IR 05000261/2021010

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000261/2021010

ML21081A078
Person / Time
Site:	Robinson
Issue date:	03/22/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Kapopoulos E Duke Energy Progress
References
IR 2021010
Download: ML21081A078 (12)

Text

March 22, 2021

SUBJECT:

H. B. ROBINSON STEAM ELECTRIC PLANT - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000261/2021010

Dear Mr. Kapopoulos,

Jr.:

On March 4, 2021, 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,

/RA/

James B. Baptist, Chief Engineering Branch 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:

05000261/2021010

Licensee:

Duke Energy Progress, LLC

Facility:

H. B. Robinson Steam Electric Plant

Location:

Hartsville, SC

Inspection Dates:

March 01, 2021 to March 05, 2021

Inspectors:

G. Ottenberg, Senior 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 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.

Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

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 March 1, 2018 until December 8, 2020.

(1)10 CFR 50.59 Screening-AR02123977, EC 291093, Revision 19, 4KV Breaker Replacement (2)10 CFR 50.59 Screening-AR02025142, EC 296680, Revision 0, MCC-5(1CR), MCC-6(3M) AND (4M) Breaker Replacement (3)10 CFR 50.59 Screening-AR01966006, EC 297202, Revision 11, Install Cut-out Switch in Main Control Room to Isolate Loads in Aux Panel DC to Eliminate SISBO as Fire Event Coping Method (4)10 CFR 50.59 Screening-AR02196053, EC 408590, Revision 0, RC-516, Anti-Rotation Kit (LTAM RNP-15-0012)

(5)10 CFR 50.59 Screening-AR02142938, EC 408709, Revision 0, MCCB Replacement of 125VDC Distribution Panel B Breaker 1 to Support NFPA 805 LAR (6)10 CFR 50.59 Screening-AR02156891, EC 409626, Revision 2, This Modification Will Install a Manual Disconnect in the Motor Power Leads for MOV LCV-115C. This Disconnect Will Allow Operator Locally in the Charging Pump Room (7)10 CFR 50.59 Screening-AR02224446, EC 412755, Revision 0, Remove CC-747A;B AND CC-774 From IST Program (8)10 CFR 50.59 Screening-AR02230817, EC 413542, Revision 0, Remove Containment Purge Valve V12-9 and Temporarily Replace With a Spool Piece (9)10 CFR 50.59 Screening-AR02245177, EC 414306, Revision 0, Hagan Replacement for NUS Setpoint Stations (10)10 CFR 50.59 Screening-AR02288932, EC 416046, Revision 0, Pressurizer PORV Safety Function Documentation Changes (11)10 CFR 50.59 Screening-AR02332953, EC 417696, Revision 0, Replace the K301 and K302 Relays in Battery Charger A Child EC (12)10 CFR 50.59 Screening-AR01995442, EC 294433, Revision 1, Unit 1 Diesel Fuel Oil System Transfer to RNP Unit 2 Control (13)10 CFR 50.59 Evaluation-ARs 02209962 and 02311356, Revisions 0 and 1, Cycle 32 Core Reload (14)10 CFR 50.59 Evaluation-AR02237127, EC 412513, Revision 0, Partial Length Shield Assemblies Removal (15)10 CFR 50.59 Evaluation-AR02195350, EC 409565, Revision 1, Replacement of Motor Control Center (MCC) - 9 Feeder Breaker (16)10 CFR 50.59 Evaluation-AR 2240867, EC 287742, Revision 9, Turbine Control System Upgrade (17)10 CFR 50.59 Evaluation-AR02192768, EC 403230, Revision 3, Adoption of GL 87-11 for Postulated Pipe Rupture Outside of Containment Admin Revision (18)10 CFR 50.59 Evaluation-AR02289112, EC 415049, Revision 1, Replace ESF Timing Relays Train A

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On March 4, 2021, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Ernest J. Kapopoulos, Jr.

and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

E1/E2 Room Loss

of HVAC Model

E1/E2 Room Loss of HVAC Model

Rev. 2

RNP-E-2.012

Overcurrent Protection and Coordination for Feeder Breaker

to MCC 6

Rev. 5

RNP-E-6.005

Overcurrent Protection and Coordination of the 125V DC

Distribution System (Trains A & B)

