IR 05000321/2020003

Integrated Inspection Report 05000321/2020003 and 05000366/2020003 and Independent Spent Fuel Storage Installation Report 07200036/2020002

ML20315A091
Person / Time
Site:	Hatch, 07200036
Issue date:	11/10/2020
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2020002, IR 2020003
Download: ML20315A091 (15)

Text

November 10, 2020

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000321/2020003 AND 05000366/2020003 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200036/2020002

Dear Ms. Gayheart:

On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant. On October 29, 2020, the NRC inspectors discussed the results of this inspection with Mr. Johnny Weissinger 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/

Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000321 and 05000366 and 07200036 License Nos. DPR-57 and NPF-5

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000321 and 05000366 and 07200036 License Numbers: DPR-57 and NPF-5 Report Numbers: 05000321/2020003 and 05000366/2020003 and 07200036/2020002 Enterprise Identifier: I-2020-003-0049 and I-2020-002-0099 Licensee: Southern Nuclear Operating Co., Inc.

Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, GA Inspection Dates: July 1, 2020 to September 30, 2020 Inspectors: J. Hickman, Senior Resident Inspector, Acting N. Peterka, Resident Inspector, Acting M. Schwieg, Senior Resident Inspector, Acting Approved By: Alan J. Blamey, Chief Reactor Projects 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 Edwin I. Hatch Nuclear 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

None.

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On August 20, 2020, the unit was down powered to 75 percent RTP due to an automatic recirculation runback due to the 1A Reactor Feed Pump minimum flow valve failing open. On August 21, 2020, the unit was returned to 100% RTP. On September 3, 2020, the unit was down powered to 49 percent RTP due to a loss of condenser vacuum due to a solenoid valve failure for the first stage steam jet air ejector. On September 4, 2020, the unit was returned to 100 percent RTP.

On September 26, 2020, the unit was down powered to 70 percent RTP for sequence exchange and quarterly turbine testing. On September 27, the unit returned to 96 percent RTP and then down powered to 84 percent RTP due to 1A condensate pump being secured due to the high temperature on the lower guide bearing. On September 28, 2020, the unit was returned to 100 percent RTP and operated there for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent RTP. On July 19, 2020, the unit was down powered to 68 percent RTP for sequence exchange and quarterly turbine testing. On July 20, 2020, the unit was returned to 100 percent RTP. On August 29, 2020, the unit was down powered to 70 percent RTP for increased testing of turbine valves. On August 30, 2020, the unit was returned to 100 percent RTP and operated there for the remainder of the inspection period.

INSPECTION SCOPES

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

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

The inspections documented below met the objectives and requirements for completion of the IP.

71111.01 - Adverse Weather Protection

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

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

(1) Alignment of Unit 2 A Core Spray System following monthly surveillance. 34SO-E21-001-2, Ver 26.5 on July 9, 2020.

(2) Alignment of Unit 2 Residual Heat Removal (RHR) System following the replacement of 2A RHR Service Water Pump, 34SO-E11-010-2, Residual Heat removal System, Version 44.2. on July 14, 2020.

(3) Alignment of Unit 2 Stand-by Gas Treatment (SBGT) System following the 'A' Train system outage. 34SO-T46-001-2, Version 15.3 on August 04, 2020.

(4) Alignment of Unit 2 'A' Stand-by Liquid Control (SLC) System while 'B' Train was inoperative for Testing. 34SO-C41-003-2, Version 12.6 on September 10, 2020.

(5) Alignment of Unit 1 Plant Service Water Division I System following monthly surveillance. 34SO-P41-001-1, Ver. 36.18 on September 29, 2020.

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) Alignment of Unit 2 Core Spray 'A' following System Outage. 34SO-E21-001-2, Ver 26.5 on August 18, 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) Unit 2 SE RHR and Core Spray Room, Drawing A-43965 Sheet 101 on July 9, 2020.

(2) Unit 2 High Pressure Coolant Injection (HPCI) Pump Room, Drawing A-43965 Sheet 103 on July 22, 2020.

