IR 05000321/2021001

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Integrated Inspection Report 05000321/2021001 and 05000366/2021001
ML21126A020
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/06/2021
From: Alan Blamey
NRC/RGN-II/DRP/RPB2
To: Gayheart C
Southern Nuclear Operating Co
References
IR 2021001
Download: ML21126A020 (33)


Text

May 6, 2021

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000321/2021001 AND 05000366/2021001

Dear Ms. Gayheart:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant. On April 22, 2021, the NRC inspectors discussed the results of this inspection with Sonny Dean 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 II; the Director, Office of Enforcement; and the NRC Resident Inspector at Edwin I. Hatch Nuclear Plant.

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 License Nos. DPR-57 and NPF-5

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000321 and 05000366 License Numbers: DPR-57 and NPF-5 Report Numbers: 05000321/2021001 and 05000366/2021001 Enterprise Identifier: I-2021-001-0067 Licensee: Southern Nuclear Operating Co., Inc.

Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, GA Inspection Dates: January 01, 2021 to March 31, 2021 Inspectors: J. Hickman, Resident Inspector B. Kellner, Senior Health Physicist M. Magyar, Reactor Inspector A. Nielsen, Senior Health Physicist W. Pursley, Health Physicist D. Simpkins, Senior Technical Training Program Specialist R. Smith, Senior Resident Inspector N. Staples, Senior Project Engineer 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. A licensee-identified non-cited violation is documented in report Section: 71124.0

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 05000321/2020-001-00 LER 2020-001-00 for Edwin 71153 Closed I. Hatch Nuclear Plant Unit 1, 1A EDG Inoperable Due to Water in the Day Tank

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On January 9, 2021, the unit was down powered to 70 percent RTP to perform a sequence exchange and turbine valve testing and on January 10, 2021, the unit was returned to 100 percent RTP. On March 20, 2021, the unit was down powered to 70 percent RTP to perform a sequence exchange, scram time testing, turbine valve testing and attempted to repair a steam leak in the condenser bay and on March 21, 2021, the unit was returned to 100 percent RTP. On March 22, 2021, the unit was down powered to 93.5 percent RTP for rod pattern adjustment and was retuned to 100 percent RTP on the same day and operated there for the remainder of the inspection period.

Unit 2 began the inspection period at 91 percent RTP in its end cycle coast down for the winter refueling outage. On January 7, 2021, the unit was down powered to 70 percent RTP to remove the fourth stage feed water heaters from service, this was to achieve an increase in RTP due to removing feed water heating. On January 7, 2021, the Unit returned to 97 percent RTP and continued the end cycle coast down to the refueling outage. On February 8, 2021, the operators shut down the unit for the scheduled refueling outage. The unit was restarted on March 7, 2021 and reached approximately 100 percent RTP on March 13, 2021. On March 19, 2021, the unit was down powered to 98 percent RTP to perform the final rod pattern adjustment after startup was returned to 100 percent RTP on the same day. On March 26, 2021, the unit was down powered to 93 percent RTP due to isolation of the fourth stage B high pressure feed water heater and was returned to 100 percent RTP on March 29, 2021 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 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.

REACTOR SAFETY

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 severe weather for a tornado watch in the area on

===February 15 and 18, 2021.

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 on February 23, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

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

(1) Alignment of 2C Emergency Diesel Generator (EDG) following 34SV-R43-003-2 Diesel Generator 2C Monthly Test, 34SO-R43-001-2, Diesel Generator Standby AC System, Attachments 2 and 3, Version 30.8 on January 19, 2021.
(2) Alignment of 2B Core Spray (CS) during refueling outage, the system was relied on for Emergency Reactor Pressure Vessel inventory control on 02/10/2021.
(3) Alignment of 2A CS during refueling outage, the system was relied on for emergency reactor pressure vessel inventory control on 02/10/2021.
(4) Alignment of 1A EDG following 34SV-R43-001-1 Diesel Generator 1A Monthly Test, 34SO R43-001-1, Diesel Generator Standby AC System, Attachments 1, 2 and 3, Version 29.4, on March 11, 2021.

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 Primary Containment Purge & Inerting System on March 23, 2021.

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 1/2 Station Battery Rooms, Drawing A-43965 Sheets 011, 012, 017, and 018 on January 14, 2021.
(2) Unit 1 EDG 1C and Switchgear Room 1G, drawings A43966 Sheets 8A, 8B, 9A and 9B on January 20, 2021.
(3) Unit 2 600V Switchgear Rooms 2C and 2D Drawing A-43956 Sheets 37A and 38A, on January 27, 2021.
(4) Unit 1 Northeast Residual Heat Removal (RHR) and CS pump room, and the control rod drive (CRD) and the High Pressure Coolant Injection (HPCI) Pump room Drawing A-43965 Sheets 53A, 54A, 55A, 53B, 54B and 55B, on February 3, 2021.
(5) Unit 1 Reactor Core Isolation Cooling (RCIC) Pump and Turbine Room, and the Southeast RHR and CS pump room, Drawings A43965 Sheets 51A, 52A, 51B and 52B on February 3, 2021.
(6) Unit 1 Reactor Building (RB) 130 foot elevation including CRD Hydraulic Units, various switchgears, drawing 43965 Sheets 51A, 51B, 52A, 52A, 53A, 53B, 54A, 54B, 55A and 55B on February 2, 2021.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protection in the:

(1) Unit 2, RCIC and HPCI rooms on March 19, 2021.

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) 1A EDG associated heat exchangers: jacket water cooler, lube oil cooler and scavenger air cooler.

71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding

Activities (IP Section 03.01)

(1) The inspectors evaluated BWR Non-destructive Testing by reviewing the following examinations from February 22 - 26, 2021:
  • Ultrasonic Testing (UT)a. 2B11/2N8A, A Loop JP INSTR Nozzle to Shell, ASME Class 1 (reviewed)b. 2B11/2N8A (IR), A Loop JP INSTR Nozzle IR, ASME Class 1 (reviewed)

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 plant shutdown, they observed power decrease by reducing Reactor Recirculation Flow to minimum, inserting control rods to 20 percent RTP, followed by a Main Turbine trip, and the insertion of a Manual Reactor SCRAM to complete the shutdown. They then observed the operating crew establish a controlled cooldown rate within Technical Specification (TS) limits, for the Unit 2 Refueling Outage, on February 7 and 8, 2021.

