IR 05000321/2023001

– Integrated Inspection Report 05000321/2023001 and 05000366/2023001

ML23111A291
Person / Time
Site:	Hatch
Issue date:	04/26/2023
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Brown R Southern Nuclear Operating Co
References
IR 2023001
Download: ML23111A291 (27)

Text

April 26, 2023

SUBJECT:

EDWIN I. HATCH, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000321/2023001 AND 05000366/2023001

Dear R. Keith Brown:

On March 31, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch, Units 1 and 2. On April 12, 2023, the NRC inspectors discussed the results of this inspection with Mr. Johnny Weissinger, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, 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:

05000321/2023001 and 05000366/2023001

Enterprise Identifier:

I-2023-001-0024

Licensee:

Southern Nuclear Operating Company, Inc.

Facility:

Edwin I. Hatch, Units 1 and 2

Location:

Baxley, GA

Inspection Dates:

January 01, 2023 to March 31, 2023

Inspectors:

J. Bell, Health Physicist

J. Diaz-Velez, Senior Health Physicist

J. Hickey, Senior Project Engineer

J. Hickman, Resident Inspector

B. Kellner, Senior Health Physicist

M. Magyar, Reactor Inspector

J. Rivera, Health Physicist

R. Smith, Senior Resident Inspector

S. Temple, Resident Inspector

Approved By:

Alan J. Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Edwin I. Hatch, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On January 23, 2023, the unit was down powered to 95 percent RTP to perform an average power range monitor instrumentation calibration and returned to 100 percent RTP on January 25, 2023. On March 11, 2023, the unit was down powered to 70 percent RTP to perform a control rod sequence exchange and turbine valve testing. On March 12, 2023, the unit was returned to 100 percent RTP and operated there for the remainder of the inspection period.

Unit 2 began the inspection period at approximately 95 percent RTP due to its end of cycle coast down for the Cycle 27 refueling outage (2R27). On January 29, 2023, the operators shut down the unit for the scheduled refueling outage. The unit was restarted on February 26, 2023, and reached approximately 100 percent RTP on March 6, 2023. On March 11, 2023, the unit automatically decreased power to approximately 79 percent RTP due to a recirculation pump runback caused by low suction pressure to the condensate booster pumps while lowering hotwell level. The licensee determined the cause of the runback and restored the unit to 100 percent RTP on March 12, 2023. On March 29, 2023, the operators reduced power to approximately 20 percent RTP to perform maintenance on the digital controls for the main generator. After repairs were completed, on March 30, 2023, the operators proceeded to increase power. On March 31, 2023, while operating at 97 percent RTP, operators inserted a manual reactor scram (rapid shutdown), as required by technical specifications, due to the unexpected trip of both reactor recirculation pumps. The unit remained shut down 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of general preparations to protect risk-significant systems from impending severe weather during a Tornado Watch on January 4, 2023.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 2 decay heat removal (DHR) system, during refueling outage 2R27, due to being the primary means of decay heat removal, using procedure 34SO-G71-001-0, on February 6-7, 2023

(2) Unit 2 loop B residual heat removal (RHR) system, during refueling outage 2R27, following inspection of the associated heat exchanger, using 34SO-E11-010-2, on February 8, 2023

(3) Unit 2 reactor core isolation cooling (RCIC) system after being placed in stand-by for plant start-up, using 34SO-E51-001-2, on February 28, 2023

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

(1) The inspectors evaluated system configurations during a complete walkdown of the unit 2 high pressure coolant injection (HPCI) system the weeks of March 20 and March 27, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)

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

(1) Unit 2 turbine building 112-foot elevation on January 12, 2023

(2) Control building 180-foot elevation on January 13, 2023

(3) Control building 112-foot elevation on January 24, 2022

(4) Unit 2 reactor building 130-foot elevation and below on February 9, 2023

(5) Unit 2 reactor building steam chase on February 15, 2023

(6) Unit 2 reactor building 203-foot elevation on March 13, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)

(1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill in the unit 2 C/D switchgear room 130-foot elevation control building, on March 17, 2023.

(2) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill in the unit 1 C/D switchgear room 130-foot elevation control building, on March 24, 2023.

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal and external flooding mitigation protections in the intake building:

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 2 RHR B-division heat exchanger

71111.08G - Inservice Inspection Activities (BWR)

BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding

Activities (IP Section 03.01)

(1) The inspectors evaluated boiling water reactor non-destructive testing by reviewing the following examinations from February 1 - 15, 2023:

03.01.a - Nondestructive Examination and Welding Activities.

1. Ultrasonic Testing

a.

2B11\\2BHD-A, Bottom Head Dome Meridional Weld, Class 1 (observed)b.

2B11\\2BHD-B, Bottom Head Dome Meridional Weld, Class 1 (observed)c.

2B11\\2BHT-E, Bottom Head Torus Meridional Weld, Class 1 (observed)

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the control room during unit 2 plant shutdown for refueling outage 2R27. Specifically, the inspectors observed power decrease operations through reduction of reactor recirculation flow to minimum, insertion of control rods to 20 percent RTP, followed by a main turbine trip. The inspectors observed a further reduction of power, via control rods insertion, to 12 percent RTP in support of a containment entry to inspect for unidentified leakage noted during the operating cycle. The inspectors then observed operators manually insert a reactor scram, to complete the shutdown, and establish a controlled cooldown rate within technical specification limits, on January 28-29, 2023.

