IR 05000266/2020011
| 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:
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
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)
=
- (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
- 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
- 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
- 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
- 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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculations
2000-0036
pH of Post LOCA Sump and Containment Spray
2001-0001
Hydraulic Pressures Associated with SI-850 Valves
2001-0033
Electrical Input Calculation: 345kV to 480V Switchgear
Circuits
2003-046
Battery Charger Sizing and Current Limit Setpoint
2004-0002
AC Electrical System Analysis
2005-0007
PBNP Electrical System Transient Analysis
2010-0024
Point Beach EOP Time Setpoints
2014-04473
Internal Flooding Assessment of Emergency Diesel
Generator Building
2016-005
25 Vdc Cable Protection
CN-CRA-08-47
Steam Generator Tube Rupture (SGTR) Margin to Overfill
Analysis for Point Beach Units 1 and 2 (WEP/WIS) to
Support the Extended Power Uprate
N-92-005
25 Vdc Protection Devices Calculation
N-92-086
ECCS Pump Protection
N-93-076
1(2) SI-851A, 851B 1(2) SI-856A, 856B (Group 16) MOV
Differential Pressure Calculation
N-93-079
1(2)SI-896A/B and 1(2)SI-870A/B (Group 19) MOV
Differential Pressure Calculation
N-94-019
Determination of Conditions for MOV Pressure Locking and
N-94-142
Emergency Diesel Generator, Gas Turbine and Fire Pump
Diesel Engine Fuel Oil Systems
P-89-031
Voltage Drop Across MOV Power Lines
P-90-017
MOV Undervoltage Stem Thrust and Torque
P-94-004
MOV Overload Heater Evaluation
P-94-005
Motor Stem Thrust Calculation for Gate and Globe Valves
P-94-005
Motor Stem Thrust Calculation for Gate and Globe Valves
Minor B
Corrective Action
Documents
1345764
NRC Information Notice 2008-02: Findings Identified During
06/20/2008
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1391503
NRC Information Notice 2010-0011: LHSI Operability in
Mode 4
06/23/2010
1788486
Low Margin on Overcurrent Set Points
07/27/2012
1788537
Impact to Plant Procedures due to New Revision to
Calculation
07/27/2012
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
2/11/2017
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
Sources
09/15/2003
Corrective Action
Documents
Resulting from
Inspection
2361293
20 DBAI: SI-850 Electrical Analysis
06/29/2020
2360746
20 DBAI Need Review of EOP 1.3 for Both Units
06/23/2020
2360749
NRC Identified Typo in EOP 1.3 Unit 2
06/23/2020
2361017
Substandard MOV Design Basis Calculation
06/25/2020
2361018
DBAI 2020 -EC284675 Valve Quality Level Testing
Requirement
06/20/2020
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
110E017 Sh 2
P&ID - Safety Injection System
110E029 Sh 1
P&ID Auxiliary Coolant System Point Beach Nuclear Plant
Unit 2
110E035 Sh 1
P&ID Safety Injection System
110E035 Sh 2
P&ID Safety Injection System
541F091 Sh 1
541F445 Sh 1
541F445 Sh 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
8551-1
Containment Isolation Valve
E-222201
Diesel Generator Building Piping Arrangement
M-219 Sh 1
P&ID Fuel Oil System
M-219 Sh 2
P&ID Fuel Oil System Diesel Generator Building
M-219 Sh 3
P&ID Fuel Oil System Diesel Generator Building
Engineering
Changes
257171
Stator Rewind Using Equivalent Materials and Processes by
259510
Emergency Diesel Generator Air Start Motor Replacement
(G-01, G-02, G-03, G-04)
2464
Equivalency Needed to Replace the ID-205 Batteries, Inter
Rack, Inter Tier and Crossover Cables
273236
Reset SI Accumulator Pressure and Level Alarm Setpoints
to Allow for Wider Operating Bands Within Tech Specs
284675
GSI-191 Risk-Informed Unit 1 Modifications; Extend Drain
Pan Under Stairway 22, Modify Cavity Drain Line, Convert
Debris Interceptors to Flow Diverters
289692
Update Setpoint Document STPT 17.1 Heating and
Ventilation System Section 1.13 Battery Room VAC
System (VNBI) Actuation Setpoints and Remove Reset
Values
290751
Temporary Change in Support of Maintenance Evaluation
291259
Y-16 Breaker Replacement
291434
RHR Pump Suction Piping Grout Penetration Repair
Engineering
Evaluations
2017-0012
Basis for Recovering/Realigning RHR Following a Mode 4
278719
Basis for Mission Time of Emergency Diesel Generators
EQCK-PRONTO-
001
Environmental Qualification (EQ) Binder for Marathon
Electric Hydraulic Pump Unit Motor
Miscellaneous
BG EOP-1.4
Background Document - Transfer to Containment Sump
Recirculation High Head Safety Injection
CE01175866-01
NRC Information Notice 2010-0011
07/09/2010
EQMR-PRONTO-
EQ Maintenance Requirements for Hydraulic Pump Unit
Motor
IST Program
PBNP Inservice Testing Program 5th Interval
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Document
NP 8.4.17
PBNP Flooding Program
VTM 00558
Vendor Manual for Containment Sump Isolation Valves
VTM-00176
Basler Electric (Relay)/Westinghouse X-03
Operability
Evaluations
000122
Complications with D-09 Charger
Procedures
EDG Load Management
CL 11A G-03
G-03 Diesel Generator Checklist
Loss of Reactor or Secondary Coolant
Transfer to Containment Sump Recirculation - Low Head
Injection
Transfer to Containment Sump Recirculation - High Head
Injection
OI 92A
Fuel Oil Ordering, Receipt Sampling, and Offloading
OM 4.3.8
Control of Time Critical and Time Sensitive Operator Actions
Hot Standby to Cold Shutdown Unit 2
RMP 9314
1(2)SI-850A/B Maintenance, Static Test, and Adjustment
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
Relay
03/20/2011
40412681
25 Vdc Distribution Panel
03/03/2016
40430297-01
TS-31, Unit 2 High/Low Head Safety Injection Check
Leakage Test
04/09/2017
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
2/18/2017
40526137-01
TS-31, Unit 2 High/Low Head Safety Injection Check
Leakage Test
10/21/2018
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
Adjusting Weights Applied to Suction Piping
03/07/2018
40635246-01
TS-31, Unit 2 High/Low Head Safety Injection Check
04/02/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Removal Mode
03/11/2020
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
2/17/2019
40651478-01
IT 04 Low Head Safety Injection Pumps and Valves Train A
Unit 2
2/10/2019
40651481-01
IT 45 Train A Safety Injection Valves (Quarterly) Unit 2
2/17/2019
40664852-01
IT 04 Low Head Safety Injection Pumps and Valves Train A
Unit 2
03/11/2020
40664855-01
IT 45 Train A Safety Injection Valves Train A Unit 2
03/13/2020