IR 05000321/2019003

Integrated Inspection Report 05000321/2019003 and 05000366/2019003 and Exercise of Enforcement Discretion

ML19317D284
Person / Time
Site:	Hatch
Issue date:	11/12/2019
From:	Mark Miller Division Reactor Projects II
To:	Gayheart C Southern Nuclear Operating Co
Geanette D
References
EA-19-062 IR 2019003
Download: ML19317D284 (17)

Text

{{#Wiki_filter:ber 12, 2019

SUBJECT:

EDWIN I HATCH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000321/2019003 AND 05000366/2019003 AND EXERCISE OF ENFORCEMENT DISCRETION

Dear Ms. Gayheart:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I Hatch Nuclear Plant. On October 17, 2019, the NRC inspectors discussed the results of this inspection with Edwin D. (Sonny) Dean site Vice President and other members of your staff. The results of this inspection are documented in the enclosed report.

Section 71111.11 of the enclosed inspection report discusses NRC review and final determination of an inspection issue, identified by facility staff in January 2019, involving the reactivation of Senior Reactor Operator (SRO) licenses at Plant Hatch. For this issue, the NRC is exercising enforcement discretion in accordance with Section 3.5, Violations Involving Special Circumstances, of the NRC Enforcement Policy and will not issue enforcement action for this violation.

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 the 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 Documents Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /Steven D. Cochrum RA for/ Mark S. Miller, Director 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: 05000321/2019003 and 05000366/2019003 Enterprise Identifier: I-2019-003-0028 Licensee: Southern Nuclear Operating Co. Inc.

Facility: Edwin I Hatch Nuclear Plant Location: Baxley GA 31513 Inspection Dates: July 01, 2019 to September 30, 2019 Inspectors: B. Collins, Reactor Inspector J. Hickman, Resident Inspector C. Jones, Senior Resident Inspector J. Viera, Operations Engineer Approved By: Mark S. Miller, Director, Division of Reactor Projects Enclosure

SUMMARY

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

List of Findings and Violations None.

Additional Tracking Items Type Issue Number Title Report Section Status EDG EA-19-062 Improper SRO License 71111.11Q Closed Reactivation

PLANT STATUS

Unit 1 operated at or near rated thermal power (RTP) for the entire inspection period.

Unit 2 began the inspection period at RTP. On September 12, 2019, the unit was down powered to 50 percent to repair a steam leak on the 'A' reactor feed pump turbine. The unit was returned to RTP on September 17, 2019. On September 20, 2019, the unit was taken offline to repair a steam leak on a feed water check valve and remained offline 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 03.03)

(1) The inspectors evaluated readiness for impending adverse weather conditions for hurricane Dorian on August 30, 2019.

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Unit 1 C Emergency Diesel Generator (EDG) following the monthly EDG operability surveillance testing on July 17, 2019.

(2) Unit 1 A Core Spray (CS) system alignment following surveillance testing on July 30, 2019.

(3) Unit 1 A Standby Gas Treatment (SBGT) system alignment during dispersed oil particulate (DOP) testing on the B train on August 19, 2019.

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

(1) The inspectors evaluated fire brigade performance on August 31, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

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

(1) Unit 1 SBGT system, Fire Zones 1205N and 1205Q on August 27, 2019.

(2) Unit 2 Reactor Core Isolation Cooling (RCIC) Pump and Turbine Room, Fire Zone 2203C on August 27, 2019.

(3) Unit 1 and Unit 2 Refueling Floor, Fire Zones 0201 A/B on September 16, 2019.

(4) Unit 2 High Pressure Coolant Injection (HPCI) Pump Room, Fire Zone 2205Z on September 25, 2019.

(5) Unit 2 Adjustable Speed Drive (ASD) Room, Fire Zones 2210 and 2211 on September 29, 2019.

(6) Unit 2 Chiller Room, Fire Zone 2205N on September 30, 2019.

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 1 northeast and southeast diagonal rooms.