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

(1) The inspectors observed and evaluated licensed operator performance in the simulator for just-in-time training, or JITT, to support the unit 2 shutdown for refueling outage 2R27, on January 24, 2023.

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) Primary containment vent T23 and purge valves 2T48-F319 and 2T48-F320 that failed local leak rate test for the penetration and resulted in a containment leakage rate that exceeded the allowable limit, on February 7, 2023

(2) Concrete foundations for the unit 2 500-kilovolt (KV) switchyard towers, on March 15-21, 2023

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Replacement of the unit 2 PSW system flow venturi with ultrasonic transducers under the alternate treatment requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, on February 4, 2023.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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 during critical lift of the 356-kilopound main generator rotor to the turbine deck, in preparation of refueling outage 2R27, on January 11, 2023

(2) Unit 2 elevated risk as the unit entered refueling outage 2R27, on January 30, 2023

(3) Unit 2 elevated risk due to placing the B-division RHR system in shutdown cooling mode prior to reactor cavity drain down, on February 15, 2023

(4) Unit 2 elevated risk due to placing the A-division RHR system in shutdown cooling mode prior to integrated leakage rate test, on February 21, 2023

(5) Unit 1 elevated risk due to a start failure of the A-division emergency diesel generator (EDG) during a monthly surveillance, on March 3, 2023

(6) Unit 1 elevated risk due to the A-division RHR system outage, on March 27, 2023

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) Condition Report (CR) 10936048. Main control room air handling unit, 1Z41-B003B, failure to automatically start on demand.

(2) CRs 10931208, 10931224, 10931346, 10931584. Main control room penetration, 1Z43H661J, breached without a pre-approved barrier impairment checklist.

(3) CRs 10938241, 10939152, and 10939155. RHR snubbers, 2E11RHRR146 and 2E11RHRR245A, failed visual inspection due to having no hydraulic fluid in the reservoir.

(4) CR 10944365. Potential impact to cable jacket insulation due to electro-hydraulic control fluid found in cable trays.

(5) CR 10947938. Swing EDG 1B did not shut down during performance of logic system functional test (LSFT).

(6) CR 10952899. Unit 1 A-division EDG failure to start and common cause failure review.

(7) CR 10957414. Unit 2 HPCI following a high-water level logic actuation.

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) Unit 2 design changes associated with RHR motor-operated valves and breaker coordination of critical instrument buses to meet NFPA 805 commitments.

(2) Unit 2 design change to replace PSW flow venturis with ultrasonic transducers and flow meters to develop a better flow profile, reduce flow uncertainty, and increase data repeatability caused by erosion and aging of the venturis.

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, 2R27, activities from January 28 to March 6, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)

(1) Procedure 34SO-G71-001-0, after replacement of the unit 1 DHR primary pump 1G71C001A, on January 9, 2023

(2) Work order (WO) SNC1441689 and 34SV-R43-021-2, swing EDG 1B retest after replacement of the ES1 relay in the relay terminal box 1R43S001B, on February 14, 2023 (3)57CP-C51-012-0, 57GM-MIC-016-0, and 57IT-C51-001-0, after replacement of six local power range monitor (LPRM) detector strings, on February 15, 2023 (4)42SV-C11-003-0, after replacement of 20 control rod drive mechanisms, four control rod blades, and eight control rod blade shuffle pairs across 16 locations, on February 20, 2023 (5)34SV-R43-004-1, after replacement of the unit 1 A-division EDG governor, on March 3-5, 2023 (6)57SV-R43-001-2, after replacement of the K-19 relay due to unit 2 receiving a "Diesel Generator B loading Timer Failure" alarm, on March 16, 2023 (7)34SV-E11-002-1, 34SO-E11-010-1, and 34SV-E11-001-1, after maintenance on unit 1 RHR valves during a system outage, on March 29, 2023

(8) WOs SNC1455959 and SNC1458235, test of the unit 2 main generator digital excitation system controls (EX2100 EDCF cards on M1, M2, and C controllers), after fuse and power supply replacements, on March 31, 2023

Surveillance Testing (IP Section 03.01) (4 Samples)

(1)34SV-R43-025-2, "Diesel Generator 2C Logic System Functional Test," Version 3.0, on February 1, 2023 (2)34SV-R43-022-2, "Diesel Generator 2C Loss of Coolant Accident / Loss of Offsite Power Logic System Functional Test," Version 2.6, on February 8, 2023 (3)34SV-R43-024-2, "Diesel Generator 1B Logic System Functional Test," Version 4.0, on February 12, 2023 (4)34SV-B21-012-2, "Low Low Set Logic System Functional Test," Version 1.1, and 34SV-B21-010-2, "Main Steam Isolation Valve Logic System Functional Test," Version 1.1, on February 14 and 20, 2023

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1)34SV-E51-002-1, "Reactor Core Isolation Cooling Pump Operability Inservice Test," Version 29.1, on January 4, 2023

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

(1)42SV-TET-001-2, "Primary Containment Periodic Type B & C Leakage Tests," Version 37.3, for main steam isolation valves, on February 2, 2023

Reactor Coolant System Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) CR 10952393. Unit 2 drywell floor drain leakage increase, on March 1, 2023.

