IR 05000321/2020004

Integrated Inspection Report 05000321/2020004 and 05000366/2020004 and Independent Spent Fuel Storage Installation Report 07200036/2020003

ML21041A073
Person / Time
Site:	Hatch, 07200036
Issue date:	02/10/2021
From:	Alan Blamey Division Reactor Projects II
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2020003, IR 2020004
Download: ML21041A073 (23)

Text

February 10, 2021

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000321/2020004 AND 05000366/2020004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200036/2020003

Dear Ms. Gayheart:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant. On January 25, 2021, the NRC inspectors discussed the results of this inspection with 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, 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:

05000321/2020004, 05000366/2020004 and 07200036/2020003

Enterprise Identifier: I-2020-004-0043 and I-2020-003-0076

Licensee:

Southern Nuclear Operating Co., Inc.

Facility:

Edwin I. Hatch Nuclear Plant

Location:

Baxley, GA

Inspection Dates:

October 01, 2020 to December 31, 2020

Inspectors:

B. Caballero, Senior Operations Engineer

C. Dykes, Senior Health Physicist

C. Fontana, Emergency Preparedness Inspector

J. Hickman, Resident Inspector

M. Kennard, Sr. Operations Engineer

D. Lanyi, Senior Operations Engineer

N. Peterka, Fuel Facility Inspector

W. Pursley, Health Physicist

A. Rosebrook, Senior Reactor Analyst

S. Sanchez, Senior Emergency Preparedness Inspector

S. Sandal, Senior Reactor Analyst

R. Smith, Senior Resident Inspector

N. Staples, Senior Project Engineer

J. Walker, Emergency Response Inspector

Approved By:

Alan J. Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

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 October 30, 2020, the unit was down powered to 50 percent RTP due to removing the 1A Circulating Water Pump (CWP) from service due to motor bearing issue. On October 30, 2020, the unit increased in power to 63 percent RTP until repairs were completed to the 1A CWP. On November 6, 2020, the unit was returned to 100 percent RTP. On December 19, 2020, the unit was down powered to 90 percent RTP for turbine bypass valve testing. On December 19, 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 October 17, 2020, the unit was down powered to 70 percent RTP for sequence exchange and quarterly turbine testing. On October 18, 2020, the unit was returned to 98 percent RTP due to issues with computer hard drive associated with feedwater uncertainty recapture. On October 24, 2020, the unit was returned to 100 percent RTP after issues with the computer hard drive were resolved. On November 2, 2020, the unit was down powered to 88.5 percent RTP for a rod pattern adjustment and on November 2, 2020, it was return to 100 percent RTP. On November 12, 2020, the unit was down powered to 82.5 percent RTP for a rod pattern adjustment and on November 12, 2020, it was return to 100 percent RTP. On November 22, 2020, the unit was down powered to 87.5 percent RTP for a rod pattern adjustment and on November 22, 2020, it was return to 100 percent RTP. On December 5, 2020, the unit down powered to 70 percent RTP for turbine valve testing and on December 5, 2020, the unit was returned to 100 percent RTP. On December 9, 2020, the unit reached maximum core flow and began the coast down in power for the 2021, spring refueling outage.

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 Disease 2019 (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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; 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 portions 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 below freezing temperatures for the following systems on December 1, 2020:

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 severe weather during a Tornado Watch on April 23, 2020.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

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

(1) Alignment of the 1E, 1F, and 1G switchgear during the 1B Emergency Diesel Generator (EDG) outage, using 34SO-R22-00-1, 4160 VAC System Attachment 1, 34SO-R43-001-1, Diesel Generator Standby AC System Attachment 2, and 34SV-SUV-013-1, Breaker Alignment Checks Attachments 2 and 3, on October 19 and 21, 2020.

(2) Alignment of Unit 2 Residual Heat Removal (RHR) System following the 2B RHR maintenance outage, 34SO-E11-010-2, Residual Heat Removal System, Version 44.2 on December 21 and 23, 2020.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 Standby Gas and Heating Ventilation Air Conditioning (HVAC), Drawing A-

===43965 Sheets 115, 118, and 119 on October 9, 2020.

(2) Unit 1 and Unit 2 Intake Structure, Drawing A-43966 Sheet 027 on November 24, 2020.

(3) Unit 1 Railroad Airlock, Drawing A-43966 Sheet 41 on December 18, 2020.

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

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill on October 14, 2020.

