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=Text=
=Text=
{{#Wiki_filter:May 20, 2022
{{#Wiki_filter:==SUBJECT:==
 
==SUBJECT:==
EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000321/2022010 AND 05000366/2022010
EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000321/2022010 AND 05000366/2022010


Line 30: Line 28:
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.
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, Signed by Baptist, James on 05/20/22 James B. Baptist, Chief Engineering Br 1 Division of Reactor Safety Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5
Sincerely, James B. Baptist, Chief Engineering Br 1 Division of Reactor Safety Docket Nos. 05000321 and 05000366 License Nos. DPR-57 and NPF-5


===Enclosure:===
===Enclosure:===
As stated
As stated  


==Inspection Report==
==Inspection Report==
Docket Numbers: 05000321 and 05000366 License Numbers: DPR-57 and NPF-5 Report Numbers: 05000321/2022010 and 05000366/2022010 Enterprise Identifier: I-2022-010-0036 Licensee: Southern Nuclear Operating Company Facility: Edwin I. Hatch Nuclear Plant Units 1 & 2 Location: Baxley, GA 31513 Inspection Dates: April 04-April 08, 2022 Inspectors: T. Su, Reactor Inspector C. Franklin, Reactor Inspector J. Lizardi-Barreto, Construction Inspector Approved By: James B. Baptist, Chief Engineering Br 1 Division of Reactor Safety Enclosure
Docket Numbers:
05000321 and 05000366
License Numbers:
DPR-57 and NPF-5
Report Numbers:
05000321/2022010 and 05000366/2022010
Enterprise Identifier:
I-2022-010-0036
Licensee:
Southern Nuclear Operating Company
Facility:
Edwin I. Hatch Nuclear Plant Units 1 & 2
Location:
Baxley, GA 31513
Inspection Dates:
April 04-April 08, 2022
Inspectors:
T. Su, Reactor Inspector
C. Franklin, Reactor Inspector
J. Lizardi-Barreto, Construction Inspector
Approved By:
James B. Baptist, Chief
Engineering Br 1
Division of Reactor Safety


=SUMMARY=
=SUMMARY=
Line 42: Line 63:


===List of Findings and Violations===
===List of Findings and Violations===
No findings or violations of more than minor significance were identified.
No findings or violations of more than minor significance were identified.


Line 53: Line 73:


==REACTOR SAFETY==
==REACTOR SAFETY==
 
===71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)===
===71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01) ===
{{IP sample|IP=IP 71111.17|count=23}}
{{IP sample|IP=IP 71111.17|count=23}}
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from April 4-April 8, 2022.
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from April 4-April 8, 2022.
Line 75: Line 94:
: (17) SNC1117345, 1/2E11R608A/B Moving Average Function
: (17) SNC1117345, 1/2E11R608A/B Moving Average Function
: (18) SNC1134609-21, Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA)
: (18) SNC1134609-21, Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA)
: (19) SNC1138556, Master Recirc Controller Software Change
: (19) SNC1138556, Master Recirc Controller Software Change (20)31EO-EOP-113-1, Terminating and Preventing Injection into The RPV 5.0 (21)31EO-SAG-002-1, RPV Pressure Reactor Power and Containment Control 8.0 (22)31GO-OPS-019-0, Use and Control of the Fuse Kit 2.0 (23)34AB-R22-003-1-100, Station Blackout (SBO) Flow Chart
: (20) 31EO-EOP-113-1, Terminating and Preventing Injection into The RPV 5.0
: (21) 31EO-SAG-002-1, RPV Pressure Reactor Power and Containment Control 8.0
: (22) 31GO-OPS-019-0, Use and Control of the Fuse Kit 2.0
: (23) 34AB-R22-003-1-100, Station Blackout (SBO) Flow Chart


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Line 91: Line 106:
=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


