IR 05000266/2020011

Design Basis Assurance Inspection (Teams) Inspection Report 05000266/2020011 and 05000301/2020011

ML20211L794
Person / Time
Site:	Point Beach
Issue date:	07/29/2020
From:	Karla Stoedter NRC/RGN-III/DRS/EB2
To:	Strope M Point Beach
References
IR 2020011
Download: ML20211L794 (12)

Text

July 29, 2020

SUBJECT:

POINT BEACH NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000266/2020011 AND 05000301/2020011

Dear Mr. Strope:

On July 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear 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/

Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000266 and 05000301 License Nos. DPR-24 and DPR-27

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000266 and 05000301 License Numbers: DPR-24 and DPR-27 Report Numbers: 05000266/2020011 and 05000301/2020011 Enterprise Identifier: I-2020-011-0027 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant Location: Two Rivers, WI Inspection Dates: June 22, 2020 to July 10, 2020 Inspectors: C. Baron, Contractor J. Corujo-Sandin, Reactor Inspector A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector B. Jose, Senior Reactor Inspector E. Sanchez Santiago, Senior Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 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 Point Beach Nuclear 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), regional inspectors were directed to begin telework. Regional based inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. For the inspection documented below portions of the IP were completed remotely as well as on site and all the objections and requirements for completion of the IP were met.

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)

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(1) Station Service Transformer 2X-14

• Material condition and configuration control

• Surveillance and testing procedures

• Electrical rating and loading design

• Grounding requirements

• Maintenance history and effectiveness

(2) Emergency Diesel Generators (EDGs) G-03 and G-04

• Electrical Steady State and Transient Load Flow, Short Circuit and Voltage Drop Calculations

• Surveillance and Testing

• Updated Final Safety Analysis Report

• Technical Specifications

• Overall system health

• Fuel oil capacity

• Emergency refueling capability

• Mission time of EDGs

• Air start system capability

• Technical Specification amendment associated with fuel oil capacity

• EDG testing and acceptance criteria

• Normal and emergency procedures associated with EDG operation

(3) Containment Sump Suction Valves 2SI-HOV-850A and 2SI-MOV-851A

• Minimum Voltage available at the Motor Terminals During Worst Case Degraded Voltage Condition

• Thermal Overload Set-points

• Breaker Coordination

• Vendor Manual

• Updated Final Safety Analysis Report

• Technical Specifications

• Overall system health

• Inservice & Generic Letter 89-10 testing and acceptance criteria

• Weak link analysis

• Pressure lock/thermal binding evaluation

• Generic Letter 89-10 motor operated valve thrust analysis

• Design basis flows and delta pressures

• Normal and emergency operating procedures associated with motor operated valves

• Design and testing of valve interlocks

• Accessibility and timing of local valve operation

(4) 125 VDC Buses D03 and D04

• Short Circuit Calculation

• Voltage Drop Calculation

• Maintenance Work Orders and Surveillance Procedures

• Battery Charger Sizing and Setpoints

• Cable Protection Calculations

• Protective Devices Coordination

(5) Residual Heat Removal Pumps 2P-10A and 2P-10B

• Flow and Head Requirements

• Surveillance and Testing Procedures

• Operating Procedures

• Updated Final Safety Analysis Report

• Technical Specifications

• American Society of Mechanical Engineers (ASME) Code Requirements

• Vendor Manual

• Permanent Modifications

• Corrective Action History

• Past Operability Evaluations

• Calculations for Emergency Core Cooling System Pump Protection

Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)

(1) Residual Heat Removal Return Line Isolation Valve 2RH-MOV-720

• Maintenance Work Orders

• Surveillance and Test Work Orders

• Vendor Manual

• ASME Code Requirements

• Updated Final Safety Analysis Report

• Technical Specifications and Bases

• Design Basis Flows and Delta Pressures

• Boric Acid Evaluations

• Corrective Action History

• Motor Stem Thrust Calculation

Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)

(1) EC-289692, Update Battery Room VAC System Temperature Setpoints

(2) EC-2622464, Equivalency Needed to Replace the 1D-205 and 2D-205 Batteries, Inter Rack, Inter Tier, and Crossover Cables with 4 3/0 Multi Strand Cables Per Set

(3) EC-291259, Y16 Breaker Replacement

(4) EC-273236, Reset Safety Injection Accumulator Pressure and Level Alarm Setpoints to Allow for Wider Operating Bands within Technical Specifications

(5) EC-259510, Emergency Diesel Generator Air Start Motor Replacement (G-01, G-02, G-03, G-04)

(6) EC-284675, Generic Safety Issue 191 Unit 1 Modifications

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

(1) NRC Information Notice 17-06, Battery and Battery Charger Short-circuit Current Contributions to a Fault on the Direct Current Distribution System

(2) Regulatory Issue Summary 00-24, Offsite Power Voltage and Grid Reliability due to Industry Deregulation

