IR 05000334/2021001

Integrated Inspection Report 05000334/2021001 and 05000412/2021001

ML21133A006
Person / Time
Site:	Beaver Valley
Issue date:	05/13/2021
From:	Matt Young NRC/RGN-I/DORS
To:	Grabnar J Energy Harbor Nuclear Corp
Young M
References
IR 2021001
Download: ML21133A006 (18)

Text

May 13, 2021

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2021001 AND 05000412/2021001

Dear Mr. Grabnar:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On April 21, 2021, 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 NRC-identified or self-revealing findings were identified during this inspection.

A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)

consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity 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 I; the Director, Office of Enforcement; and the NRC Resident Inspector at Beaver Valley Power Station, Units 1 and 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, X /RA/

Signed by: Matthew R. Young Matt R. Young, Chief Reactor Projects Branch 5 Division of Operating Reactor Safety Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000334 and 05000412 License Numbers: DPR-66 and NPF-73 Report Numbers: 05000334/2021001 and 05000412/2021001 Enterprise Identifier: I-2021-001-0086 Licensee: Energy Harbor Nuclear Corporation Facility: Beaver Valley Power Station, Units 1 and 2 Location: Shippingport, PA 15077 Inspection Dates: January 1, 2021 to March 31, 2021 Inspectors: G. Eatmon, Senior Resident Inspector R. Rolph, Resident Inspector D. Werkheiser, Senior Reactor Analyst T. Marshall, Contractor Approved By: Matt R. Young, Chief Reactor Projects Branch 5 Division of Operating Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Beaver Valley Power Station, Units 1 and 2, 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. A licensee-identified non-cited violation (NCV) is documented in report section 7115

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 05000412/2021-001-00 LER 2021-001-00 for Beaver 71153 Closed Valley Power Station, Unit 2,

Operation Prohibited by Technical Specifications During a Loss of Control Rod Position Indication Even

PLANT STATUS

Unit 1 operated at or near rated thermal power for most of the inspection period. On March 23, 2021, Unit 1 commenced end-of-cycle coast down operations and ended the inspection period at 96.5 percent power.

Unit 2 operated at or near rated thermal power for the entire 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 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 March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.

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

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold and extremely cold temperatures for the following systems during the week of February 15, 2021:

• Unit 1 and Unit 2 service water and main intake

• Unit 1 and Unit 2 refueling water storage tank and associated temperature sensitive instrumentation

• Unit 1 and Unit 2 low head safety injection and associated temperature conditions in the safeguards buildings

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) Unit 1 auxiliary feed water system, train 'B', after surveillance testing on January 13, 2021

(2) Unit 1 recirculation spray system, train 'B', after surveillance testing on March 4, 2021

(3) Unit 1 quench spray system, train 'B', after surveillance testing on March 30, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

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

(1) Unit 1 and Unit 2 main intake structure screen area, Unit 1 reactor plant river water and Unit 2 service water pump cubicles on January 13, 2021

(2) Unit 1 emergency diesel generator (EDG) number 1 on January 21, 2021

(3) Unit 1 EDG number 2 on February 20, 2021

(4) Unit 1 AE emergency switchgear room on March 17, 2021

(5) Unit 2 main steam valve room and emergency switchgear ventilation room on March 17, 2021

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 Unit 2 control room during quarterly surveillance of steam driven auxiliary feedwater pump, cooling tower effluent monitor calibration, fire suppression test carbon dioxide in switchgear, and observation from another fleet shift manager on January 21, 2021

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated Unit 1 operators response to a main steam pressure transmitter failure high followed by a reactor coolant pump high vibration induced reactor coolant leak that continued to degrade through the scenario on January 13, 2021

(2) The inspectors observed and evaluated Unit 2 loss of feed water in the simulator on January 13, 2021

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1) Unit 1 'C' reactor plant river water, (System 30) continued degradation for ALERT range vibrations and delta-P on February 2, 2021

