IR 05000321/2021001
| ML21126A020 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| 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:
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
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 I. Hatch Nuclear Plant Unit 1, 1A EDG Inoperable Due to Water in the Day Tank 71153 Closed
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:
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)
- Penetrant Testing (PT)a. 2B31-1RC-2A-1-RI, BC to Pipe, ASME Class 1 (reviewed)b. 2E11F073B FW3, RHRSW to RHR Crosstie (FLEX), ASME Class 3 (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
- RWP 21-2608, Control Rod Drive (CRD) Exchange
- 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:
- (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
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
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.
- (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.
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
SCNH-13-020
Hatch Probable Maximum Flood Hydraulics - Severe
Accident Management (SAM) for Fukushima Near-Term
Task Force (NTTF) Recommendation 2.1 Flooding
Reevaluation
1.0
Calculations
SCNH-13-021
Evaluation of Plant Hatch Local Intense Precipitation -
Severe Accident Management (SAM) for Fukushima
Near-Term Task Force (NTTF) Recommendation 2.1
Flooding Evaluation
1.0
Corrective Action
Documents
Resulting from
Inspection
10776017
2/18/2021
Miscellaneous
HNP-2-FSAR-2
Hatch Nuclear Plant, Final Safety Analysis Reports
Updates, Chapter 2
Miscellaneous
Natural Weather
Service Watch,
Warning & Advisories
Tornado Watch
2/15/2021
Procedures
Naturally Occurring Phenomena
19.2
Procedures
Plant Service Water Valve Pit Sumps Level High
1.2
Procedures
NMP-OS-017
Severe Weather Attachments 1 through 8
2/15/2021
Procedures
NMP-OS-017
Severe Weather Attachments 1 through 9
2/18/2021
Procedures
NMP-OS-017
Severe Weather
3.0
Corrective Action
Documents
Resulting from
Inspection
10773366
2/10/2021
Corrective Action
Documents
Resulting from
Inspection
10784664
03/23/2021
Drawings
H-26018
Unit 2 Core Spray System P&ID
40.0
Drawings
H-26083
Hatch Unit 2 Nitrogen Inerting System P&ID
45.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
H-26084
Hatch Nuclear Plant Unit 2 Primary Containment Purge
and Inerting System P&ID
2.0
Procedures
Core Spray System operating procedure
26.5
Procedures
Diesel Generator Standby System
29.2
Procedures
Diesel Generator Standby AC System, Attachments 2
and 3
30.8
Procedures
Containment Atmospheric Control and Dilution Systems
29.7
Corrective Action
Documents
Resulting from
Inspection
10768272
01/21/2021
Corrective Action
Documents
Resulting from
Inspection
10769666
01/27/2021
Corrective Action
Documents
Resulting from
Inspection
10770244
01/29/2021
Corrective Action
Documents
Resulting from
Inspection
10771474
2/03/2021
Corrective Action
Documents
Resulting from
Inspection
10771727
2/04/2021
Corrective Action
Documents
Resulting from
Inspection
10771737
2/04/2021
Drawings
A-43965 Sheets 53A
and 53B
NE RHR & Core Spray Room
2.0
Drawings
A-43965 Sheets 011,
Unit 1/2 Station Battery Rooms
3.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2, 017, and 018
Drawings
A-43965 Sheets 51A
and 51B
SE RHR & Core Spray Room
2.0
Drawings
A-43965 Sheets 52A
and 52B
RCIC Pump and Turbine Room
2.0
Drawings
A-43965 Sheets 54A
and 54B
2.0
Drawings
A-43965 Sheets 55A
and 55B
HPCI Pump Room
2.0
Drawings
A-43966 8A, 8B, 9A
and 9B
PRE-Fire Plan Diesel Generator Room 1C
2.0
Drawings
H11846
Fire Hazards Analysis Diesel Generator BLDG
3.0
Fire Plans
A-43965 Sheet 37A
Pre-Fire Plan 600V Switchgear Room 2C
4.0
Miscellaneous
Email from the Senior
Fire Protection
Engineer Plant Hatch
Update on CR 10769666
2/03/2021
Miscellaneous
