IR 05000261/2019010

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Design Basis Assurance Inspection Report 05000261/2019010
ML19158A358
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 06/06/2019
From: Jonathan Montgomery
NRC/RGN-II/DRS/EB1
To: Kapopoulos E
Duke Energy Progress
References
IR 2019010
Download: ML19158A358 (13)


Text

June 6, 2019

SUBJECT:

H.B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 - DESIGN BASIS ASSURANCE INSPECTION REPORT 05000261/2019010

Dear Mr. Kapopoulos,

Jr.:

On May 16, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Robinson Unit 2 and discussed the results of this inspection with Mr. John Krakuszeski, plant manager, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Jonathan M. Montgomery, Chief Engineering Branch 1 Division of Reactor Safety

Docket No.: 05000261 License No.: DPR-23

Enclosure:

Inspection Report 05000261/2019010

Inspection Report

Docket Number(s):

50-261

License Number(s):

DPR-23

Report Number(s):

05000261/2019010

Enterprise Identifier:

I-2019-010-0027

Licensee:

Duke Energy Progress, LLC

Facility:

H.B. Robinson Steam Electric Plant, Unit 2

Location:

Hartsville, SC 29550

Inspection Dates:

April 29, 2019 to May 16, 2019

Inspectors:

P. Braxton, Reactor Inspector

C. Franklin, Reactor Inspector

R. Patterson, Reactor Inspector

M. Riley, Reactor Inspector

M. Yeminy, Mechanical Contractor

S. Kobylarz, Electrical Contractor

Approved By:

Jonathan M. Montgomery, Chief

Engineering Branch 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 (Team) at H.B. Robinson Steam Electric Plant, Unit 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 were identified.

INSPECTION SCOPE

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 - Large Early Release Frequency (LERFs) (IP Section 02.02)===

RHR-750/751, Residual Heat Removal System Isolation Valves

  • UFSAR/TS/TRM and other design and licensing basis requirements
  • Design and licensing basis document accuracy
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Applicable operating procedures
  • Maintenance effectiveness
  • Capability of design
  • Corrective maintenance
  • Corrective action history
  • Testing adequacy and trending results
  • Preventive maintenance schedule and implementation
  • Translation of vendor specifications
  • Calculations for valve set-up
  • System health reports
  • Surveillance and in-service testing procedure, acceptance criteria, and results
  • Operator actions Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)
(1) CCW-HTX-A, Component Cooling Water Heat Exchanger A
  • Overall capability of heat removal capacity considering the most limiting conditions
  • CCW heat exchanger design (tube length, number of tubes, tube material, wall thickness, number of passes)
  • CCW pump flow rate to each heat exchanger and number of pumps operating
  • CCW maximum temperature leaving the heat exchanger
  • Heat exchanger design fouling factor
  • Number of tubes plugged
  • Verification of turbulent flow
  • Method of confirming heat removal capacity (performance testing or inspect-and-clean)
  • Frequency of cleaning the CCW heat exchangers
  • CCW operating procedures affecting the operation of the heat exchangers
  • Impact of leaking by CCW pump discharge check valve on the CCW flow rate to the heat exchanger
(2) BAT-CHRGR-A-1, Station Battery Charger A-1
  • Corrective action and preventative maintenance history
  • Translation of vendor specifications
  • Material condition and configuration (i.e. visual inspection and walkdown)
  • Voltage profile and short circuit calculations
  • Procedures that provide instructions to recover from loss of power
  • Battery and cable sizing

(3)480V-E2, 480V Emergency Bus E2

  • Material condition and configuration (e.g., visual inspection during a walkdown)
  • Consistency between station documentation (e.g. procedures) and vendor specifications
  • Maintenance effectiveness
  • Corrective action history and corrective maintenance records
  • Consistency between load flow and short circuit current calculations and breaker coordination settings
(4) REFUEL-WTR-STR-TNK, Refueling Water Storage Tank
  • Material condition and configuration (e.g. visual inspection during a walkdown)
  • Operating procedures
  • Maintenance effectiveness
  • Component health reports, corrective maintenance records, and corrective action history
  • Operator actions
  • Surveillance and calibration testing and recent test results
  • Modifications performed
  • Calculation for system flow rates, vortex limits, and NPSH for each pump
  • Calculation for tank size, including high and low water levels
  • Requirements and analysis for tank protection from natural phenomena
  • Suction flow rates, including combined pump suction capabilities and transfer of flow rate to another source when tank level is low
  • Tank level and flow instrumentation, and control room indications.

