IR 05000321/2022010

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000321/2022010 and 05000366/2022010

ML22140A110
Person / Time
Site:	Hatch
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)

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)

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