(2) Unit 1 area ventilation system miscellaneous (system 44F) focused on the EA switchgear function when approved corrective actions were modified on March 10, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 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) Unit 2 emergent work control and risk management plans for the loss of both A and B train of digital rod position indication on January 4, 2021

(2) Unit 1 elevated yellow risk due to steam generator narrow range water level calibration, loop 3, channel 1 on January 19, 2021

(3) Unit 1 and Unit 2 planned yellow risk work rescheduled due to risk management procedural guidance for cold weather on February 15 through February 19, 2021

(4) Unit 2 risk plan for potential power reduction for water box access due to elevated steam generator sodium levels on March 4, 2021

(5) Unit 1 elevated risk for 'A' intake bay cleaning with reactor plant river water pump 'A' extended unavailability with planned maintenance and high river water elevation on March 8, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) Unit 2 non-safety 480V bus 2E de-energized causing a complete loss of Digital Rod Position Indication on January 5, 2021

(2) Unit 2 failure of core exit thermocouple 2RCS-TE34E reduces number of operable core exit thermocouple channels to minimum per Technical Specification (TS)3.3.3 on January 12, 2021

(3) Unit 1 and Unit 2 emergency response facility system (ERFS) loss of the load shed programmable controller and the ERFS diesel generator on January 27, 2021

(4) Unit 2 sampling device lost while sampling EDG 'A' fuel oil storage tank on January 28, 2021

(5) Unit 2 elevated steam generator sodium concentration on February 12, 2021

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) Unit 1 Evaluation No. 21-00172 - License Surveillance Requirement 3.3.9.6 Remove Requirements for Beaver Valley Power Station Turbine Reheat Stop and Intercept Valve inspections approved on March 5, 2021

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) 2OST-7.4 for Unit 2 charging pump A operating surveillance test after heat exchanger inspection, clean and inspect speed increaser, auxiliary oil pump and main reservoir on January 22, 2021

(2) 1OST-30.2 for Unit 1 reactor plant river water pump '1A' after motor bearing replacement on March 8, 2021

(3) Testing of the Unit 2 digital radiation monitoring system post software upgrade as outlined in engineering change package No. 20-0016 on March 29, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 1OST-36.1, Unit 1 diesel generator number 1 [1EGS*EG1-1] monthly test on February 20, 2021

(2) 1OST-13.7B, Unit 1 recirculation spray pump flow test, train 'B' on March 2, 2021

(3) 1OST-30.12A, Unit 1 train A reactor plant river water system full flow test using the C reactor plant river water pump aligned on the AE emergency bus on March 16, 2021

(4) 2OST-36.1, Unit 2 EDG number 1 [2EGS*EG2-1] monthly test on March 24, 2021

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 2OST-24.4, Unit 2 steam driven auxiliary feed pump quarterly test on January 21, 2021

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) White Team integrated drill major event sequence was loss of offsite power, dropped rods with manual reactor scram and loss of coolant accident, containment radiation levels increase, then loss of containment and radiation release on March 25,

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Unit 1 and Unit 2 Supplementary Leak Collection Release System

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) SP-700 portable high efficiency particulate air filter #206 placed at the Spent Fuel Pool up-ender for inspection and repair work

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

OTHER ACTIVITIES - BASELINE

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

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01) ===

(1) Unit 1 for the period of January 1, 2020 to December 31, 2020

(2) Unit 2 for the period of January 1, 2020 to December 31, 2020 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02)

(2 Samples)

(1) Unit 1 for the period of January 1, 2020 to December 31, 2020

(2) Unit 2 for the period of January 1, 2020 to December 31, 2020

IE04: Unplanned Scrams with Complications Sample (IP Section 03.03) (2 Samples)

(1) Unit 1 for the period of January 1, 2020 to December 31, 2020

(2) Unit 2 for the period of January 1, 2020 to December 31, 2020

71152 - Problem Identification and Resolution

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

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

(1) Selected Non-Compliances with Beaver Valley Cyber Security Plan. The results of the review are documented in NRC inspection report 05000334/2021403 and

===05000412/2021403 (ADAMS Accession Nos. ML21133A022 and non-public ML21133A021) due to the information being security-related and non-publicly available.

