidentified leakage on April 4, 2019.

Surveillance Tests (other) (IP Section 03.01) (2 Samples)

(1) Reactor core isolation cooling pump low discharge flow channel calibration on April 10, 2019;

(2) High pressure coolant injection quarterly pump flow test on April 26, 2019.

71114.02 - Alert and Notification System Testing Inspection Review (IP Section 02.01-02.04)

The inspectors evaluated the maintenance and testing of the alert and notification system, including outdoor warning sirens and tone alert radios, for the period July 2017 through May 2019. The inspectors also observed a silent test of the outdoor emergency warning sirens conducted June 18, 2019.

71114.03 - Emergency Response Organization Staffing and Augmentation System Inspection Review (IP Section 02.01-02.02)

The inspectors evaluated the readiness of the Emergency Preparedness Organization for the period July 2017 through May 2019.

71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)

The inspectors evaluated Revisions 72 and 73 of the Cooper Nuclear Station Emergency Plan. These evaluations do not constitute NRC approval of the changes made by the licensee.

71114.05 - Maintenance of Emergency Preparedness Inspection Review (IP Section 02.01 - 02.11)

The inspectors evaluated the maintenance of the emergency preparedness program for the period July 2017 through May 2019. The inspectors observed a quarterly meeting between licensee staff and state and county offsite emergency response organizations on June 20, 2019, which included a discussion of the quality of interfaces between the licensee and offsite response organizations led by the licensee's Quality Assurance organization.

71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

Emergency preparedness drill on May 14,

71124.01 - Radiological Hazard Assessment and Exposure Controls Contamination and Radioactive Material Control (IP Section 02.03)

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors verified the following sealed sources are accounted for and are intact:

• S741;

• S256.

High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)

The inspectors evaluated risk-significant high radiation area and very high radiation area controls.

Instructions to Workers (IP Section 02.02) (1 Sample)

The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.

Radiation work packages:

• 2018-106; Transverse Incore Probe; Radiation Protection High Risk Activities;

• 2019-100; Reactor Building; LOCKED High Radiation Area Activities;

• 2019-102; High Integrity Container Preparation / Shipments.

Electronic alarming dosimeter alarms:

• no alarms occurred during the period of this inspection.

Labeling of containers:

• Three Main Steam Relief Valves;

• Dry Active Waste Pump;

• Box of Hoses and Fittings in Radioactive Waste Processing Area.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)

The inspectors evaluated radiation worker performance and radiation protection technician proficiency.

Radiological Hazard Assessment (IP Section 02.01) (1 Sample)

The inspectors evaluated radiological hazards assessments and controls. The inspectors reviewed the following:

Radiological surveys:

• Reactor Water Clean-Up Heat Exchanger Room;

• Radwaste Collector Tanks;

• Refuel Floor;

• High Pressure Core Injection Pump Room.

Risk significant radiological work activities:

• Locked High Radiation Area Verification Surveillance;

• Spent Resin Sample Collection;

• Residual Heat Removal Heat Exchanger Inspection and Eddy Current.

Air sample survey records:

• Reactor Head Bolt Cleaning;

• Cavity Decontamination;

• Reactor Water Clean-Up Heat Exchanger Room Decontamination.

Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

Radiological work package for areas with airborne radioactivity:

• No work packages were available for review during this inspection.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation Engineering Controls (IP Section 02.01)

The inspectors evaluated airborne controls and radioactive monitoring. The inspectors reviewed the following:

Installed Ventilation Systems

• Control Room Emergency Filter System

• Standby Gas Treatment (SGT) System Temporary Ventilation System Setups

• None were available during this inspection Portable or Installed Monitoring Systems

• Continuous air monitor (AMS-4) in the Augmented Radwaste Building

• Continuous air monitor (AMS-4) on the Refuel Floor Self-Contained Breathing Apparatus (SCBA) for Emergency Use (IP Section 02.03)

(1 Sample)

The inspectors evaluated SCBA program implementation. The inspectors reviewed the following:

Status and Surveillance Records for Self-Contained Breathing Apparatus

• SCBA No. IL845597

• SCBA No. IL845658

• SCBA No. IL846625

• SCBA No. IL846876

• SCBA No. IL846907 Self-Contained Breathing Apparatus Fit for On-Shift Operators

• Two senior reactor operators (SROs) and one reactor operator (RO)

Self-Contained Breathing Apparatus Maintenance Check

• Due to the entire fleet of SCBAs (Scott X-3) being newly purchased in June 2018, the time frame for the maintenance checks has not been reached. Therefore, none were available during this inspection.

Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample)

The inspectors evaluated respiratory protection. The inspectors reviewed the following:

Evaluations for the Use of Respiratory Protection

• None were available during this inspection Respiratory Protection Use During Work Activities

• None were available during this inspection Medical Fitness for Use of Respiratory Protection Devices

• One nonlicensed operator

• One Maintenance Support individual

• One Electrical Maintenance individual Observation of Donning, Doffing and Functional Test

• Observed demonstration of donning, doffing, and functional test of an SCBA unit and full face respirator by a radiation protection technician Respiratory Protection Device Evaluation

• Five Scott AV 30000HT full face respirators

• One Versaflo Powered Air Purifying Respirator (PAPR)

• One Delta Mururoa Delta Suite

OTHER ACTIVITIES - BASELINE

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

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) ===

April 1, 2018 - March 31, 2019

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

April 1, 2018 - March 31, 2019 EP01: Drill/Exercise Performance (IP Section 02.12) (1 Sample) July 1, 2018 - March 31, 2019

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

July 1, 2018 - March 31, 2019 EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

July 1, 2018 - March 31, 2019 MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)

April 1, 2018 - March 31, 2019 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

October 31, 2018 - March 31, 2019

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

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

Post event flooding technical requirements manual changes on June 19, 2019.

71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

(1) The inspectors evaluated the licensee's retraction of Event Notification 53646 regarding main steam isolation valve local leak-rate test values on June 11, 2019;

(2) The inspectors evaluated the unplanned trip of a reactor recirculation pump and the resulting single loop operations on June 12, 2019.

Event Report (IP Section 03.02) (1 Sample)

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

1. LER 05000298/2017-004-01, Torus to Drywall Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function (ADAMS Accession No. ML19031B333).