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Safety related cable vaults PB1-DO, and PB1-DP,

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

On November 12, 2020, the licensee completed the annual requalification operating test, which is required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), Requalification Requirements, of the NRCs Operators Licenses. On November 20, 2020, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP

===71111.11.

(1) On November 20, 2020, the inspector reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating test administration completed on November 12, 2020.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Program (IP Section 03.04)===

(1) Biennial Requalification Written Examinations

The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered in December 2019.

Annual Requalification Operating Tests

The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test

The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security

The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.

Remedial Training and Re-examinations

The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.

Operator License Conditions

The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.

Control Room Simulator

The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution

The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.

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 sequence exchange, deep control rod exercises and scram time testing on October 17, 2020.

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

(1) The inspectors observed and evaluated License Operator Requalification Program (LORP) Scenario H-LTC-SE-00306, "Station Service Air Compressor Trip, Recirculation Pump Trip, Reactor Feed Pump Turbine High Vibration, Lost of Second Recirculation Pump, Anticipated Transient Without a Scram (ATWS), and Generator Output Breakers Failed to Auto Open," for two teams during annual simulator evaluations on October 28, 2020.

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 (SSCs) remain capable of performing their intended function:

(1) Review of the Hatch Living a(3) Documentation Package with emphasis on Primary Containment penetration failure on January 4, 2020.

(2) Unit 1 and Unit 2 Emergency Diesel Generator Fuel Oil Transfer System water intrusion issues on November 20, 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) Unit 2 elevated risk due to the Reactor Core Isolation Cooling (RCIC) System Outage on October 7, 2020.

(2) Unit 1 and Unit 2 elevated risk due to the liner replacement on 1B EDG on October 20, 2020.

(3) Unit 1 elevated risk due to the liner replacement on 1C Emergency Diesel Generator on December 3, 2020.

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) Unit 1 water intrusion into terminal box of 'B' fuel oil transfer pump on 1B EDG on October 14, 2020.

(2) Unit 1 'B' Plant Service Water (PSW) Pump inoperable due to low In-Service Test (IST) differential pressure ratio on October 30, 2020.

(3) Unit 1 'B' Reactor Protection System (RPS) output breaker 52-3B failure to trip during function testing on November 12, 2020.

(4) Unit 1 'A' Plant Service Water pump differential pressure (DP) in the required action range on November 12, 2020.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

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

(1)34SO-E51-001-2, RCIC Pump Discharge Line Venting, Version 28.2, following Unit 2 RCIC system outage on October 7, 2020.

(2)52SV-R43-001-0, Diesel, Alternator, and Accessories Inspection, Version 31.16, following the liner replacement on 1B EDG on October 22, 2020.

(3) Work Order (WO) SNC814149 1C Residuals Heat Removal Service Water (RHRSW)

Pump Functional Test following the internal inspection of check-valve 1E11F005C on October 28, 2020.

(4) Work Orders SNC631596 and SNC929660 for 2B Reactor Protection System (RPS)one-year preventive maintenance including inspections, lubrication and functional testing and calibration of the power monitoring breakers, on November 10, 2020.

(5) Work Orders SNC1063991 and SNC1092799 for 1D Residual Heat Removal Service Water pump and check valve replacement functional testing on November 23, 2020.

(6)52SV-R43-001-0, Diesel, Alternator, and Accessories Inspection, Version 31.19, following the liner replacement on 1C EDG on December 9, 2020.

(7)34SV-R43-006-1, Diesel Generator 1C Semi-annual Test, Version 15.1, following the liner replacement on 1C EDG on December 10, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) RCIC 2-E51-F012 Motor Operated Valve Acceptance Testing, Work Order SNC842422 on October 6, 2020.

Inservice Testing (IP Section 03.01) (1 Sample)

(1)34SV-E51-002-1, RCIC Pump Operability, Version 28.8 (IST, Operating Pressure Test) on October 2, 2020.

FLEX Testing (IP Section 03.02) (1 Sample)

(1) Work Order SNC947907, FLEX PM: FLEX Pump Hose Trailer Hose Inspection & Refold, on December 8, 2020.

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the maintenance and testing of the alert and notification system during the week of November 2, 2020.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the Emergency Response Organization during the week of November 2, 2020.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors evaluated submitted Emergency Action Level, Emergency Plan, and Emergency Plan Implementing Procedure changes during the week of November 2, 2020. This evaluation does not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program during the week of November 2, 2020.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) Emergency Preparedness Drill 20EX06, Seismic event with a loss of all offsite and onsite AC Power on October 28,

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (4 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Unit 1 Reactor building ventilation stack monitor.