Inspection Type             Designation   Description or Title                                         Revision or
Inspection
Procedure                                                                                                Date
Procedure
71111.17T Calculations      BH1-E-0088     DC Control Circuit Voltage Drop in Diesel Battery System     Rev. 8
Type
CN-MRCDA-14-8 Hatch Refueling Platform Assembly Structural Evaluation       Rev. 7
Designation
MC-H-12-0179   Plant Service Water System Return Line - North East           Rev. 4
Description or Title
MC-H-12-0180   Plant Service Water System Supply Line - North East           Rev. 3
Revision or
MC-H-15-0019   Diesel Generator Bldg Heating and Ventilation                 Rev. 2
Date
MC-H-15-0023   Emergency Diesel Batteries 1A, 1B, & 1C Sizing               Rev. 1
BH1-E-0088
MC-H-17-0026   Refueling Platform Crane Rail and Stops                       Ver. 3.0
DC Control Circuit Voltage Drop in Diesel Battery System
MC-H-17-0029   Hatch Nuclear Plant Unit 1 - Floor at Nominal El. 228-0     Ver. 1.0
Rev. 8
SCNH-15-021   Qualification of Anchorage for Wall-Mounted DVR Panel         Rev. 1
CN-MRCDA-14-8
Hatch Refueling Platform Assembly Structural Evaluation
Rev. 7
MC-H-12-0179
Plant Service Water System Return Line - North East
Rev. 4
MC-H-12-0180
Plant Service Water System Supply Line - North East
Rev. 3
MC-H-15-0019
Diesel Generator Bldg Heating and Ventilation
Rev. 2
MC-H-15-0023
Emergency Diesel Batteries 1A, 1B, & 1C Sizing
Rev. 1
MC-H-17-0026
Refueling Platform Crane Rail and Stops
Ver. 3.0
MC-H-17-0029
Hatch Nuclear Plant Unit 1 - Floor at Nominal El. 228-0
Ver. 1.0
SCNH-15-021
Qualification of Anchorage for Wall-Mounted DVR Panel
H21-P080 - Diesel Generator Building, Unit 1 Switchgear
H21-P080 - Diesel Generator Building, Unit 1 Switchgear
Room
Room
SCNH-15-022   Qualification of Anchorage for Wall-Mounted DVR Panel         Rev. 1
Rev. 1
SCNH-15-022
Qualification of Anchorage for Wall-Mounted DVR Panel
H21-P081 - Diesel Generator Building, Unit 1 Switchgear
H21-P081 - Diesel Generator Building, Unit 1 Switchgear
Room
Room
SINH-15-001   Technical Specifications 3.3.8.1-1 Setpoint Determination for Rev. 3
Rev. 1
SINH-15-001
Technical Specifications 3.3.8.1-1 Setpoint Determination for
4.16kV Emergency Buses 1E, 1F and 1G Degraded Voltage
4.16kV Emergency Buses 1E, 1F and 1G Degraded Voltage
Relay Loops
Relay Loops
SINH-15-002   Setpoint Determination for 4.16 kV Emergency Buses 1E, 1F     Rev. 3
Rev. 3
SINH-15-002
Setpoint Determination for 4.16 kV Emergency Buses 1E, 1F
and 1G Degraded Voltage Alarm Relay Loops
and 1G Degraded Voltage Alarm Relay Loops
SQDS-H-19-0001 Seismic and Dynamic Qualification Data Summary               Ver. 1.0
Rev. 3
Corrective Action CR 10585230   Loss of indication from multiple instruments powered from     02/24/2019
Calculations
Documents                       Instrument bus 2B
SQDS-H-19-0001
CR 10771124   Expected Response not received during DECP SNC632608         02/02/2021
Seismic and Dynamic Qualification Data Summary
Ver. 1.0
CR 10585230
Loss of indication from multiple instruments powered from
Instrument bus 2B
2/24/2019
Corrective Action
Documents
CR 10771124
Expected Response not received during DECP SNC632608
Bench Test FT
Bench Test FT
Corrective Action CR 10872216   Hatch NRC 50.59 Inspection Observance                         04/07/2022
2/02/2021
Documents         CR 10873618    System Response Time Not Addressed                            04/13/2022