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) FLDAIRCOMP3Y-H, "Diesel Air Compressor Performance Test Work Instructions," for the performance test of the flex air compressor, on March 14, 2023

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)

The inspectors evaluated:

(1) Licensed reactor operators respond to a loss of coolant accident in the drywell during a simulator scenario. The inspectors observed the crew make an emergency declaration and notification. This represented a drill and exercise performance opportunity on March 15, 2023.

(2) Licensed reactor operators respond to a loss of coolant accident in the drywell during a simulator scenario. The inspectors observed the crew make an emergency declaration and notification. This represented a drill and exercise performance opportunity on March 22,

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)

(1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Workers exiting the unit 2 drywell contaminated area

(2) Workers exiting the radiologically controlled area (RCA)

(3) Radiation protection technicians surveying bags of dry active waste for disposal

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) Unit 2 A recirculation pump motor replacement

(2) Valve work including safety relief valves and inboard main steam isolation valves in the unit 2 drywell

(3) Welding and grinding activities in the unit 2 condenser bay

(4) Diving activities in the unit 2 torus High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (4 Samples)

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

(1) Unit 2 reactor water cleanup valve nest locked high radiation area (LHRA)

(2) Unit 1 fuel pool cooling heat exchanger LHRA

(3) Unit 2 torus filters LHRA

(4) Unit 1 185-foot east-west hallway very high radiation area 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.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (2 Samples)

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

(1) Main control room ventilation

(2) Unit 1 A and B-trains, and unit 2 B-train, stand by gas treatment in-place filtration and charcoal adsorption test results.

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

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

(1) High efficiency particle air-filter ventilation unit, MCF-9118-2, used on the unit 2 turbine deck

(2) High efficiency particle air-filter ventilation unit, MCF-9118-1, used on the unit 2 turbine deck

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

(1) The inspectors evaluated the licensees use of respiratory protection devices. Reviewed respiratory protection equipment used during the outage, air sampling results during the outage, total effective dose equivalent (TEDE) as low as reasonably achievable (ALARA) evaluations for selected work activities, verified self-contained breathing apparatus (SCBA) respirator use, and qualifications of selected licensee employees, including shift control room operators, and SCBA glasses availability and use.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of SCBAs. Reviewed annual Posi3 USB Regulator Test Results for SCBA Kit number 851 and 863 (regulator serial numbers (SNs) e0040150d39cdd89 and e0040150d39d4d5a).

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

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

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (3 Samples)

The inspectors evaluated the following internal dose assessments:

(1) The inspector reviewed a whole-body counter dosimetry assessment (worker #1)

(2) The inspector reviewed a whole-body counter dosimetry assessment (worker #2)

(3) The inspector reviewed a whole-body counter dosimetry assessment (worker #3)

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

The inspectors evaluated the following special dosimetric situations:

(1) The inspector reviewed a declared pregnant worker (DPW) dose assessment that occurred between February 2022 and February 2023 (DPW #1)

(2) The inspector reviewed a DPW dose assessment that occurred between February 2022 and February 2023 (DPW #2)

(3) The inspector reviewed an extremity dose assessment that occurred between February 2022 and February 2023 (worker #3)

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (9 Samples)

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

(1) Portable ion chambers ready for use in the instrumentation lab

(2) Portable Geiger Muller detectors ready for use in the instrumentation lab

(3) Portable wide range telescopic survey meters ready for use in the instrumentation lab

(4) Continuous air monitors in the unit 2 reactor building

(5) Portable neutron survey meters ready for use in the instrumentation lab

(6) Small article monitors at the RCA exit

(7) Portal monitors at the RCA exit and protected area exit

(8) Personnel contamination monitors at the RCA exit

(9) Area radiation monitors in the unit 2 reactor building

Calibration and Testing Program (IP Section 03.02) (12 Samples)

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

(1) SAM-12, SN 286

(2) GEM-5, SN 1301-016

(3) ARGOS-5AB, SN 1301-002

(4) RO-20, SN 4197

(5) Ludlum-3, SN 273271

(6) Telepole, SN 0173

(7) Telepole, SN 6615-060

(8) AMS-4, SN 1903

(9) AMS-4, SN 1900

(10) REM Ball, SN 1354 / 4641

(11) Unit 2 drywell high range area radiation monitor, no. 57SV-D11-019-2

(12) Hatch whole body counter, HNP-DO Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

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

(1) WO SNC1106409, unit 1 main stack radiation monitor calibration, August 3, 2021

(2) WO SNC1135551, unit 1 liquid radwaste radiation monitor calibration, July 20,

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 02.01)===

(1) Unit 1 (January 1, 2022 to December 31, 2022)

(2) Unit 2 (January 1, 2022 to December 31, 2022)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)