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) ===

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

(1) LER 0500000412/2021-001-00, Operation Prohibited by Technical Specifications During a Loss of Control Rod Position Indication Event (ADAMS Accession No.

ML21077A119). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is closed.

INSPECTION RESULTS

Observation: Selected Non-Compliances with Beaver Valley Cyber Security Plan 71152 During the Beaver Valley Power Station, Units 1 and 2, cyber security inspection completed in February 2018, non-compliances with the cyber security plan were identified. Three NRC-identified NCVs were documented in Beaver Valley Cyber Security Inspection Report 05000334/2018403 and 05000412/2018403 (ADAMS Accession Nos. ML18117A265 and non-public ML18129A098).

On May 24, 2018, FirstEnergy Nuclear Operating Company (FENOC), the former license holder for Beaver Valley, disputed NCV 2018403-02 (ADAMS Accession No. ML18149A138).

After a subsequent NRC detailed review, this NCV was upheld on August 30, 2018, and determined to have occurred as originally described in the inspection report (ADAMS Accession No. ML18242A429 and non-public ML18242A258).

The scope of this inspection evaluated Beaver Valleys initial, interim, and long-term corrective actions and extent of condition related to the three NCVs that were attributed to the licensee's specific implementation of the cyber security plan. These issues were documented in the licensees corrective action program as CRs 2018-00957, 2018-01339, 2018-01259, and notification 601112882. Corrective actions documented in CRs 2018-00933 and 2018-00872 were also reviewed. The inspectors reviewed the cause analysis, technical evaluations performed, and the corrective actions taken and planned. The inspectors assessed the licensee's problem identification threshold, prioritization of the issues, apparent cause analyses, use of operating experience, and timeliness of corrective actions.

The results of the review are documented in NRC inspection report 05000334/2021403 and 05000412/2021403 (ADAMS Accession Nos. ML21133A022 and non-public ML21133A021)due to the information being security-related and non-publicly available.

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as an NCV, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: When Beaver Valley Power Station Unit 2 is in Mode 1 or 2, TS limiting condition of operation (LCO) 3.1.7.2, Unit 2 Rod Position Indication, condition 'A', requires, in part, that when one digital rod position indication (DRPI) in one or more groups is determined to be inoperable in one or more groups, operators must: verify the position of the rods with inoperable DRPI using movable incore detectors once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, verify the position of the rod with inoperable DRPI indirectly using movable incore detectors, or reduce thermal power to less than 50 percent rated thermal power within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. If at least one of these actions is not completed within the stated required completion time, operators must then return the plant to Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failing to meet the associated required completion times or 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> from the time of discovery of the inoperable DRPI.

Contrary to the above, when both trains of Unit 2 DRPI were identified to be inoperable due to a loss of electrical power on January 4, at 1752 hours0.0203 days <br />0.487 hours <br />0.0029 weeks <br />6.66636e-4 months <br />, operators did not enter and perform the required actions associated with TS LCO 3.1.7.2, condition 'A', to verify rod position of the affected rods or reduce thermal power to less than 50 percent prior to January 5, at 0152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br />, and then did not return the plant to Mode 3 prior to January 5, at 0752 hours0.0087 days <br />0.209 hours <br />0.00124 weeks <br />2.86136e-4 months <br />.

Operators restored electrical power and declared both trains of DRPI operable following completion of testing per the operating procedure at 0805 on January 5, 2021. Unit 2 exited TS LCO 3.1.7.2, condition 'B' after DRPI was inoperable for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and 13 minutes. Unit 2 did not enter TS LCO 3.1.7.2, condition 'A' during this evolution.

