IR 05000321/2018003

Nuclear Regulatory Commission Integrated Inspection Report 05000321/2018003 and 05000366/2018003

ML18317A419
Person / Time
Site:	Hatch
Issue date:	11/08/2018
From:	Alan Blamey NRC/RGN-II
To:	Vehec T Southern Nuclear Operating Co
References
IR 2018003
Download: ML18317A419 (17)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 8, 2018

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000321/2018003 AND 05000366/2018003

Dear Mr. Vehec:

On September 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Edwin I. Hatch Nuclear Plant Units 1 and 2. On October 25, 2018, the NRC inspectors discussed the results of this inspection with Richard Spring and other members of your staff. The results of this inspection are documented in the enclosed report.

NRC inspectors documented one finding of very low safety significance (Green) in this report.

This finding involved a violation of NRC requirements. The NRC is treating this violation as non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of this NCV, 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 the Edwin I. Hatch Nuclear Plant Units 1 and 2.

If you disagree with a cross-cutting aspect assignment, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC resident inspector at the Edwin I. Hatch Nuclear Plant Units 1 and 2. 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Alan Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos.: 50-321, 50-366 License Nos.: DPR-57 and NPF-5

Enclosure:

IR 05000321/2018003, 05000366/2018003

Inspection Report

Docket Number(s): 50-321, 50-366 License Number(s): DPR-57, NPF-5 Report Number(s): 05000321/2018003; and 05000366/2018003 Enterprise Identifier: 2018-003-0040 Licensee: Southern Nuclear Operating Company, Inc.

Facility: Edwin I. Hatch Nuclear Plant Location: Baxley, Georgia Inspection Dates: July 1, 2018 to September 30, 2018 Inspectors: C. Jones, Senior Resident Inspector J. Hickman, Resident Inspector J. Viera, Operations Engineer A. Goldau, Operations Engineer Approved By: A. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting baseline inspections 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. NRC and self-revealed findings, violations, and additional items are summarized in the table below. Licensee-identified non-cited violations are documented in the Inspection Results section of the Report.

List of Findings and Violations Inoperability of 2A Emergency Diesel Generator Due to Inadequate Acceptance Criteria for Determining Cleaning Requirements of Emergency Diesel Generator Day Tanks Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Self-Revealing Green Non-Cited H.1 - Resources 71111.22 Systems Violation (NCV)05000366/2018003-001 Opened/Closed A Self Revealing Green NCV of Unit 2 Technical Specification 5.4.1(a) for the licensees failure to incorporate preventative maintenance criteria for Emergency Diesel Generator (EDG) day tanks as recommended by Regulatory Guide (RG) 1.33, 9.a. Specifically, procedure 52SV-R43-001-0, Diesel, Alternator, and Accessories Inspection, Ver. 30.4, did not contain deterministic criteria in the visual inspection of the fuel filters to initiate the cleaning of the EDG day tanks and thus prevent EDG inoperability. The EDG day tanks had never been inspected and cleaned.

PLANT STATUS

Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On September 9, 2018, power was reduced to 70 percent to replace Control Rod 1C11H50-35 accumulator level switch. The unit returned to 100 percent RTP on September 10, 2018, and operated at or near 100 percent RTP for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent RTP and operated at or near 100 percent RTP 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.

71111.01 - Adverse Weather Protection External Flooding

The inspectors evaluated readiness to cope with external flooding on September 17, 2018.

71111.04 - Equipment Alignment Partial Walkdown

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

(1) Diesel Fire Pumps (FP-2 and FP-3) following relief valve replacements on July 26, 2018.

(2) Unit 2, Reactor Core Isolation Cooling (RCIC) system following an operability surveillance on September 5, 2018.

(3) Unit 1, 1C EDG following maintenance outage on September 11, 2018.

71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Cable Spreading Room, Fire Zone 0024A on July 11, 2018.

(2) Unit 2, RCIC Pump and Turbine Room, Fire Zone 2203A on July 23, 2018.