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-50322, "Shutdown Cooling (SDC) Operation / Loss of SDC / SOER 09-1," for one team during simulator training on January 12, 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 Unit 2 Drywell Chillers system 2P64 due to unplanned trips during 2020, on March 24, 2021.
(2) Review of the Unit 1 and 2 FLEX Equipment due to Operating Experience Smart Sample 2020/01, Flex Equipment Design Control, Maintenance and Testing, on March 31, 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 elevated risk due to the HPCI system outage on January 13, 2021.
(2) Unit 1 elevated risk due RHR Loop A out of service to perform a repair on 2E11-F047A heat exchanger inlet valve, on January 27, 2021.
(3) Unit 2 elevated risk as the unit entered refueling outage 26, on February 7, 2021
(4) Unit 1 and Unit 2 evaluated risk due to the Plant Service Water (PSW) underground pipe leak and repairs which resulted in 2C EDG inoperability, on March 1, 2021.
(5) Unit 1 elevated risk due to the liner replacement on 1A EDG on March 22, 2020.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

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

(1) Unit 2 HPCI Pump inoperable due to high Comprehensive Pump Test (CPT)differential pressure ratio on January 6, 2021.
(2) Unit 2 Main Turbine Emergency Overspeed Trip Protection loss of ability to test the sensors on June 6, 2020.
(3) Unit 1 EDG 1A, scavenging air is leaking from the air receiver covers 2C and 3C due to missing gasket material on January 25, 2021.
(4) Unit 1 Scaffold Impact on SCRAM Discharge Volume Drain Isolation Line and Scaffold over High Energy Line Break (HELB) grating on February 4, 2021.
(5) Unit 2 Drywell Air Lock and Equipment Hatches Seal Grease on the Sealing Surfaces Potential Effect on Local Leak Rate Test Results, on February 12, 2021.
(6) Unit 2 EDG 2C trip during monthly testing, on March 11, 2021.
(7) Unit 2 NE Diagonal room coolers after 2T41B003A room cooler fan rotor assembly catastrophically failed, on March 15, 2021.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) SNC632608, Unit 2 Main Control Room Feedwater Controller replacement due to current controllers being obsolete.
(2) SNC1010116CCP, Unit 2, Change Power Supply Breaker Micro Versa Trip settings due to breaker coordination issues associated with National Fire Protection Association (NFPA) 805 requirements.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (10 Samples)

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

(1) 34SV-P41-001-1, Plant Service Water Operability, Version 15.2 following replacement of the 1C Plant Service Water Pump Motor, Work Order SNC556025, on January 10, 2021.
(2) 34SV-R43-001-2, Diesel Generator 2A Monthly Test, Version 29.4 following the replacement of expansion joint 2P41D002D, Work Order SNC1139786, on January 29, 2021.
(3) 34SV-R43-003-1, Diesel Generator 1C Monthly Test, Version 20.2 following repair of a lube oil leak, Work Order SNC137368, on February 5, 2021.
(4) 42SV-TET-001-2, Primary Containment Periodic Type B & C Leakage Test, Version 37.2 following the replacement of 2T48-F320 containment vent and purge valve, on February 26. 2021.
(5) 34SV-B21-011-2, Automatic Depressurization System Logic System Functional Test, Version 1.1 following safety relief valve maintenance, on February 26, 2021.
(6) NMP-ES-024, Nondestructive Examination and Certification Processes, Version 7.0 following 2C EDG Plant Service Water pipe repairs, on March 2, 2021.
(7) 57CP-C51-002-0, Intermediate Range Monitor (IRM) Detector Testing, Version 3.3 following the installation of new IRM E detector, on February 26, 2021.
(8) 42SV-C11-003-0, Control Rod SCRAM Timing, Version 11.1, following the replacement of 20 control rod drive mechanisms, on March 2, 2021.
(9) 34SO-C51-001-0, Tip System Operation and Local Power Range Monitor (LPRM)

Calibration, Version 19.4, following the replacement of three LPRM strings during the Unit 2 refueling outage, on March 10 and 16, 2021.

(10) 52SV-R43-001-0, Diesel, Alternator, and Accessories Inspection, Version 31.21, following the liner replacement on 1A EDG on March 28, 2021.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated Unit 2 refueling outage 26 activities from February 7, 2020 to March 9, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) 34SV-R43-003-1, Diesel Generator 1C Monthly Test, Ver. 20.2 on January 13, 2021.
(2) 34SV-E21-001-1, Core Spray Pump 1A Pump Operability, Version 24.2, January 26, 2021.
(3) 34SV-E11-004-1, RHR Service Water Pump Operability, Version 22.1, on February 4, 2021.
(4) 34SV-E41-010-2, HPCI Logic Function System Test, Version 1.2, on February 10, 2021 and March 5, 2021.
(5) 34SV-E51-010-2, RCIC Logic Function System Test, Version 1.5, on February 10, 2021.
(6) 34SV-R43-020-2, Diesel Generator 2A Loss of Coolant Accident/Loss of Offsite Power (LOCA/LOSP) Logic Function System Test, Version 4.0, on February 12, 2021.
(7) 34SV-T48-002-2, Suppression Chamber to Drywell Vacuum Breaker Operability And Containment Purge/Vent Valve Position Check, Version 5.8, on March 4, 2021.

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 34SV-E41-002-2, HPCI Pump Operability CPT, Version 39.1 on January 6, 2021.

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) 42SV-TET-001-0, Local leak Rate Testing (LLRT) Testing Methodology, Version 13.0, on 2E11-F016B RHR Containment Spray Outboard Isolation Valve on February 17, 2021.