Rev. 4

RNP-E-9.005

FUSE ANALYSIS FOR EMERGENCY BUSES E1 AND E2

Rev. 3

RNP-E-9.008

Control Circuit Fuse Analysis for 4.16KV Switch Gear

Busses 1, 2, 3 and 4

Rev. 4

RNP-M/HVAC-

1069

E1/E2 Room Loss of HVAC Model

Rev. 2

RNP-M/MECH-

21

THERMAL RELIEF VALVES CC-774, CC-747A, CC-747B

OVER-PRESSURE PROTECTION ANALYSIS

Rev. 0

Corrective Action

Documents

2018-3125

Potentially non-conservative design limit for Biasi CHF

Correlation

2019-170

Inconsistent CHF design limit / application for Biasi CHF

correlation

NCR 02203295,

2310600,

00712316,

2145569

Various

Various

Corrective Action

Documents

Resulting from

Inspection

NCR 02372104

21 NRC 50.59 Inspection: UFSAR Change wording and

5059 con

dated

03/01/2021

NCR 02372708

21 NRC 50.59 Insp: Removal of CCW relief valves from

IST

dated

03/04/2021

NCR 02372743

21 NRC 50.59 Inspection: NRC Observation for EC 415049

dated

03/04/2021

Drawings

5379-00685

SH00001

CHEMICAL AND VOLUME CONTROL SYSTEM

PURIFICATION AND MAKE-UP FLOW DIAGRAM

Rev. 62

5379-00685

SH00002

CHEMICAL AND VOLUME CONTROL SYSTEM

PURIFICATION AND MAKE-UP FLOW DIAGRAM

Rev. 65

5379-00685

CHEMICAL & VOLUME CONTROL SYSTEM

Rev. 1

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SH00004

PURIFICATION & MAKE-UP FLOW DIAGRAM

5379-376

SH00001

COMPONENT COOLING WATER SYSTEM FLOW

DIAGRAM

Rev. 44

5379-376

SH00002

COMPONENT COOLING WATER SYSTEM FLOW

DIAGRAM

Rev. 34

5379-376

SH00003

COMPONENT COOLING WATER SYSTEM FLOW

DIAGRAM

Rev. 30

5379-376

SH00004

COMPONENT COOLING WATER SYSTEM FLOW

DIAGRAM

Rev. 36

5379-684

CHEMICAL & VOLUME CONTROL SYSTEM BORON

RECIRC. DISTILLATE - FLOW DIAGRAM

Rev. 11

5379-685

SH00003

CHEMICAL & VOLUME CONTROL SYSTEM

PURIFICATION & MAKE-UP FLOW DIAGRAM

Rev. 40

5379-686

SH00001

CHEMICAL & VOLUME CONTROL SYS - BORON

RECIRCULATION PROCESS & STORAGE - FLOW DIAG

Rev. 29

5379-686

SH00002

CHEMICAL & VOLUME CONTROL SYS - BORON

RECIRCULATION PROCESS & STORAGE - FLOW DIAG

Rev. 19

B-190628

SH00479

CHEMICAL AND VOLUME CONTROL SYSTEM

Rev. 20

B-190628

SH00523

CV PURGE OR REFUELING FAN, HVE 1A, CONTROL

WIRING DIAGRAM

Rev. 11

B-190628

SH00524

CV PURGE OR REFUELING FAN, HVE-1B, CONTROL

WIRING DIAGRAM

Rev. 10

B-190628

SH00525

CONTAINMENT PURGE SUPPLY AND EXHAUST VALVE

CONTROL V12-6, 7, 8, AND 9

Rev. 22

G-190234

SH00001

STEAM GENERATOR BLOW-DOWN AND WET LAYUP

SYSTEM FLOW DIAGRAM

Rev. 40

G-190234

SH00002

STEAM GENERATOR BLOW-DOWN AND WET LAYUP

SYSTEM FLOW DIAGRAM

Rev. 46

HBR2-11260

SH00004

ZONE MAP FOR ENVIRONMENTAL PARAMETERS

REACTOR AUX BLDG. EL. 242`-6" AND 246`-0"

