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

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

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations 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 Rev. 1

H21-P080 - Diesel Generator Building, Unit 1 Switchgear

Room

SCNH-15-022 Qualification of Anchorage for Wall-Mounted DVR Panel Rev. 1

H21-P081 - Diesel Generator Building, Unit 1 Switchgear

Room

SINH-15-001 Technical Specifications 3.3.8.1-1 Setpoint Determination for Rev. 3

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

Relay Loops

SINH-15-002 Setpoint Determination for 4.16 kV Emergency Buses 1E, 1F Rev. 3

and 1G Degraded Voltage Alarm Relay Loops

SQDS-H-19-0001 Seismic and Dynamic Qualification Data Summary Ver. 1.0

Corrective Action CR 10585230 Loss of indication from multiple instruments powered from 02/24/2019

Documents Instrument bus 2B

CR 10771124 Expected Response not received during DECP SNC632608 02/02/2021

Bench Test FT

Corrective Action CR 10872216 Hatch NRC 50.59 Inspection Observance 04/07/2022

Documents CR 10873618 System Response Time Not Addressed 04/13/2022

Resulting from

Inspection

Drawings H-16290 Edwin I. Hatch Nuclear Plant Unit No. 1 Penetrations in Rev. 13

Reactor Building Walls Below EL. 130' - 0"

H-16610 Edwin I. Hatch Nuclear Plant Unit No. 1&2 Types of Rev. 10

Penetration Seals for Non Rated Walls, Pipe and Duct

Inspection Type Designation Description or Title Revision or

Procedure Date

H-17241 Reactor Building 250V DC Essential MMC 1A-R24-S021 Rev. 13

External Connection Diagram Sheet 1 of 2

H-17244 Reactor Building 250V DC Essential MMC 1A-R24-S021 Ver. 18

External Connection Diagram Sheet 1 of 3

Engineering SNC1002069 2T41-611B & 2T41-612B Replacement Rev. 2.0

Changes 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 Rev. 1.0

Cable Configuration Change for Frame 1

SNC1077794 1B RHR Heat Exchanger Channel Cover Gasket Mod Rev. 2

SNC1109070 Urgent Modification Required for Discontinued PRNM Rev. 0

System Components

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 Rev. 4

Northeast Diagonal North Wall

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 Rev. 2.0

Upgrade N22

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-Ver. 2.0

N003

SNC933973 As-found limit switch wiring for Recirc B Suction Valve Ver. 1.0

(1B31F023B)

Miscellaneous HM-S-10-004 Procurement Specification for Refueling Platform AssembliesVer. 3.0

LDCR15-57 Degraded Grid U1 Final Configuration Ver. 2.0

LDCR15-60 DEGRADED GRID-U1 FINAL CONFIGURATION Ver. 1.0

Inspection Type Designation Description or Title Revision or

Procedure Date

NL-19-0107 Edwin I. Hatch Nuclear Plant Unit 1&2 License Amendment 04/30/2019

Request for Technical Specification 3.3.8.1 and 3.8.1

Regarding Unit 1 Degraded Voltage Protection

Procedures 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 Ver. 8.0

Modes 1-4

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-STATION BLACKOUT (SBO) FLOW CHART 3.0 Ver. 3.0

100

34SO-P33-001-1 Primary Containment Atmosphere H2O2 Analyzer System Ver. 11.7

NMP-GM-002 Corrective Action Program Ver. 16.0

NMP-GM-002-Corrective Action Program Instructions Ver. 43.0

001

Work Orders SNC1078884

7