Evaluation of Fire
Barrier Degradation
2/10/2020
Procedures
DI-OPS-72-1204
Fire Brigade Gear Restoration
15.2
Calculations
H-RIE-IF-U00-001
Hatch Internal Flood Notebook - Tasks 1, 2, and 3
1.0
Corrective Action
Documents
Resulting from
Inspection
10783738
03/19/2021
Fire Plans
A-43965 Sheet 38A
Pre-Fire Plan 600V Switchgear Room 2D
Procedures
Drywell and Reactor Building Sump Systems
1.4
Procedures
Sump Isolation Valve Actuation Test
0.3
Procedures
Diesel, Alternator, and Accessories Inspection
31.21
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
71111.11Q Procedures
Shutdown/Refueling Mode Preparation Strategy For
Flex
1.2
71111.11Q Procedures
Normal Plant Shutdown
33.5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10676552
01/09/2020
Corrective Action
Documents
10702333
04/12/2020
Corrective Action
Documents
10704587
04/23/2020
Corrective Action
Documents
10744782
10/09/2020
Corrective Action
Documents
10744782
10/09/2020
Corrective Action
Documents
10753668
11/13/2020
Corrective Action
Documents
10755578
11/21/2020
Corrective Action
Documents
Unit 2A drywell Chiller Trip
2/29/2020
Corrective Action
Documents
Unit 2A Drywell Chiller Trip
2/29/2020
Corrective Action
Documents
Resulting from
Inspection
10786885
3/31/2021
Engineering
Evaluations
EVAL-H-P64-05230
Applicable to Both 2P64B006A and 2P64B006B Drywell
Chillers a(1) Review
2/30/2020
Engineering
Evaluations
TE1066690
05/22/2020
Engineering
Evaluations
TE1068785
06/30/2020
Engineering
Evaluations
TE1076069
11/05/2020
Engineering
Evaluations
TE1078644
2/02/2020
Engineering
Evaluations
TE4078088
2/08/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Maintenance Rule
SSC Function
Consolidation and
Performance Criteria
Selection Form for P-
Primary
Containment Chilled
Water (Unit 2)
11/12/2019
Miscellaneous
PMCR99240
2P64-B006A/B Main Oil Pump Motor Starter
03/12/2021
Procedures
FL600DG1Y-H
Flex 600V Diesel Generator Operational Inspection
Work Instructions
08/16/2018
Procedures
FL600VDG1Y-H4
FLLEX 600V Stack Diesel Generator Performance Test
Work Instructions
01/07/2021
Procedures
FL600VDG3Y-H
FLEX 600V Diesel Generator Performance Test Work
Instructions
08/16/2018
Procedures
FL600VDG3Y-H4
FLEX 600V Stack Diesel Generator Performance Test
Work Instructions
01/07/2021
Procedures
FL60KW3Y-H
FLEX 60KW Generator Performance Test Work
Instructions
8/16/2018
Procedures
FL60KW6M-H
60KW Generator Operational Inspection Work
Insructions
08/16/2018
Procedures
FLBSTRPMP3Y
FLEX Booster Pump Performance Test Work
Instructions
03/02/2021
Procedures
FLBSTRPMP6M
Flex Booster Pump Functional Test and Inspection Work
Instructions
10/26/2020
Procedures
NMP-)S-019-013-
GL02
Hatch BDB Equipment Unavailability Tracking Guideline
5.1
Procedures
NMP-ES-002-006
System Vulnerability Review Process
3.4
Procedures
NMP-ES-027
9.0
Procedures
NMP-GM-038
Diverse and Flexible Coping Strategies (FLEX) Program
4.0
Procedures
NMP-OS-019
Beyond Design Basis Events
2.0
Procedures
NMP-OS-019-013
Beyond Design Basis Equipment Unavailability Tracking
4.0
Procedures
NMP-OS-019-291
FLEX Core Cooling Pump Operating Instruction
2.0
Procedures
NMP-OS-019-292
FLEX Mode 4/5 Core Cooling Pump Operating
2.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Instruction
Procedures
NMP-OS-019-293
FLEX 600V Diesel Generator Operating Instruction
1.1
Procedures
NMP-OS-019-294
FLEX 60KW Diesel Generator Operating Instruction
1.0
Procedures
Industry Guideline for Monitoring the Effectiveness of
Maintenance at Nuclear Power Plants
4A
Work Orders
SNC1060565
Mode 5 Core Cooling Pump Functional Test
1/11/2021
Corrective Action
Documents
Resulting from
Inspection
10784404
03/22/2021
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
Procedures
Shutdown/Refueling Mode Preparation Strategy for Flex
1.2
Procedures