(3) Unit 2, South East Residual Heat Removal & Core Spray Pump Room, Fire Zone 2205B on July 27, 2018.

(4) Unit 2, High Pressure Coolant Injection Pump Room, Fire Zone 2205Z on August 29, 2018.

(5) Unit 1, Standby Gas and HVAC Room, Fire Zones 1205N and 1205Q, on September 4, 2018.

Annual Inspection (1 Sample)

The inspectors evaluated fire brigade performance on September 6, 2018.

71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated a crew of licensed operators in the plants simulator during licensed operator requalification training on August 16, 2018.

Operator Performance (1 Sample)

(1) The inspectors observed and evaluated Unit 1 Reactor Operator performance during Traversing In-core Probe System Operation and Local Power Range Monitor calibration on July 24, 2018.

(2) The Inspectors observed and evaluated Unit 2 Reactor Operator performance during RCIC operability test on September 5, 2018.

Operator Requalification Program (1 Sample)

The inspectors evaluated the operator requalification program from August 20, 2018 to August 23, 2018 and on September 26, 2018.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Review of the Licensees (a)(3) Periodic Evaluation on September 27, 2018.

Quality Control (2 Samples)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issues:

(1) 1B/D RHR pump motor lube oil sampling and replacement on July 20, 2018.

(2) Diesel oil commercial grade dedication on August 30, 2018.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Unit 1 and Unit 2 elevated risk due to both Diesel Fire Pumps were removed from service for maintenance on August 2, 2018.

(2) Unit 1 elevated risk due to 1A Standby Gas Treatment System maintenance outage on July 12, 2018.

(3) Unit 1 and Unit 2 elevated risk due to 1B EDG inoperability on August 16, 2018.

(4) Unit 1 elevated risk due to 1C EDG planned outage and impending adverse weather (Hurricane Florence) on September 12, 2018.

71111.15 - Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1 - 1D Startup Auxiliary Transformer (SAT) dissolved hydrogen found to be elevated on July 18, 2018.

(2) Unit 2 - 2B Drywell Chiller outboard motor bearing found to be leaking oil on August 14, 2018.

(3) Unit 1 and Unit 2 - Cracks found on battery cell covers on August 30, 2018.

(4) Unit 2 - RCIC secured due to high barometric condenser level during operability test on Sep 7, 2018.

(5) Unit 2 - Recorder 2T48-R607A alarm set-point found out of tolerance on September 13, 2018.

(6) Unit 2 - HPCI Pump discharge check valve found to be leaking on September 24, 2018.

71111.18 - Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 1 Plant Service Water (PSW) Division 1 non-code leak repair on July 18, 2018.

71111.19 - Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) NMP-ES-051-002, Tan Delta Testing after underground cable replacement for 2D RHR Service Water Pump motor on July 7, 2018.

(2) 34SV-T46-003-1, Standby Gas Treatment (SBGT) Ventilation and Operability Test after 1A SBGT check valve replacement on July 20, 2018.

(3) NMP-RE-008-F01, Detailed Reactivity Plan for return of Control Rod 1C11H50-35 to service and perform 42CC-ERP-011-0, Scram Time Testing, following the replacement of the control rod accumulator level switch on September 9, 2018.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) 34SV-E21-001-2, Core Spray Pump Operability, Ver. 23.4.

(2) 34SV-E21-001-1, Core Spray Pump Operability, Ver. 23.4.

(3) Work Order SNC823977, SBGT control switch replacement.

(4) 34SV-R43-005-1, Diesel Generator 1B Semi-Annual Test, Ver. 17.1.

In-service (1 Sample)

(1) 34SV-E51-002-1, RCIC Pump Operability, Ver. 28.0.

71114.06 - Drill Evaluation Emergency Planning Drill

The inspectors evaluated a simulator based emergency scenario on August 16,

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below for the period from July 2017 through June 2018

(1) Emergency AC Power Systems, MS06, both units.

(2) High Pressure Injection Systems, MS07, both units.

(3) Residual Heat Removal Systems, MS09, both units.

