IR 05000440/2020002

Integrated Inspection Report 05000440/2020002

ML20227A073
Person / Time
Site:	Perry
Issue date:	08/14/2020
From:	April Nguyen NRC/RGN-III/DRP/B2
To:	Payne F Energy Harbor Nuclear Corp
References
IR 2020002
Download: ML20227A073 (16)

Text

August 14, 2020

SUBJECT:

PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000440/2020002

Dear Mr. Payne:

On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Perry Nuclear Power Plant. On July 23, 2020, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

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

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

Sincerely,

/RA/

April M. Nguyen, Acting Chief Branch 2 Division of Reactor Projects Docket No. 05000440 License No. NPF-58

Enclosure:

As stated

Inspection Report

Docket Number: 05000440 License Number: NPF-58 Report Number: 05000440/2020002 Enterprise Identifier: I-2020-002-0034 Licensee: Energy Harbor Nuclear Corp.

Facility: Perry Nuclear Power Plant Location: Perry, OH Inspection Dates: April 01, 2020 to June 30, 2020 Inspectors: S. Bell, Health Physicist J. Nance, Reactor Engineer T. Ospino, Resident Inspector J. Steffes, Senior Resident Inspector Approved By: April M. Nguyen, Acting Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY

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

List of Findings and Violations

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

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000440/2019-002-00 LER 2019-002-00 for Perry 71153 Closed Nuclear Power Plant, Loss of Safety Function Due to Low Pressure Core Spray Inoperability LER 05000440/2018-003-00 LER 2018-003-00 for Perry, 71153 Closed Unanalyzed Condition Resulting from Unfused Alternating Current Control Circuits

PLANT STATUS

The plant began the inspection period at rated thermal power. On June 12, 2020, reactor power was lowered to 58 percent to perform a rod sequence exchange. The unit was returned to rated thermal power on June 13, 2020. The unit remained at, or near, rated thermal power for the remainder of the inspection period with the exception that on several occasions, power was reduced to maintain condensate demineralizer outlet temperature and/or high condenser circulating water outlet temperature at or below their respective upper limits due to environmental conditions. The power reductions varied between 1 and 16 percent of rated thermal power and lasted from a few hours to several days.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html.

Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities, and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk- significant systems from impending high winds and thunderstorms on June 2, 2020

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Train 'B' emergency closed cooling system on April 10, 2020

(2) Division 2 emergency diesel generator on April 16, 2020

(3) High pressure core spray on April 22, 2020

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Control complex 4160-volt and 480-volt switchgear room, 620-foot elevation, on April 6, 2020

(2) Auxiliary building, 574-foot elevation, fire zone (FZ) 1AB-1g, on April 10, 2020

(3) Diesel generator division 2, (FZ) 1DG-1a, on April 10, 2020

(4) Fuel handling building, 574, 585, and 599-foot elevations, fire zones (FZ) 0FH-1, 0FH-2A, and 0FH-2B, on April 22, 2020

(5) Intermediate building, 574, 585, and 599-foot elevations, fire zones (FZ) 0IB-1 and 2, on April 22, 2020

(6) Emergency service water pump house, (FZ) 0EW-1a, and Diesel fire pump room, (FZ) 0EW-1b, on May 14, 2020

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on May 8, 2020

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Underground cable inspection and condition review for safety-related manhole 3 on June 24, 2020

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

(1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during heightened risk activities, including offsite power source manipulations and reactor protection system main steam line half isolations due to maintenance on May 4, 2020 and power maneuvers to complete a rod sequence exchange on June 12 to 13, 2020

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

(1) The inspectors observed and evaluated an operations crew-evaluated scenario in the plant training simulator on June 8, 2020

71111.12 - Maintenance Effectiveness

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Procurement and installation quality control activities for the replacement of the low-pressure core injection residual heat removal 'C' flush line vent valve performed under WO 200808828 on May 27, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Emergent work associated with the unplanned inoperability of the RCIC system on April 21 to 22, 2020

(2) Division 3 emergency diesel generator emergent lubrication oil leak, identified on May 12, 2020, and repaired under WO 200823511

(3) Replacement of low-pressure core injection residual heat removal 'C' flush line vent valve under WO 200808828

