IR 05000261/2022010
| ML22269A334 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/26/2022 |
| From: | James Baptist NRC/RGN-II |
| To: | Flippin N Duke Energy Progress |
| References | |
| IR 2022010 | |
| Download: ML22269A334 (13) | |
Text
SUBJECT:
H.B. ROBINSON STEAM ELECTRIC PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000261/2022010
Dear Ms. Flippin:
On August 12, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at H.B. Robinson Steam Electric Plant and discussed the results of this inspection with you 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 No. 05000261 License No. DPR-23
Enclosure:
As stated
Inspection Report
Docket Number:
05000261
License Number:
Report Number:
Enterprise Identifier:
I-2022-010-0049
Licensee:
Duke Energy Progress, LLC
Facility:
H.B. Robinson Steam Electric Plant
Location:
Hartsville, SC
Inspection Dates:
July 25, 2022 to August 12, 2022
Inspectors:
P. Braxton, Reactor Inspector
T. Fanelli, Senior Reactor Inspector
R. Fanner, Reactor Inspector
C. Franklin, Reactor Inspector
W. Sherbin, Contractor
T. Su, Reactor 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 design basis assurance inspection (teams) inspection at H.B.
Robinson Steam Electric Plant, 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
===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (6 Samples)
- (1) Boron Injection Valves SI-870A & SI-870B
Design bases documents, system descriptions, and training documents
Primary design calculations
Normal, Abnormal, and Emergency Operating Procedures
Surveillance Test Procedures and Recent Results
Material Condition of Valves and Associated Equipment
Vendor Instruction Manuals
Corrective Action History and System Health Reports
Condition reports associated with component
Local Leak Rate Test Procedure and Recent Results (2)480V-E1, 480V-E2, MCC-9
Compliance with UFSAR, TS and TS Bases
Material Condition and Configuration
Design Requirements
Environmental Conditions
Maintenance and Surveillance Test reviews
Protective relay setting and calibration (3)125 VDC (Distribution Panel D-3) (Batteries or Inverters or Chargers)
verified adequacy of battery capacity
Verified short circuit calculations and protection capacity
Verified voltage drop calculations
- (4) Unit Service Water (SW) System, Including SW Pumps, Ultimate Heat Sink (UHS),and Deep Well Pump For SW Pumps:
Normal and Emergency Operating Procedures
Surveillance Test Procedures and Recent Results
Inservice Test Procedures and Recent Results
Basis for Pump Test Acceptance Criteria, Including Instrument Uncertainty
System Hydraulic Calculations Indicating Required SW Flow Criteria to Safety Related Heat Exchangers are Met
Material Condition of Pumps and Associated Equipment
Corrective Action History For UHS (Lake Robinson):
Calculation for Determining the Volume of Water Available to the SW Pumps for the Licensing Basis Time Requirement (22 Days)
Technical Specification for Lake Level Requirement to Ensure SW Pumps Suction Bell Submergence is Sufficient to Prevent Votexing
Discussions With Staff to Ensure Water Quality is Maintained For Deep Well Pump:
Procedure Used to Align Deep Well Pump in the Event That Lake Robinson Water Level is Lost
Pump Surveillance Test Procedures and Recent Results
- (5) Steam Driven Auxiliary Feedwater Pump
Normal and Emergency Operating Procedures
Surveillance Test Procedures and Recent Results
Inservice Test Procedures and Recent Results
Basis for Pump Test Acceptance Criteria, Including Instrument Uncertainty
CST Level Instrumentation Setpoints Which Actuate Alarms to Notify Operators to Transfer AFW Suction Source from CST to Service Water
Vortex Calculation for Pump Suction from CST
Seismic Qualification of preferred AFW pump suction water source (CST)
Material Condition of Pump and Associated Equipment
Modification Performed to Install CST Bladder
Corrective Action History
- (6) Emergency Diesel Generator (EDG) Room Ventilation System
Normal and Emergency Operating Procedures
Surveillance Test Procedures and Recent Results
EDG Room Heat Load Calculation Which Determines Ventilation Air Flow
Ventilation Supply and Exhaust Fan Specifications
Surveillance Test Procedures and Recent Results Which Verify Fan Operation During EDG Operation Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