NMP-GM-031-003
Risk Management Actions for 10 CFR 50.65(a)(4) and
the Risk Informed Completion Time Program
8.0
Procedures
NMP-OS-010
Protected Train/Division and Protected Equipment
Program
8.1
Procedures
NMP-OS-010-002
Hatch Protected Equipment Logs
11.1
Procedures
NMP-OS-019-253
Hatch Unit C SIG-12, Mode 4/5 RPV Inventory Control
2.3
Corrective Action
Documents
10714013
06/07/2020
Corrective Action
Documents
10763139
2/28/2020
Corrective Action
Documents
10763247
2/29/2020
Corrective Action
Documents
10764816
01/06/2021
Corrective Action
Documents
10769088
01/25/2021
Corrective Action
Documents
107819557
03/11/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
10782116
03/12/2020
Corrective Action
Documents
10782586
03/15/2021
Corrective Action
Documents
10783262
03/17/2021
Corrective Action
Documents
10786180
03/29/2021
Corrective Action
Documents
10786184
03/29/2021
Corrective Action
Documents
Resulting from
Inspection
10771474
2/03/2021
Corrective Action
Documents
Resulting from
Inspection
10783264
03/17/2021
Drawings
H-21033
Unit 2 Turbine Building Service Water System
61.0
Drawings
H-21704
Diesel Engine & Fuel Oil System
56.0
Engineering
Changes
SNC1148794
Design Equivalent Change Package for 2T41-B003B
Cooler Fan Failure TCC
03/30/2021
Engineering
Evaluations
NMP-AD-012-F01
Operability Determination Support Basis for
CR10764816
4.0
Engineering
Evaluations
TE 313720
01/18/2012
Engineering
Evaluations
TE457436
07/05/2012
Miscellaneous
APC 2-20-024
Alarm 2N32-K4001A/B Monitoring Actions
06/08/2020
Miscellaneous
Specification Sheet
Lube Oil Heat Exchanger Specification Sheet
1.0
Operability
Evaluations
NMP-AD-012-F01
Operability Determination Support Basis for 2T41-
B003B
03/25/2021
Procedures
LLRT Testing Methodology
13.0
Procedures
Primary Containment Periodic Type B and Type C
37.2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Leakage Tests
Procedures
NMP-AD-002-F04
Troubleshooting Log for the 2C EDG
1.1
Procedures
NMP-AD-012-F01
Operability determination Support Basis for the 2C EDG
03/16/2021
Work Orders
SNC1100180
Work Orders
SNC1135192
Work Orders
SNC865011
2/08/2021
Calculations
MC-H-19-0020
Coordination Study for 600V and 208V Switchgear
Busses
05/04/2020
Corrective Action
Documents
10771124
2/02/2021
Corrective Action
Documents
10778925
2/25/2021
Corrective Action
Documents
10780926
03/08/2021
Engineering
Changes
SNC1010116
Commercial Change
Package
NFPA 805 - Coordination for Breakers 2R25-S021 &
08/04/2020
Miscellaneous
SNC1010116FPP5
Fire Protection Program Impact Screen of Commercial
Change Package SNC1010116
07/06/2020
Procedures
2SP-10-30-20-RR-1-
Yokogawa YS1700 Reactor Feed Pump Controllers
2C32-R600, 2C32-R601A/B, 2C32-R619, and 2C32-
R609 FT for DECP SNC632608
1.1
Procedures
NMP-AD-008
Applicability Determinations
2.0
Procedures
NMP-AD-009
Licensing Document Change Requests
17.0
Procedures
NMP-AD-010
CFR 50.59 Screenings and Evaluations
17.0
Procedures
NMP-MA-014
Post Maintenance Testing/Post Modification Testing
2.2
Shipping
Records
SNC 1107054
Revise the Micro Versa Trip Unit Setting on 2R23-S021
FR 4M
2/25/2021
Work Orders
SNC1107044
Revise the Micro Versa Unit Setting on 2R23-S021 FR
4B
2/24/2021
Work Orders
SNC632608
Main Control Room Feedwater Controller Replacement
06/18/2020
Work Orders
SNC632608DLL
Critical Digital Asset (CDA) Screening
05/15/2020
Work Orders
SNC632608DOEJJ001 EMI/RFI Evaluation of Equipment Added for
DCPSNC632608
03/17/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
SNC632608MAX1, 2
and 3
Work Orders
SNC632608OE
Applicable Operating Experience Review
Work Orders
SNC632608PE
Work Orders
SNC632608REF
Walkdown Plan and Observations Record
2/24/2020
Work Orders
SNC632608RF
05/06/2020
Work Orders
SNC632608SCP
Software Quality Assurance Classification
05/14/2020
Corrective Action