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues

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

(1) Operator workarounds (CRs 10509207, 10337665, 10524395, 10504595, and 10496677).

(2) Battery Charger Issues (CRs 10520948, 10522621, 10524379, 10528024, 10530041, and 10530384).

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation The inspectors evaluated the licensees independent spent fuel storage installation cask campaign from July 9, 2018 to September 28,

INSPECTION RESULTS

Inoperability of 2A EDG Due to Inadequate Acceptance Criteria for Determining Cleaning Requirements of Emergency Diesel Generator Day Tanks Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green NCV H.1 - Resources 71111.22 Systems05000366/2018003-001 Opened/Closed

Introduction:

The inspectors documented a Green, self-revealing, non-cited violation of Unit 2 Technical Specification 5.4.1(a) for the licensees failure to incorporate preventative maintenance criteria for Emergency Diesel Generator (EDG) day tanks as recommended by Regulatory Guide (RG) 1.33, 9.a. Specifically, procedure 52SV-R43-001-0, Diesel, Alternator, and Accessories Inspection, Ver. 30.4, did not contain deterministic criteria in the visual inspection of the fuel filters to initiate the cleaning of the EDG day tanks and thus prevent EDG inoperability. The EDG day tanks had never been inspected and cleaned.

Description:

On May 29, 2018, during the performance of the 2A EDG 24-month operability surveillance, 34SV-R43-001-2, the licensee discovered a high differential pressure across the fuel oil duplex filter. Operations shifted duplex filters due to low fuel oil pressure at the fuel header supply. After shifting filters, the differential pressure initially decreased but increased again to higher than normal levels. A work order was generated for maintenance to install new filters while the EDG was running, since there were no operating procedures to perform the installation of new filters. However, due to the fuel oil pressure to the 2A EDG reaching the Operations established critical parameter (10psi header pressure) and lowering at a rate of approximately 1 psi per minute, the operators secured the EDG prior to installing the new filter. Therefore, although the EDG did not trip, the EDG was declared inoperable due to a degraded fuel oil system and a failed Technical Specification Surveillance 3.8.1.12.

Investigation revealed the 2A EDG fuel oil day tank was found to have increased levels of water which most likely led to the microbiological fouling of the fuel and the clogging of the duplex strainers. An increasing trend in the fuel filter differential pressure and industry Operating Experience (OE), indicating the EDG day tanks should be cleaned at some periodicity, was available from Limerick (2012), Palo Verde (2007), Arkansas Nuclear One (1989), and Diablo Canyon (1988, provided in Information Notice No. 91-46) which would provide the licensee with the ability to foresee and prevent this event from occurring.

Corrective Action(s): The licensee entered these issues in their corrective action program and planned to revise the preventive maintenance procedures. This will require the EDG day tanks be inspected and cleaned at a 10 year interval, add procedural guidance on analyzing the water samples taken with the fuel oil samples, and on adding biocide following performance of a filter press.

Corrective Action Reference(s): Condition reports (CRs) 10498152, 10501126 and 10501887; technical evaluation (TE) 1013667 and corrective action report (CAR) 274028.

Performance Assessment:

Performance Deficiency: The failure to incorporate preventative maintenance criteria for Emergency Diesel Generator (EDG) day tanks was a performance deficiency that was within the licensees ability to foresee and correct. An increasing trend in the fuel filter differential pressure and industry OE was available providing the licensee with the ability to foresee and prevent this event from occurring.

Screening: The PD was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the lack of preventative maintenance could result in degradation of fuel oil in the EDG day tanks to the extent of a loss of operability to one or more of the EDGs.

Significance: The inspectors assessed the significance of the finding using Exhibit 2, Mitigating Systems Screening Questions, of Inspection Manual Chapter (IMC) 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, issued June 19, 2012. The finding was of very low safety significance (i.e. Green) because the performance deficiency did not result in an actual loss of safety system function, and it did not represent a loss of function of one or more than one train for more than its TS allowed outage time of greater than 7 days.

