IR 05000321/2022010
| 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:
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)
- (13) SNC105747, U1 Refuel Bridge Replacement
- (14) SNC1077582, Reactor Building 250VDC MCC 1B 1R24S022 - Feeder Cable Configuration Change for Frame 1
- (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
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
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
Terminating and Preventing Injection Into the RPV
Ver. 5.0
RPV Pressure, Reactor Power, and Containment Control for
Modes 1-4
Ver. 8.0
Ver. 7.6
Use and Control of the Fuse Kit
Ver. 2.0
100
STATION BLACKOUT (SBO) FLOW CHART 3.0
Ver. 3.0
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