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

ust 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 Enterprise Identifier: I-2019-011-0005 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 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, 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 Unresolved Item, Potential 71111.17T Closed 016008-04 departure from protection system design basis

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

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations BH1-E-0104 Heat Load Generated by HNP-1&2 Electrical Equipment in Version 10.0

the Main Control Room

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 Revision 1

the Main Control Room

MC-H-15-0219 Loading for Vital AC Panel 2R25-S063 Revision 1

S-75087 E. I. Hatch Nuclear Plant - Unit No. 1 Crane Version 1.0

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

F003

S-75089 E. I. Hatch Nuclear Plant - Unit No. 1 Weak Link Analysis Version 1.0

Report RAL-7822 for MOV 1E41-F001

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 Version 2.0

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

Relay Loops

SMNH-03-005 DC MOV Motor Performance Methodology Version 1.0

SMNH-95-013 Determine Valve Maximum Closing Time for 1/2 E11-F008 & Revision 1.0

1/2 E11-F009

SMSH-97-002 Pipe Stress Analysis of HPCI System Piping from Version 3.0

Penetration no. X11 to HPCI Turbine Inlet

Corrective Action 2010106225

Documents CR 10138133

CR 10240030

CR 10299840

71111.17T Corrective Action TE 967961

Documents CR 10622848 Typographical Error 06/24/2019

Corrective Action CR 10623461 Red Light Bulb Light Out at 2R22S005, Frame 1 06/25/2019

Documents CR 10623462 Red Light Bulb Light Out at 2R22S005, Frame 11 06/25/2019

Resulting from CR 10623800 Yokogawa Recorder PM Strategy 06/26/2019

Inspection

Drawings A-21392 Pipe Supports Service Air to Diesel Generators Version 0.0

A-27001 Electrical Separation Criteria and Raceway and Cable Version 26

Numbering System

H-11631 E. I. Hatch Nuclear Plant Unit No. 1 P&ID Diesel Generator Version 9.0

1A & 1C

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 Version 15.0

Diagram

S-64424 Schematic, 400A Battery Charger Version 2.0

S-64425 Schematic, 400A Battery Charger Version 3.0

Engineering 34AB-R22-003-1 Station Blackout (SBO) 11/14/2017

Changes 34AB-S11-001-0 Operation with Degraded System Voltage 11/7/2018

DCP1080654701 Unit 1 RHRSW Valve Modification and Orifice Installation 12/18/2009

DCP1081999401 Residual Heat Removal Service Water (RHRSW) Control 06/29/2012

Valves Replacement

DCP1082070201 Hatch Unit 1 JOB MOV Modification 02/28/2012

DCP110175501 Inboard and Outboard Feedwater Check Valves 05/21/2013

Replacement

SNC467474 Unit 2 Flex Alternate Power 04/5/2016

SNC489852 Degraded Grid - Unit 1 Safety-Related (Class 1E) Bus 02/13/2018

Upgrade

SNC489866 Degraded Grid - Unit 2 Degraded Voltage Relay 04/20/2018

Replacement

SNC528997 Unit 1 Recorder Replacement Panel 1H11P603 02/25/2016

SNC539300 Unit 1 Reliable Hardened Containment Vent Design 02/29/2019

SNC548828 Unit 1 Recorder Replacement Panel 1H11P601 05/14/2015

71111.17T Engineering SNC595828 Unit 2 Division I Station Service Battery Chargers Version 2.0

Changes Replacement

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, Version 2.0

2H11P602)

SNC629427 Unit 2 Non-Outage Recorder Replacement Version 3.0

SNC701928 Molded Case Circuit Breaker Replacement (4A, 6A, & 9C) Version 1.0

on 1R24S022 MCC

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 04/26/2018

Air Starter Piping Supports

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 Revision 2

V&V/EMI Test Report

S-57861

E. I. Hatch Nuclear Plant - Unit No. 1 / 2, DX1000/2000 Revision 2.0

SEISMIC Test Report

S-64429 Instruction and Operating Manual with Drawings (400A Version 2.0

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

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

S-75515 DAQ Station DX2000 Operation Guide Revision 1.0

S25092 Design Specification for Residual Heat Removal System with 02/03/1971

Steam Condensing

S44268 NLI Qualification Report for Westinghouse Motor Control Version 2.0

Center Components & Buckets

S76080 Test Report for Software/ Firmware Validation of Yokogawa Revision 1

DX Advanced Series Recorders

SN9604-002 Southern Nuclear Operating Company, EMI Qualification Version 2.0

Requirements Specifications

SNC489866FMEA Hatch Unit 2 DVR Replacement Version 1.0

71111.17T Miscellaneous TB-04-13 Replacement Solutions for Obsolete Classic Molded Case 06/28/2004

Circuit Breakers, UL Testing Issues, Breaker Design Life and

Trip Band Adjustment

Operability 34SV-E41-001-1 HPCI Valve Operability 03/11/2019

Evaluations

Procedures 52GM-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 10 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 Version 6.0

Process

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

8