IR 05000321/2019003
| 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
November 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:
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
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 Reactivation 71111.11Q Closed
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
- (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) (3 Samples)
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 Sample)
- (1) The inspectors evaluated fire brigade performance on August 31, 2019.
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (6 Samples)
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.) (1 Sample)
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) (1 Sample)
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) (6 Samples)
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) (4 Samples)
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) (4 Samples)
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 Sample)
- (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) (2 Samples)
- (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 Sample)
- (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 Discretion Enforcement Action EA-19-062: Improper SRO License Reactivation 71111.11 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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 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 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
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
Core Spray System
Version 24.6
Diesel Generator Standby AC System
Version 29.1
Version 21.5
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
Engineering
Evaluations
E. I. Hatch Individual Plant Examination
December
1992
Miscellaneous
Updated Final Safety Analysis Report
Corrective Action
Documents
Resulting from
Inspection
10632323
GL 89-13 Heat Exchanger As-Found Condition Inspections
7/26/2019
Miscellaneous
Safeguard Equipment Area Cooler Data: HPCI Pump Room
Cooler 2A
1/4/08
Safeguard Equipment Area Cooler Data: HPCI Pump Room
Cooler 2A
1/27/11
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Safeguard Equipment Area Cooler Data: HPCI Pump Room
Cooler 2A
3/25/14
NDE Reports
Inspection Summary Hatch Unit 1B Emergency Diesel
Generator Jacket Water Cooler - 1R43B005B
May 2018
Inspection Summary Hatch Unit 1 High Pressure Coolant
Injection Pump Room Cooler - 1T41B005A
May 2017
Inspection Summary Hatch Unit 1B Emergency Diesel
Generator Lube Oil Cooler - 1R43B004B
May 2018
Piping/Component Inspection Report: 1A RHR Heat
Exchanger
2-8-08
Piping/Component Inspection Report: 1A RHR Heat
Exchanger
2-14-08
Piping/Component Inspection Report: 1A RHR Heat
Exchanger
2-15-14
RER SNC843238
Hatch Unit 2 Structural Monitoring Inspection Report: Intake
Structure
2017
RER SNC921613
Hatch Unit 1 Structural Monitoring Inspection Report: Intake
Structure
2018
SNC425433
(excerpt)
Piping/Component Visual Inspection Report: 1B EDG Heat
Exchangers
4-29-14
SNC785938
(excerpt)
Piping/Component Visual Inspection Report: 1B EDG Heat
Exchangers
5/30/2018
Procedures
NMP-CH-005
E.I. Hatch Nuclear Plant Chemistry Program
Ver. 4.1
71111.11Q Corrective Action
Documents
10186462
Fuel Assembly Damaged During Fuel Movement
2/22/16
10577066
NMP-TR-406 (Option 1) does not meet NUREG 1021
requirements
01/31/19
10577173
CFAM: SRO License activation for Core Alterations
01/31/19
2172
Fuel movement error during execution of Fuel Shuffle Step
- 69
04/14/2011
2206
Step 103 of Fuel movement
04/14/2011
777912
Fuel Assembly Hits Core Light
2/24/2014
Miscellaneous
H-LT-AF-112
RFPT Oil Temp Cont/ASD Cell bypass/SDV Fail/ATWS
Version 1.0
014
Recovery from Power Reduction Due to Elevated Conbay
Temperatures
08/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Main Condenser Vacuum System and Closeout
Version 27.0
Target Rod Pattern Development
Version 16.0
Target Rod Pattern Development,
Version 16.0
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
Corrective Action
Documents
CR10640117
HPCI System inverter circuit failure
08/22/2019
CR10648029
Maintenance Rule Functional Failure on 2E41K065
09/20/2019
Procedures
Regulatory Assessment Performance Indicator Guigeline
Revision 7
NMP-AD-006
Infrequently Performed Tests and Evolutions
Version 12.8
NMP-ES-027
Version 10.0
Industry Guideline for Monitoring the Effectiveness of
Maintenance at Nuclear
Power Plants
Revision 4A
Corrective Action
Documents
CR 10629568
Generator outboard bearing issues on the 1B EDG
07/17/2019
CR10627205
Diesel Generator B Loading Timer Failure
07/09/2019
Drawings
H-21084
Edwin I. Hatch Nuclear Plant Unit No.2 Condensate Make-
Up and Storage at Tank Outside Building
Version 18.0
Engineering
Evaluations
ODMI 2-19-001
Unit 2 Conbay Elevated Temperatures
08/14/2019
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
Main Condenser Vacuum Parameters and Limitations
Version 36.4
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
newly installed test flange.
Revision 0
SNC952338
Unit 1 RHR Heat Exchanger Tube Leak Testing
07/25/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
6511-20
Electrical Equipment Separation for Safeguard Sys.
Revision 1
H-24100
Edwin I. Hatch Nuclear Plant Unit No.2 HPCI System 2E41
Elementary Diagram Sheet 10 of 11
Version 20.0
H-24435
Edwin I. Hatch Nuclear Plant Unit No.2 Elementary Diagram
ATTS, System 2A70, Sheet 35 of 35
Revision 3
H-27664
Edwin I. Hatch Nuclear Plant Unit No.2 HPCI System 2E41
Elementary Diagram Sheet 1 of 11
Version 42.0
H-27666
Edwin I. Hatch Nuclear Plant Unit No.2 High Pressure
Coolant Injection Sys 2E41 Elementary Diagram Sheet 3
Version 28.0
Miscellaneous
Unit 1 Technical Specifications
Ammendment
294
Unit 2 Technical Specifications
Ammendment
239
Operability
Evaluations
2-2019-003
Prompt Determination of Operability for 2B21F077A -
09/16/2019
CR10626823
Unit 1 PSW pump 1A differential pressure ratio and vibration
point landed in the alert range
07/08/2019
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
Engineering
Changes
SNC1041769
Emergent TCC for condenser bay temperature switches
Revision 1.0
Procedures
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-
001
Post Maintenance Testing Guidance
Version 5.2
Work Orders
SNC1039991
Received a half scram on Unit 2 during performance of
08/05/2019
SNC1049024
Seal weld leak off plug on check valve 2B21F007A
09/29/2019
SNC952338
07/25/2019
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Temperatures
Miscellaneous
H-LT-AF-112
RFPT oil temp controller fails, ASD cell bypass, scram
discharge volume drain valves fail, ATWS
Version 1.0
Corrective Action
Documents
CR 10629568
1B EDG being declared Operable but
Degraded/Nonconforming (OBDN) due to minor defect in
the outer race of the generators outboard bearing
07/17/2019
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-
2
Effectiveness Review Instructions
Version 5.2
Corrective Action
Documents
10640117
Shift received "HPCI System inverter circuit failure" (P601-
20)
08/22/2019