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 Enterprise Identifier: I-2021-010-0034 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations E1/E2 Room Loss E1/E2 Room Loss of HVAC Model Rev. 2

of HVAC Model

RNP-E-2.012 Overcurrent Protection and Coordination for Feeder Breaker Rev. 5

to MCC 6

RNP-E-6.005 Overcurrent Protection and Coordination of the 125V DC Rev. 4

Distribution System (Trains A & B)

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 Rev. 4

Busses 1, 2, 3 and 4

RNP-M/HVAC- E1/E2 Room Loss of HVAC Model Rev. 2

1069

RNP-M/MECH- THERMAL RELIEF VALVES CC-774, CC-747A, CC-747B Rev. 0

21 OVER-PRESSURE PROTECTION ANALYSIS

Corrective Action 2018-3125 Potentially non-conservative design limit for Biasi CHF

Documents Correlation

2019-170 Inconsistent CHF design limit / application for Biasi CHF

correlation

NCR 02203295, Various Various

2310600,

00712316,

2145569

Corrective Action NCR 02372104 2021 NRC 50.59 Inspection: UFSAR Change wording and dated

Documents 5059 con 03/01/2021

Resulting from NCR 02372708 2021 NRC 50.59 Insp: Removal of CCW relief valves from dated

Inspection IST 03/04/2021

NCR 02372743 2021 NRC 50.59 Inspection: NRC Observation for EC dated

415049 03/04/2021

Drawings 5379-00685 CHEMICAL AND VOLUME CONTROL SYSTEM Rev. 62

SH00001 PURIFICATION AND MAKE-UP FLOW DIAGRAM

5379-00685 CHEMICAL AND VOLUME CONTROL SYSTEM Rev. 65

SH00002 PURIFICATION AND MAKE-UP FLOW DIAGRAM

5379-00685 CHEMICAL & VOLUME CONTROL SYSTEM Rev. 1

Inspection Type Designation Description or Title Revision or

Procedure Date

SH00004 PURIFICATION & MAKE-UP FLOW DIAGRAM

5379-376 COMPONENT COOLING WATER SYSTEM FLOW Rev. 44

SH00001 DIAGRAM

5379-376 COMPONENT COOLING WATER SYSTEM FLOW Rev. 34

SH00002 DIAGRAM

5379-376 COMPONENT COOLING WATER SYSTEM FLOW Rev. 30

SH00003 DIAGRAM

5379-376 COMPONENT COOLING WATER SYSTEM FLOW Rev. 36

SH00004 DIAGRAM

5379-684 CHEMICAL & VOLUME CONTROL SYSTEM BORON Rev. 11

RECIRC. DISTILLATE - FLOW DIAGRAM

5379-685 CHEMICAL & VOLUME CONTROL SYSTEM Rev. 40

SH00003 PURIFICATION & MAKE-UP FLOW DIAGRAM

5379-686 CHEMICAL & VOLUME CONTROL SYS - BORON Rev. 29

SH00001 RECIRCULATION PROCESS & STORAGE - FLOW DIAG

5379-686 CHEMICAL & VOLUME CONTROL SYS - BORON Rev. 19

SH00002 RECIRCULATION PROCESS & STORAGE - FLOW DIAG

B-190628 CHEMICAL AND VOLUME CONTROL SYSTEM Rev. 20

SH00479

B-190628 CV PURGE OR REFUELING FAN, HVE 1A, CONTROL Rev. 11

SH00523 WIRING DIAGRAM

B-190628 CV PURGE OR REFUELING FAN, HVE-1B, CONTROL Rev. 10

SH00524 WIRING DIAGRAM

B-190628 CONTAINMENT PURGE SUPPLY AND EXHAUST VALVE Rev. 22

SH00525 CONTROL V12-6, 7, 8, AND 9

G-190234 STEAM GENERATOR BLOW-DOWN AND WET LAYUP Rev. 40

SH00001 SYSTEM FLOW DIAGRAM

G-190234 STEAM GENERATOR BLOW-DOWN AND WET LAYUP Rev. 46

SH00002 SYSTEM FLOW DIAGRAM

HBR2-11260 ZONE MAP FOR ENVIRONMENTAL PARAMETERS Rev. 5

SH00004 REACTOR AUX BLDG. EL. 242`-6" AND 246`-0"

HBR2-11260 ZONE MAP FOR ENVIRONMENTAL PARAMETERS Rev. 21

SH00008

HBR2-12646 Schematic 300A Battery Charger 480VAC 3 Phase 60 HZ Rev. 2

Inspection Type Designation Description or Title Revision or

Procedure Date

25VDC

HBR2-12647 Schematic 300AMP Battery Charger 480VAC 3phase 60Hz Rev. 1

25VDC

Engineering EC 287742 TCS Base - System Integration Rev. 9

Changes EC 291093 4KV Breaker Replacement Rev. 19

EC 296680 Evaluation for MCC-5 (1CR), MCC-6 (3M) and (4M) Breaker Rev. 0

Replacement

EC 403230 Adoption Of GL 87-11 For Postulated Pipe Rupture Outside Rev. 3

Of Containment

EC 409626 This Modification Will Install a Manual Disconnect in the Rev. 2

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

Will Allow Operator Locally in the Charging Pump Room

EC 412755 REMOVE CC-747A;B AND CC-774 FROM IST PROGRAM Rev. 0

EC 413542 REMOVE CONTAINMENT PURGE VALVE V12-9 AND Rev. 0

TEMPORILY REPLACE WITH A SPOOL PIECE

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 Zachry ROBINSON COMPONENT COOLING WATER (CCW) Rev. 0