The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER; therefore, no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

INSPECTION RESULTS

Failure to Evaluate Operability in Accordance with Procedures for a High Pressure Coolant Injection System Degraded Condition Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.7] - 71111.15 Systems NCV 05000298/2019002-01 Documentation Open/Closed The inspectors identified a finding of very low safety significance and an associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, for the licensees failure to evaluate operability of the high pressure coolant injection system in accordance with Procedure 0.5.OPS, Operations Review of Condition Reports / Operability Determination, Revision 62. Specifically, on January 25, 2019, when the high pressure coolant injection pump low discharge flow instrument failed to generate the required minimum flow valve closure signal during surveillance testing, the licensee failed to recognize that high pressure coolant injection surveillance requirements for pump flow could not be met. As a result, the instrument was inoperable, and although it was repaired within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of discovery, the inoperability was not recognized until inspectors challenged the initial determination.

Description:

On January 25, 2019, during technical specification (TS) surveillance-required functional testing, the licensee discovered that Switch 2 on HPCI-FIS-78, HPCI pump discharge low flow switch, did not actuate within calibration tolerances. The licensee subsequently performed a calibration of the instrument, and technicians were unable to get the switch to actuate or calibrate. As a result, later that day, maintenance personnel removed the switch cover and inspected the internals and linkages within the instrument, and then adjusted the actuation plunger on Switch 2. These actions restored the instrument's ability to function. Until then, the switch was unable to perform its function for a total of 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Because there is only one of these instruments, loss of the instrument results in a loss of the function. With the loss of function of Switch 2, the high pressure coolant injection (HPCI)minimum flow valve would open upon pump start, as required, but would fail to close when the pump reached higher flows and approached operating conditions. This failure would cause a diversion of flow through the minimum flow line when all flow should be directed into the reactor vessel during an emergency event. Operations personnel determined that HPCI-FIS-78 was operable for the condition, despite the loss of Switch 2s function.

Specifically, operations personnel noted that the successful operation of Switch 2 was not a surveillance procedure acceptance criterion. They also noted that the TS Bases for Limiting Condition for Operation (LCO) 3.3.5.1 - Function 3f, HPCI Pump Discharge Flow - Low, stated, The valve is automatically closed if flow is above the minimum flow setpoint. It is not necessary for the minimum flow valve to close to achieve adequate system flow assumed in the accident analysis (Ref. 4).

The inspectors reviewed the licensees operability evaluation. The inspectors noted that the instrument in question opens and closes the minimum flow valve automatically based on HPCI flow, and both of these functions were covered under LCO 3.3.5.1 - Function 3f. They also noted that the General Electric Standard TS Bases stated for Function 3f, The HPCI Pump Discharge Flow - Low Function is assumed to be OPERABLE and capable of closing the minimum flow valve to ensure that the emergency core cooling system flow assumed during the transients and accidents analyzed in References 2, 3, and 4 are met. Next, the inspectors reviewed the Ref. 4 cited in Coopers TS Basis document, Calculation NEDC 97-023, "HPCI Minimum Flow Line Evaluation, Revision 3. The inspectors identified that in the section labeled, Conclusions and Recommendations, the calculation stated, in part, that the HPCI system minimum flow line bypass valve must close for the system to be able to meet an injection flowrate of 4250 gpm at lower reactor pressures. However, closure is not required to ensure that the HPCI minimum injection flow rate assumed in the accident and transient analysis is met. The inspectors observed that TS Surveillance Requirements 3.5.1.7 and 3.5.1.8 for HPCI pump flow require HPCI to develop 4250 gpm of injection flow against reactor pressure when reactor pressure is between 150 psig and 1020 psig. Therefore, with the instrument failed, HPCI would not be able to meet its TS surveillance-required flow rates. The inspectors also observed that Cooper TS Surveillance Requirement 3.0.1 states, Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO.

The inspectors reviewed the licensees operability Procedure 0.5.OPS, Operations Review of Condition Reports / Operability Determination, Revision 62. Section 5 of this procedure describes the requirements for performance of immediate operability determinations.

Section 5.1.13.6 states, in part, that when a degraded condition is identified, operability evaluations should include documentation of a reasonable expectation of operability and the basis for that determination. Section 5.1.13.6.a, states, select and use appropriate references to ensure the scope of the SSC function is identified. Reference to program documents, calculations, alarm cards, or other documents may provide additional insights into SSC performance requirements. The inspectors noted that the operations personnel performing the evaluation in this case had failed to reference the calculation that was listed as the reference for the erroneous TS Basis document statement. Step 5.1.13.6 states, Ensure all Tech Spec Surveillance Requirements can be met. The inspectors determined that this step was not accomplished in accordance with the procedure, in that with the degraded condition on HPCI-FIS-78, TS Surveillance Requirements 3.5.1.7 and 3.5.1.8 for HPCI pump flow could not be met. The inspectors challenged the licensee's operability determination, and after further review, operations personnel determined that the instrument should have been declared inoperable. As a result, the inspectors concluded that operations personnel had performed an inadequate evaluation of operability for this issue. The inspectors also noted that the TS Basis document lacked clarity and accuracy, and the surveillance procedure for this instrument had incorrectly listed the function in question as not being a TS function.

Corrective Actions: Corrective actions included repair of the degraded instrument; determination that the system was inoperable under LCO 3.3.5.1, Condition E; revision of the surveillance procedure acceptance criteria; and revision of the TS Basis document to more accurately describe the instruments safety functions.

Corrective Action References: Condition Reports CR-CNS-2019-00757 and CR-CNS-2019-02325

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensees failure to evaluate operability of the high pressure coolant injection (HPCI) system and pump low discharge flow instrument in accordance with Procedure 0.5.OPS was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Mitigating Systems cornerstone. Specifically, the HPCI pump low discharge flow instrument was not recognized as being inoperable, and if called upon, it would not have generated the signal to close the minimum flow valve when required, allowing for diverted flow and preventing HPCI from generating its TS surveillance-required flow (4250 gpm) at lower reactor pressures.

Significance: The inspectors assessed the significance of the finding using Appendix A, Significance Determination of Reactor Inspection Findings for At - Power Situations. The inspectors determined this finding was of very low safety significance (Green) because it:

was not a design deficiency; did not represent a loss of system and/or function; did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time; and did not result in the loss of a high safety-significant nontechnical specification train. Specifically, although the minimum flow valve would not have automatically closed when required, HPCI would have maintained the ability to generate the amount of flow used in the licensees accident analysis (3825 gpm). Therefore, the inspectors concluded that from a probabilistic risk assessment perspective, the actual safety function of HPCI was not lost.

Cross-Cutting Aspect: H.7 - Documentation: The organization creates and maintains complete, accurate, and up-to-date documentation. Specifically, the licensee failed to maintain complete and accurate TS basis documents and surveillance procedures to ensure that the function of the HPCI minimum flow valve closure instrumentation was properly described.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," states, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. Licensee Procedure 0.5.OPS, Operations Review of Condition Reports / Operability Determination, Revision 62, an Appendix B quality related procedure, was established to control the operability evaluation process for technical specification equipment. Step 5.1.13.6.d. includes operability determination requirements for degraded conditions, and states, ensure all Tech Spec Surveillance Requirements can be met.