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) Nuclear steam supply shutoff isolation outboard logic test switch 1B21H-S19D inoperability determination of reactor protection system channel 'D' on May 22, 2020

(2) Drywell unidentified leakage increase on April 2 to 3, 2020

(3) Auxiliary building 574-foot elevation east area radiation monitor failed check source on April 7, 2020

(4) Review of licensee actions and limits following identification by the fuel vendor of possible non-conservative thermal limit calculations on June 16 to 17, 2020

71111.18 - Plant Modifications

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

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Replacement of standby liquid control storage tank level instrumentation from May 13-21, 2020

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)

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

(1) Functional check of APRM 'F' channel following reactor protection system relay replacement on April 15, 2020

(2) Functional check of RCIC high steam flow time delay relay following replacement on April 22, 2020

(3) VT-2 visual examination and MT magnetic particle examination of the low-pressure coolant injection residual heat removal 'C' flush line vent valve replacement on May 27, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Remote Shutdown Panel 1C61-P001 Control Operability Test RHR 'A', ESW 'A', ECC

'A' and Division 1 Diesel Generator per WO 200743154

(2) SVI-B21-T0061D, RPV Low Level 1 and 2 Channel 'D' Functional for 1B21-N681D, on May 4, 2020

(3) SVI-B21-T0072D, MSL Low Pressure Channel 'D' Functional for 1B21-N676D, on May 4, 2020

(4) SVI-B21-T0076D, MSL Low Condenser Vacuum Channel 'D' Functional for 1B21-N675D, on May 4, 2020

(5) SVI-E31-T0074F, MSL High Flow Channel 'B' Functional for 1E31-N687B and 1E31-N689B, on June 18,

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses

71124.04 - Occupational Dose Assessment

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

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

External Dosimetry (IP Section 03.02) (1 Sample)

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

Internal Dosimetry (IP Section 03.03) (1 Sample)

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

(1) The inspectors evaluated the internal dose determination for an event on March 17, 2019, which occurred during insulation removal work in the steam tunnel

Special Dosimetric Situations (IP Section 03.04) (1 Sample)

The inspectors evaluated the following special dosimetric situations:

(1) The inspectors evaluated declared pregnant worker records dated May 30, 2019, and July 16,

OTHER ACTIVITIES - BASELINE

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

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===

(1) Unit 1 (April 2019-March 2020)

MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)

(1) Unit 1 (April 2019-March 2020)

MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)

(1) Unit 1 (April 2019-March 2020)

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in the redundant reactivity control system that might be indicative of a more significant safety issue. The inspectors did not find an adverse trend that would cause the inspectors to question the redundant reactivity control system's ability to carry out its design function

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

(1) Scaffolding and seismic concerns as documented in CRs 2020-03544, 2019-04494, 2019-04490, 2018-07838, 2018-01407, and 2017-06860

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 05000440/2019-002-00, Loss of Safety Function Due to Low Pressure Core Spray Inoperability (ADAMS Accession No. ML19199A150). The issue of concern associated with the event described by this LER was documented in Inspection Report 05000440/2019003 Section 71152. The closure review of this LER did not identify any additional performance deficiencies or violations of NRC requirements

(2) LER 05000440/2018-003-00, Unanalyzed Condition Resulting from Unfused Alternating Current Control Circuits (Adams Accession No. ML18334A366). The issue of concern associated with the event described by this LER was documented in Inspection Report 05000440/2018011 Section 71111.05T. The closure review of this LER did not identify any additional performance deficiencies or violations of NRC requirements

INSPECTION RESULTS

Observation: Scaffolding and seismic concerns 71152 The inspectors performed a detailed review of Condition Reports (CRs) 2020-03544, NRC ID: NRC Walkdown Results 4-22-2020; 2019-04490, NRC ID - Unrestrained Scaffold in Residual Heat Removal (RHR) 'B' Pump Room; and 2018-01407, NRC ID: Control Complex 574' Elevation Scaffold Laydown Area Storage in Close Proximity to Control Complex Chilled Water Piping. Each of these condition reports identified minor non-conformances with the licensee's control of scaffolding procedure.