(2) Plant Main Stack Radiation Monitors.

(3) Liquid Radwaste Monitor.

(4) Unit 2 Reactor building ventilation stack monitor.

Sampling and Analysis (IP Section 03.02) (3 Samples)

(1) Inspectors evaluated compensatory sampling on the Unit 2 Reactor building ventilation stack monitor.

(2) Inspectors evaluated effluent particulate and iodine sampling on the main plant stack monitor.

(3) Inspectors evaluated tritium sampling methodology on the Unit 2 Reactor building ventilation stack monitor.

Dose Calculations (IP Section 03.03) (2 Samples)

The inspectors evaluated the following dose calculations:

(1)64CH-RPT-006-0 Liquid Effluents Discharge Permit WSTA-1 L-20191225-624-B, 12/24/2019.

64CH-RPT-006-0 Liquid Effluents Discharge Permit L-20191219-606-C, Y22-N008A, 12/20/2019.

64CH-RPT-006-0 Liquid Effluents Discharge Permit L-2018213-372-C, Y22-N008A, 12/14/2018.

64CH-RPT-006-0 Liquid Effluents Discharge Permit L-20181213-373-C, Y22-N008A, 12/20/2018.

(2)64CH-RPT-007-0 GASEOUS EFFLUENTS: DISCHARGE PERMIT PARTICULATE, IODINE AND NOBLE GAS SAMPLE INFORMATION, G-20181211-200-C, 12/13/2018.

64CH-RPT-007-0 GASEOUS EFFLUENTS: DISCHARGE PERMIT PARTICULATE, IODINE AND NOBLE GAS SAMPLE INFORMATION, G-20181218-204-C, 12/19/2018.

64CH-RPT-007-0 GASEOUS EFFLUENTS: DISCHARGE PERMIT PARTICULATE, IODINE AND NOBLE GAS SAMPLE INFORMATION, G-20191210-198-C, 12/12/2019.

64CH-RPT-007-0 GASEOUS EFFLUENTS: DISCHARGE PERMIT PARTICULATE, IODINE AND NOBLE GAS SAMPLE INFORMATION, G-20191217-202-C, 12/28/2019.

Abnormal Discharges (IP Section 03.04)

There were no abnormal discharges during the period covered by the inspection which began in May 1, 2018.

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (IP Section 02.12)===

(1) EP01: Drill & Exercise Performance for the period July 1, 2019, through June 30, 2020.

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

(1) EP02: Emergency Response Organization Drill Participation for the period July 1, 2019, through June 30, 2020.

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) EP03: Alert & Notification System Reliability for the period July 1, 2019, through June 30, 2020.

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (October 1, 2019 to September 30, 2020).

(2) Unit 2 (October 1, 2019 to September 30, 2020).

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 (July 1, 2019 to September 30, 2020).

(2) Unit 2 (July 1, 2019 to September 30, 2020).

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (October 1, 2019 to September 30, 2020).

(2) Unit 2 (October 1, 2019 to September 30, 2020).

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) Unit 1 January 1, 2019 through October 31, 2020.

Unit 2 January 1, 2019 through October 31, 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 Appendix R Emergency Lighting failures, due to high number of failures through the year that might be indicative of a more significant safety issue.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

41502 - Nuclear Power Plant Simulation Facilities Nuclear Power Plant Simulation Facilities

(1) The inspector completed inspection of the Unit 1 Plant Reference Simulator (PRS)

"B" in accordance with Inspection Procedure (IP) 41502 "Nuclear Power Plant Simulation Facilities.

This inspection reviewed a sample of activities to ensure that Simulator B was being tested in accordance with ANSI/ANS-3.5-2009, Nuclear Power Plant Simulators for Use in Operator Training and Examination and appropriate approved plant procedures.

The inspectors reviewed testing to verify that the simulator utilizes models relating to nuclear and thermal-hydraulic characteristics replicating the most recent core load from cold shutdown to rated power plant conditions. Additionally, six transient tests, two steady state tests, five malfunction tests, and one core performance test. Additionally, inspectors reviewed a sample of simulator discrepancies to ensure that they were dispositioned in accordance with appropriate approved plant procedures.

Finally, this inspection reviewed simulator physical fidelity with its reference unit to ensure that PRS "B" was sufficiently designed to allow the performance of evolution's prescribed by 10 CFR 55.45 and 55.59.