71111.07T - Heat Sink Performance Triennial Review (IP Section 02.02)

The inspectors evaluated heat exchanger/sink performance on the following from July 22 - 26, 2019:

(1) 1A Residual Heat Removal Heat Exchanger (1E11B001A), Section 02.02b

(2) Emergency Diesel Generator 1B Jacket Water/Lube Oil Coolers (1R435004B/5B),

Section 02.02b

(3) High Pressure Coolant Injection Pump Room Cooler 2A (1T41B005A), Section 02.02b

(4) Service Water Intake structure and Altamaha River, Section 02.02d, Specifically Sections 02.02d.4, 02.02d.6 and 02.02d.7 were completed.

==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 Rod Pattern Adjustment, Unit 2 power ascension from 90 to 100 percent power, Unit 1 Steam Jet Air Ejector (SJAE) adjustments due to high condensate temperatures, and Unit 2 power ascension from 50 to 100 percent power following steam/feed leak repairs on 2A Reactor Feed Pump on July 2, 2019, August 5, 2019, September 6, 2019, and September 16, 2019.

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

(1) The inspectors observed and evaluated licensed operator requalification scenario in the simulator on September 12, 2019.

   (2)     (Partial)

The inspectors evaluated maintenance of operator license conditions in the area of license reactivations performed for refueling activities. Results of this evaluation can be found in Enforcement Action EA-19-062.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)==

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

(1) Unit 2 HPCI Turbine speed control was lost due to inverter circuit failure on August 22, 2019.

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

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

(1) Unit 2 elevated risk when testing the Loss of Coolant Accident/Loss of Site Power (LOCA/LOSP) timer cards after 1B EDG power supply (P/S) replacement, on July 12, 2019.

(2) Unit 1 elevated risk during B residual heat removal (RHR) heat exchanger (HX) tube plugging, on July 24, 2019.

(3) Unit 1 and 2 elevated risk with 1B EDG being declared Operable but Degraded/Nonconforming (OBDN), on July 25, 2019.

(4) Unit 2 elevated risk due to excavation of underground Condensate Storage Tank (CST) piping, on August 2, 2019.

(5) Unit 1 and Unit 2 elevated risk due to high ambient temperatures and elevated Unit 2 condenser bay temperatures on August 14, 2019.

(6) Unit 2 risk during emergent HPCI repairs on August 23, 2019.

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1 Plant Service Water (PSW) pump A differential pressure ratio and vibration point landed in the alert range on July 11, 2019.

(2) Unit 1 through wall leak of RHR piping during performance of flushing of PSW and RHR Service Water (SW) piping dead-legs on August 9, 2019.

(3) Unit 2 HPCI system inverter failure and the post accident monitoring instrumentation on August 23, 2019.

(4) Unit 2 feedwater check valve steam leak on September 19, 2019.

==71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample) The inspectors evaluated the following temporary or permanent modifications:

(1) Emergent temporary configuration change (TCC) for condenser bay temperature switches on Unit 2.

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

[[IP sample::=

=IP 71111.18|count=4}}

The inspectors evaluated the following post maintenance tests:

(1) 57SV-R43-001-2, Testing the LOCA/LOSP Timer Cards, Ver.7.0 following the replacement of 1B EDG 2B LOCA/LOSP Timer Power Supply on July 15, 2019.

(2) Unit 1 leak test and inspection following RHR Heat Exchanger repairs, Work Order SNC952338, on July 26, 2019.

(3) 57SV-C11-002-2, Scram Discharge Volume Level (Thermal Sensors) FT&C, Ver.12.2 following a Unit 2 half scram on August 6, 2019.

(4) Penetrant and leak tests following seal weld of leak off plug on Unit 2 check valve 2B21F007A, work order SNC1049024, on September 30, 2019.

71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01)

(1) The inspectors evaluated Unit 2 forced outage activities due to leak repairs of feedwater check valve 2B21F007A from September 24, 2019, to September 30, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)

(1) 34SV-R43-001-1, Diesel Generator 1A Monthly Test, Version 25.0 on July 2, 2019.

(2) 34SV-E51-002-1, RCIC Pump Operability, Version 28.5 on August 8, 2019.

