IR 05000321/2019011

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000321/2019011 and 05000366/2019011

ML19213A338
Person / Time
Site:	Hatch
Issue date:	08/01/2019
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Dean E Southern Nuclear Operating Co
References
IR 2019011
Download: ML19213A338 (10)

Text

August 1, 2019

SUBJECT:

EDWIN I. HATCH, UNITS 1 AND 2 - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000321/2019011 AND 05000366/2019011

Dear Mr. Dean:

On June 28, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Edwin I. Hatch, Units 1 and 2 and discussed the results of this inspection with Mr. Tony Spring, plant manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

James B. Baptist, Chief Engineering Branch 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:

05000321/2019011 and 05000366/2019011

Licensee:

Southern Nuclear Operating Co., Inc.

Facility:

Edwin I. Hatch, Units 1 and 2

Location:

Baxley, GA 31513

Inspection Dates:

June 24, 2019 to June 28, 2019

Inspectors:

C. Franklin, Reactor Inspector

M. Riley, Reactor Inspector

T. Su, Reactor Inspector

Approved By:

James B. Baptist, Chief

Engineering Branch 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, Units 1 and 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

Type Issue Number Title Report Section Status URI 05000366,05000321/2 016008-04 Unresolved Item, Potential departure from protection system design basis 71111.17T Closed

INSPECTION SCOPE

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 June 24, 2019, to June 28, 2019.

(1) SNC467474, Unit 2 Flex Alternate Power

(2) SNC548828, Unit 1 Recorder Replacement Panel 1H11P601

(3) SNC629427, Unit 2 Non-Outage Recorder Replacement (2H11P650 and 2H11P689)

(4) SNC539300, SAM - Unit 1 Reliable Hardened Vent System

(5) SNC629425, Unit 2 Outage Recorder Replacement (2H11P650, 2H11P601, 2H11P602)

(6) SNC528997, Unit 1 Recorder Replacement Panel 1H11P603

(7) SNC105633, Replace the Unit 1 inboard and outboard feedwater check valves

(8) SNC598529, Replace 1E41-F001 Steam Admission Valve

(9) SNC919937, DOC to Evaluate increase in load for Emergency Diesel Generator Air Starter Piping

(10) SNC99233, Main Control Room Isolation Damper Modification

(11) SNC99382, RHRSW Control Valves Replacement

(12) SNC99451, Hatch Unit 1 JOG MOV Modification

(13) SNC489852, Degraded Grid - Unit 1 Safety Related (Class 1E) Bus Upgrade

(14) SNC595828, Unit 2 Division 1 Station Service Battery Chargers Replacement

(15) SNC489866, Degraded Grid - Unit 2 Degraded Voltage Relay Replacement

(16) SNC732678, Discrepancy in NLI Qualification Report S-75264

(17) SNC701928, Molded Case Circuit Breaker Replacements (4A, 6A, & 9C) on

1R24 S022 MCC (18)34AB-R22-003-1, Station Blackout (SBO) (19)

SNC811298, 2P41-F316A/C/D Fuse Size Change (20)34AB-S11-001-0, Operation with Degraded System Voltage

INSPECTION RESULTS

Unresolved Item (Closed)

Unresolved Item, Potential departure from protection system design basis 05000366,05000321/2016008-04 71111.17T

Description:

Unresolved Item (URI) 05000321, 366/2016008-04 was opened on August 1, 2016, in NRC Evaluation of Changes, Tests, and Experiments and Permanent Plant Modifications Inspection Report 05000321/2016008 and 05000366/2016008 (ADAMS Accession Number: ML16215A429) to determine if a performance deficiency existed. The inspectors questioned whether the Edwin I. Hatch design complied with channel independence requirements identified in IEEE 279-1971 Section 4.6. The licensee provided documentation related to the original submittal of the design to the NRC and the NRCs acceptance of the design.

The inspectors reviewed additional information provided by the licensee, performed further inspection, held discussions with NRR, and NRC management to resolve this URI.

Additionally, the inspectors reviewed new service life guidance Dispositioning Information Related to Service Life of Installed Safety Related SSCs, the updated guidance in ADAMS Accession Number ML18338A088 and Inspection Manual Chapter Inspection Procedure 71111.21N (Accession No. ML19036A556). The service life guidance stated that:

"There is no regulatory requirement to define replacement/refurbishment intervals for all safety-related SSCs.