CR 2020-03544 documented the inspectors' questions concerning an unrestrained scaffold in the turbine building chilled water-cooling system area that was being used as a tool bench and was within six feet of the Emergency Closed Cooling System Ventilation (ECCS) Control Panel. The scaffolding was not built in accordance with the requirements of NOP-WM-5008, Control of Scaffolding, which required that free-standing scaffolding height shall be less than 1.5 times its width. The scaffolding in question measured six feet in height and was seven feet wide. The licensee performed an engineering evaluation that documented that the scaffold would not have impacted the ECCS Control Panel during a seismic event. Likewise, the inspectors had previously identified an unrestrained scaffold built in the residual heat removal room 'B' on May 17, 2019, which was documented in CR 2019-04490. The CR documented that the scaffolding did not meet the seismic restraint requirements of NOP-WM-5008, for scaffolding installed near safety-related equipment. The inspectors determined that there was no direct impact to safety-related equipment and, therefore, the inspectors concluded that the non-conformance was minor.

On February 16, 2018, the inspectors identified that the scaffold laydown area on Control Complex 574' Elevation had scaffold material stored above the documented nine foot maximum height and was in close proximity to the Control Complex Chilled Water piping.

The inspectors were concerned that during a seismic event, loose scaffolding could become an impact hazard to safety-related piping. The licensee documented the inspectors' concerns in CR 2018-01407. The licensee documented in its Engineering Evaluation Report that scaffold parts were stored above the approved height of nine feet as specified in the licensee's Field Clarification Request (FRC) which was the precursor of the Engineering Evaluation Report process. The licensee also documented in its EER that the scaffolding would not adversely impact the Control Complex Chilled Water System, which is a safety-related system nor would it have impacted any other safety-related system during a design basis earthquake. The inspectors reviewed the licensee's response to their concerns and determined that the non-conformances identified in CR 2018-01407 were minor because there no was real or potential impact to safety-related structures or equipment.

The inspectors concluded that the licensee's actions taken in accordance with their corrective action program were reasonable given the overall safety significance of the issues. The inspectors did not identify any findings or violations of NRC requirements that exceeded the more than minor threshold in the course of their review.

Observation: Semi-Annual Trend Review - Redundant Reactivity Control System 71152 The inspectors conducted a search of the corrective action program of the previous six-month period for issues associated with the redundant reactivity control system (RRCS). The inspectors noted that CR 2020-00272, "RRCS Division 2 Trouble Alarm," CR 2020-00694, "Division 2 RRCS Trouble Alarm," and CR 2020-02507, "RRCS Division 2 Trouble Alarm,"

documented discrepant conditions associated with the RRCS which warranted further review.

The inspectors reviewed the associated documentation and determined that because of the similar nature associated with each condition and the relatively close proximity in time over which they occurred to further extend the time over which the review was to be conducted.

The inspectors extended out their search over a year and noted a further three condition reports highlighted discrepant conditions associated with RRCS cards. The inspectors engaged licensee staff to gain an understanding of the RRCS overall condition and issue disposition. The inspectors were made aware of a licensee review conducted and associated with CR 2020-00358, "Roll up Condition Report for Adverse Trend-Redundant Reactivity Control System." The inspectors reviewed CR 2020-00358 and noted the primary cause for card failure was likely associated with age-related degradation. The inspectors reviewed the licensee's plan for card replacement and the associated maintenance strategy and did not identify any concerns.

The review conducted by the inspectors did not identify any instances where the discrepant conditions identified within condition reports would have impaired the design function of the redundant reactivity control system. The inspectors did not identify an adverse trend associated with the design function of the RRCS and did not identify any concerns.

EXIT MEETINGS AND DEBRIEFS

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

• On July 23, 2020, the inspectors presented the integrated inspection results to Mr. F. Payne, Site Vice President and other members of the licensee staff.