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 34SV-E11-001-1, Residual Heat Removal Pump Operability, Version 28.0 on August 3, 2019.

==71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated a simulator based emergency scenario on September 12,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below: MS06: Emergency AC Power Systems (IP Section 02.05)==

(1) Unit 1 (July 2018 to June 2019)

(2) Unit 2 (July 2018 to June 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) ===

(1) Unit 1 (July 2018 to June 2019)

(2) Unit 2 (July 2018 to June 2019)

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

(1) Unit 1 (July 2018 to June 2019)

(2) Unit 2 (July 2018 to June 2019)

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in feedwater flow control that might be indicative of a more significant safety issue.

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) Unit 1 B EDG being declared Operable but Degraded/Nonconforming (OBDN) due to minor defect in the outer race of the generators outboard bearing, Condition Report (CR) 10629568.

71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

(1) The inspectors evaluated the Unit 2 High Pressure Coolant Injection System Inoperability report and licensees response on August 22,

INSPECTION RESULTS

Enforcement Enforcement Action EA-19-062: Improper SRO License 71111.11 Discretion Reactivation Q

Description:

From February 1 through August 8, 2019, NRC inspectors evaluated an inspection issue identified by facility staff on January 31, involving the reactivation of Senior Reactor Operator (SRO) licenses at Plant Hatch. NRC inspection concluded that during refueling outages conducted from 2005 through 2018, there were seventy occurrences of senior operators failing to perform license reactivation in accordance with 10 CFR Part 55.53(f)(2). Specifically, twenty senior operators failed to perform the required minimum number of under instruction reactivation hours prior to assuming duties required of an SRO license.

The failure to achieve the required minimum number of reactivation hours originated from the requirements of NMP-TR-406, License Administration, Section 4.7, Reactivation of a Senior Reactor Operator for Supervising Core Alterations. Section 4.7 permitted licensee staff the option of performing SRO reactivation using a training-only option where training was used as credit in lieu of obtaining the required minimum number of under instruction reactivation hours.

The NRC concluded using a training-only option resulted in violation of 10 CFR Part 55.53(f)(2), which requires that a senior operator licensee must complete a minimum of 40 hours of shift functions under the direction of a senior operator in the position to which the individual will be assigned before a resumption of senior operator functions.

Corrective Actions: The following Condition Reports document facility corrective actions to correct the licensed operator reactivation issue identified on January 31, 2019. Final closure corrective actions included an immediate policy change for senior operators reactivating for the Unit 2 Spring 2019 refueling outage and process procedure changes that removed use of a 'training-only' option from NMP-TR-406.

Corrective Action References:

• 10577066, NMP-TR-406 (Option 1) does not meet NUREG 1021 requirements, 1/31/19
• 10577173, CFAM: SRO License activation for Core Alterations, 1/31/19

Enforcement:

Significance/Severity: As discussed in Section 6.4.c of the NRC Enforcement Policy, the potential existed for this violation to be characterized at Severity Level III, because multiple licensed SROs were in noncompliance with reactivation requirement conditions.

Violation: Title 10 of the Code of Federal Regulations (10 CFR) Section 55.2, Scope, states that the regulations present in Part 55, Operators Licenses, apply to facility licensees.

Title 10 CFR 55.53 (f), Conditions of Licenses, states, in part, that before the resumption of functions authorized by a senior operator license, an authorized representative of the facility licensee shall ensure completion of Part 55.53(f)(2) requirements.

Title 10 CFR 55.53(f)(2), Conditions of Licenses, states, in part, that a senior operator licensee must complete a minimum of 40 hours of shift functions under the direction of a senior operator in the position to which the individual will be assigned before a resumption of senior operator functions if that senior operator licensee has not been active in the performance of senior operator functions.

Contrary to the above, Southern Nuclear Company (SNC) failed to ensure completion of the minimum hours of shift functions under the direction of a senior operator prior to permitting a resumption of functions that required performance by a senior operator licensee. Specifically, for refueling outages conducted from 2005 through 2018, the facility licensee failed to ensure completion of the minimum number of required reactivation hours prior to assigning twenty senior operators, on seventy occasions, the limited duty of supervising Core Alterations, as required by a senior operator licensee.

