IR 05000334/2020011

Design Basis Assurance Inspection (Teams) Inspection Report 05000334/2020011 and 05000412/2020011

ML20300A542
Person / Time
Site:	Beaver Valley
Issue date:	10/26/2020
From:	Mel Gray Engineering Region 1 Branch 1
To:	Penfield R Energy Harbor Nuclear Corp
Gray M
References
IR 2020011
Download: ML20300A542 (11)

Text

October 26, 2020

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000334/2020011 AND 05000412/2020011

Dear Mr. Penfield:

On October 2, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2 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, X /RA/

Signed by: Melvin K. Gray

Mel Gray, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000334 and 05000412

License Numbers:

DPR-66 and NPF-73

Report Numbers:

05000334/2020011 and 05000412/2020011

Licensee:

Energy Harbor Nuclear Corp

Facility:

Beaver Valley Power Station, Units 1 and 2

Location:

Shippingport, PA

Inspection Dates:

September 14, 2020 to October 2, 2020

Inspectors:

P. Finney, Senior Project Engineer

C. Hobbs, Reactor Inspector

S. Kobylarz, Electrical Contractor

J. Kulp, Senior Reactor Inspector

K. Mangan, Senior Reactor Inspector

G. Stock, Senior Resident Inspector

Approved By:

Mel Gray, 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 (teams) inspection at Beaver Valley Power Station, Units 1 and 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 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

===71111.21M - Design Bases Assurance Inspection (Teams)

The team evaluated the following components, permanent modifications, and operating experience during the weeks of September 14 and September 28, 2020.

For the components, the team reviewed the attributes listed in IP 71111.21M, Appendix A, Component Review Attributes, such as those listed below. Specifically, the team evaluated these attributes as per 71111.21M, Appendix B, Component Design Review Considerations and 71111.21M, Appendix C, Component Walkdown Considerations. Specific documents reviewed are listed in the Documents Reviewed section.

Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples)

(1) Time Critical Operator Action - Conduct rapid depressurization during a station blackout or loss of offsite power

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases documents and procedures

• Operator actions

• Surveillance testing and recent test results

• Energy sources, fuel and air (e.g., engine start, operation, and control) attributes inspected

(2) Time Critical Operator Action - Actions to cross-tie 4 kV power from one unit to the other during a station blackout or loss of offsite power

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Emergency operating procedures

• Consistency among design and licensing bases documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Adequacy of electrical power supply for motor and controls

• Equipment protection from fire, flood, and water intrusion or spray

• Heat removal, cooling water and ventilation

• Energy sources, fuel and air (e.g., engine start, operation, and control) attributes inspected (e.g., maximum available fault current)

(3) Beaver Valley 2 to Beaver Valley 1 Station Blackout Cross-Tie Bus 1A Circuit Breaker (4KVS-1A-1A8)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Protection coordination; Load in-rush and full load current

• Range, accuracy, and setpoint of installed instrumentation

• Contactor and fuse ratings; Component adequacy for minimum voltage

(4) Unit 1 EDG Load Sequencers (BV-PNL-DG-SEQ)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Equipment/environmental controls and qualification

• Surveillance testing and recent test results

• Preventative maintenance and calibration tests

• Relay ratings; Component adequacy for minimum voltage (5)1A River Water Pump Discharge Valve to A Header (MOV-1RW-102A2)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases and other documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Adequacy of electrical power supply for motor and controls

• Range, accuracy, and setpoint of installed instrumentation

• Energy sources, fuel and air (e.g., engine start, operation, and control) attributes inspected

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

(1) Intake Structure Cubicle #1 Supply Fan (BV-1VS-F-57A)

• Material condition and installed configuration (e.g., visual inspection/walkdown)

• Normal, abnormal, and emergency operating procedures

• Consistency among design and licensing bases documents and procedures

• System health report, maintenance effectiveness and records, and corrective action history

• Control logic

• Equipment/environmental controls and qualification

• Operator actions

• Design calculations

• Surveillance testing and recent test results

• Adequacy of electrical power supply for motor and controls

• Thermal overload protection settings

• Protection coordination; Load in-rush and full load current

• Range, accuracy, and setpoint of installed instrumentation

• Heat removal cooling water and ventilation attributes inspected

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

(1) ECP 18-0166-00, Replace Residual Heat Release Valve (HCV-1MS-104)