• On May 8, 2020, the inspectors presented the radiation protection baseline inspection results to Mr. B. Blair, Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures ONI-ZZZ-1 Acts of Nature-Severe Weather 32

71111.04 Drawings 302-0352-00000 Standby Diesel Generator Fuel Oil System LL

2-0353-00000 Standby Diesel Generator Lube Oil T

2-0354-00000 Standby Diesel Generator Jacket Water V

Procedures VLI-E22A High Pressure Core Spray 10

VLI-P42 Emergency Closed Cooling System 20

VLI-R45 Division 1 and 2 Diesel Generator Fuel Oil System (Unit 1) 5

VLI-R46 Division 1 and 2 Diesel Generator Jacket Water Systems 4

(Unit 1)

VLI-R47 Division 1 and 2 Diesel Generator Lube Oil 7

71111.05 Fire Plans FPI-0CC Control Complex 12

FPI-0EW Emergency Service Water Pumphouse 7

FPI-0FH Fuel Handling Building 6

FPI-0IB Intermediate Building 10

FPI-1AB Auxiliary Building Unit 1 4

FPI-1DG Diesel Generator Building 9

Miscellaneous PNPP No. 7015 Scenario FD-1100 Fire Drill 05/08/2020

71111.06 Work Orders 200688892 MANHOLE 3 &4 / DIVISION 1 Inspections (Visual 06/24/2020

Inspection)

71111.11Q Miscellaneous Evolution June 2020 Sequence Exchange 0

Specific

Reactivity Plan

Simulator OTLC-3058202007_PY-SGC1 Evaluated Simulator 0

Scenario Guide Scenario C1

71111.12 Corrective Action CR 2020-04954 Documentation Not Included in Receipt Inspection Report 06/09/2020

Documents

Resulting from

Inspection

Procedures NOP-CC-5708 Written Practice for the Qualification and Certification of 11

Nondestructive Examination Personnel

Work Orders 200808828 Replace Manual Valve with ValveTech Ball Valve per 05/27/2020

EER#601262736 to Promote More Efficient and Effective

Inspection Type Designation Description or Title Revision or

Procedure Date

Air Vent during SVI-E12-T1182C

71111.13 Corrective Action CR 2020-04202 Lube Oil Leak on Lube Oil Cooler Clamping Plate 05/12/2020

Documents

Miscellaneous NOP-OP-1007- Risk Management Plan for Racking of Breakers that 09/19/2019

Involve Calculated Incident Energy > 40 cal/cm2

Procedures NOP-OP-1007 Risk Management 31

Work Orders 200823511 Cooler HPCS Diesel Lube Oil 05/12/2020

71111.15 Corrective Action CR 2020-03272 Drywell Identified Leak Rate Determined to have Risen 04/15/2020

Documents from 2.0 to 2.1 Gallons Per Minute

CR 2020-05085 Fuel Vendor Identified Possible Non-Conservative 06/15/2020

Thermal Limit Calculation

Corrective Action ATL-2020-0298- NRC Resident Question Regarding SVI-B21-T0061D 05/05/2020

Documents ATA-27

Resulting from CR 2020-03263 NRC ID. Basis for Redundant Instrumentation in EOP-3 04/15/2020