Modification Review - Permanent Mods (IP Section 02.03) (5 Samples)

(1) EC 402230, Replace HVE-17 and HVE-18 Emergency Diesel Generator Room Exhaust Dampers
(2) EC 266720, Replace Transformer SST-2F
(3) EC 277392, Modify SI-869, SI-870A/B to Conform to G.L 96-05
(4) EC 412755, Remove CC-747A/B and CC-774 from In-service Testing Program
(5) EC 284187, RNP Transmission Upgrade Project

Review of Operating Experience Issues (IP Section 02.06) (2 Samples)

(1) NRC Information Notice 2012-14, Motor-Operated Valve Inoperable due to Stem-Disc Separation
(2) NRC Information Notice 2013-18, Refueling Water Storage Tank Degradation

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On May 16, 2019, the inspector presented the design basis assurance inspection results to Mr. John Krakuszeski, plant manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

RNP-C/STRU-

1119

Analysis & Design Verification of RWST & Anchorages

Rev. 2

RNP-E-2.009

Overcurrent Protection Emergency Bus E1 & E2

Emergency Supply

Rev. 3

RNP-E-2.019

MCC 5,6,9,10, Protective Devices

Rev. 13

RNP-E-5.018

Ampacity Evaluation of Safety Related 125V DC and 120

VAC Power Cables

Rev. 10

RNP-E-5.031

Cable Sizing for Battery Charger A-1 for H.B. Robinson

Steam Generating Plant Unit 2

Rev. 0

RNP-E-6.004

DC Short Circuit Study

Rev. 8

RNP-E-6.005

Overcurrent Protection and Coordination of the 125V DC

Distribution System (TRAINS A & B)

Rev. 3

RNP-E-6.022

DC Voltage Profile

Rev. 5

RNP-E-6.024

Battery Charger Sizing

Rev. 4

RNP-E-7.002

Emergency Equipment Load Factor Study

Rev. 17

RNP-E-8.002

AC Auxiliary Electrical Distribution System Voltage/Load

Flow/Fault Current Study

Rev. 10

RNP-I/INST-1023

RWST Uncertainty and Scaling Calculation

Rev. 6

RNP-I/INST-1084

AOP Tank Level Setpoints

Rev. 1

RNP-I/INST-1111

RWST Level EOP Setpoint Parameters

Rev. 1

RNP-M/MECH-

202

RWST Percent Level vs. Inventory - RNP Curve Book 8.11

Rev. 3

RNP-M/MECH-

1411

Set-up Calculation for MOV RHR-750 Set-up

Rev. 8

RNP-M/MECH-

23

Set-up Calculation for MOV RHR-751

Rev. 9

RNP-M/MECH-

24

Set-Up Calculation for MOV SI-870A

Rev. 12

RNP-M/MECH-

29

Set-Up Calculation for MOV SI-870B

Rev. 12

71111.21M Calculations

RNP-M/MECH-

28

Set-up Calculation for SI-869

Rev. 11

RNP-M/MECH-

1556

Safety Injection/Residual Heat Removal System Hydraulic

Model

Rev. 3

RNP-M/MECH-

1586

Evaluation of Potential for Inadvertent MOV Opening Due

to System Pressurization

Rev. 2

RNP-M/MECH-

1598

RWST and Line 16-SI-151R Temperature Calculation

Rev. 0

RNP-M/MECH-

1637

CS/SI/RHR System Hydraulic Model

Rev. 15

RNP-M/MECH-

1642

Safety Injection Pump NPSH Improvement Line Flow

Calculations (Revised Piping Configuration)