Documents
10776153
2/18/2021
Corrective Action
Documents
10776156
2/18/2021
Corrective Action
Documents
10776158
2/18/2021
Corrective Action
Documents
10776420
2/19/2021
Corrective Action
Documents
10776752
2/20/2021
Corrective Action
Documents
10778039
2/25/2021
Corrective Action
Documents
10781022
03/08/2021
Corrective Action
Documents
Resulting from
Inspection
10771741
2/04/2021
Engineering
Changes
SNC1142049
03/03/2021
Procedures
Tip Operation and LPRM Calibration
19.4
Procedures
Plant Service Water Operability
15.2
Procedures
Diesel Generator 2A Monthly Test
29.4
Procedures
Diesel Generator 1C Monthly Test
20.2
Procedures
ICA Transfer Authorization for Nuclear Detector
Installation
5.0
Procedures
ICA Transfer Authorization
5.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
U2C27 BOC Control Rod Scram Timing
11.1
Procedures
LLRT Testing Methodology
13.0
Procedures
Volumetric Leak Rate Monitor Local Leak Rate Test
Data Sheet for, 2T48-F319 & 2T48-F320
03/02/2021
Procedures
Unit 2 LLRT 2T48-F320 Shaft & Flange O-Rings
03/02/2021
Procedures
Primary Containment Periodic Type B & Type C
Leakage Tests
37.2
Procedures
LPRM Removal and Installation
17.3
Procedures
Diesel, Alternator, And Accessories Inspection, Section
7.9 Diesel Generator Run In
03/28/2021
Procedures
Diesel, Alternator, and Accessories Inspection
31.21
Procedures
NMP-MA-014
Post Maintenance Testing/Post Modification Testing
2.1
Procedures
NMP-MA-014-001
Post Maintenance Testing Guidance
5.2
Work Orders
SNC1093049
2/17/2021
Work Orders
SNC1130203
01/29/2021
Work Orders
SNC1137368
2/05/2021
Work Orders
SNC1137428
2/26/2021
Work Orders
SNC1139786
01/29/2021
Work Orders
SNC1139991
01/29/2021
Corrective Action
Documents
Resulting from
Inspection
10773870
2/12/2021
Corrective Action
Documents
Resulting from
Inspection
10773870
2/12/2021
Miscellaneous
OCC - All OPS Activities Next 7 Days By Team, Outage
Schedule
01/21/2021
Miscellaneous
H2R26 Final Outage Safety Assessment Report
0.0
Miscellaneous
H2R26 Final Outage Safety Assessment Report
1.0
Procedures
34GO-OPS 001-2
Plant Startup
51.9
Procedures
Normal Plant Shutdown
33.5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Maintaining Cold Shutdown or Refueling Condition
16.2
Procedures
3.3
Procedures
Drywell Closeout
7.21
Procedures
Torus & Torus Area Closeout
3.2
Procedures
Reactor Vessel Reassembly
21.0
Procedures
Reactor Vessel Disassembly
18.9
Procedures
NMP-RE-007,
Attachments 1, 2 And
H2C27 Core Loading Verification
2/26/2021
Procedures
NMP-RE-008-F01
Detailed Reactivity Management Plan
03/08/2021
Work Orders
SNC946845
2/01/2021
Calibration
Records
10773100, 10773182,
10773184 and
10773217
2/10/2021
Corrective Action
Documents
10766461
01/11/2021
Corrective Action
Documents
10766491
01/13/2021
Corrective Action
Documents
10769440
01/26/2021
Corrective Action
Documents
10780410
03/05/2021
Corrective Action
Documents
10780501
03/05/2021
Drawings
H-16329-16330
84.0 and
75.0
Procedures
RHR Service Water Pump Operability
2.1
Procedures
Core Spray Pump Operability
24.2
Procedures
High Pressure Coolant Injection Pump Operability CPT
39.1
Procedures
HPCI Logic System Functional Test
1.2
Procedures
RCIC Logic System Functional Test
1.5
Procedures
Diesel Generator 1C Monthly Test
20.2
Procedures
Diesel Generator 2A LOCA/LOSP LSFT
4.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Suppression Chamber to Drywell Vacuum Breaker
Operability And Containment Purge/Vent Valve Position
Check
5.8
Work Orders
SNC1060565
Mode 5 Core Cooling Pump Functional Test
January 11,
21
Corrective Action
Documents
CR 10752676
Radiation
Surveys
2603
U2 CPS A Pump Room
08/25/20
Procedures
NMP-AD-035
ALARA Program
Version 1.9
Procedures
NMP-HP-204
ALARA Planning and Job Review
Ver. 7.2
Procedures
NMP-HP-204-001
ALARA Planning
Version 2.2