(3) Unit 2 Chiller Room, Drawing A-43965 Sheet 112 on August 14, 2020.

(4) Unit 1/2 Refueling Floor, Drawing A-43965 Sheets 074 and 123 on August 28, 2020.

(5) Unit 2 Reactor Core Isolation Cooling (RCIC) Pump and Turbine Room, Drawing A-

===43965 Sheet 100 on September 4, 2020.

(6) Unit 1 Standby Gas Treatment Reactor Building, Drawing A-43965 Sheets 65 and 66 on September 24, 2020.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) ===

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 2, Northeast and Southeast Reactor Building Diagonals on July 28, 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 Unit 2 performance of 1 'B" Emergency Diesel Generator monthly operability surveillance, Unit 1 performance of 'C' Emergency Diesel Generator monthly Operability, Unit 2 Performance of RCIC pump operability surveillance, and Unit 1 Performance of HPCI Pump In-Service test on August 14, 2020, September 10, 2020, September 15, 2020, and September 16, 2020.

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

(1) The inspectors observed and evaluated licensed operator requalification program (LORP) Scenario H-LT-SE-51071, Toxic Gas Leak with Loss of High Pressure Feedwater and Emergency Depressurization on August 13, 2020.

71111.12 - Maintenance Effectiveness

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following Structures, Systems and Components that did not meet their inspection or test acceptance criteria:

(1) CR 10730343, 2D Residual Heat Removal Service Water (RHRSW) Pump Failed Inservice Testing (IST) Surveillance-Outlet Pressure on August 18, 2020.

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 elevated risk due to the Residual Heat Removal (RHR) 2A Loop System Outage on August 04, 2020.

(2) Unit 1 elevated risk due to the 'A' Residual Heat Removal Service Water Pump inoperable, CR 10727466 on August 6, 2020.

(3) Unit 1 elevated risk due to Recirculation Runback to less than 80% Rated Thermal Power, CR 10731674 on August 21, 2020.

(4) Unit 1 elevated risk due to the repairs of the Residual Heat Removal Service Water to Residual Heat Removal System crosstie on September 2, 2020.

(5) Unit 1 elevated risk due to the repairs of the underground leak of the Division 1 Residual Heat Removal Service Water piping, CR10740146 on September 22, 2020.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) CR 10718656 2B RHRSW Pump inoperable due to unsatisfactory d/p ratio on July 2, 2020.

(2) CR 10724112 1D RHRSW Pump inoperable due to unsatisfactory d/p ratio on July 24, 2020.

(3) CR 10728469 2 'A' Emergency Diesel Generator Trip during 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run on August 7, 2020.

(4) CR 10720736 Hydraulic Control Unit 06-23 accumulator seal degradation on August 17, 2020.

(5) CR 10730997 Results from sample drawn from 1B Core Spray Valve, 1E21F005B, leakage indicates reactor coolant on August 18, 2020.

(6) CR 10740146, underground leak of the Division 1 Residual Heat Removal Service Water piping on September 24, 2020.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)

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

(1) Work Order SNC1106057, Functional Test following the replacement of Unit 2 Reactor Protection System power supply transformer and control module on July 10, 2020.

(2) 34SV-E11-004-2, Residual Heat Removal Service Water (RHRSW) Pump Operability, Version 17.2 following the replacement of 2A RHRSW pump on July 13, 2020.

(3) 57SV-C51-006-0, Rod Block Monitor Calibration, Version 2.10, following the replacement of the Central Processing Unit and Analog I/O Modules. Work Orders SNC1108396 and SNC1109078 on July 23, 2020.

(4) 52IT-MEL-003-0, High Potential and Megger Testing of Electrical Equipment and Cables, Version 19.1, following the Unit 2 "B" loop Residual Heat Removal Outage.

Work Orders SNC906373 and SNC800737 on August 5, 2020.

(5) 34SV-R43-001-2, Diesel Generator 2 'A' Monthly Operability Test following trip during 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run on August 7, 2020. Work Orders SNC1030111 and SNC1041216.

