IR 05000261/2022010

– Design Basis Assurance Inspection (Teams) Inspection Report 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: DPR-23

Report Number: 05000261/2022010

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

Enclosure

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)

(1) EC 277392, Modify SI-869, Si-870A/B To Conform to GL96-05 And the Jog

(2) EC 0000402563 002, Provide Selective Coordination of 125VDC Power Supplies to Support NFPA 805 LAR

(3) EC 407275 007, Child 3 of EC 284187 4kv bus 3 and 480V E2 Bus Outage

(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 Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations16-025 NFPA 805 RNP Coordination Study Rev.1

212-C-020 A-46 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 Rev. 0

Restoration - HBR Unit 2

HBR2-11260 Zone Map for Environment Parameters Rev. 5

SH00004 Reactor Aux Bldg. EL. 242`-6" and 246`-0"

RNP-C/FLEX-0052 Seismic Fragility Analysis of the CST Rev. 1

RNP-E-2.009 Overcurrent Protection Emergency Bus E1 and E2 Rev. 3

Emergency Supply

RNP-E-2.010 Overcurrent Protection Emergency Bus E1 and E2-Normal Rev. 3

Supply

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 Rev. 4

Distribution System (Trains A and B)

RNP-E-8.002 AC Auxiliary Electrical Distribution System Voltage/Load Rev.10

Flow/Fault Current Study

RNP-I/INST-1015 CST Level Uncertainty Rev. 8

RNP-M/HVAC-A & B EDG Room Steady State Temperature Rev. 1

1064

RNP-M/MECH-Minimum SDAFW Pump Suction Pressure vs. CST Level Rev. 0

1461

RNP-M/MECH-Set Up Calculation for MOV SI-870A Rev. 14

24

RNP-M/MECH-Set Up Calculation for MOV SI-870B Rev. 14

29

RNP-M/MECH-Service Water System Operation with One Pump Rev. 0

1519

RNP-M/MECH-Availability of Lake Robinson to Provide Ultimate Heat Sink Rev. 13

1645 Cooling

RNP-M/MECH-Service Water System Hydraulic Evaluation Rev. 4

Inspection Type Designation Description or Title Revision or

Procedure Date

1653

RNP-M/MECH-AFW ProtoFlow Model Rev. 2

1655

RNP-M/MECH-Deep Well Pump D Thermal Hydraulic Analyses Rev. 4

1769

RNP-M/MECH-Safety Related Pump Minimum Performance Requirements Rev. 12

1802

RNP-M/MECH-EPRI PPM Analysis For SI-869 SI-870A/B Rev. 1

1905

RNP_E-6.020 Load Profile and Battery Sizing Calculation for Battery BRev. 9

Corrective Action AR 02268696 AMETECK Solidstate Controls Inc. (Part 21) - Vendor 04/23/2019

Documents Notification #53993, Part 21 Report - Overheating And

Failure Of Transformers

AR 02391622 Unresolved Items on Battery Chargers 10/26/2021

AR00423985,

2340607,

2342647,

2346091,

2401058,

2410961

Corrective Action CAP 02436847 2022 DBAI: Errors in RNP-E/ELEC-1220 and RNP-E-5.031 08/04/2022

Documents CR 02437413 2022 DBAI: Error in Single Line Depiction for Calculation 08/09/2022

Resulting from RNP-E-6.005, R4

Inspection

Drawings 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

G-190304 HVAC-Turbine, Fuel, Aux., Reactor, & Radwaste BuildingsRev. 66

Inspection Type Designation Description or Title Revision or

Procedure Date

G-190626 125 V DC & Vital AC One Line Diagram Rev. 27

G-190626, Sheet 3 125V DC & 120V AC One Line Diagram Rev. 25

HBR2-11260 Zone Map for Environmental Parameters, Reactor Aux Rev. 5

Bldg EL 242'6" and 246'-0", Sheet 4

Engineering EC 277392 Modify SI-869, SI-870A/B to Conform to GL 96-05 and the Rev. 13

Changes JOG

EC 402563 Provide Selective Coordination of 125VDC Power Supplies Rev. 2

to Support NFPA 805 LAR

EC 417357 Replace EDG Day Tank "B" Level Control Switches Rev. 3

EC 90617 Connect FLEX Diesel to 125 VDC Battery Chargers Rev. 51

ESR # 95-00266 Replace EDG Day Tank "A" Level Control Switches Rev. 1

Mod 680 CST Sealing Bladder 04/08/85

Miscellaneous 727-909-91 Gate and Globe Valve Rev. 11

28-562-71 SMB Valve Controls Rev. 43

28-812-46 Velan Valve Instruction Manual for Manual Valves: Rev. 12

Installation, Operation, and Maintenance

738-523-20 Breakers, 480V, MCC Westinghouse Rev.10

2-209-181 Ametek Solidstate Controls Instruction Technical Manual Rev. 3

300 amp Battery Charger

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 13

DBD/R87038/SD32 SYS DBD - Auxiliary Feedwater System Rev. 12

LP-027 Feedwater System Rev. 09

ML13252A243 First Six-Month Status Report in Response to March 12, 08/28/2013

2012 Commission Order

Modifying Licenses With Regard to Requirements for

Mitigation Strategies for

Beyond-Design-Basis External Events (Order Number EA-

2-049)

ML14063A238 Second Six-Month Status Report in Response to March 12, 02/24/2014

2012 Commission Order

Modifying Licenses With Regard to Requirements for

Mitigation Strategies for

Inspection Type Designation Description or Title Revision or

Procedure Date

Beyond-Design-Basis External Events (Order Number EA-

2-049)

ML16075A377

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 03/31/2016

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)

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

SP-1609 FUKUSHIMA FLEX 4.2 DIESEL GENERATOR 1A AND 1B Rev. 2

SITE ACCEPTANCE TEST

UFSAR Updated Final Safety Analysis Report Rev. 30

Procedures 728-800-16 Worthington Co. Instructions for Installation & Operation of Rev. 7

Centrifugal Pumps

AD-EG-ALL-1011 Engineering Technical Task Rigor: Pre-Job Brief, Risk Rev. 8

Management and Post-Job Critique

AD-EG-ALL-1202 Preventive Maintenance and Surveillance Testing Rev. 11

Administration

AD-OP-ALL-0204 Plant Status Control Rev. 5

AD-PI-ALL-0100 Corrective Action Program Rev. 27

CSD-EG-DEP-AC and DC Overcurrent Protection and Coordination Rev. 0

0106

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

EGR-NGGC-0106 AC and DC Overcurrent Protection and Coordination Rev. 5

Inspection Type Designation Description or Title Revision or

Procedure Date

EOP E-0 Reactor Trip or Safety Injection Rev. 11

EPP-28 Loss of Ultimate Heat Sink Rev. 22

FSG-004 ELAP DC Load Shed/Management Rev. 1

OP-402 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 Rev. 9

Surveillance Test

PIC-805 Westinghouse Type CV-7 Undervoltage Relays Rev. 19

Work Orders 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

WO 20321807 01 Megger Motor From MCC-6(10C) (SDAFW Pump Aux Oil 11/12/20

Pump)

11