Cross-cutting Aspect: The finding was assigned a cross cutting aspect of Resources, because the licensee did not ensure that preventive maintenance procedures for the EDG day tanks were adequate to support nuclear safety. (H.1)

Enforcement:

Violation: Technical Specification 5.4.1.a required as recommended by Regulatory Guide (RG) 1.33, 9.a, in part, that preventative maintenance schedules should be developed to specify inspections of equipment.

Contrary to the above, since initial plant operation, the licensee did not clean or inspect the EDG day tanks nor did the preventive maintenance procedures provide objective criteria to determine the need to clean the EDG day tanks.

Disposition: This violation is being treated as a Non-Cited Violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On October 25, 2018, the inspectors presented the quarterly baseline inspection results to Mr. Richard Spring, and other members of the licensee staff.

DOCUMENTS REVIEWED

Section 71111.01: Adverse Weather Protection

Procedures:

NMP-OS-017, Severe Weather, Ver. 1.1

34AB-Y22-002-0, Naturally Occurring Phenomena, Ver. 18.0

Documents:

SCNH-13-020, Hatch Probable Maximum Flood Hydraulics - Severe Accident Management

(SAM) for Fukushima Near-Term Task Force (NTTF) Recommendation 2.1 Flooding

Re-evaluation, Ver. 1.0

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 Re-evaluation, Ver. 1.0

Condition Reports:

10519182 10520835 10528320 10537426

Section 71111.04: Equipment Alignment

Procedures:

34SO-X43-001-1, Fire Pump Operating Procedure, Attachment 3, Ver. 6.4

34SO-E51-001-2, Reactor Core Isolation Cooling (RCIC) System, Attachment 1, Ver. 28.0

34SO-R43-001-1, Diesel Generator Standby AC System, Attachment 9, Ver. 28.1

Drawings:

H-13384, Ver. 30.0

H-26023, Ver. 44.0

H-26024, Ver. 33.0

Documents:

Unit 1 Technical Specifications, Amendment 288

Unit 2 Technical Specifications, Amendment 234

Condition Reports:

10532179 10539990

Section 71111.05AQ: Fire Protection Annual/Quarterly

Drawings:

A-43965 Sht. 44B, Cable Spreading Room, Fire Zone 0024A, Ver. 6.0

A-43965 Sht. 65B, HVAC Room, Fire Zone 1205N, Ver. 3.0

A-43965 Sht. 66B, Standby Gas Filters & Fan Room, Fire Zone 1205Q, Ver. 3.0

A-43965 Sht. 100B, RCIC Pump and Turbine Room, Fire Zone 2203C, Ver. 1.0

A-43965 Sht. 101B, SE RHR & Core Spray Pump Room, Fire Zone 2205B, Ver. 1.0

A-43965 Sht. 103B, HPCI Pump Room, Fire Zone 2205Z, Ver. 1.0

Documents:

Fire Protection Fire Hazards Analysis (FHA), Rev. 36.0

Fire Drill NMP-TR-425-F01, Fire Drill Scenario Development and Approval Drill H-002, Ver.5.0

Condition Reports (*NRC Identified):

• 10516258 *10518125 *10520760 10521177 10526462 *10526585

• 10532861 *10532910

Section 71111.11: Licensed Operator Requalification Program

Procedures:

34GO-OPS-005-2, Power Changes, Ver. 30

34SO-C51-001-0, TIP System Operation and LRPM Calibration, Ver. 19.2

34SV-E51-002-2, RCIC Pump Operability Test, Ver. 26.0

Documents:

Root Cause Determination on Training Deficiencies

Simulator Exam H-LTC-SE-00115, 08 16 Team C, Ver.5.1

Simulator Exam H-LTC-SE-00151, 08 22 Team B, Ver.3.5

Simulator Exam H-LTC-SE-00175, 08 22 Team B, Ver. 5.0

Simulator Exam H-LTC-SE-00129, 08 29 Team E, Ver. 3.3

Written Exam 2017-7B, 2017 Team E RO/SRO Exam

Written Exam 2017-7F, 2017 Remedial SRO Exam

Written Exam 2017 Makeup RO/SRO Exam

JPM LT-PAR-25202, Determine PARs (SRO only), Ver. 14.3

JPM LT-NL-P51-03613, Isolate FP Sprinklers, Ver. 10.3

JPM LT-C71-01018A, Insert Manual Scram (Outside CR), Ver. 0.2

JPM LT-C91-00114A, RWM Operability Check (Alt Path), Ver. 0.4

JPM LT-R43-02806A, Bus Power from EDG (Alt Path), Ver. 6.3

JPM LT-N21-00221, FW Master Controller Power Loss, Ver. 23.1

JPM LR-JP-00721, RSDP, Initiate RHR SDC, Ver. 18.4

JPM LT-E51-03902C, RCIC with MSL Break (Alt Path), Ver. 0.4

JPM LR-00502B, HPCI with Cont failure (Alt Path), Ver. 1.0

JPM LR-20034A, Pressure Control-EHC (Alt Path), Ver. 1.0

2018 FASA Self-Assessment, Pre-NRC 71111.11 Inspection, Ver. 2.0

Condition Reports:

10532179 10540859 10540862

Section 71111.12: Maintenance Effectiveness

Procedures:

NEI 99-02, Regulatory Assessment Performance Indicator Guideline. Rev. 7

NMP-ES-027, Maintenance Rule Program, Ver. 6.0

NMP-ES-027, Maintenance Rule Program, Ver. 7.0

NMP-ES-074-006, Fleet Lubrication Instruction, Ver. 3.1

NUMARC 93-01, Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear

Power Plants, Rev. 4A

50AC-MNT-001-0, Maintenance Program, Ver. 34.1

Documents:

A3 Periodic Review for Units 1 and 2, August 2018

Material/Service Receipt Inspection Report, it 648569 LT 314826, Dated March 21, 2018

Work Orders:

SNC915927, Obtain Oil Samples from RHR Pump 1B

SNC915952, Obtain Oil Samples from RHR Pump 1D

Condition Reports:

10515785 10519877 10535532 10536852 10539132

Section 71111.13: Maintenance Risk Assessments and Emergent Work Evaluation

Procedures:

NMP-DP-001, Operational Risk Awareness, Ver. 15.0

NMP-OS-010-002, Hatch Protected Equipment Logs, Ver. 11.0

34SV-R43-002-1, Diesel Generator 1B Monthly Test, Ver. 23.1

34SV-R43-005-2, Diesel Generator 1B Semi-Annual Test, Ver. 20.0

34SV-T46-003-1, Standby Gas Treatment Ventilation and Operability, Ver. 13.1

34SV-T46-005-1, Standby Gas Treatment LSFT, Ver. 2.0

Documents:

Equipment Out of Service Calculations 7/12/2018

Equipment Out of Service Calculations 8/2/2018

Equipment Out of Service Calculations 8/16/2018

Equipment Out of Service Calculations 9/12/2018

Unit 1 Technical Specifications, Amendment 288

Unit 2 Technical Specifications, Amendment 234

Work Orders:

SNC958978, Low Flow Condition on SBGT A Fan while performing 34SV-T46-005-1

Condition Reports:

10513077 10513642 10516472 10531544 10538491 10539815

Section 71111.15: Operability Determinations and Functionality Assessments

Procedures:

NMP-AD-012, Operability Determinations and Functional Assessments, Ver. 13.3

34SV-E51-002-2, RCIC Pump Operability, Ver. 26.0

Documents:

2-316, C&D Technologies Vendor Manual for KCR and KAR Batteries

BH2-M-0563, Units 1 & 2 Diesel Generator Battery Room Ventilation and Hydrogen Removal,

Ver. 6, Dated March 22, 2016.