CR 10872216
Hatch NRC 50.59 Inspection Observance
04/07/2022
Corrective Action
Documents
Resulting from
Resulting from
Inspection
Inspection
Drawings          H-16290       Edwin I. Hatch Nuclear Plant Unit No. 1 Penetrations in       Rev. 13
CR 10873618
System Response Time Not Addressed
04/13/2022
H-16290
Edwin I. Hatch Nuclear Plant Unit No. 1 Penetrations in
Reactor Building Walls Below EL. 130' - 0"
Reactor Building Walls Below EL. 130' - 0"
H-16610       Edwin I. Hatch Nuclear Plant Unit No. 1&2 Types of           Rev. 10
Rev. 13
71111.17T
Drawings
H-16610
Edwin I. Hatch Nuclear Plant Unit No. 1&2 Types of
Penetration Seals for Non Rated Walls, Pipe and Duct
Penetration Seals for Non Rated Walls, Pipe and Duct
Inspection Type         Designation   Description or Title                                       Revision or
Rev. 10
Procedure                                                                                          Date
Inspection
H-17241       Reactor Building 250V DC Essential MMC 1A- R24-S021         Rev. 13
Procedure
Type
Designation
Description or Title
Revision or
Date
H-17241
Reactor Building 250V DC Essential MMC 1A-R24-S021
External Connection Diagram Sheet 1 of 2
External Connection Diagram Sheet 1 of 2
H-17244       Reactor Building 250V DC Essential MMC 1A- R24-S021         Ver. 18
Rev. 13
H-17244
Reactor Building 250V DC Essential MMC 1A-R24-S021
External Connection Diagram Sheet 1 of 3
External Connection Diagram Sheet 1 of 3
Engineering  SNC1002069   2T41-611B & 2T41-612B Replacement                           Rev. 2.0
Ver. 18
Changes      SNC1002069   Replace Failed Indicators 2T41-R611B & 2T41-R612B           Ver. 2.0
SNC1002069
SNC105747     U1 Refueling Bridge Replacement                             Rev. 2
2T41-611B & 2T41-612B Replacement
SNC1077582   Reactor Building 250VDC MCC 1B 1R24S022 - Feeder           Rev. 1.0
Rev. 2.0
SNC1002069
Replace Failed Indicators 2T41-R611B & 2T41-R612B
Ver. 2.0
SNC105747
U1 Refueling Bridge Replacement
Rev. 2
SNC1077582
Reactor Building 250VDC MCC 1B 1R24S022 - Feeder
Cable Configuration Change for Frame 1
Cable Configuration Change for Frame 1
SNC1077794   1B RHR Heat Exchanger Channel Cover Gasket Mod             Rev. 2
Rev. 1.0
SNC1109070   Urgent Modification Required for Discontinued PRNM         Rev. 0
SNC1077794
1B RHR Heat Exchanger Channel Cover Gasket Mod
Rev. 2
SNC1109070
Urgent Modification Required for Discontinued PRNM
System Components
System Components
SNC1117345   1/2E11R608A/B Moving Average Function                       Rev. 0
Rev. 0
SNC1134609-21 Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA) Seq. 21
SNC1117345
SNC1138556   Master Recirc Controller Software Change                   Rev. 0
1/2E11R608A/B Moving Average Function
SNC419440     Install Water-Tight Seals on Sleeves in RX Building         Rev. 4
Rev. 0
SNC1134609-21
Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA)
Seq. 21
SNC1138556
Master Recirc Controller Software Change
Rev. 0
SNC419440
Install Water-Tight Seals on Sleeves in RX Building
Northeast Diagonal North Wall
Northeast Diagonal North Wall
SNC489859     Degraded Grid - U1 DVR Replacement                         Rev. 4
Rev. 4
SNC489865     Degraded Grid - U2 Final Configuration                     Ver. 4.0
SNC489859
SNC613988     U2 Refuel Floor Rail Modifications,                         Ver. 2.0
Degraded Grid - U1 DVR Replacement
SNC632608     Main Control Room Feedwater Controller Replacement         Rev. 1
Rev. 4