The inspector reviewed simulator operation during performance of two Initial License Training (ILT) simulator scenarios using IP 41502 criteria for evaluation of plant-reference simulators under 10 CFR 55.46(c) and (d).

No findings were identified. Results of this inspection were discussed with members of the facility staff on October 28, 2020.

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 activates related to long-term operation and monitoring of their independent spent fuel storage installation on November 6, 2020.

===92702 - Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders

Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders===

(1) On November 20, 2019, as a result of Alternative Dispute Resolution the NRC issued Confirmatory Order (CO) EA-18-130 and EA-18-171 (ML19249B552). The CO was the result of an apparent violation of 10 CFR 53.5, Employee Protection at Vogtle Units 3 & 4 which contained actions for the Farley, Hatch and Vogtle Units 1 & 2 nuclear plants. During the week of November 30,2020, the inspectors reviewed corrective actions for this CO. Because the CO was fleet wide for the Southern Nuclear Company, the corrective actions reviewed by the inspectors included a review of corrective actions for the Hatch, Farley, and Vogtle Units 1 through 4 nuclear plants. The details can be found in inspection report 0500025/20200012, 0500026/2020012; 11/30/2020 through 12/11/2020; Vogtle Unit 3 Combined License, Vogtle Unit 4 Combined License, CO Follow-Up and SCWE inspection report.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 25, 2021, the inspectors presented the integrated inspection results to Johnny Weissinger and other members of the licensee staff.

• On October 29, 2020, the inspectors presented the Licensed Operator Requalification and Simulator B inspection results to Johnny Weissinger and other members of the licensee staff.

• On November 6, 2020, the inspectors presented the Emergency Preparedness Program inspection results to Sonny Dean and other members of the licensee staff.

• On December 8, 2020, the inspectors presented the RP Baseline Inspection Exit inspection results to Sonny Dean and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

41502

Miscellaneous

NMP-TR-422-004 Att 20 Section 3.4

Criticality

Core Performance Testing - NMP-

TR-422-004 Att 20 Section 3.4

Criticality

1/22/2019

Test 503-1

Loss of Coolant - Outside Primary

Containment

2/10/2020

Test 505-2

Loss of Coolant - Small Reactor

Coolant Breaks including

Demonstration of Saturation

Condition

2/14/2019

Test 505-2

Loss of Coolant - Small Reactor

Coolant Breaks including

Demonstration of Saturation

Condition

2/14/2019

Test 521-0

Loss of Protective System Channel

2/14/2019

Test 522-1

Control Rod Failure including Stuck

Rods, Drifting Rods, Rod Drops,

and Misaligned Rods

2/10/2020

Test 527-0

Failure in Automatic Control

Systems that Affect Reactivity and

Core Heat Removal

2/10/2020

Test 604-0

Reactor Trip Followed by Recovery

to Rated Power

2/15/2019

Test 707-0

Transient Performance - Maximum

Power Ramp Recirc Down to

Approximately 75% and Back up to

100%

2/3/2020

Test 708-2

Transient Performance - Maximum

Size Reactor Coolant System

Rupture Combined with a Loss of

Off-Site Power

2/12/2019

Test: 615-1

SS Performance 35% Power

2/12/2019

Test: 704-0

Transient Performance -

2/6/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Simultaneous Trip of all

Recirculation Pumps

60855.1

Engineering

Evaluations

TE 1053015

Dry Cask Storage - 10 CFR 72.212

Report - Revision for 2020 UFLO

Radiation

Surveys

Plant Hatch Radiological

Information Survey # 179999 ISFSI

04/28/2020

Plant Hatch Radiological

Information Survey # 180018 ISFSI

04/28/2020

71111.01

Procedures

34AB-Y22-002-0

Naturally Occurring Phenomena

19.1

NMP-OS-017

1, Severe Weather

Preparation Checklist Maintenance

Section for 4/23/2020

2.0

NMP-OS-017

2, Severe Weather

Preparation Checklist Chemistry for

4/23/2020

2.0

NMP-OS-017

3, Severe Weather

Preparation Checklist Operations

for 4/23/2020

2.0

NMP-OS-017

4, Severe Weather

Checklist Technology Organization

for 4/23/3030

2.0

NMP-OS-017

5, Severe Weather

Preparation Checklist Security for

4/23/2020

2.0

NMP-OS-017

6, Severe Weather

Preparation Checklist Supply Chain

for 4/23/2020

2.0

NMP-OS-017

7, Severe Weather

Preparation Checklist Emergency

Preparedness for 4/23/2020

2.0

NMP-OS-017

Severe Weather

3.0

71111.04

Drawings

H-13350

Unit 1 Master Single Line Diagram

30.0

H-13350

Unit 1 Master Single Line Diagram

30.0

Procedures

34SO-R22-001-1

4160 VAC System

25.3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

34SO-R43-001-1

Diesel Generator Standby AC

System

29.3

34SV-SUV-013-1

Breaker Alignment Checks

10.4

71111.05

Fire Plans

Drawing A-43965 Sheets 115, 118, and 119.