(1) Unit 1 (January 1, 2022 to December 31, 2022)

(2) Unit 2 (January 1, 2022 to December 31, 2022)

IE04: Unplanned Scrams with Complications Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (January 1, 2022 to December 31, 2022)

(2) Unit 2 (January 1, 2022 to December 31, 2022)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) February 1, 2022 to February 9, 2023

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

(1) CR 10925361 and corrective action report (CAR) 332462. Review of corrective actions for a fire water main rupture, on February 1, 2023

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) Semi-annual trend review of steam leaks for both units during cycle year 2022 71153 - Follow Up of Events and Notices of Enforcement Discretion Event Follow-up (IP section 03.01) (1 Partial Sample)

(1)

(Partial)

The inspectors evaluated a manual reactor scram on unit 2 following a loss of both recirculation pumps and the licensees initial response on March 31, 2023. A follow-up inspection of this event (NRC Event Notification 56446) will be completed during the second quarter of

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On April 12, 2023, the inspectors presented the integrated inspection results to Mr. Johnny Weissinger, Site Vice President (SVP), and other members of the licensee staff.

On February 22, 2023, the inspectors presented the radiation safety inspection (IP71124)results to Mr. Johnny Weissinger, SVP, and other members of the licensee staff.

On February 15, 2023, the inspectors presented inservice inspection (IP71111.08G)results to Mr. Johnny Weissinger, SVP, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.01

Procedures

34AB-Y22-002-0

Naturally Occurring Phenomena

20.2

Condition Report

(CRs)

10780157, 10780410, 10780501, 10783270, 10783779,

10788423, 10788425, 10797252, 10797254, 10797255,

10797478, 10797539, 10797548, 10797559, 10797737,

10798027, 10808367, 10813160, 10824117, 10836779,

10847170, 10854350, 10854912, 10855148, 10855514,

10856192, 10856252, 10857745, 10870105, 10874276,

10883964, 10883987, 10884556, 10884651, 10884712,

10884729, 10884852, 10884877, 10884944, 10885072,

10885091, 10885941, 10890566, 10898583, 10903140,

10908138, 10916168, 10916446, 10932902, 10933182,

10933370, 10933414, 10944008, 10945151, 10946095,

10947530, 10948568, 10949002, 10949236, 10949437,

10951521, 10952186, 10926166, 10927088, 10930268,

10931128, 10931906, 10932866, 10937218, 10940570,

10942319, 10943344, 10943377, 10944008, 10944919,

10947422, 10951693, 10951883, 10892107, 10892178,

10892291, 10896990, 10898137, 10900349, 10900709,

10906813, 10906911, 10907552, 10907564, 10910224,

10910665, 10911511, 10916570, 10927362, 10929514,

10932064, 10932511, 10936892, 10936911, 10937624,

10937647, 10938156, 10938228, 10938317, 10939577,

10941302, 10943411, 10944277, 10945682

Various

Corrective Action

Documents

Corrective Action

Report (CAR)

255432

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

(CR)

10951752, 10951754

Drawings

H-26020, 26021

HPCI System P&ID Sheets 1 and 2

2.0, 41.0

71111.04

Engineering

Evaluations

Technical

Evaluations (TEs)

1118823, 1118776

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Miscellaneous

Danger 2-DT-R27

Tagout Clearance 2-DT-23-2E11-03001(3) for RHR Heat

Exchanger

2/08/2023

34SO-E11-001-2

ATT 13

Venting RHR Loop A(B) Piping

45.2

34SO-E11-010-2

Residual Heat Removal System

45.2

34SO-E41-001-2

High Pressure Coolant Injection (HPCI) System

31.2

34SO-E51-001-2

Reactor Core Isolation Cooling (RCIC) System

28.4

34SO-G71-001-0

Decay Heat Removal System

19.1

Procedures

34SV-E41-002-2

HPCI Pump Operability

39.2

Corrective Action

Documents

Condition Report

(CR)

10960416

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

(CR)

10553429, 10956429, 10958643

NMP-ES-035-

019-GL02-F01

Control Building ELEV 112'

1.0

NMP-ES-035-

019-Gl02-F05

Control Building 180-foot elevation.

1.0

NMP-ES-035-

019-GL02-F25

U2 Turbine Building ELEV 112'

1.0

NMP-ES-035-

019-GL02-F33

U2 Reactor Building ELEV 203-Foot

1.0

Fire Plans

NMP-ES-035-

GL02-F29

Unit 2 Reactor Building Elevation 130 foot and below.

