IR 05000321/2019011
| 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:
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
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
- (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
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
Station Blackout (SBO)
11/14/2017
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
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
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
HPCI Valve Operability
03/11/2019
Procedures
Sealing Entrances Into Safety Related Devices
Revision 16.32
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
FSG-ELAP (Extended Loss of AC Power)
Version 2.2
Remote Shutdown Procedure
Version 6.0
Station Blackout
Version 10.1
Diesel Generator Recovery
Version 6.1
Diesel Generator Standby AC System
Version 30.3
Cable/Raceway Installation and Cable Terminations
Revision 26.7
Work Orders
SNC325064
SNC325074
SNC576040
SNC613213
SNC613214
SNC659789
SNC659791
SNC839050
SNC881974
SNC881987
SNC99465
SNC99469
SNC99472