(6) 34SV-E11-004-2, Residual Heat Removal Service Water Pump Operability, Version 17.2 following flushing of flow instrumentation lines on August 24, 2020.

(7) 52SV-X43-002-1, Diesel-driven Fire Pump Inspection, Version 14.6 following replacement of over-speed switch and fuel pump solenoid 1 'B' Diesel Fire Pump on August 26, 2020.

(8) Work Order SNC 1118883, Liquid Penetrant Test of the RHRSW piping following the repairs of the underground pipe leak on September 24, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 34SV-R43-001-2, Diesel Generator 2A Monthly Test on July 10, 2020.

(2) 34SV-P41-001-1, Plant Service Water Pump Operability, Version 15.0 on July 08, 2020

Inservice Testing (IP Section 03.01) (2 Samples)

(1) 34SV-E11-004-1, Residual Heat Removal Service Water Pump Operability, Version 21.1 on July 22, 2020.

(2) 34SV-R43-004-2, Diesel Generator 2A Semi-annual Test, Version 18.2 on September 03, 2020.

71114.06 - Drill Evaluation

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

The inspectors evaluated:

(1) LORP Scenarios H-LT-SG-QS004, Loss of Essential Busses, and H-LT-SG-50464, Loss of 600V Bus, 2D Plant Service Water Strainer Clogging and a loss of coolant accident dated 9/16/2020.

OTHER ACTIVITIES - BASELINE

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

MS06: Emergency AC Power Systems (IP Section 02.05) ===

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (July 1, 2019 - June 30, 2020)

(2) Unit 2 (July 1, 2019 - June 30, 2020)

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

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

(1) CR 10720874 2C Emergency Diesel Generator fuel oil room fan continued to run after placing switch to off and opened breaker to deenergize fan due to Fire Hazard Analysis concerns on July 8, 2020..

(2) Operator Work Arounds, OS-BP-001, Operations Performance Ind., Ver. 4.6 on August 26,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)

Revision 0 of this Temporary Instruction (TI) was previously inspected, and closed, in Inspection Report 2019014 (ML19351E202). However, a subsequent revision to the Nuclear Energy Institute (NEI) Voluntary Initiative (Revision 3) provided licensees the option to leave the open phase protection (OPP) system in monitoring mode only in lieu of activating the automatic trip circuitry, provided it was supported by a risk evaluation. Revision 1 (and later Revision 2) of this TI was issued to provide inspection guidance for the new option.

The inspectors remotely reviewed licensee analyses and procedures that demonstrated operator manual actions would successfully mitigate the impact of an Open Phase Condition (OPC). The inspectors completed Section 03.01c of TI 2515/194, Revision 2.

The inspectors verified that modeling used for the OPC reflected the as-designed and as-built plant, assumptions made by the licensee were reasonable, and licensee procedures were adequate to respond to an OPC. The inspectors also verified that human reliability analysis and recovery evaluations were done in accordance with NEI and voluntary initiative guidance.

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

(1) The inspectors evaluated the licensees activities related to long-term operation and monitoring of their independent spent fuel storage installation on July 27,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On October 29, 2020, the inspectors presented the integrated inspection results to Mr.

Johnny Weissinger and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

2515/194 Calculations PRA-BC-H-19- Hatch Open Phase Risk Evaluation Version 1

004

2515/194 Procedures 34AB-R22-002-1 Loss Of 4160V Emergency Bus Version 2.2

2515/194 Procedures 34AB-R22-002-2 Loss Of 4160V Emergency Bus Version 2.1

2515/194 Procedures 34SO-S11-001-1 Unit 1 Transformers (1S11) and Open Phase Protection Version 4.0

(OPP) System Operation

2515/194 Procedures 34SO-S11-001-2 Unit 2 Transformers and Open Phase Protection System Version 4.3