1.0

Miscellaneous

Drill S-FP-115

(Fire Drill 1)

Charlie Team Evaluation Form

03/17/2023

NMP-TR-425-F01

Fire Drill Scenario Development and Approval Sheet (Unit 1

C/D SWGR Room 130-foot Control Building)

6.0

NMP-TR-425-F01

Fire Drill Scenario Development and Approval Sheet (Unit 2

C/D SWGR Room 130-foot Control Building)

6.0

Procedures

NMP-TR-425-F14

Fire Drill Package

4.0

71111.05

Work Orders

Work Order

(SNC)

208789

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

H-RIE-IF-U00-001

Hatch Internal Flood Notebook - Tasks 1, 2, and 3

10/03/2018

H-RIE-IF-U00-002

Hatch Internal Flooding Notebook - Task 4 - Documentation

of flood area qualitative screening

10/05/2018

H-RIE-IF-U00-006

Hatch Flood Notebook, Task 9, PRA Modeling of Flood

Scenarios

10/05/2018

H-RIE-U00-003

Hatch Flood Notebook - Task 5 - Characterization of Flood

Scenarios

10/05/2018

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

Hatch Final Safety Analysis Report, Sections 2.4 and 9.3

35.0

Miscellaneous

E. I. Hatch Individual Plant Examination

2/01/1992

34AB-P41-001-2

Loss of Plant Service Water

13.13

71111.06

Procedures

34AB-X43-002-0

Fire Protection System Failures

4.3

Corrective Action

Documents

Condition Report

(CR)

10945505, 10946536

Procedures

NMP-ES-012-F01

Heat Exchanger Inspection Report

1.0

71111.07A

Work Orders

Work Order

(SNC)

1016455

23-001

2R27 Outage Shutdown JITT

01/20/2023

Miscellaneous

Form 6: Just-In-

Time Training

2R27 Outage Shutdown JITT

01/23/2023

71111.11Q

Procedures

NMP-RE-008-F01

Detailed Reactivity Management Plan (Hatch - Unit 2 Cycle

27)

07/28/2023

Condition Reports

(CRs)

2479, 10946502, 10946508

Various

Corrective Action

Documents

Corrective Action

Report (CAR)

210108

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

(CRs)

10947418, 10951946

Various

71111.12

Drawings

H29256

Plant Hatch Unit NO. 2 Substation Conc. 500 KV Switchyard

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Tower Caissons & Fdns. NL & Reinf.

SNC1266997

U2 PSW Pump Venturi Replacement DECP

Engineering

Changes

SNC1440523

Change Orientation of Valve Disc (2T48-F319/F320)

2/14/2023

RER C100305001

2010 Structural Monitoring Inspection

03/01/2011

RER SNC546900

Plant Hatch Unit 1 Structural Monitoring Inspection Report -

2014

03/19/2016

Engineering

Evaluations

RER SNC921613

Plant Hatch Unit 1 Structural Monitoring Inspection Report -

2018

09/11/2018

200 T-ring Interchangeability

2/25/2021

Letter from

Vendor Emerson

U2 Primary Containment Vent and Purge Valve Failures

Licensee White

Paper

Discussion of the LLRT Failure Causes for the 2T48 Primary

Containment Isolation Valves

2/17/2023

NRC Event

Notification (EN)

563342

Appendix J Program - LLRT Penetration Failure Associated

with 2T23-X026 (2T48-F319 & 2t48-F320)

07/07/2023

Purchase Order

SNG10285421

Dual Channel Permanent Flow Meters

04/26/2022

Purchase Order

SNG10285421(1)

PSW Ultrasonic Flowmeters

04/24/2022

Purchase Order

SNG10300549

Flexim Dual Triax Transducer Extension Cables

2/02/2022

Miscellaneous

Purchase Order

SNG10300549(1)

PSW Ultrasonic Transducers

2/02/2022

2SV-TET-001-0

Unit 2 LLRT 2T48-F319 & 2T48-F320

2/15/2023

MNP-ES-027

Maintenance Rule Program

9.0

NMP-AD-002-F08

Support/Refute Matrix (2T48-F319/F320 Valves)

1.0

NMP-ES-021

Structural Monitoring Program for the Maintenance Rule

2.0

Procedures

NMP-ES-065

CFR 50.69 Program

5.0

SNC1388269

2A PSW Pump Venturi Replacement

2/15/2023

SNC1388271

2C PSW Pump Venturi Replacement

2/15/2023

SNC1390416

2A PSW Pump Ultrasonic flow Transmitter installation.

2/18/2023

Work Orders

(SNC)

SNC1404826

2R27-Install permanent power to the new venturi flow

meters.

2/18/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Condition Report

(CR)

10953467

Corrective Action

Documents

Resulting from

Inspection

Condition Report

(CR)

10948481, 10950293

Unit 1 RICT On-Line Configuration Risk Monitor Current

Risk Summary Report

03/03/2023

Unit 1 RICT On-Line Configuration Risk Monitor Current

Risk Summary Report

03/27/2023

1-ET-23-1E11-

00106

Equipment Tagout - RHR Loop 1A for System Outage

3/25/2023

2-ET-23-1G71-

0016

Equipment Tagout - Decay Removal System (U1 203-foot

RB, R/R Airlock Roof)

01/2702023

Miscellaneous

2-ET-23-2E11-

00025 (1)

Equipment Tagout - 2A RHR for SDC Unit 2 Outage 2R27

2/21/2023

34GO-OPS-007-0

Shutdown/Refueling Mode Preparation Strategy For Flex

1.2

34GO-OPS-024-0

Outage Safety Assessment

5.5

NMP-GM-031

On-Line Configuration Risk Management Program

6.0

71111.13

Procedures

NMP-OS-010-02

Hatch Protected Equipment Logs

2.3

Corrective Action

Documents

Condition Reports

(CRs)