Procedures
NMP-HP-206
Issuance, Use, and Control of Radiation Work Permits
Version 6.1
Corrective Action
Documents
CR 10771551
Corrective Action
Documents
Resulting from
Inspection
CR 10778343
Self-
Assessments
TE 1058722
RP Pre-NRC check-in self-assessment
2/06/2020
Corrective Action
Documents
Resulting from
Inspection
10778784
Miscellaneous
Technical Position
Evaluation of Tritium Monitoring Plant Hatch Nuclear
Station
2/06/2019
Procedures
NMP-HP-108
Issuance, Use and Collection of Personnel Dosimetry
Version 2.9
Calibration
Records
109114
Hatch Main Stack Radiation Monitor calibration source
ID # 0080.00.00 (Cd-109 simulated gas in a Marinelli
beaker) - Eckert & Ziegler Certification of Calibration
04/30/2018
Calibration
Records
29
Victoreen Model 878-10 Calibrator Certification of
Calibration (Hatch source ID # Cs-137-243)
10/01/1997
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calibration
Records
29
Victoreen Model 878-10 Calibrator Certification of
Calibration (Hatch source ID # Cs-137-243)
05/07/1991
Calibration
Records
Unit 1 Liquid Radwaste Monitor radiation monitor initial
source calibration with liquid Cs-137 source using 62CI-
CAL-009-0, v1.0
06/20/1985
Calibration
Records
Initial solid source response calibration performed per
2CI-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.
06/21/1985
Calibration
Records
Calibration source transfer performed (Cs-137-179, Cs-
137-183) per 64CI-OCB-009-0.
11/14/1995
Calibration
Records
Unit 1 Reactor Building Ventilation Radiation Monitor
(RBV) 1D1-K619B source calibration [performed after
detector replacement and HV and discriminator set]
04/20/2020
Calibration
Records
73713-06
Hatch Main Stack Radiation Monitor calibration source
ID # Cs-137-284 (simulated gas in a Marinelli beaker) -
Analytics Certification of Calibration
09/18/2006
Calibration
Records
73715-06
Hatch Main Stack Radiation Monitor calibration source
ID # Co-60-146 (simulated gas in a Marinelli beaker) -
Analytics Certification of Calibration
09/18/2006
Calibration
Records
243-121
Hatch calibration source ID # Tc-99-77 - Eckert &
Ziegler Certification of Calibration
2/12/2011
Calibration
Records
93549F
Hatch Main Stack Radiation Monitor calibration source
ID # Cd-109-147 (simulated gas in a Marinelli beaker) -
Eckert & Ziegler Certification of Calibration
06/28/2013
Calibration
Records
Unit 2 Liquid Radwaste Radiation Monitor (MPL: 2D11-
K604) source calibration (per Procedure 64CI-OCB-009-
0)
08/12/2019
Calibration
Records
W/O SNC754124
Unit 2 Drywell High Range Radiation Monitor 2D11-
21A & B Loop Calibration [24 month calibration -
electronics only]
01/26/2017
Calibration
Records
W/O SNC761756
Unit 2 Reactor Building Ventilation Post Accident Noble
Gas Radiation Monitor 2D11-K636A & B FT&C (channel
03/01/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
functional test) [24 month calibration - electronics only]
Calibration
Records
W/O SNC909309
Unit 2 Reactor Building Ventilation Post Accident Noble
Gas Radiation Monitor 2D11-K636A & B FT&C (channel
functional test) [24 month calibration - electronics only]
04/25/2019
Calibration
Records
W/O SNC961179
Reactor Building Ventilation Radiation Monitor 1D1-
K619A FT&C (channel functional test) [24 month
calibration - electronics only]
08/22/2019
Calibration
Records
Work Order (W/O)
SNC 878503
Unit 2 Drywell High Range Radiation Monitor 2D11-
21A & B Loop Calibration [24 month calibration -
electronics only]
05/11/2019
Corrective Action
Documents
CR Numbers: 10448588, 10572155, 10586543,
10629838, 10629675, and 10640037
Various
Corrective Action
Documents
Resulting from
Inspection
CR 10772650
Current certified source calibration data not being used
for Drywell radiation monitor (Victoreen 878-10 field
calibrator S/N 129, Hatch source ID # Cs-137-243).