Operation

60855.1 Procedures 52GM-F18-126-0 HI-TRAC Annual Inspection and Maintenance Version 1.0

60855.1 Procedures 52SV-F18-100-0 MPC Integrity - Loading Version 3.1

60855.1 Procedures 52SV-F18-104-0 HI-TRAC Contamination Survey Version 2.3

71111.01 Miscellaneous Hatch Nuclear Plant, Final Safety Analysis Reports Updates, Version 19

Chapter 2

71111.01 Procedures 34AR-650-206-2S Plant Service Water Valve Pit Sumps Level High Version 1

71111.01 Procedures NMP-OS-017 Severe Weather Version 3

71111.04 Drawings H-26009 Standby Liquid Control System P&ID Version 8

71111.04 Drawings H-26018 Core Spray System P&ID Version 10

71111.04 Drawings HL-26078 Standby Gas Treatment System P&ID Version 8

71111.04 Procedures 34SO-C41-003-2 Standby Liquid Control System Version 12.6

71111.04 Procedures 34SO-E21-001-2 Core Spray System Version 26.5

71111.04 Procedures 34SO-P41-001-1 Plant Service Water System Version

36.18

71111.04 Procedures 34SO-T46-001-2 Stand-by Gas Treatment System Version 15.3

71111.05 Drawings A-43965 Sheet Unit 2 RCIC Pump and Turbine Room Version 3.0

100

71111.05 Drawings A-43965 Sheet Unit 2 SE RHR and Core Spray Room Version 3.0

101

71111.05 Drawings A-43965 Sheet Unit 2 HPCI Pump Room Version 4.0

103

71111.05 Drawings A-43965 Sheet Unit 2 Chiller Room Version 2.0

2

71111.05 Drawings A-43965 Sheets Unit 1/2 Refueling Floor Version 3.0

Inspection Type Designation Description or Title Revision or

Procedure Date

074 and 123

71111.05 Drawings A-43965 Sheets Unit 1 Standby Gas Treatment Reactor Building Version 2.0

and 66

71111.05 Miscellaneous Fire Protection Fire Hazards Analysis (FHA) Version 36.0

71111.06 Calculations H-RIE-IF-U00- Hatch Internal Flood Notebook - Tasks 1, 2, and 3 Version 1

001

71111.06 Procedures 34SO-G11-013-2 Drywell and Reactor Building Sump Systems Version 1.4

71111.06 Procedures 57IT-T45-002-2 Sump Isolation Valve Actuation Test Version 0.3

71111.11Q Miscellaneous H-LT-SE-51071, LORP Scenario Toxic Gas Leak with Loss of High Pressure 08/13/2020

Feedwater and Emergency Depressurization.

71111.11Q Procedures 34SV-E41-002-1 HPCI Pump Operability Version 33.1

71111.11Q Procedures 34SV-E51-002-2 RCIC Pump Operability Version 27.0

71111.11Q Procedures 34SV-R43-002-2 Diesel Generator 1B Monthly Test Version 26.3

71111.11Q Procedures 34SV-R43-003-1 Diesel Generator 1C Monthly Test Version 20.1

71111.12 Corrective Action CR 107303432 2D RHRSW Pump Failed IST Surveillance-Outlet Pressure - 08/18/2020

Documents 343 psig (required minimum 341 psig)

71111.12 Procedures 50AC-MNT-001-0 Maintenance Program Version 35.0

71111.12 Procedures NMP-ES-027 Maintenance Rule Program Version 9.0

71111.13 Calculations Equipment Out of Service Calculations August 04,

20

71111.13 Calculations Equipment Out of Service Calculations 08/04/2020

71111.13 Calculations Equipment Out of Service Calculations 08/06/2020

71111.13 Calculations Equipment Out of Service Calculations 08/21/2020

71111.13 Calculations Equipment Out of Service Calculations 09/02/2020

71111.13 Calculations Equipment Out of Service Calculations 09/22/2020

71111.13 Corrective Action CR 10727466 Unit 1 'A' Residual Heat Removal Service Water Pump

Documents inoperable

71111.13 Corrective Action CR 10731674 Unit 1 Recirculation Runback to less than 80% Rated

Documents Thermal Power

71111.13 Corrective Action CR 10740146 Unit 1 underground leak of the Division 1 Residual Heat

Documents Removal Service Water piping

71111.13 Procedures NMP-DP-001 Operational Risk Awareness Version 16.0

71111.13 Procedures NMP-OS-010-002 Hatch Protected Equipment Logs Version 11.0

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Operability CR 10718656 2B RHRSW Pump inoperable due to unsatisfactory D/P ratio 07/02/2020