10957414, 10960409, 10952899, 10953174, 10944365,

10936048, 10936047, 10943940, 10931208, 10931224,

10931346, 10931584

Various

H-17159

Unit 1 High Pressure Coolant Injection System E41

Elementary Sheet 3

30.0

H-17160

Unit 1 High Pressure Coolant Injection System E41

Elementary Sheet 4 Of 11

H-23775

Edwin I. Hatch Nuclear Plant Elementary Diagram - 2R43B

Diesel Generator 2B Sheet 3

17.0

Drawings

H17073

Control Building Control & Cable Spreading Rooms Air

Conditions System Z41 Elementary Diagram Sheet 6

RBA-23-001-H

Evaluation of NFPA-805 Impacts From EHC Oil Spill

2/08/2023

71111.15

Engineering

Evaluations

Request for

Engineer Review

Evaluation of Insulation Integrity of Cables Exposed to EHC

Fluid

2/21/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

(RER)

Technical

Evaluations (TEs)

1117219, 1117743, 1118315

Various

Condition Reports

(CRs)

10931208,

10931224,

10931346

Crew Learning: Control Room Envelope

1-LCO-22-00216

MCR AHU 1Z41B003C is Inoperable and 1Z41B003B

Remains Tracking with Failure to Auto Start in Standby.

01/04/2023

Miscellaneous

2-LCO-22-00113

Control Room Envelope Seal Penetration 1Z43H661J

2/13/2022

34SO-Z41-001-1

Control Room Ventilation System

24.0

2EN-Z41-001-0

Control Room Habitability Program (Attachment 1)

2.0

NMP-MA-050

Work Package Preparation

2.2

Procedures

NMP-MA-050-F02

Work Planner Checklist MWO

4.0

Corrective Action

Documents

Resulting from

Inspection

Condition Report

(CR)

10951946

H-53194

Unit 2 Electrical Equip. Layout Partial Plans Control Building

1.0

H-53195

Unit 2 Electrical Equip. Layout Sections & Details Sheet 2 of

1.0

H-58347

Wiring Diagram PSW Ultrasonic Flow Transmitters

Drawings

SNC

1305918C001, 1305918C002, 1305918E001,

1305918E101, 1305918E004, 1305918SK01, 1305918SK02

Engineering

Changes

SNC1266997

Unit 2 PSW Pump Venturi Replacement DECP

Procedures

NMP-ES-065

CFR 50.69 Program

5.0

SNC1388270

2B PSW Pump Venturi Replacement

2/05/2023

SNC1388273

2D PSW Pump Venturi Replacement

2/05/2023

71111.18

Work Orders

Work Order

(SNC)

9808800, 1305918, 1364612, 1364945

Various

NMP-OS-009-F01 Restart Review Checklist

2/24/2023

71111.20

Miscellaneous

List of Temp Mods and Mods Implementation for 2R27

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Refueling Outage

Fitness for Duty Records Reviewed for Maintenance,

Operations and Security for 2R27 Refueling Outage

2/27/2023

PRB Meeting

23-004

Startup PRB - H2R27

2/23/2024

34-GO-OPS-015-

Maintaining Cold Shutdown Or Refueling Conditions

16.2

34GO-OPS-001-2

Plant Startup

51.12

34GO-OPS-013-2

Normal Plant Shutdown (Attachment 1:

Cooldown/Depressurization Checks)

01/29/2023

NMP-MA-007-001

SNC Rigging and Lifting Program Planning and Evaluation

to Lift Generator Rotor Field to the Turbine Deck

2/13/2022

NMP-OM-002

Appendix A

H2R27 Shutdown Safety Assessment (Summary Report

Meeting Final Report)

01/12/2023

NMP-OS-019-253

Hatch Unit C SIG-12, Mode 4/5 RPV Inventory Control

2.3

Procedures

NMP-RE-008-F01

Detailed Reactivity Management Plan (H2C28-022623-001)

2/25/2023

Corrective Action

Documents

Condition Reports

(CR)

10952393, 10952877

Various

Corrective Action

Documents

Resulting from

Inspection

Condition Reports

(CRs)

10944592

Unit 2 2023 New LPRM (44-21, 36-37, 12-37, 44-37, 20-

21,12, & 12-21) IV Curves and TDR Curves.