2/08/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10772654
Chemistry radiation monitor source calibration
procedures should all be revised to require recording of
the applicable work order number on the quality record
for all source calibrations.
2/08/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10773027
Chemistry procedures for source calibrations on various
radiation monitors generally specify that the technician
should ensure the source has 'sufficient strength' but
how to determine what is 'sufficient' is not defined. The
procedures should be revised to include this information.
2/09/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10773254
Revise Procedure NMP-HP-400 to include a counting
geometry for NI-63 smear sample analysis (used for
source leak testing).
2/10/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10773533
NRC observation - evaluate inclusion of Accident Range
Ventilation Effluent Monitoring System (ARVEMS) in the
Chemistry Continuing Training Program to ensure
sampling proficiency is maintained.
2/11/2021
Corrective Action
CR 10775274
NRC inspector identified that the 2020 vendor
2/16/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
calibration package for the dosimetry office whole body
counter had incorrect dates (2019 vs. 2020).
Corrective Action
Documents
Resulting from
Inspection
CR 10777540
Procedure 57SV-D11-021-1 and -2 needs to be revised
such that the special requirements state that a
Functional Test is required every time an electronic
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.
2/23/2021
Corrective Action
Documents
Resulting from
Inspection
CR 10778227
Liquid Radwaste radiation monitor calibration source #
Cs-137-183 NIST traceability documentation cannot be
located.
2/25/2021
Corrective Action
Documents
Corrective Action
Documents
CR 10600292
Corrective Action
Documents
CR 10635234
Corrective Action
Documents
TE 1071055
Miscellaneous
EPRI Groundwater Protection Program Assessment
08/20/2020
Miscellaneous
Groundwater Monitoring Data for Sample Well NW-10
01/01/2019 -
2/10/2021
Procedures
NMP-EN-002
Radiological Groundwater Protection Program
Version 9.2
Procedures
NMP-EN-002-GL02
Hatch Nuclear Plant Groundwater Monitoring Plan for
Radionuclides
Version 1.1
Procedures
NMP-EN-002-GL04
Radiological GWPP Technical Bases
Version 1.0
Procedures
NMP-ES-036-001
Underground Pipe and Tanks Monitoring Program
Implementation
Version 11
Procedures
Offsite Dose Calculation Manual for Edwin I. Hatch
Nuclear Plant
Version 26
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation
Surveys
Plant Hatch
Radiological
Information Survey #
185685
Routine Survey Unit 2 CST
01/23/2021
Radiation
Surveys
Plant Hatch
Radiological
Information Survey #
186959
U2 CST Routine Survey
2/20/2020
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
Regulatory Assessment Performance Indicator
Guideline
7.0
Corrective Action
Documents
RCE278526
2/18/2020
Corrective Action
Documents
RCE278526
2/18/2020
Corrective Action
Documents
10695910
03/15/2020
Corrective Action
Documents
10707660
05/07/2020
Corrective Action
Documents
10707858
05/08/2020
Corrective Action
Documents
10/28/2020
Corrective Action
Documents
Resulting from
Inspection
10728101
08/05/2020
Corrective Action
Documents
10747434
10/20/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Resulting from
Inspection
Corrective Action
Documents
Resulting from
Inspection
10764815
01/06/2021
Corrective Action
Documents
Resulting from
Inspection
01/06/2021
Engineering
Evaluations
TE 1067120
05/14/2020
Miscellaneous
LER 2020-001-00 for Edwin I. Hatch Nuclear Plant Unit
1, 1A EDG Inoperable Due to Water in the Day Tank
2/10/2020