FLEX Testing (IP Section 03.02) (1 Sample)

(1) SNC1060565, Mode 5 Core Cooling Pump Functional Test on January 11,

RADIATION SAFETY

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

Instructions to Workers (IP Section 03.02) (1 Sample)

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

(1)

  • RWP 21-2014, Torus Diving
  • RWP 21-2205, Vessel Disassembly/Reassembly
  • Radioactive Material Labels in the U2 Reactor Building, Refueling Floor, and Turbine Building

Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)

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

(1) Personnel and equipment released from the Radiation Controlled Area (RCA)
(2) Excavated earth released from the protected area (PA)

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

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

(1) Drywell Head Lift
(2) Reactor Head Lift
(3) Fuel Movement High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) U2 Reactor Building
(2) Turbine Building Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (RWP) (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensees radiological work planning for the following:

(1) ALARA Plan for RWP 21-2205, U2 Reactor Disassembly/Reassembly
(2) ALARA Plan for RWP 20-1602, Repair 1E11F050A
(3) ALARA Plan for RWP 20-1620, U1 Drywell Scaffolding Work
(4) 2021 Annual Site ALARA Goal Estimate Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)

The inspectors reviewed the following as low as reasonably achievable evaluations of radiological outcomes:

(1) RWP 20-1620 Post Job Review - Drywell/Steam Chase Install/Remove-Shielding, Tents & Scaffolds & Support Activities
(2) RWP 20-1205 Post Job Review - Refuel Floor Vessel Disassembly/Reassembly, Cavity/Dryer Separator Work & Support
(3) Unit One H1R29 Outage ALARA Summary Report
(4) 2019 Plant Hatch Annual ALARA Report

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls for the following work activities:

(1) RWP 21-2014, Torus Diving
(2) RWP 21-2205, Vessel Disassembly/Reassembly
(3) RWP 21-2608, CRD Exchange

Radiation Worker Performance (IP Section 03.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance during:

(1) Torus Diving Vessel Disassembly/Reassembly CRD Exchange

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) Main Control Room Habitability Filter Train

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

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

(1) HEPA filtration systems used on the refuel floor

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

(1) Observed use of powered air-purifying respirators during drywell head lift Self-Contained Breathing Apparatus (SCBA) for Emergency Use (IP Section 03.04) (1 Sample)
(1) Observed storage of SCBA designated for emergency use and discussed preventative maintenance with licensee technicians. Reviewed breathing air testing records.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01)

The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02)

The inspectors evaluated licensee's external dosimetry program

Internal Dosimetry (IP Section 03.03) (3 Samples)

The inspectors evaluated the internal dosimetry program implementation as follows:

(1) In-vivo analysis results for worker ID#22939 Dated 02/27/2019.
(2) Reviewed licensee position paper for exemption from in-vitro urinalysis in cases where tritium concentrations in the water in the torus is below 1E-2 microcuries per milliliter.
(3) In-vivo analysis results for worker ID#19564 Dated 06/21/2020.

Special Dosimetric Situations (IP Section 03.04) (3 Samples)

The inspectors evaluated the following special dosimetric situation:

(1) Licensees records for two declared pregnant workers.
(2) Licensees implementation of extremity monitoring for "under vessel" work for two workers.
(3) Licensees implementation of requirements for monitoring EDE with multiple dosimeters during diving activities in the unit 2 spent fuel storage area for two workers.

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (7 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Portable survey instruments (ion chamber, friskers, telepoles) ready for use located at the RP counting lab.
(2) Tennelec and Sodium Iodide (NaI) scaler low background counter located at the RP counting lab.
(3) Argos-5AB and Gem-5 personnel contamination monitors located at the main radiologically controlled area exit and the protected area exit.
(4) Gamma spectroscopy units located in the Chemistry counting room.
(5) Whole body counting system located in the dosimetry office.
(6) SAM-12 small article monitors located at the RCA exit.
(7) Area Radiation Monitors (ARMs) located in various areas throughout the RCA.

Calibration and Testing Program (IP Section 03.02) (11 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Serial Number (S/N) 322210, MPL #: D21-N1960, Ludlum Model 2200 Scaler with NaI detector, 12/2/2020
(2) S/N 268, MPL #: D21-N1931, Thermo-Eberline SAM-12, 12/12/2021
(3) S/N 718A, MPL #: D21-N1487, Thermo-Eberline Model RM-25 countrate meter, 5/10/2019
(4) S/N 706, MPL #: D21-N1514, Thermo-Eberline Model RM-25 countrate meter, 6/3/2019
(5) S/N 1483/725680, MPL #: D21-N1646, Thermo-Eberline Model ASP-2E with NRD HD neutron detector, 11/3/2019 and 12/9/2020
(6) S/N 3569, MPL #: D21-N1633, Bicron Electra 1B/AP5BD alpha countrate meter, 1/17/2018 and 2/18/2019
(7) S/N 7108, MPL #: D21-N180, Eberline Model E-120 countrate meter, 12/2/2019 and 12/4/2020
(8) S/N 709, MPL #: D21-N1137, Eberline Model RO-20 Ion Chamber, 7/2/2020
(9) S/N 5681, MPL #: D21-N1733, Eberline Model RO-20 Ion Chamber, 7/2/2020
(10) S/N 42123-2, MPL #: D21-N1380, automatic Tennelec low background counter, 7/1/2020
(11) S/N 1301-003, MPL #: D21-N1905, Canberra ARGOS-5AB personnel contamination monitor, 11/24/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Work Order (W/O) SNC968111, Unit 1 Drywell High Range Radiation Monitors 1D11-K621A & B Calibration [24 month calibration - electronics only], 03/12/2020
(2) W/O SNC821119, Unit 1 Drywell High Range Radiation Monitors 1D11-K621A & B Calibration [24 month calibration - electronics only], 09/27/2017
(3) W/O SNC1014242, Unit 2 Reactor Building Vent Stack D11-K636A, repair and perform Functional Test and Calibration, 4/27/2019

71124.07 - Radiological Environmental Monitoring Program

GPI Implementation (IP Section 03.03) (1 Partial)

(1) (Partial)

The inspectors evaluated a reported leak of tritium from the unit two condensate storage tank pump moat.

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 (January 1, 2020 to December 31, 2020)
(2) Unit 2 (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 (January 1, 2020 to December 31, 2020)
(2) Unit 2 (January 1, 2020 to December 31, 2020)

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

(1) Unit 1 (January 1, 2020 to December 31, 2020)
(2) Unit 2 (January 1, 2020 to December 31, 2020)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 03.15) (1 Sample)

(1) January 1, 2020 through January 31, 2021 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 03.16) (1 Sample)
(1) November 30, 2020 through January 31, 2021

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) Root Cause Determination Report 278526, Unplanned Power Changes Performance Indicator Low Margin Hatch Unit 1 during 2020, was reviewed by inspectors, on March 15, 2020.