LPRM Phase 3 Data

2/16/2023

Miscellaneous

LPRM Maintenance Overview Summary 2R27

2/13/2023

34SO-E11-010-1

Residual Heat Removal System

46.4

34SO-G71-001-0

Decay Hear Removal System

19.1

34SV-B21-010-2

MSIV LSFT

1.1

34SV-B21-012-2

Low Low Set LSFT

1.1

34SV-E11-001-1

Residual Heat Removal Pump Operability

30.1

34SV-E11-002-1

RHR Valve Operability

21.6

34SV-R43-004-1

Diesel Generator 1A Fast Start Test

16.5

71111.24

Procedures

34SV-R43-021-2

Diesel Generator 1B LOCA/LSFT

2.5

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

34SV-R43-022-2

Diesel Generator 2C LOCA/LOSP LSFT

2.6

34SV-R43-024-2

Diesel Generator 1B LSFT

4.0

34SV-R43-025-2

Diesel Generator 2C LSFT

3.0

2-SV-TET-001-0

Unit 2 LLRT 2T48-F0319 & 2T48-F320

2/15/2023

2SV-C11-003-0

Control Rod Scram Testing

2.3

2SV-TET-001-2

Primary Containment Periodic Type B & Type C Leakage

Tests (MSIV)

37.3

57CP-C51-012-0

LPRM I/V Curve Using GE Provided Laptop Program Data

Sheet

20.5

57GM-MIC-016-0

LPRM Cables And Connectors

2.2

57IT-C51-001-0

Neutron Monitoring System Detector Pre-Installation Tests 5.5

57SV-R43-001-2

Testing The LOCA/LOSP Timer Cards

7.2

FLDAIRCOMP3Y-

H

Diesel Air Compressor Performance Test Work Instructions

03/14/2023

NMP-AD-002-F04

Troubleshooting Log (1A EDG)

1.1

NMP-AD-002-F04

Troubleshooting Log (SNC1016160)

2/15/2023

NMP-MA-014-001

Post Maintenance Testing Guidance

5.9

NMP-OS-028

Adverse Condition Monitoring Program (Elevated U2 DWFD

Leakage Rate Post 2R27)

1.0

Work Orders

Work Order

(SNC)

2121, 802502, 901917, 961089, 1005194, 1015835,

1016592, 1100646, 1277279, 1290006, 1359065, 1399047,

1399048, 1399049, 1399053, 1399054, 1399061, 1450172,

1450216, 1450217, 1453110, 1455959, 1458235

Various

Emergency Preparedness Observation Form

03/22/2023

Emergency Preparedness Observation Form

03/15/2023

71114.06

Miscellaneous

H-LR-AF-00107

Reactor Feed Pump Turbine Cooling, Safety Relief Valve

Open, Loss of Feedwater Heating, Loss of Coolant Accident

in the Drywell (DW), DW Spray Failure, Reactor Core

Isolation Cooling Controller Failure

2.0

Corrective Action

Documents

Condition Reports

(CRs)

10792304, 10893012, 10893861, 10823349, 10775455,

10788677, 10802977, 10811301, 10819111, 10828518,

10838217, 10863205, 10890283, 10903314, 10906532, and

10924133

Various

71124.01

Corrective Action

CR 10946360

NRC comment concerning swing gate at High Radiation

2/7/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Area boundary of U2 TIP Room

CR 10946444

NRC Observation (Contaminated Area Boundary Needing

Improvement)

2/7/2023

CR 10946460

NRC Observation ("Contact RP" Ladder Labeling

Inconsistency)

2/7/2023

CR 10946840

Red flashing light needs bulb replaced.

2/08/2023

CR 10947178

Alpha contamination surveys not utilizing the highest smears

consistently

2/09/2023

Documents

Resulting from

Inspection

CR 10948496

High Radiation Area boundary postings in the Unit 2A

condenser did not Include all accessible points

2/15/2023

2018 Alpha characterization study

11/05/2018

NMP-HP-204-F06

Respirator Use Evaluation Worksheet (TEDE ALARA

Evaluation) for RWP 23-2602, U2 DW Initial Entry Surveys

7/8/2022

NMP-HP-204-F06

Respirator Use Evaluation Worksheet (TEDE ALARA

Evaluation) for RWP 23-2204

2/9/2022

Miscellaneous

NMP-HP-205-F06

Respirator Use Evaluation Worksheet (TEDE ALARA

Evaluation) for RWP 23-2615, CRD Removal/Replacement

1/31/2023

NMP-HP-300

Radiation and Contamination Surveys

5.8

Procedures

NMP-HP-302

Restricted Area Classification, Postings, and Access Control

2.9

Radiation

Surveys

203370

Unit 2 360 degree platform

2/07/2023

Radiation Work

Permits (RWPs)

23-2622

Unit 2 refuel outage high radiation area activities in the

drywell

Corrective Action

Documents

Condition Reports

(CRs)

10773429, 10796005, 10852194, 10872403, 10873344,

10881500, 10929659, and 10937326

Various

CR 10948467

NRC Comment - NRC RP Inspection - Respirator Wash

Room

2/15/2023

Corrective Action

Documents

Resulting from

Inspection

CR 10948469

NRC Comment - NRC RP Inspection - Hatch Site

procedures overlap and/alignment with Fleet RP procedure.