Contrary to the above, on January 25, 2019, operations personnel failed to ensure all technical specification surveillance requirements could be met for a degraded condition.

Specifically, when the HPCI pump low discharge flow instrument failed to generate the minimum flow valve closure signal during surveillance testing, the licensee failed to recognize that HPCI surveillance requirements for pump flow could not be met. As a result, the instrument was inoperable, and although it was repaired within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of discovery, the inoperability was not recognized until inspectors challenged the initial determination.

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 May 23, 2019, the inspectors presented the radiation protection inspection results to Mr. J. Dent, Jr., Site Vice President, and other members of the licensee staff.

• On June 20, 2019, the inspectors presented the emergency preparedness program inspection results to Mr. J. Dent, Jr., Site Vice President, and other members of the licensee staff.

• On July 16, 2019, the inspectors presented the integrated inspection results to Mr. D. Buman, Director of Nuclear Safety Assurance, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action CR-CNS- 2019-03587

Documents

71111.01 Miscellaneous IOA Interface Operating Agreement Between NPPD Operations 10

Business Unit and NPPD Nuclear Power Group Business

Unit - Transmissions Operations

71111.01 Procedures 5.3GRID Degraded Grid Voltage 52

71111.01 Work Orders WO 5190544, 5222296, 5286529, 5304348

71111.04 Corrective Action CR-CNS- 2019-02340, 2019-02751, 2019-02754, 2019-02783, 2019-

Documents 03125, 2019-03223, 2019-03271

71111.04 Drawings 2037 H&V Standby Gas Treatment & Offgas Filters 71

71111.04 Procedures 2.2.67A Reactor Core Isolation Cooling System Component 23

Checklist

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

Checklist

71111.04 Procedures 2.2.71 Service Water System 125

71111.04 Procedures 2.2.73 Standby Gas Treatment System 56

71111.04 Procedures 2.2A.SGT.DIV1 Standby Gas Treatment System Component Checklist (DIV 5

1)

71111.04 Procedures 2.2A.SW.DIV0 Service Water System Non-Divisional Component Checklist 9

71111.04 Procedures 2.2A.SW.DIV1 Service Water System Component Checklist (DIV 1) 20

71111.04 Procedures 2.4HVAC Building Ventilation Abnormal 23

71111.05Q Corrective Action CR-CNS- 2019-02058, 2019-02516, 2019-02591, 2019-03195

Documents

71111.05Q Miscellaneous CNS-FP-214 Reactor Building Southwest Quadrant AD/05

71111.05Q Miscellaneous CNS-FP-215 Reactor Building First Floor Elevation 903-6 AC/06

71111.05Q Miscellaneous CNS-FP-220 Reactor Building SBLC Area AC/08

71111.05Q Procedures 0-BARRIER Barrier Control Process 28

71111.05Q Procedures 0-BARRIER- Barrier Maps 9

MAPS

71111.05Q Procedures 0-BARRIER- Reactor Building 13

REACTOR

71111.05Q Procedures 6.SC.502 Secondary Containment Penetration Examination 19

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05Q Procedures CNS-FP-213 Reactor Building Northwest Quadrant Elevations 881-9 and AC/06

859-9

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

71111.06 Corrective Action CR-CNS- 2019-02921, 2019-02931

Documents

71111.06 Drawings 2038 Reactor Building Floor and Roof Drain System 55

71111.06 Miscellaneous NEDC 09-102 Internal Flooding - HELB, MELF, and Feedwater Line Break 2

71111.06 Procedures 0-BARRIER Barrier Control Process 28

71111.06 Procedures 2.3_S-1 Panel S - Annunciator S-1 30

71111.07A Corrective Action CR-CNS- 2018-00541, 2019-02541

Documents

71111.07A Miscellaneous Generic Letter 89- Program Commitments 04/30/2019

71111.07A Procedures 13.17.2 Thermal Performance Test Procedure for Residual Heat 16

Removal Heat Exchangers

71111.07A Procedures 3.10 Flow Accelerated Corrosion (FAC) and Microbiologically 16

Influenced Corrosion (MIC) Program Implementation

71111.07A Procedures 7.0.5 CNS Post-Maintenance Testing 59

71111.07A Procedures 7.2.42.2 RHR Heat Exchanger Maintenance 10

71111.07A Work Orders WO 5164185, 5210951

71111.11Q Corrective Action CR-CNS- 2019-03179

Documents

71111.11Q Drawings 2.3_K-2 Panel K - Annunciator K-2 8

71111.11Q Drawings 2.3_M-1 Panel M - Annunciator M-1 20

71111.11Q Miscellaneous 11614584 Routine Troubleshooting Plan - SGT Train B, Reactor 0

Building HVAC

71111.11Q Miscellaneous SKL 05151363 Performance Mode #7 0

71111.11Q Procedures 2.2.47 HVAC Reactor Building

71111.11Q Procedures 6.1SW.401 Diesel Generator Service Water Check Valve and Sump 3

Test (IST)

71111.11Q Procedures 6.CRD.301 Withdrawn Control Rod Operability IST Test 32

71111.11Q Procedures Emergency EOP Flow Chart 1A 22

Operating

Procedure 1A

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11Q Procedures Emergency EOP Flow Chart 5A 19