Evaluations

71111.15 Operability CR 10720736 Hydraulic Control Unit 06-23 accumulator seal degradation 08/07/2020

Evaluations

71111.15 Operability CR 10724112 1D RHRSW Pump inoperable due to unsatisfactory D/P ratio 07/24/2020

Evaluations

71111.15 Operability CR 10728469 2 'A' Emergency Diesel Generator Trip during 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run. 08/17/2020

Evaluations

71111.15 Operability CR 10730997 Results from sample drawn from 1B Core Spray Valve, 08/18/2020

Evaluations 1E21F005B, leakage indicates reactor coolant

71111.15 Operability CR 10740146 Underground leak of the Division 1 Residual Heat Removal 08/24/2020

Evaluations Service Water piping

71111.15 Procedures NMP-AD-012 Operability Determinations and Functionality Assessments Version 3.0

71111.19 Procedures 34SV-E11-004-2 Residual Heat Removal Service Water (RHRSW) Pump Version 17.2

Operability

71111.19 Procedures 34SV-E11-004-2 Residual Heat Removal Service Water Pump Operability Version 17.2

71111.19 Procedures 34SV-R43-001-2 Diesel Generator 2 'A' Monthly Operability Test Version 29.2

71111.19 Procedures 52IT-MEL-003-0 High Potential and Megger Testing of Electrical Equipment Version 19.1

and Cables

71111.19 Procedures 52SV-X43-002-1 Diesel-driven Fire Pump Inspection Version 14.6

71111.19 Procedures 57SV-C51-006-0 Rod Block Monitor Calibration Version 2.10

71111.19 Procedures NMP-MA-014 Post Maintenance Testing/Post Modification Testing Version 2.1

71111.19 Procedures NMP-MA-014-001 Post Maintenance Testing Guidance Version 5.2

71111.19 Work Orders SNC 1118883 Liquid Penetrant Test of the RHRSW piping following the 09/24/2020

repairs of the underground pipe leak

71111.19 Work Orders SNC1106057 Functional Test following the replacement of Unit 2 Reactor 07/10/2020

Protection System power supply transformer and control

module.

71111.19 Work Orders SNC1114562 1B Diesel Fire Pump over-speed switch and fuel pump August 26,

solenoid replacement 2020

71111.22 Procedures 34SV-E11-004-1 Residual Heat Removal Service Water Pump Operability Version 21.1

71111.22 Procedures 34SV-P41-001-1 Plant Service Water Pump Operability Version 15

71111.22 Procedures 34SV-R43-001-2 Diesel Generator 2A Monthly Test Version 29.2

71111.22 Procedures 34SV-R43-004-2 Diesel Generator 2A Semi-annual Test Version 18.2

Inspection Type Designation Description or Title Revision or

Procedure Date

71114.06 Miscellaneous H-LT-SG-QS004 LORP Scenario Loss of Essential Busses 09/16/2020

71114.06 Miscellaneous H-LT-SG-50464 LORP Scenario Loss of 600V Bus, 2D PSW Strainer 09/16/2020

Clogging and a LOCA

71114.06 Procedures NMP-EP-141 Event Classification Version 1.0

71114.06 Procedures NMP-EP-142 Emergency Notification Version 1.0

71151 Miscellaneous NEI 99-02 Regulatory Assessment Performance Indicator Guideline Revision 7

71152 Corrective Action CR 10720874 2C Emergency Diesel Generator fuel oil room fan continues

Documents to run after placing switch to off.

71152 Miscellaneous Fire Protection Fire Hazards Analysis (FHA) 36.0

71152 Procedures OS-BP-001 Operations Performance Indicators Version 4.6

13