Prompt Determination of Operability (PDO) 1-18-004 (001), Room Cooler Fan Motors

PDO 1-18-003, Plant Service Water (PSW) Leak, Rev. 1.0

IEEE Guide for the Interpretation of Gases Generated in Oil-Immersed Transformers,

Std C57.104-2008

Condition Reports:

10507029 10514590 10517069 10517071 10517072 10517073

10526140 10516352 10516472 10521551 10521748 10521819

10522090 10522161 10522334 10523710 10524458 10526790

10527495 10527629 10529055 10532097 10532457 10532802

10532815 10533012 10533027 10533222 10535055 10535429

10536682 10537524 10538683 10539978

Section 71111.18: Plant Modifications

Procedures:

NMP-ES-054, Temporary Modifications, Ver. 3.1

NMP-ES-054-001, Temporary Modification Processing, Ver. 3.2

Documents:

SNC946040, Temporary Pressure Pad on PSW piping, Rev. 1.0

SNC946040FCR01, Temporary Pressure Pad on PSW Piping, Rev. 1.0

PDO 1-18-003, Plant Service Water (PSW) Leak, Rev. 1.0

Condition Reports:

10492952

Section 71111.19: Post Maintenance Testing

Procedures:

NMP-MA-014-001, Post Maintenance Testing Guidance, Ver. 5.0

NMP-RE-008-F01, Detailed Reactivity Plan for control rod recovery and scram time testing, Ver.

2.1

34SV-E11-001-2, Residual Heat Removal Pump Operability, Ver. 19.3

34SV-E11-004-2, RHR Service water Pump Operability, Ver. 16.2

34SV-T46-003-1, Standby Gas Treatment Ventilation and Operability, Ver. 13.1

Work Orders:

SNC424338, Internal Inspection of SBLC Check Valve

Condition Reports:

10518217 *10526025 10526136 *10526524 10531365 10534048

Section 71111.22: Surveillance Testing

Procedures:

34SV-E21-001-1, Core Spray Pump Operability, Ver. 23.4

34SV-E21-001-2, Core Spray Pump Operability, Ver. 23.4

34SV-E51-002-1, RCIC Pump Operability, Ver. 28.0

34SV-R43-005-1, Diesel Generator 1B Semi-Annual Test, Ver. 17.1

Work Orders:

SNC823977, SBGT control switch replacement

Condition Reports:

10459395 10498152 10501126 10501887 *10523043 *10524087

10526268 10527711 10528107 10528376 10528715 10530436

10530466 10532179 10532311 10532340 10534436 10535621

10539734

Section 71114.06: Drill/Training Evaluation

Documents:

Plant Hatch Emergency Preparedness Drill 2018 Plant Drill 03, dated 9/18/2018

Section 71151: Performance Indicator Verification

Procedures:

NMP-AD-029, Preparation and Reporting of Regulatory Assessment Performance Indicator

Data and the Monthly Operating Report, Ver. 1.1

Documents:

NEI 99-02, Regulatory Assessment Performance Indicator Guideline. Rev. 7

Records and Data

Hatch Key Performance Indicators, July 2017 through June 2018

MSPI Derivation Reports for High Pressure Injection System for period through June 2018

MSPI Derivation Reports for Residual Heat Removal System for period through June 2018

MSPI Derivation Reports for Emergency AC Power System for period through June 2018

Section 71152: Problem Identification and Resolution

Procedures:

NMP-GM-002, Corrective Action Program, Version 15.0

OS-BP-001, Operations Performance Indicators, Ver. 4.3

Documents:

Unit 1 Compensatory Action Logs through August 2018

Unit 2 Compensatory Action Logs through August 2018

Condition Reports:

10337665 10496677 10504595 10504595 10520948 10522621

10524379 10524395 10526233 10527888 10528024 10528534

10529018 10529110 10530036 10530041 10530384 10532031

10532873

Section 60855.1: Operation of an Independent Spent Fuel Storage Installation

Procedures:

34FH-OPS-001-0, Fuel Movement Operation, Ver. 25.13

2GM-F18-155-0, Forced Helium Dehydration System Operation, Ver. 7.0

14