2/15/2023

Quarterly Grade "D" Air Analysis Results for Multiple

Systems (Unit 1 and Unit 2 service air compressors, Eagle

air compressor (SCBAs). [3rd qtr. 2022]

7/22/2022

71124.03

Miscellaneous

Quarterly Grade "D" Air Analysis Results for Multiple

Systems (Unit 1 and Unit 2 service air compressors, Eagle

1/27/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

air compressor (SCBAs). [1st qtr. 2023]

Respirator Issue Log - January 29 to February 7, 2023

Various

NMP-HP-501-

003, Data Sheet 1

In-Use Respirator Inspection Worksheet (July 2022)

8/10/2022

Self-Assessments TE#: 1097224

22 Pre-NRC Radiation Protection (RP) Check-In Self-

Assessment

WO #

SNC839149

Testing of Control Room Habitability Filter Trains (B Train

Charcoal Adsorber sample and analysis)

9/9/2021

WO #

SNC992454

Testing of Control Room Habitability Filter Trains (B Train

Charcoal Adsorber sample and analysis)

1/24/2023

Work Orders

Work Order (WO)

1. SNC805890

Testing of Control Room Habitability Filter Trains (A Train

Charcoal Adsorber sample and analysis)

9/9/2021

71124.04

Corrective Action

Documents

Condition Reports

(CRs)

10778929, 10818336, 10818338, 10818339, 10818341,

10818343, 10864491, 10906532, 10908820, and 10927138

Various

CR 10788003

Training Request from Performance Analysis - Evaluating

Unknown Peaks on WBC Reports.

04/05/2021

CR 10851676

WSTSF RM 25 #697 OOS.

01/17/2022

CR 10912755

AMP-100s S/N 5505-131 and 5006-146 found outside of

acceptable calibration tolerance limits.

10/06/2022

Corrective Action

Documents

CR 10939799

U2 Reactor Building Vent Radiation Monitor Not Functioning

Correctly

01/15/2023

CR 10946424

The ARM on the upper elevation of the Main Stack alarms

intermittently.

2/7/2023

CR 10947302

Adverse Trend - RB Vent Stack Rad Monitors

2/10/2023

CR 10948458

Lessons Learned - RP NRC Inspection Slow to Respond

2/15/2023

71124.05

Corrective Action

Documents

Resulting from

Inspection

CR 10950640

Gaps in the NRC 2023 RP CISA and initial information

request

2/22/2023

Unit 2 Power History Curves for Quarters 1, 2, 3 & 4 2022

Unit 1 Power History Curves for Quarters 1, 2, 3 & 4 2022

Unit 2 Control Room Operator Logs for 2022

Unit 1 Control Room Operator Logs for 2022

71151

Miscellaneous

NRC Licensee

Event Report:

LER 2022-001-00

Manual Reactor Scram due to Reactor Pressure

Perturbations

2/18/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Condition Report

(CR)

10925361

71152A

Corrective Action

Documents

Corrective Action

Report (CAR)

2462

Corrective Action

Documents

Condition Reports

(CR)

10847628, 10847670, 10847873, 10847919, 10848192,

10848210, 10848212, 10848274, 10848702, 10848760,

10849432, 10852590, 10854350, 10854912, 10855148,

10855514, 10856630, 10856718, 10863403, 10863515,

10863579, 10863937, 10863938, 10863992, 10864838,

10866195, 10868234, 10868825, 10869084, 10872650,

10872825, 10876920, 10877272, 10882194, 10883087,

10883964, 10884712, 10885749, 10887810, 10891422,

10893017, 10893859, 10900807, 10902200, 10904223,

10906852, 10907730, 10915419, 10915439, 10915569,

10915889, 10916820, 10919352, 10919470, 10919786,

10920506, 10920526, 10923219, 10926624, 10927777,

10929993, 10930947, 10931553, 10933322, 10933510,

10937689, 10942429, 10943500, 10943533, 10963403,

10857209, 10857366, 10857829, 10859427, 10921534,

10924335, 10945502, 10946038, 10949197, 10856648

Various

H-11250

RFP Seal Water, Leakoff and Drains

H-11604

Unit 1 PI&D Condensate & Feedwater System Sheet 3

54.0

H-11605

Unit 1 PI&D Condensate & Feedwater System Sheet 4

2.0

H-21031

Unit 2 Main & RFP Turbine Drains P&ID

54.0

H-21038

Unit 2 Condensate & Feedwater P&ID Sheet 2 of 3

17.0

H-46540

Unit 1 Condensate/Feedwater FAC Inspection Isometric

2.0

H-46540

Unit 1 Condensate/Feedwater FAC Inspection Isometric

(Denotes Inspection Component Numbers)

2.0

H21014

Unit 2 Extraction Steam P&ID

29.0

H21070

Unit 2 Extraction Steam To Steam To 1oth Stage LP

Heaters

2.0

H51132

Unit 2 Extraction Steam To 10th Stage Heaters FAC

Inspection Isometrics

18.0

71152S

Drawings

H51756

Core Spray System Pump A Discharge To RPV Storage

2.0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Tank FAC Inspection Isometrics

H52064

Unit 2 12th Stage Heater Vents FAC Inspection Isometrics

8.0

Engineering

Evaluations

Technical

Evaluation (TE)

1093008

Work Orders

Work Orders

(SNC)

0572272, 0646586, 1000653, 1000654, 1000655, 1095818,

1110822, 1140706, 1144133, 1144831, 1196853, 1196854,

208904, 1217443

Various

34AB-C71-001-2

Scram Procedure

14.3

71153

Procedures

34GO-OPS-013-2

Normal Plant Shutdown

33.7