SNC652171     U1 Post LOCA H2O2 Analyzer Replacement                     Rev. 2
SNC489865
SNC759053     Unit 1 Feedwater Heater & MSR Drain Tank Level Control     Rev. 2.0
Degraded Grid - U2 Final Configuration
Ver. 4.0
SNC613988
U2 Refuel Floor Rail Modifications,
Ver. 2.0
SNC632608
Main Control Room Feedwater Controller Replacement
Rev. 1
SNC652171
U1 Post LOCA H2O2 Analyzer Replacement
Rev. 2
SNC759053
Unit 1 Feedwater Heater & MSR Drain Tank Level Control
Upgrade N22
Upgrade N22
SNC818160     Isolation Valve on the Seal Oil Return Pump Line           Rev. 2
Rev. 2.0
SNC826498     XL3 Fire Panel Replacements                                 Rev. 5
SNC818160
SNC882436     Replace CST Level Switches (1/2) E41-N002, (1/2) E41-       Ver. 2.0
Isolation Valve on the Seal Oil Return Pump Line
Rev. 2
SNC826498
XL3 Fire Panel Replacements
Rev. 5
SNC882436
Replace CST Level Switches (1/2) E41-N002, (1/2) E41-
N003
N003
SNC933973     As-found limit switch wiring for Recirc B Suction Valve     Ver. 1.0
Ver. 2.0
                                      (1B31F023B)
Engineering
Miscellaneous HM-S-10-004   Procurement Specification for Refueling Platform Assemblies Ver. 3.0
Changes
LDCR15-57     Degraded Grid U1 Final Configuration                     Ver. 2.0
SNC933973
LDCR15-60     DEGRADED GRID-U1 FINAL CONFIGURATION                       Ver. 1.0
As-found limit switch wiring for Recirc B Suction Valve  
Inspection Type       Designation     Description or Title                                     Revision or
(1B31F023B)
Procedure                                                                                      Date
Ver. 1.0
NL-19-0107     Edwin I. Hatch Nuclear Plant Unit 1&2 License Amendment 04/30/2019
HM-S-10-004
Procurement Specification for Refueling Platform Assemblies
Ver. 3.0
LDCR15-57
Degraded Grid U1 Final Configuration
Ver. 2.0
Miscellaneous
LDCR15-60
DEGRADED GRID-U1 FINAL CONFIGURATION
Ver. 1.0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NL-19-0107
Edwin I. Hatch Nuclear Plant Unit 1&2 License Amendment
Request for Technical Specification 3.3.8.1 and 3.8.1
Request for Technical Specification 3.3.8.1 and 3.8.1
Regarding Unit 1 Degraded Voltage Protection
Regarding Unit 1 Degraded Voltage Protection
Procedures  31EO-EOP-113-1 Terminating and Preventing Injection Into the RPV       Ver. 5.0
04/30/2019
31EO-SAG-002-1 RPV Pressure, Reactor Power, and Containment Control for Ver. 8.0
31EO-EOP-113-1
Terminating and Preventing Injection Into the RPV
Ver. 5.0
31EO-SAG-002-1
RPV Pressure, Reactor Power, and Containment Control for
Modes 1-4
Modes 1-4
31GO-OPS-010   Scram / Transient Analysis                               Ver. 7.6
Ver. 8.0
31GO-OPS-019-0 Use and Control of the Fuse Kit                         Ver. 2.0
31GO-OPS-010
34AB-R22-003-1- STATION BLACKOUT (SBO) FLOW CHART 3.0                    Ver. 3.0
Scram / Transient Analysis
Ver. 7.6
31GO-OPS-019-0
Use and Control of the Fuse Kit
Ver. 2.0
34AB-R22-003-1-
100
100
34SO-P33-001-1 Primary Containment Atmosphere H2O2 Analyzer System     Ver. 11.7
STATION BLACKOUT (SBO) FLOW CHART 3.0
NMP-GM-002     Corrective Action Program                               Ver. 16.0
Ver. 3.0
NMP-GM-002-     Corrective Action Program Instructions                  Ver. 43.0
34SO-P33-001-1
Primary Containment Atmosphere H2O2 Analyzer System
Ver. 11.7
NMP-GM-002
Corrective Action Program
Ver. 16.0
Procedures
NMP-GM-002-
001
001
Work Orders SNC1078884
Corrective Action Program Instructions
7
Ver. 43.0
Work Orders
SNC1078884
}}
}}