Rev. 5

HBR2-11260

SH00008

ZONE MAP FOR ENVIRONMENTAL PARAMETERS

Rev. 21

HBR2-12646

Schematic 300A Battery Charger 480VAC 3 Phase 60 HZ

Rev. 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

25VDC

HBR2-12647

Schematic 300AMP Battery Charger 480VAC 3phase 60Hz

25VDC

Rev. 1

Engineering

Changes

EC 287742

TCS Base - System Integration

Rev. 9

EC 291093

4KV Breaker Replacement

Rev. 19

EC 296680

Evaluation for MCC-5 (1CR), MCC-6 (3M) and (4M) Breaker

Replacement

Rev. 0

EC 403230

Adoption Of GL 87-11 For Postulated Pipe Rupture Outside

Of Containment

Rev. 3

EC 409626

This Modification Will Install a Manual Disconnect in the

Motor Power Leads for MOV LCV-115C. This Disconnect

Will Allow Operator Locally in the Charging Pump Room

Rev. 2

EC 412755

REMOVE CC-747A;B AND CC-774 FROM IST PROGRAM

Rev. 0

EC 413542

REMOVE CONTAINMENT PURGE VALVE V12-9 AND

TEMPORILY REPLACE WITH A SPOOL PIECE

Rev. 0

EC 415049

Replace ESF Timing Relays for Train A

Rev. 1

EC 416046

Pressurizer PORV Safety Function Document Changes

Rev. 0

EC 416046

Pressurizer PORV Safety Function Documentation Changes

Rev. 0

EC 417696

Replace the K301 and K302 Relays in Battery Charger A

Rev. 0

Engineering

Evaluations

Zachry

Engineering

Study R18001

ROBINSON COMPONENT COOLING WATER (CCW)

THERMAL RELIEF VALVES (3) REQUIRE REPLACEMENT

Rev. 0

Miscellaneous

5AD 02191770

0000403230 - 002 ADOPTION OF GL 87-11 FOR

POSTULATED PIPE

dated

03/15/2018

5AD 02224444

50.59 EC 412755 R0, REMOVE CC-747A;B AND CC-774

FROM IST

dated

08/14/2018

5AD 02230815

REMOVE CONTAINMENT PURGE VALVE V12-9 AND

TEMPORARILY REPLACE

dated

09/14/2018

5AD 02230920

0000287742 - 001

TCS BASE - SYSTEM INTEGRATION

dated

09/15/2018

5AD 02245175

Hagan Replacement for NUS Setpoint Stations

dated

11/25/2018

5AD 02289109

EC 415049 replaces ten (10) A-Train Engineered

Safeguards

dated

08/28/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

5AD 02289410

EC 416046 Pressurizer PORV Safety Function

Documentation

dated

08/29/2019

2-209-234

MAGNECRAFT TDRPRO-5100 SERIES TIME DELAY

RELAY VENDOR MANUAL

Rev. 0

CC-060-

351027168-1

AZZ Nuclear Certificate of Conformance

Rev. 0

CC-060-

351027168-1

NLI CERTIFICATION OF CONFORMANCE

Rev. 0

DBD

/R87038/SD16

SYS DBD - Electrical Power Distribution System

Rev. 13

LCPR 2020-RNP-

016

NRC Safety Evaluation for DPC-NE-3008 and DPC-NE-3009

(Supporting Reference 1)

dated

10/22/2020

LDCR 18-0031

N/A

dated

03/13/2019

LDCR 20-0007

RNP-F/NFSA-0299, Revision 1

dated

06/03/2020

Letter to J. A.

Jones, CP&L

from

K. Goller,

NRC

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR

REACTOR REGULATION REGARDING THE

CONSEQUENCES OF HIGH ENERGY PIPING FAILURES

OUTSIDE CONTAINMENT

dated

11/21/1975

Letter to J. F.