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 05000321/2020-001-00, 1A EDG Inoperable due to water in day tank (ADAMS Accession No. ML20345A083) on December 10, 2020. The inspection conclusions associated with this LER are documented in Inspection Report 05000321/2020002 under Inspection Results Section

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71124.07 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 a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: 10CFR20 1406(c) requires in part, that licensees, to the extent practical, conduct operations to minimize the introduction of residual radioactivity into the site, including the subsurface. Contrary to this requirement, on February 1, 2021, as the result of the licensee's failure to perform, to the extent practical, maintenance activities on the unit two condensate storage tank transfer pump moat to minimize the introduction of residual radioactivity to the site subsurface, leakage of elevated tritium activity from the moat was detected in an adjacent ground water monitoring well.

Significance/Severity: Green.

Corrective Action References: CR

EXIT MEETINGS AND DEBRIEFS

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

  • On April 22, 2021, the inspectors presented the integrated inspection results to Sonny Dean and other members of the licensee staff.
  • On February 26, 2021, the inspectors presented the ISI Baseline Inspection and HP Occupational Baseline Inspection results to Sonny Dean, Site VP and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Calculations SCNH-13-020 Hatch Probable Maximum Flood Hydraulics - Severe 1.0

Accident Management (SAM) for Fukushima Near-Term

Task Force (NTTF) Recommendation 2.1 Flooding

Reevaluation

71111.01 Calculations SCNH-13-021 Evaluation of Plant Hatch Local Intense Precipitation - 1.0

Severe Accident Management (SAM) for Fukushima

Near- Term Task Force (NTTF) Recommendation 2.1

Flooding Evaluation

71111.01 Corrective Action 10776017 02/18/2021

Documents

Resulting from

Inspection

71111.01 Miscellaneous HNP-2-FSAR-2 Hatch Nuclear Plant, Final Safety Analysis Reports 35

Updates, Chapter 2

71111.01 Miscellaneous Natural Weather Tornado Watch 02/15/2021

Service Watch,

Warning & Advisories

71111.01 Procedures 34AB-Y22-002-0 Naturally Occurring Phenomena 19.2

71111.01 Procedures 34AR-650-206-2 Plant Service Water Valve Pit Sumps Level High 1.2

71111.01 Procedures NMP-OS-017 Severe Weather Attachments 1 through 8 02/15/2021

71111.01 Procedures NMP-OS-017 Severe Weather Attachments 1 through 9 02/18/2021

71111.01 Procedures NMP-OS-017 Severe Weather 3.0

71111.04 Corrective Action 10773366 02/10/2021

Documents

Resulting from

Inspection

71111.04 Corrective Action 10784664 03/23/2021

Documents

Resulting from

Inspection

71111.04 Drawings H-26018 Unit 2 Core Spray System P&ID 40.0

71111.04 Drawings H-26083 Hatch Unit 2 Nitrogen Inerting System P&ID 45.0

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings H-26084 Hatch Nuclear Plant Unit 2 Primary Containment Purge 42.0

and Inerting System P&ID

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

71111.04 Procedures 34SO-R43-001-1 Diesel Generator Standby System 29.2

71111.04 Procedures 34SO-R43-001-2 Diesel Generator Standby AC System, Attachments 2 30.8

and 3

71111.04 Procedures 34SO-T48-002-2 Containment Atmospheric Control and Dilution Systems 29.7

71111.05 Corrective Action 10768272 01/21/2021

Documents

Resulting from

Inspection

71111.05 Corrective Action 10769666 01/27/2021

Documents

Resulting from

Inspection

71111.05 Corrective Action 10770244 01/29/2021

Documents

Resulting from

Inspection

71111.05 Corrective Action 10771474 02/03/2021

Documents

Resulting from

Inspection

71111.05 Corrective Action 10771727 02/04/2021

Documents

Resulting from

Inspection

71111.05 Corrective Action 10771737 02/04/2021

Documents

Resulting from

Inspection

71111.05 Drawings A-43965 Sheets 53A NE RHR & Core Spray Room 2.0

and 53B

71111.05 Drawings A-43965 Sheets 011, Unit 1/2 Station Battery Rooms 3.0

Inspection Type Designation Description or Title Revision or

Procedure Date

2, 017, and 018

71111.05 Drawings A-43965 Sheets 51A SE RHR & Core Spray Room 2.0

and 51B

71111.05 Drawings A-43965 Sheets 52A RCIC Pump and Turbine Room 2.0

and 52B

71111.05 Drawings A-43965 Sheets 54A CRD and DRW Sump Room 2.0

and 54B

71111.05 Drawings A-43965 Sheets 55A HPCI Pump Room 2.0

and 55B

71111.05 Drawings A-43966 8A, 8B, 9A PRE-Fire Plan Diesel Generator Room 1C 2.0

and 9B

71111.05 Drawings H11846 Fire Hazards Analysis Diesel Generator BLDG 3.0

71111.05 Fire Plans A-43965 Sheet 37A Pre-Fire Plan 600V Switchgear Room 2C 4.0

71111.05 Miscellaneous Email from the Senior Update on CR 10769666 02/03/2021

Fire Protection

Engineer Plant Hatch

71111.05 Miscellaneous Evaluation of Fire 02/10/2020

Barrier Degradation

71111.05 Procedures DI-OPS-72-1204 Fire Brigade Gear Restoration 15.2

71111.06 Calculations H-RIE-IF-U00-001 Hatch Internal Flood Notebook - Tasks 1, 2, and 3 1.0

71111.06 Corrective Action 10783738 03/19/2021

Documents

Resulting from

Inspection

71111.06 Fire Plans A-43965 Sheet 38A Pre-Fire Plan 600V Switchgear Room 2D 4

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

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

71111.07A Procedures 52SV-R43-001-0 Diesel, Alternator, and Accessories Inspection 31.21

71111.07A Procedures NMP-ES-012-001 Inspection of Heat Exchangers 03/24/2021

71111.11Q Miscellaneous H-LT-SG-50332 Shutdown Cooling (SDC) Operations / Loss of SDC / 29.4

SOER 09-1

71111.11Q Procedures 34GO-OPS-007-0 Shutdown/Refueling Mode Preparation Strategy For 1.2

Flex

71111.11Q Procedures 34GO-OPS-013-2 Normal Plant Shutdown 33.5

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Corrective Action 10676552 01/09/2020