Operating

Procedure 5A

71111.12 Corrective Action CR-CNS- 2018-07300, 2018-07359, 2018-07893, 2018-07897, 2018-

Documents 07935, 2018-07996, 2019-03061, 2019-03256, 2019-03289,

2019-03488

71111.12 Miscellaneous Maintenance Rule Meeting Package 06/25/2019

71111.12 Miscellaneous Notifications 11384819, 11391486, 11391978, 11470097, 11490991,

11506236, 11540654, 11543417, 11546697, 11546699,

11564325, 11564880, 11569172, 11569244, 11569961,

11579431, 11604580, 11611874, 11611930, 11613897,

11616392

71111.12 Miscellaneous RR-F01 Maintenance Rule Function Basis for RR-F01 3

71111.12 Miscellaneous RRMG-F01 Maintenance Rule Function Basis for RRMG-F01 3

71111.12 Miscellaneous RW-F03 Maintenance Rule Function Basis for RW-F03 5

71111.12 Miscellaneous TG-F01 Maintenance Rule Function Basis for TG-F01 3

71111.12 Procedures 0-CNS-LI-102 Corrective Action Process 9

71111.12 Procedures 0.40 Work Control Program 94

71111.13 Corrective Action CR-CNS- 2019-02341, 2019-02450, 2019-02510, 2019-03559, 2019-

Documents 03561

71111.13 Miscellaneous Protected Equipment Tracking Form - SWBP and RHR B 0

Window Week 1917

71111.13 Miscellaneous Protected Equipment Tracking Form - HPCI Window Week 2

1916

71111.13 Miscellaneous Critical Evolutions Meeting PowerPoint for WO 5293548,

Temporary Leak Repair RF-V-527 Reactor Feed Flushing

Line Vent

71111.13 Miscellaneous Protected Equipment Tracking Form - Week 1918 RHR A 0

Window

71111.13 Miscellaneous Risk Management Plan - Main Generator MVAR Testing per 6/18/2019

15.GEN.602

71111.13 Miscellaneous Critical Evolutions Meeting Presentation - RRMG B

Clamping

71111.13 Miscellaneous Protected Equipment Tracking Form - DG2 LCO 04/11/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.13 Miscellaneous Risk Management Plan - Repair Diesel Generator 2 Jacket 04/11/2019

Water Heat Exchanger Flange Leak

71111.13 Miscellaneous SKL051-51-375 Just-in-time Training - Ops B RRMG Scoop Tube Clamp 0

and De-clamp JITT

71111.13 Procedures 0-PROTECT- Protected Equipment Program 46

EQP

71111.13 Procedures 15.GEN.602 Main Generator Power Verification 0

71111.13 Procedures 7.2.85 Reactor Recirculation Motor

71111.13 Procedures 9.EN-RP-101 Access Control for Radiologically Controlled Areas 20

71111.13 Procedures 9.EN-RP-108 Radiation Protection Posting and Labeling 15

71111.13 Work Orders WO 5130544, 5174247, 5210476, 5211716, 5292133, 5293548,

295757

71111.15 Corrective Action CR-CNS- 2005-03329, 2018-04112, 2018-08609, 2018-08614, 2018-

Documents 08621, 2018-08638, 2018-08657, 2019-00439, 2019-00443,

2019-00702, 2019-00757, 2019-01928, 2019-02061, 2019-

2073, 2019-02325, 2019-02449, 2019-02467, 2019-02471

71111.15 Drawings 2044 Flow Diagram High Pressure Coolant Injection and Reactor 76

Feedwater Systems

71111.15 Miscellaneous Admin Letter 98- Dispositioning of Technical Specifications That Are 12/29/1998

Insufficient to Assure Plant Safety

71111.15 Miscellaneous NEDC 10-004 Fire PRA Plant Boundary Definition and Partitioning 2

71111.15 Miscellaneous NEDC 10-080 NFPA 805 Chapter 3 Fundamental Fire Protection Program 4

and Design Elements Review

71111.15 Miscellaneous NEDC 14-043 Fire Safety Analysis for Entire Power Block 1

71111.15 Miscellaneous NEDC 97-023 HPCI Minimum Flow Line Evaluation 1, 2, 3

71111.15 Miscellaneous Notification 11583394

71111.15 Procedures 0-BARRIER Barrier Control Process 27

71111.15 Procedures 0.23 CNS Fire Protection Plan 79

71111.15 Procedures 0.26 Surveillance Program 71

71111.15 Procedures 0.31 Equipment Status Control 89

71111.15 Procedures 0.7.1 Control of Combustibles 40

71111.15 Procedures 5.3NBPP No Break Power Failure 23

71111.15 Procedures 6.1EE.602 Div 1 125V/250V Station Battery 92 Day Check 7

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Procedures 6.2EE.602 Div 2 125V/250V Station Battery 92 Day Check 6

71111.15 Procedures 6.EE.609 125V/250V Station Battery Intercell Connection Testing 19

71111.15 Procedures 6.FP.606 Fire Barrier/Penetration Seal Visual Examination 25

71111.15 Procedures 6.HPCI.312 HPCI Pump Low Discharge Flow Channel Calibration 10

71111.15 Procedures 6.HPCI.712 HPCI Pump Low Discharge Flow Channel Functional Test 4

71111.15 Procedures 7.2.78.2 Pipe Penetration Seal Installation Using Gasket Placement 1

71111.18 Corrective Action CR-CNS- 2016-07742, 2018-07736, 2018-07780, 2018-08411, 2019-

Documents 00668

71111.18 Miscellaneous Maintenance Rule Function MS-F04 Performance Criteria 4

Basis

71111.18 Miscellaneous 5274251 TCC

71111.18 Miscellaneous DEC-5274251 MS-AOV-739AV Indicating Lights 1

71111.18 Work Orders WO 5274155, 5274250

71111.19 Corrective Action CR-CNS- 2019-02154, 2019-02345, 2019-02346, 2019-02462, 2019-

Documents 02471, 2019-02477, 2019-03230, 2019-03242

71111.19 Drawings 791E271, Sheet 6 HPCI System Elementary Diagram 21

71111.19 Miscellaneous FMEA for CR-2019-02345; HPCI Speed Indication Issue 04/19/2019

71111.19 Miscellaneous 11602479 Routine Troubleshooting Plan - HPCI Speed Indication 3, 4

Issue

71111.19 Procedures 2.2.18.2 System Operating Procedure 4160V Breaker Operations 5

71111.19 Procedures 6.1SGT.301 SGT Operability Test/Offgas Flow Monitor Channel 16

Functional Test IST (Div 1)

71111.19 Procedures 6.2REC.101 REC Surveillance Operation 17

71111.19 Procedures 6.2RHR.101 RHR Test Mode Surveillance Operation (IST) (Div 2) 38

71111.19 Procedures 6.2SGT.301 SGT Operability Test/Offgas Flow Monitor Channel 17

Functional (Div 2)

71111.19 Procedures 6.HPCI.103 HPCI IST and 92 Day Test Mode 58

71111.19 Procedures 6.HPCI.316 HPCI Control System Calibration Test 24

71111.19 Procedures 7.0.1.7 Troubleshooting Plant Equipment 15

71111.19 Work Orders WO 5130544, 5155002, 5155003, 5155004, 5185366, 5187211,

5192542, 5207498, 5210476, 5211419, 5211716

71111.22 Corrective Action CR-CNS- 2019-02038, 2019-02222, 2019-02342, 2019-02345, 2019-

Documents 02346, 2019-02381, 2019-02469

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Miscellaneous GE SIL 336 Surveillance Testing Recommendations for HPCI and RCIC 1