Rev. 3

RNP-M/MECH-

1646

Impact of 99°F on CCW System

Rev. 1

RNP-M/MECH-

21

Thermal Relief Valves CC-774, CC-747A, CC-747B Over-

Pressure Protection Analysis

Rev. 0

Corrective Action

Documents

EN 02253092

NCR 00422032

NCR 00470257

NCR 02047575

NCR 02053938

NCR 02055160

NCR 02062735

NCR 02106394

PRR 00422679

PRR 00501886

PRR 02030371

PRR 02155136

PRR 02167812

71111.21M Corrective Action

Documents

PRR 0501974

Corrective Action

Documents

Resulting from

Inspection

NCR 02270875

CC-702A/B/C Reverse Flow Acceptance Criteria

5/1/2019

NCR 02271007

UFSAR Markup for EC 284187 needs Updating

5/2/2019

NCR 02271622

DBD Markup for EC 284187 needs Updating

5/7/2019

NCR 02272100

Procedure OP-603 Minimum Battery Voltage Limits

5/9/2019

NCR 02272568

Scope for PRR 2155136 not Complete

5/14/2019

NCR 02272746

Station Battery D and E Restoration

5/15/2019

NCR 02272808

EC 277392 Information Carryover Discrepancies

5/15/2019

NCR 02272876

Applicability of Note 21 on DWG 5379-01082 Sht. 1

5/15/2019

NCR 02272884

Review UFSAR Section 3.1.2.39

5/15/2019

NCR 02272996

MOV Limit Switch Development SI-869

5/16/2019

PRR 02270974

OP-306 Enhancement

5/2/2019

Drawings

5379-01082

Safety Injection System Flow Diagram

Rev. 49

5379-01484

Residual Heat Removal System Flow Diagram

Rev. 49

5379-01878

Inch Gate Valve Motor Operated

Rev. 1

5379-1082

Safety Injection System Flow Diagram

Rev. 55

5379-1153

Electrical Schematic Diagram for Diesel Generator

Rev. 36

5379-1573

RWST Vent

7/19/1968

5379-1740

Inch Gate Valve Assembly

Rev. 6

5379-1971

Reactor Coolant System Flow Diagram

Rev. 41

5379-376

Component Cooling Water System Flow Diagram

Rev. 44

B-190627

Auxiliary Electrical Distribution System Single Line Diagram

Motor Control Center No. 5, Sheet 2

Rev. 9

B-190628

Wiring Diagram SI-870A

Rev. 18

B-190628

Wiring Diagram SI-870B

Rev. 16

B-190628

Control Wiring Diagram SI-869

Rev. 20

EC410167

HVAC Turbine Building, Auxiliary Building, Reactor

Building, and Radwaste Building

Rev. 43

G-190626

SH00001

Main and 4160 V One Line Diagram

Rev. 22

G-190626

SH00003

25V DC and 120V Vital AC One Line Diagram

Rev. 26

71111.21M Drawings

G-190626, Sht. 1

Main & 4160 Volt One Line Diagram

Rev. 22

G-190626, Sht. 2

480 & 120/208 Volt One Line Diagram

Rev. 39

G-190626, Sht. 3

25V DC & 120V AC One Line Diagram

Rev. 26

G-190626, Sht. 4

Main & 4160 Volt One Line Diagram (Bus 6-9)