Documents

71111.12 Corrective Action 10702333 04/12/2020

Documents

71111.12 Corrective Action 10704587 04/23/2020

Documents

71111.12 Corrective Action 10744782 10/09/2020

Documents

71111.12 Corrective Action 10744782 10/09/2020

Documents

71111.12 Corrective Action 10753668 11/13/2020

Documents

71111.12 Corrective Action 10755578 11/21/2020

Documents

71111.12 Corrective Action CAR278637 Unit 2A drywell Chiller Trip 12/29/2020

Documents

71111.12 Corrective Action CAR278637 Unit 2A Drywell Chiller Trip 12/29/2020

Documents

71111.12 Corrective Action 10786885 3/31/2021

Documents

Resulting from

Inspection

71111.12 Engineering EVAL-H-P64-05230 Applicable to Both 2P64B006A and 2P64B006B Drywell 12/30/2020

Evaluations Chillers a(1) Review

71111.12 Engineering TE1066690 05/22/2020

Evaluations

71111.12 Engineering TE1068785 06/30/2020

Evaluations

71111.12 Engineering TE1076069 11/05/2020

Evaluations

71111.12 Engineering TE1078644 12/02/2020

Evaluations

71111.12 Engineering TE4078088 12/08/2020

Evaluations

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.12 Miscellaneous Maintenance Rule 11/12/2019

SSC Function

Consolidation and

Performance Criteria

Selection Form for P-

Primary

Containment Chilled

Water (Unit 2)

71111.12 Miscellaneous PMCR99240 2P64-B006A/B Main Oil Pump Motor Starter 03/12/2021

71111.12 Procedures FL600DG1Y-H Flex 600V Diesel Generator Operational Inspection 08/16/2018

Work Instructions

71111.12 Procedures FL600VDG1Y-H4 FLLEX 600V Stack Diesel Generator Performance Test 01/07/2021

Work Instructions

71111.12 Procedures FL600VDG3Y-H FLEX 600V Diesel Generator Performance Test Work 08/16/2018

Instructions

71111.12 Procedures FL600VDG3Y-H4 FLEX 600V Stack Diesel Generator Performance Test 01/07/2021

Work Instructions

71111.12 Procedures FL60KW3Y-H FLEX 60KW Generator Performance Test Work 8/16/2018

Instructions

71111.12 Procedures FL60KW6M-H 60KW Generator Operational Inspection Work 08/16/2018

Insructions

71111.12 Procedures FLBSTRPMP3Y FLEX Booster Pump Performance Test Work 03/02/2021

Instructions

71111.12 Procedures FLBSTRPMP6M Flex Booster Pump Functional Test and Inspection Work 10/26/2020

Instructions

71111.12 Procedures NMP-)S-019-013- Hatch BDB Equipment Unavailability Tracking Guideline 5.1

GL02

71111.12 Procedures NMP-ES-002-006 System Vulnerability Review Process 3.4

71111.12 Procedures NMP-ES-027 Maintenance Rule Program 9.0

71111.12 Procedures NMP-GM-038 Diverse and Flexible Coping Strategies (FLEX) Program 4.0

71111.12 Procedures NMP-OS-019 Beyond Design Basis Events 2.0

71111.12 Procedures NMP-OS-019-013 Beyond Design Basis Equipment Unavailability Tracking 4.0

71111.12 Procedures NMP-OS-019-291 FLEX Core Cooling Pump Operating Instruction 2.0

71111.12 Procedures NMP-OS-019-292 FLEX Mode 4/5 Core Cooling Pump Operating 2.0

Inspection Type Designation Description or Title Revision or

Procedure Date

Instruction

71111.12 Procedures NMP-OS-019-293 FLEX 600V Diesel Generator Operating Instruction 1.1

71111.12 Procedures NMP-OS-019-294 FLEX 60KW Diesel Generator Operating Instruction 1.0

71111.12 Procedures NUMARC 93-01 Industry Guideline for Monitoring the Effectiveness of 4A

Maintenance at Nuclear Power Plants

71111.12 Work Orders SNC1060565 Mode 5 Core Cooling Pump Functional Test 1/11/2021

71111.13 Corrective Action 10784404 03/22/2021

Documents

Resulting from

Inspection

71111.13 Miscellaneous License Amendment Request to Revise the RAS of TS 3.8.1, AC Sources - Operating, for One-Time Extension

of Completion Time for Unit 1 and Swing EDGs SNC

Responses to NRC RAI, Attachments 5 and 6

71111.13 Procedures 34GO-OPS-007-0 Shutdown/Refueling Mode Preparation Strategy for Flex 1.2

71111.13 Procedures NMP-GM-031-003 Risk Management Actions for 10 CFR 50.65(a)(4) and 8.0

the Risk Informed Completion Time Program

71111.13 Procedures NMP-OS-010 Protected Train/Division and Protected Equipment 8.1

Program

71111.13 Procedures NMP-OS-010-002 Hatch Protected Equipment Logs 11.1

71111.13 Procedures NMP-OS-019-253 Hatch Unit C SIG-12, Mode 4/5 RPV Inventory Control 2.3

71111.15 Corrective Action 10714013 06/07/2020

Documents

71111.15 Corrective Action 10763139 12/28/2020

Documents

71111.15 Corrective Action 10763247 12/29/2020

Documents

71111.15 Corrective Action 10764816 01/06/2021

Documents

71111.15 Corrective Action 10769088 01/25/2021

Documents

71111.15 Corrective Action 107819557 03/11/2021

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Corrective Action 10782116 03/12/2020