Unit 2 Standby Gas and HVAC,

Miscellaneous

Fire Protection Fire Hazards

Analysis (FHA)

36.0

NMP-TR-425-F01

Fire Drill Scenario Development

and Approval Sheet for fire in

drywell

10/13/2020

Procedures

NMP-TR-425

Fire Drill Program

9.0

NMP-TR-425-F14

Fire Drill Package

1.1

71111.06

Procedures

2PM-Y46-001-0

Inground Pullbox Debris

Removal/Inspection

10.0

71111.11B

Miscellaneous

H-LTC-SE-00314

314 NRC 2

Ver 1.0

19-7A RO

2019 RO Written Exam

2/15/2019

19-7A SRO

2019 SRO Written Exam

2/15/2019

H-LCT-SE-00302

2 Pilot 2

Rev 0.1

H-LT-JP-C11-010155

Vent the Scram Header

Ver 16.5

H-LT-JP-C82-01013A

Perform Plant Operations in

Support of a Remote Plant

Shutdown (Alternate Path)

Ver 1.0

H-lT-JP-E41-00515A

Establish Reactor Cooldown with

HPCI (Alternate Path)

Ver 0.1

H-LT-JP-EAL-25068

FG1 Emergency Classification -

Complete NMP-EP-141-F01

Ver 3.1

H-LT-JP-EAL-25208

Determine PARS (SRO only)

Ver 10.1

H-LT-JP-N33-01702B

Perform TC-1, Seal Steam Failure

(Alternate Path)

Ver 0.1

H-LT-JP-R42-02744

Place the 125/250 VDC Station

Service Battery Charger in Service

Ver 19.3

H-LT-JP-SUV-10022

Conduct of Operations, 34SV-SUV-

019-1 Average Drywell

Temperature Surveillance

Ver 2.2

H-LT-JP-T48-01362A

Fast Vent the Drywell (Alternate

Ver 0.5

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Path)

H-LTC-SE-00341

341 Pilot 1

Ver 1.0

H-LTC-SE-00342

314 NRC 1

Ver 0.1

NDE Reports

H-LT-JP-R43-02824A

Locally Start U2 EDG with Air Start

and Energ Bus (Alternate Path)

Ver 1.6

71111.11Q Corrective

Action

Documents

CR10746882, 10746887, 10746968,

10747001

Miscellaneous

H-LTC-SE-00306

Station Service Air Compressor Trip

, Recirculation Pump Trip, Reactor

Feed Pump Turbine High Vibration,

Lost of Second Recirculation Pump,

Anticipated Transient Without a

Scram (ATWS), and Generator

PCBs (Output Breakers) Failed to

Auto Open

1.0

Procedures

2CC-ERP-011-0

Control Rod Exchange

15.4

NMP-OS-001

Reactivity Management Program

20.1

NMP-OS-007-001

Conduct of Operations Standards

and Expectations

17.0

NMP-RE-008-F01

Detailed Reactivity Management

Plan (Unit 2 Sequence Exchange)

2.1

71111.12

Corrective

Action

Documents

CAR 277277

Root Cause Determination Report

for PCIVs 2T28F319 and 2T48F320

05/27/2020

CR10737209

Miscellaneous

Maintenance Rule a(1) Action Plan for 2T23-0

Procedures

34SO-T48-002-2

Containment Atmospheric Control

and Dilution System

29.5

2-PM-T48-013-0

Purge and Vent Valve T-Ring

Replacement

2.6

MNP-ES-027

Maintenance Rule Program

10.2

Self-

Assessments

Hatch Living (a)(3) Documentation

Package

08/01/2018-

05/01/2020

71111.13

Calculations

Equipment Out of Service

October 20,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Calculations

20.

Equipment Out of Service

Calculations

October 7,

20.