Rev. 1

G-190626, Sht. 5

480 & 208/120 Volt One Line Diagram

Rev. 1

N2063-LD-SUB

Robinson Louver Damper Submittal Drawing

Rev. 2

Engineering

Changes

EC 277392

Modify SI-869, SI-870A/B to Conform with JOG

Requirements

Rev. 13

EC 284187

Robinson Nuclear Plant Transmission Upgrade Project

Rev. 30

EC 406225

Update Drawings and EDB per EARS 2063574, 2065390,

and 2065463

Rev. 0

EC 409422

TIC Cable Replacement

Rev. 8

EC 412755

Remove CC-747A, B and CC-774 from IST Program

Rev. 0

Mod M-835

Gag Open RCV-609

Rev. 1

Miscellaneous

2018 RHR System Health Report 3rd and 4th Quarter

2018 RHR System Health Reports 1st and 2nd Quarters

2016-2019 RHR Maintenance Rule Trend Report

AH-CC523

Specification Sheet for CCW Heat Exchanger

3/25/1968

CCW-D01

CCW Potential Over-Pressurization

Rev. 0

CCW-D11

CCWS Relief Valve Capacities

Rev. 0

DBD/R87038/SD03 RHR System Description

Rev. 11

DBD/R87038/SD13 Component Cooling Water System

Rev. 12

DBD/R87038/SD16 SYS DBD-Electrical Power Distribution System

Rev. 11

Information Notice 2012-14

Motor Operated Valve Inoperable due to Stem-Disc

Separation

7/24/2012

Information Notice 2013-18

Refueling Water Storage Tank Degradation

9/13/2013

LDCR 18-0037

UFSAR Change Summary Form

4/16/2019

NLS-91-300

Letter CP&L to NRC Supplemental Response to Generic Letter 89-13

10/18/1991

R18001

Robinson Component Cooling Water (CCW) Thermal

Relief Valves (3) Require Replacement

Rev. 0

RNP2-E-0007

Specification For 125 V Battery Charger

Rev. 1

71111.21M Miscellaneous

SD-016

480/120 VAC Electrical Systems

Rev. 14

WELC 5379-S8

Miscellaneous Tanks Specification

Rev. 2

Procedures

AD-EG-ALL-1720

In-service Testing (IST) Program Implementation

Rev. 4

AD-EG-ALL-1720

IST Program Implementation

Rev. 4

AOP-016

Excessive Primary Plant Leakage

Rev. 27

AOP-020

Loss of Residual Heat Removal

Rev. 50

AOP-033

Shutdown LOCA

Rev. 22

EDP-004

25V DC Buses

Rev. 32

EDP-007

Power Panels

Rev. 157

EOP-ECA-0.0

Loss of All AC Power

Rev. 6

EOP-ES-1.3-BD

Transfer to Cold Leg Recirculation Basis Document

Rev. 1

FRP-H.1

Response to Loss of Secondary Heat Sink

Rev. 30

FSG-014

Electrical Power Restoration

Rev. 1

MST-E-125DC-

BATT-001

Station Battery A Test

Rev. 7

OP-603

Electrical Distribution

Rev. 137

OP-925

Cold weather Operation

Rev. 73

OST 257-1

RHR Loop RWST Isolation Valves Interlocks and Valve

Test

3/13/2017

OST-151-1

SI System Components Test Pump A

Rev. 44

OST-151-3

SI System Components Test Pump C

Rev. 43

OST-166-A1

Battery Charger A-1 Loss of Power Test

Rev. 0

OST-257-1

RHR Loop RWST Isolation Valves Interlocks and Valve

Test

10/12/2018

OST-257-2

RHR Loop RWST Isolation Valves Interlocks and Valve

Test

10/12/2018

OST-257-3

RHR Loop Supply Test

10/12/2018

OST-922

Dedicated Shutdown Equipment Identification Audit

2/18/2019

PM-440

Station Battery Charger A-1 Capacity Test

Rev. 15

SD-038

DC Electrical System

Rev. 7

TMM-004

In-service Testing Program

Rev. 95

TMM-009

In-service Testing Program Administration

Rev. 9

71111.21M Work Orders

01962215

224498

1038942-01

10424446

10635354

2098522-01

279803

13325712-05

13492289-01

13520216-01

20015784-05

20016368

20050646

20105521-01

20143584

20152841

212891

297104

774295-01