Documents

71111.15 Corrective Action 10782586 03/15/2021

Documents

71111.15 Corrective Action 10783262 03/17/2021

Documents

71111.15 Corrective Action 10786180 03/29/2021

Documents

71111.15 Corrective Action 10786184 03/29/2021

Documents

71111.15 Corrective Action 10771474 02/03/2021

Documents

Resulting from

Inspection

71111.15 Corrective Action 10783264 03/17/2021

Documents

Resulting from

Inspection

71111.15 Drawings H-21033 Unit 2 Turbine Building Service Water System 61.0

71111.15 Drawings H-21704 Diesel Engine & Fuel Oil System 56.0

71111.15 Engineering SNC1148794 Design Equivalent Change Package for 2T41-B003B 03/30/2021

Changes Cooler Fan Failure TCC

71111.15 Engineering NMP-AD-012-F01 Operability Determination Support Basis for 4.0

Evaluations CR10764816

71111.15 Engineering TE 313720 01/18/2012

Evaluations

71111.15 Engineering TE457436 07/05/2012

Evaluations

71111.15 Miscellaneous APC 2-20-024 Alarm 2N32-K4001A/B Monitoring Actions 06/08/2020

71111.15 Miscellaneous Specification Sheet Lube Oil Heat Exchanger Specification Sheet 1.0

71111.15 Operability NMP-AD-012-F01 Operability Determination Support Basis for 2T41- 03/25/2021

Evaluations B003B

71111.15 Procedures 42SV-TET-001-0 LLRT Testing Methodology 13.0

71111.15 Procedures 42SV-TET-001-2 Primary Containment Periodic Type B and Type C 37.2

Inspection Type Designation Description or Title Revision or

Procedure Date

Leakage Tests

71111.15 Procedures NMP-AD-002-F04 Troubleshooting Log for the 2C EDG 1.1

71111.15 Procedures NMP-AD-012-F01 Operability determination Support Basis for the 2C EDG 03/16/2021

71111.15 Work Orders SNC1100180

71111.15 Work Orders SNC1135192

71111.15 Work Orders SNC865011 02/08/2021

71111.18 Calculations MC-H-19-0020 Coordination Study for 600V and 208V Switchgear 05/04/2020

Busses

71111.18 Corrective Action 10771124 02/02/2021

Documents

71111.18 Corrective Action 10778925 02/25/2021

Documents

71111.18 Corrective Action 10780926 03/08/2021

Documents

71111.18 Engineering SNC1010116 NFPA 805 - Coordination for Breakers 2R25-S021 & 08/04/2020

Changes Commercial Change 2R25-S022

Package

71111.18 Miscellaneous SNC1010116FPP5 Fire Protection Program Impact Screen of Commercial 07/06/2020

Change Package SNC1010116

71111.18 Procedures 42SP-10-30-20-RR-1- Yokogawa YS1700 Reactor Feed Pump Controllers 1.1

2C32-R600, 2C32-R601A/B, 2C32-R619, and 2C32-

R609 FT for DECP SNC632608

71111.18 Procedures NMP-AD-008 Applicability Determinations 22.0

71111.18 Procedures NMP-AD-009 Licensing Document Change Requests 17.0

71111.18 Procedures NMP-AD-010 10 CFR 50.59 Screenings and Evaluations 17.0

71111.18 Procedures NMP-MA-014 Post Maintenance Testing/Post Modification Testing 2.2

71111.18 Shipping SNC 1107054 Revise the Micro Versa Trip Unit Setting on 2R23-S021 02/25/2021

Records FR 4M

71111.18 Work Orders SNC1107044 Revise the Micro Versa Unit Setting on 2R23-S021 FR 02/24/2021

4B

71111.18 Work Orders SNC632608 Main Control Room Feedwater Controller Replacement 06/18/2020

71111.18 Work Orders SNC632608DLL Critical Digital Asset (CDA) Screening 05/15/2020

71111.18 Work Orders SNC632608DOEJJ001 EMI/RFI Evaluation of Equipment Added for 03/17/2020

DCPSNC632608

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.18 Work Orders SNC632608MAX1, 2

and 3

71111.18 Work Orders SNC632608OE Applicable Operating Experience Review

71111.18 Work Orders SNC632608PE

71111.18 Work Orders SNC632608REF Walkdown Plan and Observations Record 02/24/2020

71111.18 Work Orders SNC632608RF 05/06/2020

71111.18 Work Orders SNC632608SCP Software Quality Assurance Classification 05/14/2020

71111.19 Corrective Action 10776153 02/18/2021

Documents

71111.19 Corrective Action 10776156 02/18/2021

Documents

71111.19 Corrective Action 10776158 02/18/2021

Documents

71111.19 Corrective Action 10776420 02/19/2021

Documents

71111.19 Corrective Action 10776752 02/20/2021

Documents

71111.19 Corrective Action 10778039 02/25/2021

Documents

71111.19 Corrective Action 10781022 03/08/2021

Documents

71111.19 Corrective Action 10771741 02/04/2021

Documents

Resulting from

Inspection

71111.19 Engineering SNC1142049 03/03/2021

Changes

71111.19 Procedures 34SO-C51-001-0 Tip Operation and LPRM Calibration 19.4

71111.19 Procedures 34SV-P41-001-1 Plant Service Water Operability 15.2

71111.19 Procedures 34SV-R43-001-2 Diesel Generator 2A Monthly Test 29.4

71111.19 Procedures 34SV-R43-003-1 Diesel Generator 1C Monthly Test 20.2

71111.19 Procedures 42FH-ENG-030 ICA Transfer Authorization for Nuclear Detector 5.0

Installation

71111.19 Procedures 42FH-ENG-030-0 ICA Transfer Authorization 5.0

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Procedures 42SV-C11-003-0 U2C27 BOC Control Rod Scram Timing 11.1

71111.19 Procedures 42SV-TET-001-0 LLRT Testing Methodology 13.0

71111.19 Procedures 42SV-TET-001-0 Volumetric Leak Rate Monitor Local Leak Rate Test 03/02/2021

Data Sheet for, 2T48-F319 & 2T48-F320

71111.19 Procedures 42SV-TET-001-0 Unit 2 LLRT 2T48-F320 Shaft & Flange O-Rings 03/02/2021

71111.19 Procedures 42SV-TET-001-2 Primary Containment Periodic Type B & Type C 37.2

Leakage Tests

71111.19 Procedures 52GM-C51-001-0 LPRM Removal and Installation 17.3

71111.19 Procedures 52SV-R43-001-0 Diesel, Alternator, And Accessories Inspection, Section 03/28/2021

7.9 Diesel Generator Run In

71111.19 Procedures 52SV-R43-001-0 Diesel, Alternator, and Accessories Inspection 31.21

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

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

71111.19 Work Orders SNC1093049 02/17/2021

71111.19 Work Orders SNC1130203 01/29/2021

71111.19 Work Orders SNC1137368 02/05/2021

71111.19 Work Orders SNC1137428 02/26/2021

71111.19 Work Orders SNC1139786 01/29/2021

71111.19 Work Orders SNC1139991 01/29/2021

71111.20 Corrective Action 10773870 02/12/2021

Documents

Resulting from

Inspection

71111.20 Corrective Action 10773870 02/12/2021

Documents

Resulting from

Inspection

71111.20 Miscellaneous OCC - All OPS Activities Next 7 Days By Team, Outage 01/21/2021

Schedule

71111.20 Miscellaneous H2R26 Final Outage Safety Assessment Report 0.0

71111.20 Miscellaneous H2R26 Final Outage Safety Assessment Report 1.0

71111.20 Procedures 34GO-OPS 001-2 Plant Startup 51.9

71111.20 Procedures 34GO-OPS-013-2 Normal Plant Shutdown 33.5

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.20 Procedures 34GO-OPS-015-2 Maintaining Cold Shutdown or Refueling Condition 16.2