(2) ECP 15-0234-003, EDG Parallel Synchronization & Cable Reroute

(3) ECP 16-0483, Add Power Line Filtering to the Nuclear Instrument System Racks for the Source, Intermediate and Power Range Drawers to Reduce Electrical Noise

(4) ECP 18-0070-002, Modify Wiring to K602A Relay to support the Unit 1 EDG Auto-load (Surveillance Test Risk-Informed Documented Evaluation) STRIDE

(5) ECP 11-0618-002, Unit 2 Service Water System Replacement Motor Operated Butterfly Valve - 2SWS-MOV102C1

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

(1) Information Notice 2007-14: Loss of Offsite Power and Dual Unit Scram at Catawba

(2) Information Notice 2018-07: Pump/Turbine Bearing Oil Sight Glass Problems

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On October 2, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Rod Penfield, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

10080-E-048

Emergency Diesel generator Loading with Station Blackout

Revision 14

11700-ESK-111H

4160V Bus 1A Beaker 1A8 Time - Current Coordination

Curve

Revision 1

8700-DMC-2787

Determination of Maximum Differential Pressure Across the

QA Category 1 Motor Operated Valves in the BVPS-1 River

Water System

Revision 3

8700-DMC-3002

Ventilation Calculation - Intake Structure

Revision 0

8700-E-201

D.C. System Management-BAT-1-1 / BAT-CHG1-1

Revision 4

Corrective Action

Documents

Resulting from

Inspection

20-06332

20-07025

20-07209

20-07218

20-07260

20-07270

20-07528

20-07565

20-07618

20-07621

20-07633

20-11546

20-11549

20-11557

20-11929

20-7465

ATA-2020-11546

ATA-2020-11549

ATA-2020-11557

ATA-2020-11688

Drawings

8700-RE-21CE,

Sheet 1

Elem Diag Diesel Gen 1&2 Auto Load Sequence

Revision 12

Engineering

18-0070-002

Modify Wiring to K602A Relay to support the Unit 1 EDG

Revision 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Changes

Auto-load STRIDE

DCP-1698

Cross-Tie Beaver Valley 1 and Beaver Valley 2 Diesel

Generators

Revision 0

ECP 11-0618-002 Unit 2 Service Water System Replacement Motor Operated

Butterfly Valve - 2SWS-MOV102C1

Revision 7

ECP 15-0234

NFPA 805 Item BV1-2806: Emergency Diesel Generator

Parallel Synchronization and Cable Re-route

Revision 20

ECP 16-0483

Add Power Line Filtering to the NIS Racks for the Source,

Intermediate and Power Range Drawers to Reduce

Electrical Noise on RK-2NUC-INS-1

Revision 0

ECP 18-0070-002 Modify Wiring to K602A Relay to support the Unit 1 EDG

Auto-load STRIDE

Revision 1

ECP 18-0166-000 Replace Residual Heat Release Valve HCV-1MS104

Revision 1

Engineering

Evaluations

Beaver Valley Power Station Station Blackout Shutdown

Capability Summary Unit 2

8/16/1990

EM 109797

Unit 1 and 2 Intake Structure Minimum Air Flows

03/21/1995

Miscellaneous

Amerace Corporation Model EGP Series Power Relays

Class 1E Product Specification, Revision F

NRC Letter: Safety Evaluation Related to Station Blackout

(TAC NOS. 68510 and 68511)

11/23/1990

1DBD-30

Design Basis Document for River Water, Auxiliary River

Water and Raw Water Systems

Revision 19

2DBD-30

Design Basis Document for Service Water System

Revision 19

Procedures

1OM-30.4.M

Standby Reactor Plant River Water Pump Startup

Revision 27

1OM-44.F.4.A

Miscellaneous Ventilation Systems Operation

Revision 11

1OM-53A.1.1-U

Local Operation of SG Atmospheric Steam Dump Valves or

RHR Valve

Revision 3

1OM-53A.1.ECA-

0.0

Loss of All Emergency 4KV AC Power

Revision 3

2OM-53A.1.A-

1.11

Manual Handpump Operation of Hydraulically Actuated

Valves

Revision 5

2OM-53A.1.A-

1.13AE(DF)

Actions to Establish BV-1 Cross-tie to Bus 2AE(DF) During

Station Blackout

Revision 5

2OM-53A.1.ECA-

Loss of All Emergency 4KV AC Power

Revision 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

0.0

2OM-53A.1.ECA-

0.0

Loss of All Emergency 4KV AC Power

Revision 3

BVPS-OPS-0029

Control of Time Critical Actions

Revision 9

Work Orders

200744720