- (1) Service Water Booster Pump A
Compliance with the Update Final Safety Analysis Report and the Technical Specifications
Primary design calculations
Normal, Abnormal, and Emergency Operating Procedures
Material condition and configuration
Surveillance test procedures and recent results
System health report
Normal and emergency operating procedures
Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)
- (2) EC 0000402563 002, Provide Selective Coordination of 125VDC Power Supplies to Support NFPA 805 LAR
- (4) EC 417357/417864, EDG Day Tank Level Switches Design Change
Review of Operating Experience Issues (IP Section 02.06) (3 Samples)
- (1) Information Notice 2021-01 Lessons Learned from NRC Inspections of Design-Basis Capability of Power-Operated Valves at Nuclear Power Plants
- (2) Part 21 2019-11-00, 2021-07-00 and 01, AMETEK Solid state Controls Notification of Potential Defect
- (3) Information Notice 2016-09, Recent Issues Identified When Using Reverse Engineering Techniques in the Procurement of Safety-Related Components
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On August 12, 2022, the inspectors presented the design basis assurance inspection (teams) inspection results to Nicole Flippin and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
16-025
NFPA 805 RNP Coordination Study
Rev.1
212-C-020
Relays Requiring System Consequence Review
Rev. 0
213-C-066
Atmosphere Storage Tanks-CST
Rev. 0
84065-M-06-F
New Basis for CST Level Indication for CST Repair and
Restoration - HBR Unit 2
Rev. 0
HBR2-11260
SH00004
Zone Map for Environment Parameters
Reactor Aux Bldg. EL. 242`-6" and 246`-0"
Rev. 5
RNP-C/FLEX-0052
Seismic Fragility Analysis of the CST
Rev. 1
RNP-E-2.009
Overcurrent Protection Emergency Bus E1 and E2
Emergency Supply
Rev. 3
RNP-E-2.010
Overcurrent Protection Emergency Bus E1 and E2-Normal
Supply
Rev. 3
RNP-E-5.031
Cable Sizing for Battery Charger A-1
Rev. 0
RNP-E-6.004
Short Circuit Calculation
Rev. 9
RNP-E-6.005
Overcurrent Protection and Coordination of the 125 VDC
Distribution System (Trains A and B)
Rev. 4
RNP-E-8.002
AC Auxiliary Electrical Distribution System Voltage/Load
Flow/Fault Current Study
Rev.10
RNP-I/INST-1015
CST Level Uncertainty
Rev. 8
RNP-M/HVAC-
1064
A & B EDG Room Steady State Temperature
Rev. 1
RNP-M/MECH-
1461
Minimum SDAFW Pump Suction Pressure vs. CST Level
Rev. 0
RNP-M/MECH-
24
Set Up Calculation for MOV SI-870A
Rev. 14
RNP-M/MECH-
29
Set Up Calculation for MOV SI-870B
Rev. 14
RNP-M/MECH-
1519
Service Water System Operation with One Pump
Rev. 0
RNP-M/MECH-
1645
Availability of Lake Robinson to Provide Ultimate Heat Sink
Cooling
Rev. 13
Calculations
RNP-M/MECH-
Service Water System Hydraulic Evaluation
Rev. 4
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1653
RNP-M/MECH-
1655
AFW ProtoFlow Model
Rev. 2
RNP-M/MECH-
1769
Deep Well Pump D Thermal Hydraulic Analyses
Rev. 4
RNP-M/MECH-
1802
Safety Related Pump Minimum Performance Requirements
Rev. 12
RNP-M/MECH-
1905
EPRI PPM Analysis For SI-869 SI-870A/B
Rev. 1
RNP_E-6.020
Load Profile and Battery Sizing Calculation for Battery B
Rev. 9
AMETECK Solidstate Controls Inc. (Part 21) - Vendor
Notification #53993, Part 21 Report - Overheating And
Failure Of Transformers
04/23/2019
Unresolved Items on Battery Chargers
10/26/2021
Corrective Action
Documents
2340607,
2342647,
2346091,
2401058,
2410961
CAP 02436847
22 DBAI: Errors in RNP-E/ELEC-1220 and RNP-E-5.031
08/04/2022
Corrective Action
Documents
Resulting from
Inspection
CR 02437413
22 DBAI: Error in Single Line Depiction for Calculation
RNP-E-6.005, R4
08/09/2022
5379-01082 SH 1 -
Safety Injection System Flow Diagram
Rev. 50
5379-05374
480V One Line Diagram
Rev. 32
5379-2762
Diagrams - AUX. Feedwater Pump Start-Up
Rev. 15
2-M-2005
CST Details, Bladder
Rev. C
G-190197
Feedwater, Condensate, and Air Evacuation System
Rev. 75
G-190199
Service and Cooling Water System
Rev. 87
G-190199 SH7
Service And Cooling Water System Flow Diagram
Rev. 41
G-1902040
Fuel Oil System
Rev. 1
Drawings
G-190304
HVAC-Turbine, Fuel, Aux., Reactor, & Radwaste Buildings
Rev. 66
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
G-190626
25 V DC & Vital AC One Line Diagram
Rev. 27
G-190626, Sheet 3