In accordance with Section 6.4.c of the NRC Enforcement Policy, this violation is characterized at Severity Level III.

Basis for Discretion: In reviewing the circumstances of this issue, the NRC concluded that prior NRC communication from 2005 as well as a lack of clarity in existing guidance, contributed to the facility licensees use of the training-only option in their limited duty SRO reactivation program with subsequent non-compliance. Additionally, the NRC factored in the facility licensees prompt corrective actions which included entering this issue into its Corrective Action Program (CAP) and institution of an immediate policy change for senior operators reactivating for the Unit 2 Spring 2019 refueling outage (February - March 2019).

Lastly on April 29, 2019, process procedure changes to NMP-TR-406 were finalized which removed the training-only option in lieu of reactivation hours as an accepted facility method for performing senior operator reactivation.

Based on these facts, Region 2, in consultation with Office of Enforcement, has refrained from issuing a Notice of Violation and has exercised enforcement discretion in accordance with Section 3.5 of the NRC Enforcement Policy. Enforcement action will not be issued for this violation.

EXIT MEETINGS AND DEBRIEFS

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

• On October 17, 2019, the inspectors presented the integrated inspection results to Edwin D. (Sonny) Dean site Vice President and other members of the licensee staff.
• On July 25, 2019, the inspectors presented the Triennial Heat Sink Performance Debrief inspection results to Daniel Komm, Plant Manager (Acting Site VP) and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 71111.01 Procedures 34AB-Y22-002-0 Naturally Occurring Phenomena Version 19.0 NMP-OS-017 Severe Weather Version 1.1 NMP-OS-020 Station Response to Southern Company Alert Conditions Version 1.2 71111.04Q Drawings H-13414 Elementary Diagram Diesel Generator 1C Version 54.0 H-16020 Unit 1 Standby Gas Treatment System P & I D Sheet 1 Version 30.0 H-16331 Unit 1 Core Spray System P & I D Version 37.0 Procedures 34SO-E21-001-1 Core Spray System Version 24.6 34SO-R43-001-1 Diesel Generator Standby AC System Version 29.1 34SO-T46-001-1 Standby Gas Treatment System Version 21.5 71111.05A Procedures NMP-TR-425 Fire Drill Program Version 9.0 NMP-TR-425-F01 Fire Drill Scenario Development and Approval Sheet 08/15/2019 NMP-TR-425-F08 Pre-Drill Checklist Version 4.0 NMP-TR-425-F14 Fire Drill Package Version 1.1 71111.05Q Drawings A-43865, Sh. 074 Refueling Floor, Fire Zones 0201 A/B Version 3.0 A-43956, Sh. 100 Unit 2 RCIC Pump and Turbine Room, Fire Zone 2203C Version 2.0 A-43965, Sh. 065 Standby Gas and HVAC, Fire Zone 1205N Revision 2 A-43965, Sh. 103 Unit 2 HPCI Pump Room, Fire Zone 2205Z Version 2.0 A-43965, Sh. 112 U2 Chiller Room, Fire Zone 2205N Version 4.0 A-43965, Sh. 113 Unit 2 ASD, Fire Zone 2210 Version 5.0 Miscellaneous Fire Protection Fire Hazards Analysis Version 36.0 71111.06 Engineering E. I. Hatch Individual Plant Examination December Evaluations 1992 Miscellaneous Updated Final Safety Analysis Report 71111.07T Corrective Action 10632323 GL 89-13 Heat Exchanger As-Found Condition Inspections 7/26/2019 Documents Resulting from Inspection Miscellaneous 42IT-TET-014-1 Safeguard Equipment Area Cooler Data: HPCI Pump Room 1/4/08 Cooler 2A 2IT-TET-014-1 Safeguard Equipment Area Cooler Data: HPCI Pump Room 1/27/11 Cooler 2A Inspection Type Designation Description or Title Revision or Procedure Date 2IT-TET-014-1 Safeguard Equipment Area Cooler Data: HPCI Pump Room 3/25/14 Cooler 2A NDE Reports Inspection Summary Hatch Unit 1B Emergency Diesel May 2018 Generator Jacket Water Cooler - 1R43B005B Inspection Summary Hatch Unit 1 High Pressure Coolant May 2017 Injection Pump Room Cooler - 1T41B005A Inspection Summary Hatch Unit 1B Emergency Diesel May 2018 Generator Lube Oil Cooler - 1R43B004B 2IT-TET-012-1S Piping/Component Inspection Report: 1A RHR Heat 2-8-08 Exchanger 2IT-TET-012-1S Piping/Component Inspection Report: 1A RHR Heat 2-14-08 Exchanger 2IT-TET-012-1S Piping/Component Inspection Report: 1A RHR Heat 2-15-14 Exchanger RER SNC843238 Hatch Unit 2 Structural Monitoring Inspection Report: Intake 2017 Structure RER SNC921613 Hatch Unit 1 Structural Monitoring Inspection Report: Intake 2018 Structure SNC425433 Piping/Component Visual Inspection Report: 1B EDG Heat 4-29-14