Systems

71111.22 Miscellaneous GE SIL 351 HPCI and RCIC Turbine Control System Calibration 2

71111.22 Procedures 6.HPCI.103 HPCI IST and 92 Day Test Mode 58

71111.22 Procedures 6.HPCI.316 HPCI Control System Calibration Test 24

71111.22 Procedures 6.RCIC.302 RCIC Pump Low Discharge Flow Channel Calibration 11

71111.22 Procedures 6.SUMP.101 Z Sump and Air Ejector Holdup Line Drain Test 32

71111.22 Procedures 8.8DWAM Particulate and Iodine Sample Collection for Drywell 8

Atmosphere Monitor

71111.22 Procedures EN-OP-109 Drywell Leakage 2C0

71111.22 Work Orders WO 5183570, 5185369

71114.02 Corrective Action CR-CNS- 2017-04854, 2017-05001, 2018-00160, 2018-00650, 2018-

Documents 01477, 2018-02873, 2018-03033, 2018-03695, 2018-06852,

2019-00624, 2019-03074

71114.02 Miscellaneous Letter, Mr.

T. Morgan, Technological Hazards Branch Chief, 8/15/2018

FEMA Region VII, to Ms.

T. Haynes, Emergency

Preparedness Coordinator, Cooper Nuclear Station; Subject:

Cooper Nuclear Station Alert and Notification System Design

Report, Revision 15

71114.02 Miscellaneous Cooper Nuclear Station Alert and Notification System Design June 2018

Report, Revision 15

71114.02 Miscellaneous Letter, Mr.

T. Morgan, Technological Hazards Branch Chief, 5/21/19

FEMA Region VII, to Ms.

T. Haynes, Emergency

Preparedness Coordinator, Cooper Nuclear Station; Subject:

Evaluation of Cooper Nuclear Station Alert and Notification

Design Report Revision and Narrative Summary of

Proposed Changes dated 16 April 2019

71114.02 Miscellaneous Cooper Nuclear Station Alert and Notification System Design April 2019

Report, Revision 16

71114.02 Miscellaneous WPS 2900 Series High Power Voice and Siren System, 2005

Operating and Troubleshooting Manual

71114.02 Miscellaneous EPDG #2, Quarterly EAS Newspaper and Radio Advisories 3/5/2018

C-2

71114.02 Miscellaneous EPDG #2, Quarterly EAS Newspaper and Radio Advisories 9/6/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

C-2

71114.02 Miscellaneous EPDG #2, Quarterly EAS Newspaper and Radio Advisories 3/27/2019

C-2

71114.02 Miscellaneous EPDG #2, Quarterly EAS Newspaper and Radio Advisories 6/17/2019

C-2

71114.02 Miscellaneous EPDG #2, Annual Fixed Siren Maintenance 7//19/2017

C-6

71114.02 Miscellaneous EPDG #2, Annual Fixed Siren Maintenance 7/25/2018

C-6

EPDG #2, Annual Fixed Siren Maintenance 8

C-6

EPDG #2, Issuance of NOAA/EAS Radio Receivers 2

C-7

EPDG #2, Quarterly Update of NOAA/EAS Radio Receiver Recipient 4

C-8 Data Base

71114.02 Miscellaneous EPDG #2, Quarterly Review/Update of NOAA/EAS Radio Receiver 3/28/2019

C-8 Recipient Data Base

71114.02 Miscellaneous EPDG #2, Quarterly Review/Update of NOAA/EAS Radio Receiver 9/27/2018

C-8 Recipient Data Base

71114.02 Miscellaneous EPDG #2, Quarterly Review/Update of NOAA/EAS Radio Receiver 3/22/2018

C-8 Recipient Data Base

71114.02 Miscellaneous EPDG #2, Quarterly Review/Update of NOAA/EAS Radio Receiver 12/20/2017

C-8 Recipient Data Base

71114.02 Procedures 5.7.27 Alert and Notification System, Revisions 19 & 20 12/5/2018

71114.02 Procedures 5.7.27.1 False Activation of the Alert and Notification System, 12/5/2018

Revision 9

71114.02 Procedures 5.7.27.2 NOAA/EAS Radio Malfunction, Revisions 10 & 11 12/12/17

71114.03 Corrective Action CR-CNS- 2017-06338, 2017-06676, 2018-00536, 2018-01047, 2018-

Documents 01119, 2018-02836, 2018-03795, 2018-03810, 2018-04574,

2018-08060, 2018-08524, 2018-08663, 2019-01594, 2019-

2750

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 8/1/2017

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 8/22/2017

Inspection Type Designation Description or Title Revision or

Procedure Date

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 10/26/2017

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 12/18/2017

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 2/25/2018

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 4/26/2018

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 6/20/18

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 11/27/2018

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 12/10/2018

E-3

71114.03 Miscellaneous EPDG #2, Bi-Monthly ERO Call-In Test 3/1/2019

E-3

EPDG #2, Quarterly ERO Call-In Test 20

E-3

EPDG #2, Weekly Pager Test 1

E-4

71114.03 Procedures 5.7.6 Notification, Revision 74 7/18/2018

71114.03 Work Orders WT-2018-0024-

2

71114.05 Corrective Action CR-CNS- 2017-04238, 2017-04422, 2017-04466, 2017-04696, 2017-

Documents 04812, 2017-04854, 2017-05001, 2017-06271, 2018-00524,

2018-00534, 2018-02306, 2018-03069, 2018-03075, 2018-

03080, 2018-03100, 2018-03157, 2018-03445, 2018-03810,

2018-03876, 2018-04581, 2018-04582, 2018-04628, 2018-

04671, 2018-04705, 2018-04859, 2018-05600, 2018-06852,

2018-07340, 2018-08150, 2018-08615, 2018-08638, 2018-

08647, 2018-08657, 2018-08663, 2019-00171, 2019-01118,

2019-01387, 2019-01467, 2019-02739, 2019-02756, 2019-

2791, 2019-02842, 2019-02875

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Miscellaneous Cooper Nuclear Station Emergency Plan 71, 72, 73