25V DC & 120V AC One Line Diagram
Rev. 25
HBR2-11260
Zone Map for Environmental Parameters, Reactor Aux
Bldg EL 242'6" and 246'-0", Sheet 4
Rev. 5
Modify SI-869, SI-870A/B to Conform to GL 96-05 and the
Rev. 13
Provide Selective Coordination of 125VDC Power Supplies
Rev. 2
Replace EDG Day Tank "B" Level Control Switches
Rev. 3
Connect FLEX Diesel to 125 VDC Battery Chargers
Rev. 51
ESR # 95-00266
Replace EDG Day Tank "A" Level Control Switches
Rev. 1
Engineering
Changes
Mod 680
CST Sealing Bladder
04/08/85
27-909-91
Gate and Globe Valve
Rev. 11
28-562-71
SMB Valve Controls
Rev. 43
28-812-46
Velan Valve Instruction Manual for Manual Valves:
Installation, Operation, and Maintenance
Rev. 12
738-523-20
Breakers, 480V, MCC Westinghouse
Rev.10
2-209-181
Ametek Solidstate Controls Instruction Technical Manual
300 amp Battery Charger
Rev. 3
AR 02377519-01
AMETEK Part 21 Notice for TVA Diodes
04/21/2021
DBD/R87038/SD02
Design Basis Document Safety Injection System
Rev. 24
DBD/R87038/SD16
SYS DBD-Electrical Power Distribution System
DBD/R87038/SD32
SYS DBD - Auxiliary Feedwater System
Rev. 12
Feedwater System
Rev. 09
First Six-Month Status Report in Response to March 12,
2012 Commission Order
Modifying Licenses With Regard to Requirements for
Mitigation Strategies for
Beyond-Design-Basis External Events (Order Number EA-
2-049)
08/28/2013
Miscellaneous
Second Six-Month Status Report in Response to March 12,
2012 Commission Order
Modifying Licenses With Regard to Requirements for
Mitigation Strategies for
2/24/2014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Beyond-Design-Basis External Events (Order Number EA-
2-049)
- H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2
SAFETY
EVALUATION REGARDING IMPLEMENTATION OF
MITIGATING
STRATEGIES AND RELIABLE SPENT FUEL
INSTRUMENTATION RELATED
TO ORDERS EA-12-049 AND EA-12-051 (CAC NOS.
MF0720 AND MF0793)
03/31/2016
RNP-E-2.019
MCC 5,6,9, and 10 Protective Devices
Rev. 14
RNP-F/PSA-0133
Robinson Operator Action Risk Ranking
Rev. 000
RNP2-E-0007
Specification for 125 Volt Battery Charger
Rev. 1
RNPD/85-907
H. B. Robinson Region II Inspection Report
05/02/1985
SD-016
480/120VAC Electrical Systems
Rev. 12
SD-042
Auxiliary Feedwater System
Rev. 11
FUKUSHIMA FLEX 4.2 DIESEL GENERATOR 1A AND 1B
SITE ACCEPTANCE TEST
Rev. 2
Updated Final Safety Analysis Report
Rev. 30
28-800-16
Worthington Co. Instructions for Installation & Operation of
Centrifugal Pumps
Rev. 7
AD-EG-ALL-1011
Engineering Technical Task Rigor: Pre-Job Brief, Risk
Management and Post-Job Critique
Rev. 8
AD-EG-ALL-1202
Preventive Maintenance and Surveillance Testing
Administration
Rev. 11
AD-OP-ALL-0204
Plant Status Control
Rev. 5
AD-PI-ALL-0100
Corrective Action Program
Rev. 27
CSD-EG-DEP-
0106
AC and DC Overcurrent Protection and Coordination
Rev. 0
EDP-001
4160 VAC Buses
Rev 11
EDP-002
480 VAC Buses
Rev 19
EDP-003
MCC Buses
Rev. 97
EDP-006
Lighting Panels
Rev. 92
Procedures
EGR-NGGC-0106
AC and DC Overcurrent Protection and Coordination
Rev. 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EOP E-0
Reactor Trip or Safety Injection
Rev. 11
EPP-28
Loss of Ultimate Heat Sink
Rev. 22
FSG-004
Rev. 1
Auxiliary Feedwater System
Rev. 112
OST-151-1
Safety Injection System Components Test Pump 'A'
Rev. 46
OST-151-2
Safety Injection System Components Test Pump B
Rev. 42
OST-151-3
Safety Injection System Components Test Pump C
Rev. 43
OST-151-4
Comprehensive Flow Test for Safety Injection Pump 'A'
Rev. 30
OST-151-5
Comprehensive Flow Test for Safety Injection Pump 'B'
Rev. 28
OST-151-6
Comprehensive Flow Test for Safety Injection Pump 'C'
Rev. 26
OST-154
Safety Injection System High Head Check Valve Test
Rev. 53
OST-160
Pressure Isolation Check Valve Back Leakage Test
Rev. 53
OST-303-1
Service Water Booster Pump A Test
Rev. 29
OST-453
Fukushima FLEX 4.2 Diesel Generator 1A and 1B
Surveillance Test
Rev. 9
PIC-805
Westinghouse Type CV-7 Undervoltage Relays
Rev. 19
20106087,
20327494,
20145768-01,
20152000-01,
20182465-01,
21243-01,
20370563-01,
20371486-01,
20410693-01,
20416978-03,
01800271,
2051481101,
204851145,
011180093
WO 20072906 01
Clean/Inspect MCC-6(10C) (SDAFW Pump Aux Oil Pump)
01/30/2018
Work Orders
WO 20321807 01
Megger Motor From MCC-6(10C) (SDAFW Pump Aux Oil
Pump)
11/12/20
11