Evaluations Engineering THERMAL RELIEF VALVES (3) REQUIRE REPLACEMENT

Study R18001

Miscellaneous 5AD 02191770 0000403230 - 002 ADOPTION OF GL 87-11 FOR dated

POSTULATED PIPE 03/15/2018

5AD 02224444 50.59 EC 412755 R0, REMOVE CC-747A;B AND CC-774 dated

FROM IST 08/14/2018

5AD 02230815 REMOVE CONTAINMENT PURGE VALVE V12-9 AND dated

TEMPORARILY REPLACE 09/14/2018

5AD 02230920 0000287742 - 001 dated

TCS BASE - SYSTEM INTEGRATION 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 dated

Safeguards 08/28/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

5AD 02289410 EC 416046 Pressurizer PORV Safety Function dated

Documentation 08/29/2019

2-209-234 MAGNECRAFT TDRPRO-5100 SERIES TIME DELAY Rev. 0

RELAY VENDOR MANUAL

CC-060- AZZ Nuclear Certificate of Conformance Rev. 0

351027168-1

CC-060- NLI CERTIFICATION OF CONFORMANCE Rev. 0

351027168-1

DBD SYS DBD - Electrical Power Distribution System Rev. 13

/R87038/SD16

LCPR 2020-RNP- NRC Safety Evaluation for DPC-NE-3008 and DPC-NE-3009 dated

016 (Supporting Reference 1) 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. SAFETY EVALUATION BY THE OFFICE OF NUCLEAR dated

Jones, CP&L REACTOR REGULATION REGARDING THE 11/21/1975

from

K. Goller, CONSEQUENCES OF HIGH ENERGY PIPING FAILURES

NRC OUTSIDE CONTAINMENT

Letter to J. F. ACCEPTANCE FOR REFERENCING OF TOPICAL dated

Mallay, SPC from REPORT EMF-84-093(P), REVISION 1, "STEAMLINE 02/16/1999

F. Akstulewicz, BREAK METHODOLOGY FOR PWRS" (TAC NO. MA2438)

NRC

ML031150493 RELAXATION IN ARBITRARY INTERMEDIATE PIPE dated

RUPTURE REQUIREMENTS (GENERIC LETTER 87- 11] 06/19/1987

ML15156A209 RESPONSE TO REQUEST FOR ADDITIONAL dated

INFORMATION (RAI) REGARDING TECHNICAL 06/05/2018

SPECIFICATION CHANGES TO SUPPORT SELF

PERFORMANCE OF CORE RELOAD DESIGN AND

SAFETY ANALYSES

ML17292A040 TECHNICAL SPECIFICATION CHANGES TO SUPPORT dated

SELF PERFORMANCE OF CORE RELOAD DESIGN AND 10/19/2017

SAFETY ANALYSES

Inspection Type Designation Description or Title Revision or

Procedure Date

ML17292A040 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 dated

AND

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 04/29/2019

NO. 2 - ISSUANCE OF AMENDMENTS REVISING

TECHNICAL SPECIFICATIONS TO SUPPORT SELF-

PERFORMANCE OF CORE RELOAD DESIGN AND

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

ML18310A131 SUPPLEMENT FOR LICENSE AMENDMENT REQUEST dated

TO SELF-PERFORM CORE RELOAD DESIGN AND 11/06/2018

SAFETY ANALYSES

NUS-A417SA SET800 Equivalency Evaluation Rev. 1

NUS-AxxxSA SET800 Requirements Rev. 0

QR-351027168-1 QUALIFICATION REPORT FOR TIME DELAY RELAY Rev. 0

MAGNECRAFT PIN: TDRPRO-5102

RNP-RA/17-0082 License Amendment Request Proposing to Revise Technical dated

Specification 3.4.3, "RCS Pressure and Temperature (P/T) 02/07/2018

Limits

Westinghouse Remote/Manual Set Point Station dated

Bulletin IB-129- 11/1968

154

Procedures AD-DC-ALL-0201 Development and Maintenance of Controlled Procedure Rev. 26

Manual Procedures

AD-EG-ALL-1122 Failure Modes and Effects Analysis and Single Failure Rev. 2

Analysis

AD-EG-ALL-1130 ACTIVATION OF ENGINEERING CHANGES Rev. 4

AD-EG-ALL-1132 PREPARATION AND CONTROL OF DESIGN CHANGE Rev. 16

ENGINEERING CHANGES

AD-EG-ALL-1134 PREPARATION AND CONTROL OF EVALUATION Rev. 5

ENGINEERING CHANGES

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 Rev. 13

DIGITAL ASSETS IDENTIFICATION AND ASSESSMENT

AD-LS-ALL-0005 UFSAR UPDATES Rev. 8

AD-LS-ALL-0007 APPLICABILITY DETERMINATION PROCESS Rev. 7

Inspection Type Designation Description or Title Revision or

Procedure Date

AD-LS-ALL-0008 10 CFR 50.59 REVIEW PROCESS Rev. 2

DSP-020 Shutdown from the Control Room with a Fire in the Rev. 1

Emergency Switchgear Room

GP-002 COLD SHUTDOWN TO HOT SUBCRITICAL AT NO LOAD Rev. 145

TAVG

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 Rev. 7

POSITION VERIFICATION

Work Orders 13316126-01, Various Various

13316126-02,

13316127-01,

13316127-02,

13316127-04

10