71111.20 Procedures 34GO-OPS-025-0 RPV Water Inventory Control 3.3

71111.20 Procedures 34GO-OPS-028-2 Drywell Closeout 7.21

71111.20 Procedures 34GO-OPS-029-0 Torus & Torus Area Closeout 3.2

71111.20 Procedures 52GM-MME-004-2 Reactor Vessel Reassembly 21.0

71111.20 Procedures 52GM-MME-015-2 Reactor Vessel Disassembly 18.9

71111.20 Procedures NMP-RE-007, H2C27 Core Loading Verification 02/26/2021

Attachments 1, 2 And

71111.20 Procedures NMP-RE-008-F01 Detailed Reactivity Management Plan 03/08/2021

71111.20 Work Orders SNC946845 02/01/2021

71111.22 Calibration 10773100, 10773182, 02/10/2021

Records 10773184 and

10773217

71111.22 Corrective Action 10766461 01/11/2021

Documents

71111.22 Corrective Action 10766491 01/13/2021

Documents

71111.22 Corrective Action 10769440 01/26/2021

Documents

71111.22 Corrective Action 10780410 03/05/2021

Documents

71111.22 Corrective Action 10780501 03/05/2021

Documents

71111.22 Drawings H-16329-16330 RHR System P&ID Sheets 1 & 2 84.0 and

75.0

71111.22 Procedures 34SV-E11-004-1 RHR Service Water Pump Operability 22.1

71111.22 Procedures 34SV-E21-001-1 Core Spray Pump Operability 24.2

71111.22 Procedures 34SV-E41-002-2 High Pressure Coolant Injection Pump Operability CPT 39.1

71111.22 Procedures 34SV-E41-010-2 HPCI Logic System Functional Test 1.2

71111.22 Procedures 34SV-E51-010-2 RCIC Logic System Functional Test 1.5

71111.22 Procedures 34SV-R43-003-1 Diesel Generator 1C Monthly Test 20.2

71111.22 Procedures 34SV-R43-020-2 Diesel Generator 2A LOCA/LOSP LSFT 4.0

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Procedures 34SV-T48-002-2 Suppression Chamber to Drywell Vacuum Breaker 5.8

Operability And Containment Purge/Vent Valve Position

Check

71111.22 Work Orders SNC1060565 Mode 5 Core Cooling Pump Functional Test January 11,

21

71124.01 Corrective Action CR 10752676

Documents

71124.01 Radiation 182603 U2 CPS A Pump Room 08/25/20

Surveys

71124.02 Procedures NMP-AD-035 ALARA Program Version 1.9

71124.02 Procedures NMP-HP-204 ALARA Planning and Job Review Ver. 7.2

71124.02 Procedures NMP-HP-204-001 ALARA Planning Version 2.2

71124.02 Procedures NMP-HP-206 Issuance, Use, and Control of Radiation Work Permits Version 6.1

71124.03 Corrective Action CR 10771551

Documents

71124.03 Corrective Action CR 10778343

Documents

Resulting from

Inspection

71124.03 Self- TE 1058722 RP Pre-NRC check-in self-assessment 12/06/2020

Assessments

71124.04 Corrective Action 10778784

Documents

Resulting from

Inspection

71124.04 Miscellaneous Technical Position Evaluation of Tritium Monitoring Plant Hatch Nuclear 02/06/2019

Station

71124.04 Procedures NMP-HP-108 Issuance, Use and Collection of Personnel Dosimetry Version 2.9

71124.05 Calibration 109114 Hatch Main Stack Radiation Monitor calibration source 04/30/2018

Records ID # 0080.00.00 (Cd-109 simulated gas in a Marinelli

beaker) - Eckert & Ziegler Certification of Calibration

71124.05 Calibration 129 Victoreen Model 878-10 Calibrator Certification of 10/01/1997

Records Calibration (Hatch source ID # Cs-137- 243)

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Calibration 129 Victoreen Model 878-10 Calibrator Certification of 05/07/1991

Records Calibration (Hatch source ID # Cs-137- 243)

71124.05 Calibration 1D11-K604 Unit 1 Liquid Radwaste Monitor radiation monitor initial 06/20/1985

Records source calibration with liquid Cs-137 source using 62CI-

CAL-009-0, v1.0

71124.05 Calibration 1D11-K604 Initial solid source response calibration performed per 06/21/1985

Records 62CI-OCB-009-0, Rev 1 after NBS-traceable liquid Cs-

137 source for efficiency factor determination. Cs-137

source, Serial number Cs-137-179, used for traceable

source count rate determination.

71124.05 Calibration 1D11-K604 Calibration source transfer performed (Cs-137-179, Cs- 11/14/1995

Records 137-183) per 64CI-OCB-009-0.

71124.05 Calibration 1D11-K619B Unit 1 Reactor Building Ventilation Radiation Monitor 04/20/2020

Records (RBV) 1D1-K619B source calibration [performed after

detector replacement and HV and discriminator set]

71124.05 Calibration 73713-06 Hatch Main Stack Radiation Monitor calibration source 09/18/2006

Records ID # Cs-137-284 (simulated gas in a Marinelli beaker) -

Analytics Certification of Calibration

71124.05 Calibration 73715-06 Hatch Main Stack Radiation Monitor calibration source 09/18/2006

Records ID # Co-60-146 (simulated gas in a Marinelli beaker) -

Analytics Certification of Calibration

71124.05 Calibration 86243-121 Hatch calibration source ID # Tc-99-77 - Eckert & 12/12/2011

Records Ziegler Certification of Calibration

71124.05 Calibration 93549F Hatch Main Stack Radiation Monitor calibration source 06/28/2013

Records ID # Cd-109-147 (simulated gas in a Marinelli beaker) -

Eckert & Ziegler Certification of Calibration

71124.05 Calibration W/O 1036883 Unit 2 Liquid Radwaste Radiation Monitor (MPL: 2D11- 08/12/2019

Records K604) source calibration (per Procedure 64CI-OCB-009-

0)