71114.05 Miscellaneous After-Action Report: December 29, 2018, NOUE on HU3.1 1/8/2019

71114.05 Miscellaneous After-Action Report: March 15, 2019, NOUE on HU1.5 River 4/15/2019

Level

71114.05 Miscellaneous Media Communication Letter 12/22/2017

71114.05 Miscellaneous Evaluation Report for the July 31, 2018, Biennial NRC- 8/10/2018

Graded Exercise Summary Report

71114.05 Miscellaneous Evaluation Report for the August and September 2018 Mini- 9/21/2018

Drills

71114.05 Miscellaneous Evaluation Report for the September 12, 2018, Medical Drill 9/26/2018

71114.05 Miscellaneous Evaluation Report for the September 13, 2018, Qualification 10/1/2018

Drill

71114.05 Miscellaneous Evaluation Report for the December 26, 2018, Radiological 12/26/2018

Protection Drill

71114.05 Miscellaneous Evaluation Report for the December 18, 2018, Full Team 12/26/2018

Drill

71114.05 Miscellaneous Evaluation Report for the February 26, 2019, Full Team Drill 3/12/2019

71114.05 Miscellaneous Evaluation Report for the May 14, 2019, Full Team Drill 5/21/2019

71114.05 Miscellaneous Evaluation Report for the January 30, 2018, Full Team Drill, 2/14/2018

Radiological Monitoring and Protection Drill

71114.05 Miscellaneous Evaluation Report for the February and March 2018 Mini- 6/15/2018

Drills Critique

71114.05 Miscellaneous 2016-0183 2017 Emergency Preparedness Pre-NRC Focused Self- 2/10/2017

Assessment Report

71114.05 Miscellaneous 2017-048 Emergency Preparedness Regulatory Review: Training 8/24/2017

Qualification Documents, Courses ERO0010105Q and

ERO0010105/CT66103

71114.05 Miscellaneous 2017-054 Emergency Preparedness Regulatory Review: CNS 8/24/2017

Emergency Plan Revision 70

71114.05 Miscellaneous 2017-08 Emergency Preparedness Regulatory Review: Procedure 12/14/2017

5.7.6, Notification, Revision 73

71114.05 Miscellaneous 2017-084 Emergency Preparedness Regulatory Review: Commercial 1/3/2018

Change CC-5229779, MET Alarm Remediation

71114.05 Miscellaneous 2018-077 Emergency Preparedness Regulatory Review: Procedure 11/11/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

8.11.1 Effects Program, Revision 21

71114.05 Miscellaneous 2018-086 Emergency Preparedness Regulatory Review: Procedure 12/10/2018

5.7.20, Protective Action Recommendations, Revision 31

71114.05 Miscellaneous 2018-088 Emergency Preparedness Regulatory Review: Training 3/4/2019

Qualification Document 0675, ERO Designated

Spokesperson, Revision 4

71114.05 Miscellaneous 2019-003 Emergency Preparedness Regulatory Review: Procedure 1/21/2019

5.7.25, Recovery Operations, Revision 23

71114.05 Miscellaneous 2019-011 Emergency Preparedness Regulatory Review: Procedure 2/22/2019

5.7.10, Personnel Assembly and Accountability, Revision 42

71114.05 Miscellaneous 2019-023 Emergency Preparedness Regulatory Review: Position 4/16/2019

Instruction Manual EOF17, Field Team Driver, Revision 0

71114.05 Miscellaneous EPDG #2 E-2 Attachment Monthly and Post-Drill Emergency Response 6/28/2018

Facility Walkdowns and Testing of Facility Equipment

71114.05 Miscellaneous EPDG #2, Monthly State Notification Telephone System Testing 2/5/2019

B-1

71114.05 Miscellaneous EPDG #2, Monthly State Notification Telephone System Testing 6/5/2018

B-1

71114.05 Miscellaneous EPDG #2, Monthly State Notification Telephone System Testing 11/6/2018

B-1

71114.05 Miscellaneous EPDG #2, Monthly State Notification Telephone System Testing 12/5/2017

B-1

71114.05 Miscellaneous EPDG #2, Monthly Testing of Cell Phones and Headsets 12/18/2017

B-3

71114.05 Miscellaneous EPDG #2, Monthly Testing of Cell Phones and Headsets 11/6/2018

B-3

71114.05 Miscellaneous EPDG #2, Monthly Testing of Cell Phones and Headsets 6/27/2018

B-3

71114.05 Miscellaneous EPDG #2, Monthly Testing of Cell Phones and Headsets 2/19/2019

B-3

71114.05 Miscellaneous EPDG #2, Monthly Testing of Alternate Intercom 2/19/2019

B-4

71114.05 Miscellaneous EPDG #2, Monthly Testing of Alternate Intercoms 6/27/2018

B-4

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Miscellaneous EPDG #2, Monthly Testing of Alternate Intercom 11/6/2018

B-4

71114.05 Miscellaneous EPDG #2, Monthly Testing of Alternate Intercom 12/15/2017

B-4

71114.05 Miscellaneous EPDG #2, Monthly Testing 2-Way Radios 12/19/2017

B-5

71114.05 Miscellaneous EPDG #2, Monthly Testing of 2-Way Radios 11/6/2018

B-5

71114.05 Miscellaneous EPDG #2, Monthly Testing of 2-Way Radios 6/27/2018

B-5

71114.05 Miscellaneous EPDG #2, Quarterly Satellite Phone Test and Battery Swap 3/27/2018

B-8

71114.05 Miscellaneous EPDG #2, Quarterly Satellite Phone Test and Battery Swap 3/25/2019

B-8

71114.05 Miscellaneous EPDG #2, Semi-Annual Alert and Notification System Sig and 5/31/2018

C-4 Evacuation Map Verification

71114.05 Miscellaneous EPDG #2, Semi-Annual Alert and Notification System Sig and 11/13/18

C-4 Evacuation Map Verification

71114.05 Miscellaneous EPDG #2, Weekly/Monthly/Semi-Annual Emergency Vehicle 11/20/2018

E-1 Maintenance

71114.05 Miscellaneous EPDG #2, Weekly/Monthly/Semi-Annual Emergency Vehicle 6/29/2018

E-1 Maintenance

71114.05 Miscellaneous EPDG #2, Weekly/Monthly/Semi-Annual Emergency Vehicle 12/20/2017

E-1 Maintenance

71114.05 Miscellaneous EPDG #2, Weekly/Monthly/Semi-Annual Emergency Vehicle 2/28/2019

E-1 Maintenance

71114.05 Miscellaneous EPDG #2, Monthly and Post-Drill Emergency Response Facility 2/27/2019

E-2 Walkdowns and Testing of Facility Equipment

71114.05 Miscellaneous EPDG #2, Monthly and Post-Drill Emergency Response Facility 12/20/2017

E-2 Walkdowns and Testing of Facility Equipment

71114.05 Miscellaneous EPDG #2, Monthly and Post-Drill Emergency Response Facility 11/6/2018

E-2 Walkdowns and Testing of Facility Equipment

71114.05 Miscellaneous EPDG #2, Quarterly Emergency Telephone Directory Revisions 1/31/2018

F-1

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Miscellaneous EPDG #2, Quarterly Emergency Telephone Directory Revisions 7/31/2018