Latest revision as of 17:02, 27 November 2024

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000321/2022010 and 05000366/2022010
ML22140A110
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 05/20/2022
From: James Baptist
Division of Reactor Safety II
To: Gayheart C
Southern Nuclear Operating Co
References
IR 2022010
Download: ML22140A110 (9)
v • d • e


Text

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000321/2022010 AND 05000366/2022010

Dear Ms. Gayheart:

On April 8, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Edwin I. Hatch Nuclear Plant Units 1 & 2 and discussed the results of this inspection with Mr. Sonny Dean 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, James B. Baptist, Chief Engineering Br 1 Division of Reactor Safety 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:

05000321/2022010 and 05000366/2022010

Enterprise Identifier:

I-2022-010-0036

Licensee:

Southern Nuclear Operating Company

Facility:

Edwin I. Hatch Nuclear Plant Units 1 & 2

Location:

Baxley, GA 31513

Inspection Dates:

April 04-April 08, 2022

Inspectors:

T. Su, Reactor Inspector

C. Franklin, Reactor Inspector

J. Lizardi-Barreto, Construction Inspector

Approved By:

James B. Baptist, Chief

Engineering Br 1

Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline inspection at Edwin I. Hatch Nuclear Plant Units 1 & 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.

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.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

Main article: IP 71111.17

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from April 4-April 8, 2022.

(1) SNC105747, U1 Refuel Bridge Replacement
(2) SNC419440, Install Water-Tight Seals on Sleeves in RX Building Northeast Diagonal North Wall
(3) SNC489858, Degraded Grid - U1 DVR Replacement
(4) SNC489865, Degraded Grid - U2 Final Configuration
(5) SNC632608, Main Control Room Feedwater Controller Replacement
(6) SNC652171, U1 Post LOCA H2O2 Analyzer Replacement
(7) SNC759053, Unit 1 Feedwater Heater & MSR Drain Tank Level Control Upgrade N22
(8) SNC818160, Isolation Valve on the Seal Oil Return Pump Line
(9) SNC826498, XL3 Fire Panel Replacements
(10) SNC882436, Replace CST Level switches (1/2) E41-N002, (112) E41-N003
(11) SNC933973, As-Found limit switch wiring for Recirc B Suction Valve (1B31F023B)
(12) SNC1002069, 2T41-611B & 2T41-612B Replacement
(13) SNC105747, U1 Refuel Bridge Replacement
(14) SNC1077582, Reactor Building 250VDC MCC 1B 1R24S022 - Feeder Cable Configuration Change for Frame 1
(15) SNC1077794, 1B RHR Heat Exchanger Channel Cover Gasket Mod
(16) SNC1109070, Urgent Modification Required for Discontinued PRNM System Components
(17) SNC1117345, 1/2E11R608A/B Moving Average Function
(18) SNC1134609-21, Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA)
(19) SNC1138556, Master Recirc Controller Software Change (20)31EO-EOP-113-1, Terminating and Preventing Injection into The RPV 5.0 (21)31EO-SAG-002-1, RPV Pressure Reactor Power and Containment Control 8.0 (22)31GO-OPS-019-0, Use and Control of the Fuse Kit 2.0 (23)34AB-R22-003-1-100, Station Blackout (SBO) Flow Chart

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 8, 2022, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Sonny Dean and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

BH1-E-0088

DC Control Circuit Voltage Drop in Diesel Battery System

Rev. 8

CN-MRCDA-14-8

Hatch Refueling Platform Assembly Structural Evaluation

Rev. 7

MC-H-12-0179

Plant Service Water System Return Line - North East

Rev. 4

MC-H-12-0180

Plant Service Water System Supply Line - North East

Rev. 3

MC-H-15-0019

Diesel Generator Bldg Heating and Ventilation

Rev. 2

MC-H-15-0023

Emergency Diesel Batteries 1A, 1B, & 1C Sizing

Rev. 1

MC-H-17-0026

Refueling Platform Crane Rail and Stops

Ver. 3.0

MC-H-17-0029

Hatch Nuclear Plant Unit 1 - Floor at Nominal El. 228-0

Ver. 1.0

SCNH-15-021

Qualification of Anchorage for Wall-Mounted DVR Panel

H21-P080 - Diesel Generator Building, Unit 1 Switchgear

Room

Rev. 1

SCNH-15-022

Qualification of Anchorage for Wall-Mounted DVR Panel

H21-P081 - Diesel Generator Building, Unit 1 Switchgear

Room

Rev. 1

SINH-15-001

Technical Specifications 3.3.8.1-1 Setpoint Determination for

4.16kV Emergency Buses 1E, 1F and 1G Degraded Voltage

Relay Loops

Rev. 3

SINH-15-002

Setpoint Determination for 4.16 kV Emergency Buses 1E, 1F

and 1G Degraded Voltage Alarm Relay Loops

Rev. 3

Calculations

SQDS-H-19-0001

Seismic and Dynamic Qualification Data Summary

Ver. 1.0

CR 10585230

Loss of indication from multiple instruments powered from

Instrument bus 2B

2/24/2019

Corrective Action

Documents

CR 10771124

Expected Response not received during DECP SNC632608

Bench Test FT

2/02/2021

CR 10872216

Hatch NRC 50.59 Inspection Observance

04/07/2022

Corrective Action

Documents

Resulting from

Inspection

CR 10873618

System Response Time Not Addressed

04/13/2022

H-16290

Edwin I. Hatch Nuclear Plant Unit No. 1 Penetrations in

Reactor Building Walls Below EL. 130' - 0"