Based on the additional review and the above-mentioned guidance, the inspectors did not identify a performance deficiency associated with these concerns. URI 05000321, 366/2016008-04 is now closed.

EXIT MEETINGS AND DEBRIEFS

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

• On June 28, 2019, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Tony Spring, plant manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

BH1-E-0104

Heat Load Generated by HNP-1&2 Electrical Equipment in

the Main Control Room

Version 10.0

MC-H-14-0102

Emergency Diesel Batteries 2A & 2C Sizing

Version 2.0

MC-H-14-0215

Torus Vent Rupture Disc Setpoint

Version 1.0

MC-H-15-0046

DC MOV Motor Performance Methodology

Version 1.0

MC-H-15-0047

Motor Operated Valve Torque Switch Setting Guide

Version 1.0

MC-H-15-0132

Heat Load Generated by HNP-1&2 Electrical Equipment in

the Main Control Room

Revision 1

MC-H-15-0219

Loading for Vital AC Panel 2R25-S063

Revision 1

S-75087

E. I. Hatch Nuclear Plant - Unit No. 1 Crane

Seismic/Weaklink Report (SR-306) for 1E41-F002 and 1E41-

F003

Version 1.0

S-75089

E. I. Hatch Nuclear Plant - Unit No. 1 Weak Link Analysis

Report RAL-7822 for MOV 1E41-F001

Version 1.0

SENH-00-010

Loading for Vital AC Panel 2R25-S063

Version 9.0

SENH-00-010

Loading for Vital AC Panel 2R25-S063

Version 10

SENH-13-005

Load Data for Sizing the Inverters for FLEX and HVAC

Version 1.0

SENH-13-010

Unit 2 Station Auxiliary System Study - Interim/Final

Version 1.0

SINH-14-007

Technical Specification 3.3.8.1-1 Setpoint Determination for

4.16kV Emergency Buses 2E, 2F and 2G Degraded Voltage

Relay Loops

Version 2.0

SMNH-03-005

DC MOV Motor Performance Methodology

Version 1.0

SMNH-95-013

Determine Valve Maximum Closing Time for 1/2 E11-F008 &

1/2 E11-F009

Revision 1.0

SMSH-97-002

Pipe Stress Analysis of HPCI System Piping from

Penetration no. X11 to HPCI Turbine Inlet

Version 3.0

Corrective Action

Documents

2010106225

CR 10138133

CR 10240030

CR 10299840

71111.17T

Corrective Action

Documents

TE 967961

CR 10622848

Typographical Error

06/24/2019

Corrective Action

Documents

Resulting from

Inspection

CR 10623461

Red Light Bulb Light Out at 2R22S005, Frame 1

06/25/2019

CR 10623462

Red Light Bulb Light Out at 2R22S005, Frame 11

06/25/2019

CR 10623800

Yokogawa Recorder PM Strategy

06/26/2019

Drawings

A-21392

Pipe Supports Service Air to Diesel Generators

Version 0.0

A-27001

Electrical Separation Criteria and Raceway and Cable

Numbering System

Version 26

H-11631

E. I. Hatch Nuclear Plant Unit No. 1 P&ID Diesel Generator

1A & 1C

Version 9.0

H-13350

Edwin I. Hatch Plant Unit 1 Master Single Line Diagram

Version 29.0

H-16332

E. I. Hatch Nuclear Plant Unit No. 1 HPCI System P&ID

Version 67.0

H-23350

Edwin I. Hatch Nuclear Plant Unit 2 Master Single Line

Diagram

Version 15.0

S-64424

Schematic, 400A Battery Charger

Version 2.0

S-64425

Schematic, 400A Battery Charger

Version 3.0

Engineering

Changes

34AB-R22-003-1

Station Blackout (SBO)