Significance/Severity: Green. The inspectors assessed the significance of the finding using IMC 0609, Attachment 4, Initial Characterization of Findings, effective December 20, 2019, and IMC 0609, Appendix A, The Significance Determination Process for Findings at Power, Exhibit 3, for safety significance and determined that the finding was of very low safety significance (Green) because there was no unintentional positive reactivity addition, there was no mismanagement of reactivity by operators that challenged fuel cladding integrity, there was no mismanagement of foreign material exclusion or reactor coolant chemistry, and the finding was not a result of fuel handling errors.

Corrective Action References: CR2021-00242, CR2021-00045

EXIT MEETINGS AND DEBRIEFS

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

• On February 18, 2021, the inspectors presented the Cyber Security Problem Identification and Resolution Sample inspection results to Mr. William Cohen, Acting Plant Manager and other members of the licensee staff.

• On March 11, 2021, the inspectors presented the Exit Debrief inspection results to Mr. Brian Kremer, Acting Site Vice President and other members of the licensee staff.

• On April 21, 2021, the inspectors presented the integrated inspection results to Mr. John Grabnar, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 2014-01274

Documents 2018-00147

Procedures 1OM-30.4.AAN Unit 1 Traveling Water Screen Diff High Revision 3

Unit 1/Unit 2 Extreme Cold Weather Protection Verification Revision 2

OST-45.1

71111.04 Drawings 8700-RM-0413- Valve Oper No Diagram Containment Depressurization Revision 13

2 System

8700-RM-0513- Flow Diagram Containment Depressurization System Revision 27

RM-0018A Flow Diagram Feed Water Revision 55

Procedures 1OST-13.2 Quench Spray Pump [1QS-P-1B] Test Revision 48

1OST-24.3 Motor Driven Auxiliary Feed Pump Test [1FW-P-3B] Revision 54

71111.05 Procedures 1PFP-DG/BX- Diesel Generator 1 Room

735-DG-1

1PFP-DGBX-735- Diesel Generator 2 Room Fire Compartment 1-DG-2 Revision 2

DG-2

1PFP-INTS-705- Pump Cubicles Fire Compartment 3-IS-1,2,3,4 Revision 2

PUMP

1PFP-SRVB-713- AE Switchgear Room Fire Compartment 1-ES-1 Revision 3

AE

2PFP-MSCV-773- Main Steam Valve Room/Emerg Switchgear Vent Room Fire Revision 1

MAIN Compartment 2-MS-1 & 2-CV-4

71111.12 Corrective Action 2020-01576

Documents 2020-09249

20-09758

21-00268

21-00658

21-00839

21-01046

21-01365

21-08343

Inspection Type Designation Description or Title Revision or

Procedure Date

Miscellaneous Maintenance Rule (a)(1) evaluation for 1VS-D-262 (grill

upsteam)

1DBD-30 Design Basis Document for River Water, Auxiliary River Revision 19

Water and Raw Water Systems

20-01051-ATA-

20-01051-ATA-

ATA-2020-14185 Maintenance Rule Paragraph (a)(3) Periodic Assessment for 12/15/2020

July 1, 2018 thru December 31, 2019

ATL-2020-0632

Maintenance Rule River Water System 30 Revision 8

System Basis

Document

Unit 1 Maintenance Rule Condition Monitoring General Corrosion

Rate trending spreadsheet

71111.13 Corrective Action 2021-00045

Documents 2021-01186

21-01387

21-01390

Miscellaneous Risk Management Plan for Heavy Load Lift of the River

Water pump 'A' motor for WO200771248

Heavy Lift Plan for 1WR-P-A-Motor 03/03/2021

Risk Management Plan for restoring power to 480V bus2E 01/05/2021

and perform 2OM-1.4.C to startup DRPI

Procedures 1MSP-24.23-1 Unit 1 L-1FW494, loop 3 narrow range steam generator Revision 18