Rev. 13

71111.17T

Drawings

H-16610

Edwin I. Hatch Nuclear Plant Unit No. 1&2 Types of

Penetration Seals for Non Rated Walls, Pipe and Duct

Rev. 10

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

H-17241

Reactor Building 250V DC Essential MMC 1A-R24-S021

External Connection Diagram Sheet 1 of 2

Rev. 13

H-17244

Reactor Building 250V DC Essential MMC 1A-R24-S021

External Connection Diagram Sheet 1 of 3

Ver. 18

SNC1002069

2T41-611B & 2T41-612B Replacement

Rev. 2.0

SNC1002069

Replace Failed Indicators 2T41-R611B & 2T41-R612B

Ver. 2.0

SNC105747

U1 Refueling Bridge Replacement

Rev. 2

SNC1077582

Reactor Building 250VDC MCC 1B 1R24S022 - Feeder

Cable Configuration Change for Frame 1

Rev. 1.0

SNC1077794

1B RHR Heat Exchanger Channel Cover Gasket Mod

Rev. 2

SNC1109070

Urgent Modification Required for Discontinued PRNM

System Components

Rev. 0

SNC1117345

1/2E11R608A/B Moving Average Function

Rev. 0

SNC1134609-21

Hatch-1 Cycle 31 Reload 50.59 (Accident Tolerant Fuel LTA)

Seq. 21

SNC1138556

Master Recirc Controller Software Change

Rev. 0

SNC419440

Install Water-Tight Seals on Sleeves in RX Building

Northeast Diagonal North Wall

Rev. 4

SNC489859

Degraded Grid - U1 DVR Replacement

Rev. 4

SNC489865

Degraded Grid - U2 Final Configuration

Ver. 4.0

SNC613988

U2 Refuel Floor Rail Modifications,

Ver. 2.0

SNC632608

Main Control Room Feedwater Controller Replacement

Rev. 1

SNC652171

U1 Post LOCA H2O2 Analyzer Replacement

Rev. 2

SNC759053

Unit 1 Feedwater Heater & MSR Drain Tank Level Control

Upgrade N22

Rev. 2.0

SNC818160

Isolation Valve on the Seal Oil Return Pump Line

Rev. 2

SNC826498

XL3 Fire Panel Replacements

Rev. 5

SNC882436

Replace CST Level Switches (1/2) E41-N002, (1/2) E41-

N003

Ver. 2.0

Engineering

Changes

SNC933973

As-found limit switch wiring for Recirc B Suction Valve

(1B31F023B)

Ver. 1.0

HM-S-10-004

Procurement Specification for Refueling Platform Assemblies

Ver. 3.0

LDCR15-57

Degraded Grid U1 Final Configuration

Ver. 2.0

Miscellaneous

LDCR15-60

DEGRADED GRID-U1 FINAL CONFIGURATION

Ver. 1.0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NL-19-0107

Edwin I. Hatch Nuclear Plant Unit 1&2 License Amendment

Request for Technical Specification 3.3.8.1 and 3.8.1

Regarding Unit 1 Degraded Voltage Protection

04/30/2019

31EO-EOP-113-1

Terminating and Preventing Injection Into the RPV

Ver. 5.0

31EO-SAG-002-1

RPV Pressure, Reactor Power, and Containment Control for

Modes 1-4

Ver. 8.0

31GO-OPS-010

Scram / Transient Analysis

Ver. 7.6

31GO-OPS-019-0

Use and Control of the Fuse Kit

Ver. 2.0

34AB-R22-003-1-

100

STATION BLACKOUT (SBO) FLOW CHART 3.0

Ver. 3.0

34SO-P33-001-1

Primary Containment Atmosphere H2O2 Analyzer System

Ver. 11.7

NMP-GM-002

Corrective Action Program

Ver. 16.0

Procedures

NMP-GM-002-

001

Corrective Action Program Instructions

Ver. 43.0

Work Orders

SNC1078884

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