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On July 10, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. M. Strope, Site Director and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21M Calculations 2000-0036 pH of Post LOCA Sump and Containment Spray 3

2001-0001 Hydraulic Pressures Associated with SI-850 Valves 1

2001-0033 Electrical Input Calculation: 345kV to 480V Switchgear 0

Circuits

2003-046 Battery Charger Sizing and Current Limit Setpoint 9

2004-0002 AC Electrical System Analysis 5

2005-0007 PBNP Electrical System Transient Analysis 3

2010-0024 Point Beach EOP Time Setpoints 4

2014-04473 Internal Flooding Assessment of Emergency Diesel 2

Generator Building

2016-005 125 Vdc Cable Protection 1

CN-CRA-08-47 Steam Generator Tube Rupture (SGTR) Margin to Overfill 1

Analysis for Point Beach Units 1 and 2 (WEP/WIS) to

Support the Extended Power Uprate

N-92-005 125 Vdc Protection Devices Calculation 3

N-92-086 ECCS Pump Protection 5

N-93-076 1(2) SI-851A, 851B 1(2) SI-856A, 856B (Group 16) MOV 1

Differential Pressure Calculation

N-93-079 1(2)SI-896A/B and 1(2)SI-870A/B (Group 19) MOV 3

Differential Pressure Calculation

N-94-019 Determination of Conditions for MOV Pressure Locking and 0

Thermal Binding

N-94-142 Emergency Diesel Generator, Gas Turbine and Fire Pump 8

Diesel Engine Fuel Oil Systems

P-89-031 Voltage Drop Across MOV Power Lines 13

P-90-017 MOV Undervoltage Stem Thrust and Torque 23

P-94-004 MOV Overload Heater Evaluation 14

P-94-005 Motor Stem Thrust Calculation for Gate and Globe Valves 11

P-94-005 Motor Stem Thrust Calculation for Gate and Globe Valves Minor B

Corrective Action 1345764 NRC Information Notice 2008-02: Findings Identified During 06/20/2008

Documents CDBIs

Inspection Type Designation Description or Title Revision or

Procedure Date

1391503 NRC Information Notice 2010-0011: LHSI Operability in 06/23/2010

Mode 4

1788486 Low Margin on Overcurrent Set Points 07/27/2012

1788537 Impact to Plant Procedures due to New Revision to 07/27/2012

Calculation

1952942 2-87-2/A06 as Found Target Test Unsatisfactory 05/14/2014

2196130 2P-10B, RHR Pump Vibration Trend 04/04/2017

209496 Change in 2P-10B RHR Pump Vibrations 06/18/2017

27317 IN 2017-07 Battery Charger Fault Current Test 04/27/2018

239980 Increasing Vibration Trend 2P-10B RHR Pump 12/11/2017

244199 2P-10B Pump Suction Pipe Resonance 01/11/2018

252938 2P-10B RHR Vibrations Post Coupling Replacement 03/07/2018

2340495 0DA-3056A Relief Valve Documentation 01/08/2020

CAP050179 Industry OE - Callaway -Inoperability of Both Offsite Power 09/15/2003

Sources

Corrective Action 02361293 2020 DBAI: SI-850 Electrical Analysis 06/29/2020

Documents 2360746 2020 DBAI Need Review of EOP 1.3 for Both Units 06/23/2020

Resulting from 2360749 NRC Identified Typo in EOP 1.3 Unit 2 06/23/2020

Inspection 2361017 Substandard MOV Design Basis Calculation 06/25/2020

2361018 DBAI 2020 -EC284675 Valve Quality Level Testing 06/20/2020

Requirement

2361545 Potential for Accelerated RWST Draw-Down 07/01/2020

2362062 Review EOP-1.4 for Enhancement 07/07/2020

2362318 No Explicit Design Doc for Local SI-857 Operation 07/09/2020

Drawings 110E017 Sh 1 P&ID Safety Injection System 60

110E017 Sh 2 P&ID - Safety Injection System 66

110E029 Sh 1 P&ID Auxiliary Coolant System Point Beach Nuclear Plant 57

Unit 2

110E035 Sh 1 P&ID Safety Injection System 56

110E035 Sh 2 P&ID Safety Injection System 60

541F091 Sh 1 P&ID Reactor Coolant System 58

541F445 Sh 1 P&ID Reactor Coolant System 52

541F445 Sh 2 P&ID Reactor Coolant System 34

Inspection Type Designation Description or Title Revision or

Procedure Date

8551-1 Containment Isolation Valve 4

E-222201 Diesel Generator Building Piping Arrangement 6

M-219 Sh 1 P&ID Fuel Oil System 51

M-219 Sh 2 P&ID Fuel Oil System Diesel Generator Building 16

M-219 Sh 3 P&ID Fuel Oil System Diesel Generator Building 17

Engineering 257171 Stator Rewind Using Equivalent Materials and Processes by 1

Changes Westinghouse

259510 Emergency Diesel Generator Air Start Motor Replacement 0

(G-01, G-02, G-03, G-04)