Corrective

Action

Documents

CR 10746694

Procedures

NMP-DP-001

Operational Risk Awareness

16.0

NMP-OS-010-002

Hatch Protected Equipment Logs

11.0

71111.15

Corrective

Action

Documents

CR 10747548

CR10753268

CR10753270

Engineering

Evaluations

TE1077753

Miscellaneous

Unit 1 Technical Specifications

Amendment

294

Unit 2 Technical Specifications

Amendment

239

Procedures

34SV-P41-001-1

Plant Service Water Pump

Operability

15.2

NMP-AD-012

Operability Determinations and

Functional Assessments

13.3

NMP-AD-012-GL04

Mission Times

1.1

71111.19

NDE Reports

NMP-ES-024-515

Ultrasonic Gas/Void Examination

Report for Unit 2 RCIC

10/07/2020

Procedures

34SO-E51-001-2

RCIC Pump Discharge Line Venting 28.2

2SV-R43-001-0

Diesel, Alternator, and Accessories

Inspection

31.16

57SV-R43-001-0

Diesel, Alternator, and Accessories

Inspection

31.19

NMP-MA-014

Post Maintenance Testing/Post

Modification Testing

2.2

NMP-MA-014-001

Maintenance Testing Guidance

5.2

Work Orders

SNC 814149

Internal inspection of check-valve

1E11F005C

October 28,

20.

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SNC631596, SNC929660

11/10/2020

71111.22

Miscellaneous

NEI 12-06

Diverse and Flexible Coping

Strategies (FLEX) Implementation

Guide

Revision 4

Procedures

34SV-E51-002-1

RCIC Pump Operability

28.8

Work Orders

SNC842422

RCIC 2-E51-F012 Motor Operated

Valve Acceptance Testing

10/06/2020

71114.06

Corrective

Action

Documents

CR 10749692

Miscellaneous

Southern Nuclear Operating

Company (SNC) Standard

Emergency Plan (SEP)

1.0

SNC Standard Emergency Plan

Annex for Hatch Nuclear Plant

(HNP) Units 1 & 2

1.0

20EX06

Emergency Preparedness Drill

Guide

10/07/2020

Procedures

NMP-EP-141

Event Classification

1.0

NMP-EP-142

Emergency Notification

1.0

NMP-EP-143

Facility Activation,

1.0

71124.06

Calibration

Records

64CH-RCL-006-0

Interlaboratory Cross-Check;

Gamma Spec

08/2019

Corrective

Action

Documents

10559574, 10724533

Miscellaneous

Annual Radioactive Effluent Report

2018; 2019

Procedures

NMP-EN-002;

NMP-EN-002-GL02

Radiological Groundwater

Protection Program;

Hatch Nuclear Plant Groundwater

Monitoring Plan for Radionuclides

VERSION

9.1, 9.2;

Version 1.1

71124.07

Corrective

Action

10616583

10697831

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

10726878

10724533

Miscellaneous

Annual Radiological Environmental

Operating Report

2018; 2019

71151

Miscellaneous

NEI 99-02

Regulatory Assessment

Performance Indicator Guideline

Revision 7

Procedures

NMP-AD-029

Preparation and Reporting of

Regulatory Assessment

Performance Indicator Data and the

Monthly Operating Report

Version 1.1

71152

Corrective

Action

Documents

CR10674923,10674928,10674930,10683597,

106844712, 10691713, 10692524, 10693660,

10702308, 10702309, 10702310, 10707157,

10707157, 10708283, 10711197, 10714683,

10719206, 10721524, 10743478, 10743512,

10743517, 10743783, 10743785, 10743797,

10743800, 10743801, 10744767, 10744769,

10744792, 10745209, 10745211, 10745214,

10747562, 10683988, 10687821, 10698864,

10698867, 10698868, 10698871, 10698926,

10698928, 10698929, 10721527, 10721529,

10721530, 10721531, 10732840, 10737206,

10743805, 10744770, 10744794, 10745187

Engineering

Evaluations

TE1061317, 1062509, 1062593, 1065490,

1065491, 1066692, 1068404,

1068405,1068406,1068407, 1068407,

1070192, 1071151

Fire Plans

Edwin I. Hatch Nuclear Plant Unit 1

and 2 Fire Hazards Analysis,

Sections 4.12, 1.9.1, and IV.B5.a/b

38.0

Miscellaneous

FAS 1-20-003, 004, 005, 020, 030, 048, 068,

069, 070, 075, 079, 080, 081

Work Orders

SNC1117152, 1107322

21