71124.05 Calibration W/O SNC754124 Unit 2 Drywell High Range Radiation Monitor 2D11- 01/26/2017

Records 621A & B Loop Calibration [24 month calibration -

electronics only]

71124.05 Calibration W/O SNC761756 Unit 2 Reactor Building Ventilation Post Accident Noble 03/01/2017

Records Gas Radiation Monitor 2D11-K636A & B FT&C (channel

Inspection Type Designation Description or Title Revision or

Procedure Date

functional test) [24 month calibration - electronics only]

71124.05 Calibration W/O SNC909309 Unit 2 Reactor Building Ventilation Post Accident Noble 04/25/2019

Records Gas Radiation Monitor 2D11-K636A & B FT&C (channel

functional test) [24 month calibration - electronics only]

71124.05 Calibration W/O SNC961179 Reactor Building Ventilation Radiation Monitor 1D1- 08/22/2019

Records K619A FT&C (channel functional test) [24 month

calibration - electronics only]

71124.05 Calibration Work Order (W/O) Unit 2 Drywell High Range Radiation Monitor 2D11- 05/11/2019

Records SNC 878503 621A & B Loop Calibration [24 month calibration -

electronics only]

71124.05 Corrective Action CR Numbers: 10448588, 10572155, 10586543, Various

Documents 10629838, 10629675, and 10640037

71124.05 Corrective Action CR 10772650 Current certified source calibration data not being used 02/08/2021

Documents for Drywell radiation monitor (Victoreen 878-10 field

Resulting from calibrator S/N 129, Hatch source ID # Cs-137-243).

Inspection

71124.05 Corrective Action CR 10772654 Chemistry radiation monitor source calibration 02/08/2021

Documents procedures should all be revised to require recording of

Resulting from the applicable work order number on the quality record

Inspection for all source calibrations.

71124.05 Corrective Action CR 10773027 Chemistry procedures for source calibrations on various 02/09/2021

Documents radiation monitors generally specify that the technician

Resulting from should ensure the source has 'sufficient strength' but

Inspection how to determine what is 'sufficient' is not defined. The

procedures should be revised to include this information.

71124.05 Corrective Action CR 10773254 Revise Procedure NMP-HP-400 to include a counting 02/10/2021

Documents geometry for NI-63 smear sample analysis (used for

Resulting from source leak testing).

Inspection

71124.05 Corrective Action CR 10773533 NRC observation - evaluate inclusion of Accident Range 02/11/2021

Documents Ventilation Effluent Monitoring System (ARVEMS) in the

Resulting from Chemistry Continuing Training Program to ensure

Inspection sampling proficiency is maintained.

71124.05 Corrective Action CR 10775274 NRC inspector identified that the 2020 vendor 02/16/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents calibration package for the dosimetry office whole body

Resulting from counter had incorrect dates (2019 vs. 2020).

Inspection

71124.05 Corrective Action CR 10777540 Procedure 57SV-D11-021-1 and -2 needs to be revised 02/23/2021

Documents such that the special requirements state that a

Resulting from Functional Test is required every time an electronic

Inspection calibration is performed. It also needs to also require a

source calibration per the Chemistry procedure when

the 2-year cal is performed as well.

71124.05 Corrective Action CR 10778227 Liquid Radwaste radiation monitor calibration source # 02/25/2021

Documents Cs-137-183 NIST traceability documentation cannot be

Resulting from located.

Inspection

71124.07 Corrective Action CAR 276603

Documents

71124.07 Corrective Action CR 10600292

Documents

71124.07 Corrective Action CR 10635234

Documents

71124.07 Corrective Action TE 1071055

Documents

71124.07 Miscellaneous EPRI Groundwater Protection Program Assessment 08/20/2020

71124.07 Miscellaneous Groundwater Monitoring Data for Sample Well NW-10 01/01/2019 -

2/10/2021

71124.07 Procedures NMP-EN-002 Radiological Groundwater Protection Program Version 9.2

71124.07 Procedures NMP-EN-002-GL02 Hatch Nuclear Plant Groundwater Monitoring Plan for Version 1.1

Radionuclides

71124.07 Procedures NMP-EN-002-GL04 Radiological GWPP Technical Bases Version 1.0

71124.07 Procedures NMP-ES-036-001 Underground Pipe and Tanks Monitoring Program Version 11

Implementation

71124.07 Procedures ODCM Offsite Dose Calculation Manual for Edwin I. Hatch Version 26

Nuclear Plant

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.07 Radiation Plant Hatch Routine Survey Unit 2 CST 01/23/2021

Surveys Radiological

Information Survey #

185685

71124.07 Radiation Plant Hatch U2 CST Routine Survey 02/20/2020

Surveys Radiological

Information Survey #

186959

71151 Miscellaneous LER 2020-001-000 March 2,

20

71151 Miscellaneous LER 2020-001-000 December

10, 2020

71151 Miscellaneous LER 2020-002-000 June 18,

20

71151 Miscellaneous NEI 99-02 Regulatory Assessment Performance Indicator 7.0

Guideline

71152 Corrective Action RCE278526 12/18/2020

Documents

71152 Corrective Action RCE278526 12/18/2020

Documents

71153 Corrective Action 10695910 03/15/2020

Documents

71153 Corrective Action 10707660 05/07/2020

Documents

71153 Corrective Action 10707858 05/08/2020

Documents

71153 Corrective Action CAR 277887 10/28/2020

Documents

71153 Corrective Action 10728101 08/05/2020

Documents

Resulting from

Inspection

71153 Corrective Action 10747434 10/20/2020

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

71153 Corrective Action 10764815 01/06/2021

Documents

Resulting from

Inspection

71153 Corrective Action CAR 278739 01/06/2021

Documents

Resulting from

Inspection

71153 Engineering TE 1067120 1A EDG Past Operability 05/14/2020

Evaluations

71153 Miscellaneous ML20345A083 LER 2020-001-00 for Edwin I. Hatch Nuclear Plant Unit 12/10/2020

1, 1A EDG Inoperable Due to Water in the Day Tank

31