                           (excerpt)       Exchangers

SNC785938 Piping/Component Visual Inspection Report: 1B EDG Heat 5/30/2018

                           (excerpt)       Exchangers

Procedures NMP-CH-005 E.I. Hatch Nuclear Plant Chemistry Program Ver. 4.1 71111.11Q Corrective Action 10186462 Fuel Assembly Damaged During Fuel Movement 02/22/16 Documents 10577066 NMP-TR-406 (Option 1) does not meet NUREG 1021 01/31/19 requirements 10577173 CFAM: SRO License activation for Core Alterations 01/31/19 2172 Fuel movement error during execution of Fuel Shuffle Step 04/14/2011

                                           #69

2206 Step 103 of Fuel movement 04/14/2011 777912 Fuel Assembly Hits Core Light 02/24/2014 Miscellaneous H-LT-AF-112 RFPT Oil Temp Cont/ASD Cell bypass/SDV Fail/ATWS Version 1.0 H2C26-081319- Recovery from Power Reduction Due to Elevated Conbay 08/15/2019 014 Temperatures Inspection Type Designation Description or Title Revision or Procedure Date Procedures 34SO-N61-001-1 Main Condenser Vacuum System and Closeout Version 27.0 2CC-ERP-018-0 Target Rod Pattern Development Version 16.0 2CC-ERP-018-0 Target Rod Pattern Development, Version 16.0 2TR-TRN-002-0 License Continuing Training Program Version 13.0 DI-TRN-55-601 Operations Personnel Qualification Instructions Version 4.0 NMP-TR-406 License Administration Version 7.2 NMP-TR-406 License Administration Version 8 NMP-TR-406-F02 SRO Reactivation for Core Alterations Version 3.2 71111.12 Corrective Action CR10640117 HPCI System inverter circuit failure 08/22/2019 Documents CR10648029 Maintenance Rule Functional Failure on 2E41K065 09/20/2019 Procedures NEI 99-02 Regulatory Assessment Performance Indicator Guigeline Revision 7 NMP-AD-006 Infrequently Performed Tests and Evolutions Version 12.8 NMP-ES-027 Maintenance Rule Program Version 10.0 NUMARC 93-01 Industry Guideline for Monitoring the Effectiveness of Revision 4A Maintenance at Nuclear Power Plants 71111.13 Corrective Action CR 10629568 Generator outboard bearing issues on the 1B EDG 07/17/2019 Documents CR10627205 Diesel Generator B Loading Timer Failure 07/09/2019 Drawings H-21084 Edwin I. Hatch Nuclear Plant Unit No.2 Condensate Make- Version 18.0 Up and Storage at Tank Outside Building Engineering ODMI 2-19-001 Unit 2 Conbay Elevated Temperatures 08/14/2019 Evaluations Miscellaneous Equipment Out of Service Calculations 07/12/2019 Equipment Out of Service Calculations 07/25/2019 Equipment Out of Service Calculations 07/24/2019 Procedures 34SO-N71-001-2 Main Condenser Vacuum Parameters and Limitations Version 36.4 57SV-R43-001-2 Testing the LOCA/LOSP Timer Cards Version 7.0 NMP-DP-001 Operational Risk Awareness Version 15.0 NMP-OS-010-002 Hatch Protected Equipment Logs Version 11.0 Work Orders SNC1028120 Install new 3 inch piping down stream of 2P11F051 valve to Revision 0 newly