water level channel I calibration

NOP-OP-1003 Grid Reliability Protocol Revision 12

NOP-OP-1007 Risk Management Revision 33

NORM-OP-1007 Risk Management Reference Revision 2

Unit 1/Unit 2- Handling of NUREG 0612 Heavy Loads Revision 20

ADM-0819

Unit 1/Unit 2-OM- Acts of Nature - High River Elevation Revision 36

53C.4A.75.2

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders WO 200775085

WO 200842530

WO 200842566

71111.15 Corrective Action 2020-08386

Documents 2021-00045

21-00156

21-00216

21-00242

21-00555

21-00937

Corrective Action 2021-01247

Documents

Resulting from

Inspection

Miscellaneous Unrecoverable Foreign Material Log 1/28/2021

Calculation No. ERF Diesel Generator Loading Study Revision 0,

8700.58E.1 01/10/1991

LER 2021-001 Unit 2 Operation Prohibited by Technical Specifications 03/03/2021

During a Loss of Control Rod Position Indication Event

ODMI No 2021- Unit 2 Elevated Steam Generator Sodium Revision 0

00937

TSTF-574-A Clarification of Rod Position Requirements 03/04/2016

Procedures 2OM- Unit 2 Primary or Secondary Chemistry Out of Tolerance Revision 5

53C.4.2.14.1

Unit 1/Unit 2 OM- Major Components Revision 7

58E.1.C

Unit 1/Unit 2 OM- ERFS Load Shed Programmable Controller Startup Revision 9

58E.4.AD

Unit 1/Unit 2 OM- Table 58G-2 ERF Load Shed Equipment List Revision 0

58G.5.B.2

Work Orders WO 200334827

71111.18 Corrective Action 2021-02033

Documents

Resulting from

Inspection Type Designation Description or Title Revision or

Procedure Date

Inspection

71111.19 Procedures 1OST-30.2 Reactor Plant River Water Pump 1A Test Revision 65

2OST-7.4 Operating Surveillance Test Centrifugal Charing Pump, Revision 40

2CHS-P21A

NOP-SS-1001 Administrative Program for Computer Related Activities Revision 19

Unit1/Unit2-ADM- Handling of NUREG 0612 Heavy Loads Revision 20

0819

Work Orders WO 200751517

WO 200771248

71111.22 Corrective Action 2021-01889 Flow Lower than Required During 1OST-30.12A March 16,

Documents 2021

Drawings 8700-RM-0430- Piping and Instrumentation Diagram River Water System Revision 37

001

8700-RM-0430- Piping and Instrumentation Diagram River Water System Revision 23

2

8700-RM-0430- Piping and Instrumentation Diagram River Water System Revision 33

003

Procedures 1OST-13.7B 2B Recirculation Spray Pump Flow Test Revision 15

1OST-30.12A Train A Reactor Plant River Water System Full Flow Test Revision 39

1OST-36.1 Diesel No. 1 Monthly Test Revision 72

2OST-24.4 Steam Driven Auxiliary Feed Pump [2FWE*P22] Quarterly Revision 92

Test

2OST-36.1 EDG [2EGS*EG2-1] Monthly Test Revision 79

71124.03 Corrective Action 2019-02037 Respirator fit test performed when individual's medical was

Documents expired

2019-06837 Respirator issued to Unqualified Individual

20-03550 HEPA filter not inspected as required

20-06888 Air flow rate too high

20-08116 SCBA regulator not working properly when tested

Corrective Action 2021-01659 Contractor technician performed annual SCBA inspections

Documents with lapsed training

Resulting from 2021-01677 Procedure NOP-OP-4310 has unclear and seemingly

Inspection contradictory wording

Inspection Type Designation Description or Title Revision or

Procedure Date

21-01719 Air compressor sampled and analyzed on six month

frequency instead of quarterly

Procedures NOP-OP-4310 Firehawk M7 Self-Contained Breathing Apparatus

15