IR 05000261/2019010

From kanterella
Jump to navigation Jump to search
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)
v • d • e


Text

une 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 Enclosure

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) ===

Main article: IP 71111.21

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
  • Overcurrent protection and coordination
  • 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 Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations RNP-C/STRU- Analysis & Design Verification of RWST & Anchorages Rev. 2

1119

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

Emergency Supply

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 Rev. 10

VAC Power Cables

RNP-E-5.031 Cable Sizing for Battery Charger A-1 for H.B. Robinson Rev. 0

Steam Generating Plant Unit 2

RNP-E-6.004 DC Short Circuit Study Rev. 8

RNP-E-6.005 Overcurrent Protection and Coordination of the 125V DC Rev. 3

Distribution System (TRAINS A & B)

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 Rev. 10

Flow/Fault Current Study

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- RWST Percent Level vs. Inventory - RNP Curve Book 8.11 Rev. 3

202

RNP-M/MECH- Set-up Calculation for MOV RHR-750 Set-up Rev. 8

1411

RNP-M/MECH- Set-up Calculation for MOV RHR-751 Rev. 9

23

RNP-M/MECH- Set-Up Calculation for MOV SI-870A Rev. 12

24

RNP-M/MECH- Set-Up Calculation for MOV SI-870B Rev. 12

29

71111.21M Calculations RNP-M/MECH- Set-up Calculation for SI-869 Rev. 11

28

RNP-M/MECH- Safety Injection/Residual Heat Removal System Hydraulic Rev. 3

1556 Model

RNP-M/MECH- Evaluation of Potential for Inadvertent MOV Opening Due Rev. 2

1586 to System Pressurization

RNP-M/MECH- RWST and Line 16-SI-151R Temperature Calculation Rev. 0

1598

RNP-M/MECH- CS/SI/RHR System Hydraulic Model Rev. 15

1637

RNP-M/MECH- Safety Injection Pump NPSH Improvement Line Flow Rev. 3

1642 Calculations (Revised Piping Configuration)

RNP-M/MECH- Impact of 99°F on CCW System Rev. 1

1646

RNP-M/MECH- Thermal Relief Valves CC-774, CC-747A, CC-747B Over- Rev. 0

21 Pressure Protection Analysis

Corrective Action EN 02253092

Documents 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 PRR 0501974

Documents

Corrective Action NCR 02270875 CC-702A/B/C Reverse Flow Acceptance Criteria 5/1/2019

Documents NCR 02271007 UFSAR Markup for EC 284187 needs Updating 5/2/2019

Resulting from NCR 02271622 DBD Markup for EC 284187 needs Updating 5/7/2019

Inspection 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 3 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 14 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 Rev. 9

Motor Control Center No. 5, Sheet 2

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 Rev. 43

Building, and Radwaste Building

G-190626 Main and 4160 V One Line Diagram Rev. 22

SH00001

G-190626 125V DC and 120V Vital AC One Line Diagram Rev. 26

SH00003

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 125V 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 EC 277392 Modify SI-869, SI-870A/B to Conform with JOG Rev. 13

Changes Requirements

EC 284187 Robinson Nuclear Plant Transmission Upgrade Project Rev. 30

EC 406225 Update Drawings and EDB per EARS 2063574, 2065390, Rev. 0

and 2065463

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 Motor Operated Valve Inoperable due to Stem-Disc 7/24/2012

2012-14 Separation

Information Notice Refueling Water Storage Tank Degradation 9/13/2013

2013-18

LDCR 18-0037 UFSAR Change Summary Form 4/16/2019

NLS-91-300 Letter CP&L to NRC Supplemental Response to Generic 10/18/1991

Letter 89-13

R18001 Robinson Component Cooling Water (CCW) Thermal Rev. 0

Relief Valves (3) Require Replacement

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 125V 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- Station Battery A Test Rev. 7

BATT-001

OP-603 Electrical Distribution Rev. 137

OP-925 Cold weather Operation Rev. 73

OST 257-1 RHR Loop RWST Isolation Valves Interlocks and Valve 3/13/2017

Test

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 10/12/2018

Test

OST-257-2 RHR Loop RWST Isolation Valves Interlocks and Valve 10/12/2018

Test

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

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000261/2019010&oldid=2041963"