11/14/2017

34AB-S11-001-0

Operation with Degraded System Voltage

11/7/2018

DCP1080654701

Unit 1 RHRSW Valve Modification and Orifice Installation

2/18/2009

DCP1081999401

Residual Heat Removal Service Water (RHRSW) Control

Valves Replacement

06/29/2012

DCP1082070201

Hatch Unit 1 JOB MOV Modification

2/28/2012

DCP110175501

Inboard and Outboard Feedwater Check Valves

Replacement

05/21/2013

SNC467474

Unit 2 Flex Alternate Power

04/5/2016

SNC489852

Degraded Grid - Unit 1 Safety-Related (Class 1E) Bus

Upgrade

2/13/2018

SNC489866

Degraded Grid - Unit 2 Degraded Voltage Relay

Replacement

04/20/2018

SNC528997

Unit 1 Recorder Replacement Panel 1H11P603

2/25/2016

SNC539300

Unit 1 Reliable Hardened Containment Vent Design

2/29/2019

SNC548828

Unit 1 Recorder Replacement Panel 1H11P601

05/14/2015

71111.17T

Engineering

Changes

SNC595828

Unit 2 Division I Station Service Battery Chargers

Replacement

Version 2.0

SNC595830

Unit 2 Division II Station Battery Charger Replacement

Version 3.0

SNC598529

U1 Replace HPCI Valve 1E41-F001

08/04/2015

SNC629425

U2 Outage Recorder Replacement (2H11P650, 2H11P601,

2H11P602)

Version 2.0

SNC629427

Unit 2 Non-Outage Recorder Replacement

Version 3.0

SNC701928

Molded Case Circuit Breaker Replacement (4A, 6A, & 9C)

on 1R24S022 MCC

Version 1.0

SNC732678

Discrepancy in NLI Qualification Report S-75264

Version 1.0

SNC811298

2P41-F316A, C, &D Fuse Size Change

Revision 1

SNC919937

Evaluate Increase in Load for Emergency Diesel Generator

Air Starter Piping Supports

04/26/2018

SNC99233

Main Control Room Restroom Isolation Damper Modification

05/02/2017

Miscellaneous

LTR-EMPE-14-68

Short Circuit Study - Hatch Unit 1 Buses E, F, and G

Revision 1

S-57857

DX1000 Instruction Manual

Revision 1.0

S-57860

E. I. Hatch Nuclear Plant - Unit No. 1 / 2, DX1000/2000

V&V/EMI Test Report

Revision 2

S-57861

E. I. Hatch Nuclear Plant - Unit No. 1 / 2, DX1000/2000

SEISMIC Test Report

Revision 2.0

S-64429

Instruction and Operating Manual with Drawings (400A

Battery Chargers) (MPL NOs 2R42-S026,2R42-S027,2R42-

S028,2R42-S029,2R42-S030,2R42-S031)

Version 2.0

S-75515

DAQ Station DX2000 Operation Guide

Revision 1.0

S25092

Design Specification for Residual Heat Removal System with

Steam Condensing

2/03/1971

S44268

NLI Qualification Report for Westinghouse Motor Control

Center Components & Buckets

Version 2.0

S76080

Test Report for Software/ Firmware Validation of Yokogawa

DX Advanced Series Recorders

Revision 1

SN9604-002

Southern Nuclear Operating Company, EMI Qualification

Requirements Specifications

Version 2.0

SNC489866FMEA Hatch Unit 2 DVR Replacement

Version 1.0

71111.17T

Miscellaneous

TB-04-13

Replacement Solutions for Obsolete Classic Molded Case

Circuit Breakers, UL Testing Issues, Breaker Design Life and

Trip Band Adjustment

06/28/2004

Operability

Evaluations

34SV-E41-001-1

HPCI Valve Operability

03/11/2019

Procedures

2GM-MEL-006-0

Sealing Entrances Into Safety Related Devices

Revision 16.32

57CP-CAL-097-1

Rosemount Nuclear Transmitters

Version 32.0

IP-ENG-001

Standard Design Process

Revision 0

NMP-AD-010

CFR 50.59 Screenings and Evaluations

Version 16.0

NMP-ES-038-002

Preparation of Failure Modes and Effects Analysis

Version 6.0

NMP-ES-095

Interface Procedure for IP-ENG-001, Standard Design

Process

Version 6.0

NMP-OS-019-266

Hatch Unit 1 SIG-6, Containment Integrity

Version 2.2

31EO-FSG-003-1

FSG-ELAP (Extended Loss of AC Power)

Version 2.2

31RS-OPS-002-2

Remote Shutdown Procedure

Version 6.0

34AB-R22-003-2

Station Blackout

Version 10.1

34AB-R43-001-2

Diesel Generator Recovery

Version 6.1

34SO-R43-001-2

Diesel Generator Standby AC System

Version 30.3

2GM-MEL-003-0

Cable/Raceway Installation and Cable Terminations

Revision 26.7

Work Orders

SNC325064

SNC325074

SNC576040

SNC613213

SNC613214

SNC659789

SNC659791

SNC839050

SNC881974

SNC881987

SNC99465

SNC99469

SNC99472