2464 Equivalency Needed to Replace the ID-205 Batteries, Inter 0

Rack, Inter Tier and Crossover Cables

273236 Reset SI Accumulator Pressure and Level Alarm Setpoints 0

to Allow for Wider Operating Bands Within Tech Specs

284675 GSI-191 Risk-Informed Unit 1 Modifications; Extend Drain 5

Pan Under Stairway 22, Modify Cavity Drain Line, Convert

Debris Interceptors to Flow Diverters

289692 Update Setpoint Document STPT 17.1 Heating and 0

Ventilation System Section 1.13 Battery Room VAC

System (VNBI) Actuation Setpoints and Remove Reset

Values

290751 Temporary Change in Support of Maintenance Evaluation 0

291259 Y-16 Breaker Replacement 0

291434 RHR Pump Suction Piping Grout Penetration Repair 1

Engineering 2017-0012 Basis for Recovering/Realigning RHR Following a Mode 4 0

Evaluations LOCA

278719 Basis for Mission Time of Emergency Diesel Generators 0

EQCK-PRONTO- Environmental Qualification (EQ) Binder for Marathon 1

001 Electric Hydraulic Pump Unit Motor

Miscellaneous BG EOP-1.4 Background Document - Transfer to Containment Sump 20

Recirculation High Head Safety Injection

CE01175866-01 NRC Information Notice 2010-0011 07/09/2010

EQMR-PRONTO- EQ Maintenance Requirements for Hydraulic Pump Unit 0

MTR Motor

IST Program PBNP Inservice Testing Program 5th Interval 8

Inspection Type Designation Description or Title Revision or

Procedure Date

Document

NP 8.4.17 PBNP Flooding Program 32

VTM 00558 Vendor Manual for Containment Sump Isolation Valves 8

VTM-00176 Basler Electric (Relay)/Westinghouse X-03 18

Operability 000122 Complications with D-09 Charger 2

Evaluations

Procedures AOP-22 EDG Load Management 19

CL 11A G-03 G-03 Diesel Generator Checklist 9

EOP-1 Loss of Reactor or Secondary Coolant 46

EOP-1.3 Transfer to Containment Sump Recirculation - Low Head 57

Injection

EOP-1.4 Transfer to Containment Sump Recirculation - High Head 30

Injection

OI 92A Fuel Oil Ordering, Receipt Sampling, and Offloading 29

OM 4.3.8 Control of Time Critical and Time Sensitive Operator Actions 16

OP 3C Hot Standby to Cold Shutdown Unit 2 17

RMP 9314 1(2)SI-850A/B Maintenance, Static Test, and Adjustment 18

Work Orders 315772 Bus Work Inspection 03/14/2011

368148 2-50G/A52-89 Calibration Ground 03/14/2011

380449 2-50D/A52-89 Calibration 2A-06 Instantaneous Current 03/20/2011

Relay

40412681 125 Vdc Distribution Panel 03/03/2016

40430297-01 TS-31, Unit 2 High/Low Head Safety Injection Check 04/09/2017

Leakage Test

40431018-01 IT-04D, RHR Valve Testing for Unit Operation or Shutdown 04/10/2017

40495025-01 G-03 EDG Operability Test 07/17/2017

40519260-01 G-04 EDG Operability Test 12/18/2017

40526137-01 TS-31, Unit 2 High/Low Head Safety Injection Check 10/21/2018

Leakage Test

40544138-01 IT-04D, RHR Valve Testing for Unit Operation or Shutdown 10/23/2018

40577277-04 Operation of 2P-10B RHR Pump at Test Flow While 03/07/2018

Adjusting Weights Applied to Suction Piping

40635246-01 TS-31, Unit 2 High/Low Head Safety Injection Check 04/02/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Leakage Test

40635249-01 IT-04D, RHR Valve Testing for Unit Operation or Shutdown 04/20/2020

40635309-01 IT-04A, Train A RHR Pump and Valve Tests in Decay Heat 03/11/2020

Removal Mode

40635609-01 IT-536, U2 Cont Sump B Suction Line Leak Test (RFSD) 03/23/2020

40642212-01 TS-84, G-04 Emergency Diesel Generator Operability Test 12/17/2019

40651478-01 IT 04 Low Head Safety Injection Pumps and Valves Train A 12/10/2019

Unit 2

40651481-01 IT 45 Train A Safety Injection Valves (Quarterly) Unit 2 12/17/2019

40664852-01 IT 04 Low Head Safety Injection Pumps and Valves Train A 03/11/2020

Unit 2

40664855-01 IT 45 Train A Safety Injection Valves Train A Unit 2 03/13/2020

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