installed test flange. SNC952338 Unit 1 RHR Heat Exchanger Tube Leak Testing 07/25/2019 Inspection Type Designation Description or Title Revision or Procedure Date 71111.15 Drawings 6511-20 Electrical Equipment Separation for Safeguard Sys. Revision 1 H-24100 Edwin I. Hatch Nuclear Plant Unit No.2 HPCI System 2E41 Version 20.0 Elementary Diagram Sheet 10 of 11 H-24435 Edwin I. Hatch Nuclear Plant Unit No.2 Elementary Diagram Revision 3 ATTS, System 2A70, Sheet 35 of 35 H-27664 Edwin I. Hatch Nuclear Plant Unit No.2 HPCI System 2E41 Version 42.0 Elementary Diagram Sheet 1 of 11 H-27666 Edwin I. Hatch Nuclear Plant Unit No.2 High Pressure Version 28.0 Coolant Injection Sys 2E41 Elementary Diagram Sheet 3 Miscellaneous Unit 1 Technical Specifications Ammendment 294 Unit 2 Technical Specifications Ammendment 239 Operability 2-2019-003 Prompt Determination of Operability for 2B21F077A - 09/16/2019 Evaluations Feedwater Check Valve CR10626823 Unit 1 PSW pump 1A differential pressure ratio and vibration 07/08/2019 point landed in the alert range CR10634238 Through wall leak on Unit 2 RHR Piping 08/02/2019 CR10640117 HPCI system inverter circuit failure 08/22/2019 ODMI 2-19-001 Unit 2 Condenser Bay Elevated Temperatures 08/14/2019 71111.18 Engineering SNC1041769 Emergent TCC for condenser bay temperature switches Revision 1.0 Changes 71111.19 Procedures 57SV-C11-002-2 Scram Discharge Volume Level (Thermal Sensors) FT&C Version 12.2 NMP-MA-014 Post Maintenance Testing/Post Modification Testing Version 2.1 NMP-MA-014- Post Maintenance Testing Guidance Version 5.2 001 Work Orders SNC1039991 Received a half scram on Unit 2 during performance of 08/05/2019 57SV-C11-002-2 SNC1049024 Seal weld leak off plug on check valve 2B21F007A 09/29/2019 SNC952338 Unit 1 RHR HX Repairs 07/25/2019 71111.20 Procedures 34GO-OPS-001-2 Plant Startup Version 51.4 34GO-OPS-013-2 Normal Plant Shutdown Version 33.2 NMP-RE-008-F02 Simplified Reactivity Management Plan 09/23/2019 NMP-RE-008-F02 Recovery from Power Reduction Due to Elevated Conbay 08/13/2019 Inspection Type Designation Description or Title Revision or Procedure Date Temperatures 71114.06 Miscellaneous H-LT-AF-112 RFPT oil temp controller fails, ASD cell bypass, scram Version 1.0 discharge volume drain valves fail, ATWS 71152 Corrective Action CR 10629568 1B EDG being declared Operable but 07/17/2019 Documents Degraded/Nonconforming (OBDN) due to minor defect in the outer race of the generators outboard bearing CAR 276475 Feedwater Transient on Unit 2 08/21/2019 TE 1049457 Yokogawa Controller Failure Analysis Report 08/19/2019 Procedures NMP-GM-002 Corrective Action Program Version 15.1 NMP-GM-002- Effectiveness Review Instructions Version 5.2 2 71153 Corrective Action 10640117 Shift received "HPCI System inverter circuit failure" (P601- 08/22/2019 Documents 120) 14| ]]