Inspection

Drawings 208-0013-00004 Nuclear Steam Supply Shutoff System, Switch AA

Development

71111.18 Work Orders 200789607 Replace Transmitters 1C41N0010B and 1C41N0010D for 04/18/2020

Standby Liquid Control Storage Tank

71111.19 Miscellaneous IMI-E3-20, PY-1E51Q7065, 1E51A-K65, Model No. ETR14B3C004, 04/22/2020

1, Serial No. 18330403

Agastat GP,

EGP, TR, and

ETR Relay Test

Data Sheet

Procedures SVI-C51-T0027F APRM F Channel Functional for 1C51-K605F 12

SVI-E31-T5395- RCIC Steam Line Flow High Channel Functional For 04/22/2020

A 1E31-N684A

Work Orders 200391664 Relay Replacement of 1C71A-K012F 04/03/2020

200748959 SVI-E31T5396A 1 (24M) RHR/RCIC Steam Line Flow 04/22/2020

High Channel Calibration For 1E31-N084A

200754246 SVI-R43T1317 DIV-1 D/G Start and Load Functional 06/24/2020

Testing

71111.19 Work Orders 200808828 Replace Manual Valve with ValveTech Ball Valve per 05/27/2020

EER#601262736 to Promote More Efficient and Effective

Air Vent During SVI-E12-T1182C

200821043 PY-1E51AK0065 Failed to Change State During the 04/22/2020

Performance of SVI-E31-T5396A

71124.03 Miscellaneous Control Room Personnel Respirator Qualification Records; 05/07/2020

Dayshift

LAA34801 and SCBA Maintenance and Repair Records Various

LAA348805

Procedures NOP-OP-4301 Respiratory Protection Program 10

NOP-OP-4702 Air Sampling and Analysis 08

Self- SA-BN-2019- Pre NRC-Inspection in Plant Airborne Radioactivity 02/17/2020

Assessments 1766 Control/Mitigation and Occupational Dose Assessment

Work Orders 200753612 Respirator Checks/Inspections 01/06/2020

200753613 Respirator Checks/Inspections 02/03/2020

200753614 Respirator Checks/Inspections 03/05/2020

71124.04 Calculations Internal Dose Calculation for Insulation Removal in the 03/17/2019

Steam Tunnel

Internal Dose Calculation for Shielding Removal on the 03/24/2019

Recirculation Loop

First Dosimetry Period of 2019 (01/01/19 through Undated

04/30/19) Dosimetry Comparison Data for TLD and

Electronic Dosimeters.

Cycle 17 Radioactive Source Term Report 09/30/2018

14195 TLD/SRD Deviation Investigation Report 06/10/2019

27362 TLD/SRD Deviation Investigation Report 06/10/2019

Corrective Action CR-2018-06458 Area TLD Data Not Completed and Reviewed in Timely 07/19/2018

Documents Manner

CR-2019-04423 Control TLDs Separated from Dosimeters of Legal Record 05/15/2019

CR-2019-05259 Damaged Dosimeters for PY1R17 09/25/2019

Miscellaneous Dosimetry Relocation Evaluation for Under Vessel Work 03/18/2019

Personal Contamination Monitor Internal Sensitivity Test 07/26/2016

Declared Pregnant Worker Dosimetry Evaluation 05/30/2019

Declared Pregnant Worker Dosimetry Evaluation 07/19/2019

Portal Monitor Internal Sensitivity Test 07/18/2016

100555-0 NVLAP Scope of Accreditation - Mirion Technologies Inc. 07/01/2019

Procedures NOP-OP-4201 Routine External Exposure Monitoring 05

NOP-OP-4202 Declared Pregnant Workers 02

NOP-OP-4204 Special External Exposure Monitoring 11

NOP-OP-4205 Dose Assessment 09

NOP-OP-4206 Bioassay Program 04

71151 Miscellaneous NOBP-LP-4012- Mitigating Systems Performance Index (MSPI) 04/01/2019-

Unavailability Index (UAI) and Unreliability Index (URI) for 03/31/2020

Emergency AC Power Systems

NOBP-LP-4012- Mitigating Systems Performance Index (MSPI) 04/01/2019-

Unavailability Index (UAI) and Unreliability Index (URI) for 03/31/2020

High Pressure Injection System (HPCS) and High

Pressure Emergency Diesel Generator (EDG)

NOBP-LP-4012- Safety System Functional Failures 04/01/2019-

03/31/2020

71152 Corrective Action CR 2020-00043 During Replacement of Optical Isolator Noted Charring 01/03/2020

Documents Around Two Fuses on the Card

CR 2020-00272 Redundant Reactivity Control System Division 2 Trouble 01/14/2020

Alarm

CR 2020-00358 Roll Up Condition Report for Adverse Trend-Redundant 01/17/2020

Reactivity Control System

CR 2020-00694 Division 2 Redundant Reactivity Control System Trouble 01/29/2020

Alarm

CR 2020-01416 Green Indicating Light for C22-F160A is Out on Division 1 02/23/2020

Redundant Reactivity Control Panel

CR 2020-02507 Redundant Reactivity Control System Division 2 Trouble 03/22/2020

Alarm

Procedures NOP-WM-5008 Control of Scaffolding 01

71153 Corrective Action CR 2018-08718 2018 NRC Fire Protection Inspection-Vulnerability to 10/04/2018

Documents Cause Secondary Fire due to Unfused M43 Circuit

Caused by Fire Induced Shorts

14