Mallay, SPC from

F. Akstulewicz,

NRC

ACCEPTANCE FOR REFERENCING OF TOPICAL

REPORT EMF-84-093(P), REVISION 1, "STEAMLINE

BREAK METHODOLOGY FOR PWRS" (TAC NO. MA2438)

dated

2/16/1999

ML031150493

RELAXATION IN ARBITRARY INTERMEDIATE PIPE

RUPTURE REQUIREMENTS (GENERIC LETTER 87-11]

dated

06/19/1987

ML15156A209

RESPONSE TO REQUEST FOR ADDITIONAL

INFORMATION (RAI) REGARDING TECHNICAL

SPECIFICATION CHANGES TO SUPPORT SELF

PERFORMANCE OF CORE RELOAD DESIGN AND

SAFETY ANALYSES

dated

06/05/2018

ML17292A040

TECHNICAL SPECIFICATION CHANGES TO SUPPORT

SELF PERFORMANCE OF CORE RELOAD DESIGN AND

SAFETY ANALYSES

dated

10/19/2017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ML17292A040

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1

AND

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT

NO. 2 - ISSUANCE OF AMENDMENTS REVISING

TECHNICAL SPECIFICATIONS TO SUPPORT SELF-

PERFORMANCE OF CORE RELOAD DESIGN AND

SAFETY ANALYSES (EPID L-2017-LLA-0356)

dated

04/29/2019

ML18310A131

SUPPLEMENT FOR LICENSE AMENDMENT REQUEST

TO SELF-PERFORM CORE RELOAD DESIGN AND

SAFETY ANALYSES

dated

11/06/2018

NUS-A417SA

SET800 Equivalency Evaluation

Rev. 1

NUS-AxxxSA

SET800 Requirements

Rev. 0

QR-351027168-1

QUALIFICATION REPORT FOR TIME DELAY RELAY

MAGNECRAFT PIN: TDRPRO-5102

Rev. 0

RNP-RA/17-0082

License Amendment Request Proposing to Revise Technical Specification 3.4.3, "RCS Pressure and Temperature (P/T)

Limits

dated

2/07/2018

Westinghouse

Bulletin IB-129-

154

Remote/Manual Set Point Station

dated

11/1968

Procedures

AD-DC-ALL-0201

Development and Maintenance of Controlled Procedure

Manual Procedures

Rev. 26

AD-EG-ALL-1122

Failure Modes and Effects Analysis and Single Failure

Analysis

Rev. 2

AD-EG-ALL-1130

ACTIVATION OF ENGINEERING CHANGES

Rev. 4

AD-EG-ALL-1132

PREPARATION AND CONTROL OF DESIGN CHANGE

ENGINEERING CHANGES

Rev. 16

AD-EG-ALL-1134

PREPARATION AND CONTROL OF EVALUATION

ENGINEERING CHANGES

Rev. 5

AD-EG-ALL-1137

ENGINEERING CHANGE PRODUCT SELECTION

Rev. 8

AD-EG-ALL-1157

Engineering of Plant Digital Systems and Components

Rev. 4

AD-EG-ALL-1903

CYBER SECURITY CRITICAL SYSTEMS AND CRITICAL

DIGITAL ASSETS IDENTIFICATION AND ASSESSMENT

Rev. 13

AD-LS-ALL-0005

UFSAR UPDATES

Rev. 8

AD-LS-ALL-0007

APPLICABILITY DETERMINATION PROCESS

Rev. 7

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

AD-LS-ALL-0008

CFR 50.59 REVIEW PROCESS

Rev. 2

DSP-020

Shutdown from the Control Room with a Fire in the

Emergency Switchgear Room

Rev. 1

GP-002

COLD SHUTDOWN TO HOT SUBCRITICAL AT NO LOAD

TAVG

Rev. 145

GP-007

PLANT COOLDOWN FROM MODE 3 TO MODE 5

Rev. 111

OP-306

COMPONENT COOLING WATER SYSTEM

Rev. 78

OP-910

SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM Rev. 46

OP-921

CONTAINMENT AIR HANDLING

Rev. 59

OST-942

CCW TO SAFETY RELATED EQUIPMENT VALVE

POSITION VERIFICATION

Rev. 7

Work Orders

13316126-01,

13316126-02,

13316127-01,

13316127-02,

13316127-04

Various

Various