F-1

71114.05 Miscellaneous EPDG #2, Quarterly Emergency Telephone Directory Revisions 1/31/2019

F-1

71114.05 Miscellaneous EPDG #2, Quarterly Emergency Telephone Directory Revisions 4/13/2019

F-1

71114.05 Miscellaneous EPDG #2, Monthly EOF Diesel Generator Run 6/27/2018

I-1

71114.05 Miscellaneous EPDG #2, Monthly EOF Diesel Generator Run 11/13/2018

I-1

71114.05 Miscellaneous EPDG #2, Monthly EOF Diesel Generator Run 12/29/2017

I-1

71114.05 Miscellaneous EPO001-01-01 Lesson Plan: Drill Exercise Controller Training 7

71114.05 Miscellaneous KLD TR-1023 Cooper Nuclear Station 2018 Population Update Analysis 9/22/2018

71114.05 Miscellaneous KLD TR-939 Cooper Nuclear Station 2017 Population Update Analysis 9/23/2017

71114.05 Miscellaneous LO2016-0183 2017 Emergency Preparedness Pre-NRC Focused Self- 2/10/2017

Assessment Report

71114.05 Miscellaneous LO2018-0074 Pre-NRC Evaluated Exercise Assessment 6/21/2018

71114.05 Miscellaneous LO2018-0080 2018 Emergency Preparedness 50.54(Q) Focused Self- 3/21/2018

Assessment

71114.05 Miscellaneous Notifications 11280194, 11567855, 11590153

71114.05 Miscellaneous OTH004-04-03 Lesson Plan: Classification, Notification, and PARs 0

71114.05 Miscellaneous OTH004-04- Training Lesson Plan: Classification, Notifications, and 2/7/2019

03/70926 PARs, Revision 0

71114.05 Miscellaneous QAD 2017-0029 QA Audit 17-06, Emergency Preparedness 9/25/2017

71114.05 Miscellaneous QAD 2018-0023 QA Audit 18-06, Emergency Preparedness 9/27/2018

71114.05 Procedures Evaluation Report for the December 12, 2018, Post-Accident

Sampling Drill

71114.05 Procedures Evaluation Report for the May 22, 2018, Team 3B Dress 6/6/2018

Rehearsal

71114.05 Procedures 5.7.21 Maintaining Emergency Preparedness, Emergency 10/26/2018

Exercises, Drills, Tests, and Evaluations, Revision 58

71114.05 Procedures 5.7.28 Administration of the Positional Instruction Manuals, 7/5/2016

Revision 9

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.05 Procedures 5.7COMMUN Communications, Revisions 29 & 30 1/19/2019

71114.05 Procedures EPDG #2, Monthly State Notification Telephone System Testing 13

B-1

71114.05 Procedures EPDG #2, Monthly Testing of FTS-2001 System Telephones 14

B-2

71114.05 Procedures EPDG #2, Monthly Testing of Cell Phones and Headsets 15

B-3

71114.05 Procedures EPDG #2, Monthly Testing of Two-Way Radios 13

B-5

71114.05 Procedures EPDG #2, Quarterly EAS Newspaper and Radio Advisories 10

C-2

71114.05 Procedures EPDG #2, Semi-Annual Dissemination of Emergency Public 10

C-3 Information/Transient Population Information

71114.05 Procedures EPDG #2, Semi-Annual Alert and Notification System Sign and 10

C-4 Evacuation Map Verification

71114.05 Procedures EPDG #2, Annual Nemaha County Hospital Training 8

D-1

71114.05 Procedures EPDG #2, Annual Emergency Plan Training for Law Enforcement 10

D-2 Agencies

71114.05 Procedures EPDG #2, Annual Auburn Rescue Squad and Midwest Medical 10

D-3 Transport Training

71114.05 Procedures EPDG #2, Annual Volunteer Fire Department Training 9

D-4

71114.05 Procedures EPDG #2, Annual News Media Orientation/Training 9

D-5

71114.05 Procedures EPDG #2, Annual Emergency Plan Training for Local Emergency 0

D-6 Management Agencies

71114.05 Procedures EPDG #2, Monthly and Post-Drill Emergency Response Facility 30

E-2 Walkdowns and Testing of Facility Equipment

71114.05 Procedures EPDG #2, Annual EAL Review 9

F-2

71114.05 Procedures EPDG #2, Maintenance of Emergency Plan Letters of Agreement 14

F-3

71114.05 Procedures EPDG #2, Annual CNS Emergency Plan Review 1

Inspection Type Designation Description or Title Revision or

Procedure Date

F-7

71114.05 Procedures EPDG #2, Drill and Exercise Guide, Scenario Development 11

H-2

71114.05 Procedures EPDG #2, Monthly EOF Diesel Generator Run 5

I-1

71114.05 Work Orders WO 5121615, 5146472, 5148893, 5166231, 5167152, 5167449,

5169963, 5192375, 5197886, 5255090, 5273942, WT-2017-

0040-041

71114.06 Corrective Action CR-CNS- 2019-02739, 2019-02756, 2019-02779, 2019-02791, 2019-

Documents 02805

71114.06 Miscellaneous Drill Scenario Guide 5/14/2019

71124.01 Corrective Action CR-CNS- 2018-06530, 2018-06811, 2018-07755, 2018-07999, 2019-

Documents 00434, 2019-02361

71124.01 Corrective Action CR-CNS- 2019-02870

Documents

Resulting from

Inspection

71124.01 Miscellaneous CNS-RP-138 Source Report - Leak Test Results 06/27/2018

71124.01 Miscellaneous CNS-RP-138 Source Report - Leak Test Results 12/14/2018

71124.01 Procedures 9.EN-RP-141 Job Coverage 19

71124.01 Procedures 9.RADOP.5 Airborne Radioactivity Sampling 32

71124.01 Radiation CNS-1811-0063 Reactor Water Clean-Up Heat Exchanger Room 11/13/2018

Surveys

71124.01 Radiation CNS-1811-0066 Reactor Water Clean-Up Heat Exchanger Room 11/14/2018

Surveys

71124.01 Radiation CNS-1811-0069 Reactor Water Clean-Up Heat Exchanger Room 11/14/2018

Surveys

71124.01 Radiation CNS-1812-0036 Refuel Floor 12/20/2018

Surveys

71124.01 Radiation CNS-1902-0026 Waste Collector Tanks 02/21/2019

Surveys

71124.01 Radiation CNS-1902-0027 Waste Collector Tanks 02/21/2019

Surveys

71124.01 Radiation CNS-1903-0013 Residual Heat Removal Heat Exchanger 03/20/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Surveys

71124.01 Radiation CNS-1903-0020 Refuel Floor 03/27/2019

Surveys

71124.01 Radiation CNS-1904-0020 Residual Heat Removal Heat Exchanger 04/20/2019

Surveys

71124.01 Radiation Work 2018-106 TIP - RP HIGH RISK - Activities 02

Permits (RWPs)

71124.01 Radiation Work 2019-100 REACTOR BLD - LOCKED HRA Activities 00

Permits (RWPs)

71124.01 Radiation Work 2019-102 HIC Prep / Shipments 00

Permits (RWPs)

71124.01 Self-Assessments LO 2018-0185 Pre-NRC Assessment for Radiological Hazard Assessment 01/21/2019

and Exposure Controls-IP 71124.01 and In-Plant Airborne

Radioactivity Control and Mitigation-IP 71124.03

71124.03 Corrective Action CR-CNS- 2017-04470, 2017-06407, 2017-07491, 2018-01888, 2018- 07/24/2017

Documents 05697, 2019-02485

71124.03 Corrective Action CR-CNS- 2019-02877

Documents

Resulting from

Inspection

71124.03 Miscellaneous CNS RP-402 SCBA Functionals 03/18/2019

71124.03 Miscellaneous CNS RP-402 SCBA Functionals 04/02/2019

71124.03 Miscellaneous CNS RP-403 Annual Respirator Inspection 10/12/2017

71124.03 Miscellaneous CNS RP-403 Annual Respirator Inspection 05/23/2019

71124.03 Miscellaneous CNS RP-411 Plant Service Air, Air Quality Data Sheet 07/30/2018

71124.03 Miscellaneous CNS RP-411 Plant Service Air, Air Quality Data Sheet 08/28/2017

71124.03 Miscellaneous CNS RP-415 Bauer Air Quality Review 01/22/2019

71124.03 Miscellaneous CNS RP-415 Bauer Air Quality Review 03/28/2019

71124.03 Miscellaneous GEN002-01-13 Respiratory Protection SCBA Refresher Rev. 01

(CT#47231)

71124.03 Miscellaneous Surveillance Control Room Emergency Filter System Flow Test, Charcoal 05/22/2017

5078037 and HEPA Filter Leak Test,

Filter DP Test, and Charcoal Sample Analysis

71124.03 Miscellaneous Surveillance SGT B Carbon Sample, Carbon Adsorber and HEPA Filter 05/18/2018

Inspection Type Designation Description or Title Revision or

Procedure Date

5132845 In-Place Leak Test, and Components Leak Test

71124.03 Procedures 9.EN-RP-122 Alpha Monitoring Rev. 4

71124.03 Procedures 9.RESP.1 Respiratory Protection Program Rev. 16

71124.03 Procedures 9.RESP.2 Self-Contained Breathing Apparatus Rev. 26

71124.03 Self-Assessments LO 2018-0185 Pre-NRC Assessment for Radiological Hazard Assessment 01/21/2019

and Exposure Controls-IP 71124.01 and In-Plant Airborne

Radioactivity Control and Mitigation-IP 71124.03

71151 Corrective Action CR-CNS- 2018-02306, 2018-04184, 2018-04315, 2018-05838, 2018-

Documents 05839, 2018-06236, 2018-06546, 2018-06852, 2018-07394,

2019-00111, 2019-00242, 2019-00243, 2019-00352, 2019-

00353, 2019-00623, 2019-01274, 2019-01467, 2019-02752,

2019-02755, 2019-02791, 2019-02841

71151 Miscellaneous Memorandum, Subject: 2018 Drill and Exercise 6/11/2018

Opportunities

71151 Miscellaneous Memorandum, Subject: 2019 Drill and Exercise 5/9/2019

Opportunities, Revision 3

71151 Miscellaneous 2Q18 thru 1Q19 PI Verification Package

71151 Miscellaneous 0-EN-LI-114; PI Documentation and Data Review Form; Performance 10/01/2018

9.3 Indicator - Occupational Exposure Effectiveness through

03/31/2019

71151 Procedures 5.7.1 Emergency Classification, Revisions 61 & 62 2/6/2019

71151 Procedures 5.7.2 Emergency Director EPIP, Revision 36 2/28/2018

71151 Procedures 5.7.20 Protective Action Recommendations, Revisions 30 & 31 12/13/2018

71151 Procedures 5.7.27 Alert and Notification System, Revisions 19 & 20 12/5/2018

71151 Procedures 5.7.6 Notification, Revision 74 7/18/2018

71151 Procedures EPDG #.2, Semi-Monthly Alert and Notification System Siren Testing 17

C-1

71151 Procedures EPDG #2, Annual Full-Cycle Sounding of the Alert and Notification 14

C-5 System Sirens

71151 Procedures EPDG #2, Emergency Preparedness Performance Indicator Guide 25

G-1

71151 Procedures EPDG #2, Drill and Exercise Manual, EP DEP Evaluation Process for 11

H-3 Limited Scope Simulator Drills

71151 Work Orders WO 5255284, 5267418, 5267419, 5273175, 5284182, 5284775,

Inspection Type Designation Description or Title Revision or

Procedure Date

285025, 5290430

71152 Corrective Action CR-CNS- 2018-07934, 2018-07935, 2018-07996, 2018-08127, 2019-

Documents 01754, 2019-01757, 2019-01765, 2019-02773, 2019-03367

71152 Drawings 44D209845 Voltage Regulator N04

71152 Drawings 44D209846 Static Exciter & Voltage Regulator N03

71152 Miscellaneous LBDCR 2007-018 TRM 3.7.1 and Bases River Level Change 06/12/2007

71152 Miscellaneous LBDCR 2019-007 TRM 3.7.1, River Level Including Bases 4/18/2019

71152 Procedures 5.1FLOOD Flood 25, 26, 27

71152 Procedures 7.3.30.2 RRMG Set Voltage Regulator Tuning 8

71152 Work Orders WO 5057910, 5179313

71153 Corrective Action CR-CNS- 2017-03721, 2017-05081, 2018-05904, 2018-05907

Documents

71153 Miscellaneous ANSI/ANS-56.8 Containment System Leakage Testing Requirements 1994

71153 Miscellaneous Engineering RE30 Past Operability of MSIVs and MS Pathway 0

Report 2018-034

71153 Procedures 6.PC.207 Torus to Drywell Vacuum Breaker Operation 10

71153 Work Orders WO 5054353, 5080846, 5094244, 5096873, 5102515, 5195069

2