IR 05000280/2020010

NRC Design Bases Assurance Inspection Report 05000280/2020010 and 05000281/2020010

ML20310A112
Person / Time
Site:	Surry
Issue date:	11/05/2020
From:	James Baptist NRC/RGN-II
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2020010
Download: ML20310A112 (11)

Text

November 5, 2020

SUBJECT:

SURRY POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000280/2020010 AND 05000281/2020010

Dear Mr. Stoddard:

On October 2, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station and discussed the results of this inspection with Mr. Doug Lawrence, Site Vice President, 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/

James B. Baptist, Chief Engineering Br 1 Div of Reactor Safety

Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000280 and 05000281

License Numbers:

DPR-32 and DPR-37

Report Numbers:

05000280/2020010 and 05000281/2020010

Licensee:

Virginia Electric and Power Company

Facility:

Surry Power Station

Location:

Surry, VA

Inspection Dates:

September 14, 2020 to October 02, 2020

Inspectors:

P. Braxton, Reactor Inspector

W. Deschaine, Senior Resident Inspector

A. Lerch, Reactor Inspector

R. Patterson, Senior Reactor Inspector

B. Pinson, Reactor Inspector

M. Riley, Senior Reactor Inspector

T. Su, Reactor Inspector

M. Yeminy, Contractor

Approved By:

James B. Baptist, Chief

Engineering Br 1

Div 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 Surry Power Station, 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 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) (4 Samples)

(1) Unit 1 Motor Driven Auxiliary Feedwater Pump 1-FW-P-3A

• Calculation for system flow rates, vortex limits, and net positive suction head for each pump

• Calculation for emergency condensate storage tank size, including high and low water levels

• Suction flow rates, including combined pump suction capabilities and transfer of flow rate to another source when tank level is low

• 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

(2) Unit 2 Auxiliary Building Backflow Preventers

• Calculations for expected internal flood heights in turbine and auxiliary buildings

• Updated Final Safety Analysis Report (UFSAR), including applicable design and licensing basis requirements

• Material condition and configuration (e.g. visual inspection during a walkdown)

• Time critical operator actions associated with internal flooding scenario

• Maintenance effectiveness

• Corrective action and corrective maintenance history

• Preventive maintenance history

• Component modification history

(3) Unit 2 4160V 2H Emergency Bus

• Operating Environment

• Compliance with UFSAR, Technical Specifications (TS), and TS Bases

• Conformance with manufacturer instructions for installation, maintenance, and operation

• Material condition and configuration (e.g. visual inspection during a walkdown)

• Verification that system health reports accurately reflect current system conditions

• Design requirements (rating, loading, short circuit analysis, etc.)

• Protective relays and coordination

• Adequacy of corrective action activities

(4) Emergency Diesel Generator #3 Output Breaker 25J3

• Operating Environment

• Compliance with UFSAR, TS and TS Bases

• Conformance with manufacturer instructions for installation, maintenance, and operation

• Material condition and configuration (e.g. visual inspection during a walkdown)

• Identification and follow-up of issues identified in system health reports

• Verification of system design requirements (Rating, loading, etc.)

• Adequacy of corrective action activities

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

(1) Unit 2 Main Steam Safety Valve (MSSV) 2-MS-SV-201A

• UFSAR, TS, and other design and licensing basis requirements

• MSSV capacity and system steam flow (normal and accident)

• MSSV seismic qualification

• Corrective actions

• In-service test requirements and required maintenance

• Susceptibility to tornado missiles

• Component condition and walkdown

• System health reports

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

(1) SU-18-00116, Stem and Disc Arm Replacement for 1-SI-MOV-1863A

(2) SU-19-01068, Replacement of 01-FW-LT-1495-IXMITR

(3) SU-19-00113, 1-RC-P-1A Abeyance Seal Upgrade

(4) SU-17-00104, MOV Hot Short MCC Wiring Modification

(5) SU-19-01001, Replacement of Service Water Transmitter, 01-SW-FT-106A

(6) SU-PTE-000, Fuel Oil Day Tank ASCO SOV Series 8210

Review of Operating Experience Issues (IP Section 02.06) (3 Samples)

(1) NRC Information Notice 09-11, Configuration Control Errors

(2) NRC Information Notice 15-01, Degraded Ability to Mitigate Flooding Events

(3) NRC Information Notice 16-08, Inadequate Work Practices Resulting in Faulted Circuit Breaker Connections

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. Doug Lawrence, 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

ME-0747

MOV Differential Pressure Calculation for the LHSI Supply

Isolation Valves to the Charging Pump

Revision 0

ME-3330

JOG Calculation of Required Thrust Settings for MOV 1-SI-

MOV-1863A

Revision 4

14937.44-C-11

Main Steam Relief Valve Capacity Limits at 110%

Revision 1

DCP-00-20

Miscellaneous NSSS Protection and Control System

Setpoints

09/13/2001

EE-0339

Relay Setting Calculations for the Protection of Safety Bus

2H at Surry Power Station

Revision 0

EE-0879

SPS 4160V and 480 V Short-Circuit Analysis

Revision 0

ME-0277

North Anna 1&2 / Surry 1&2 Secondary-Side Design

Thermal Performance and Heat Balances

Revision 2

ME-0637

PEPSE Heat Balance Model for Surry Power Station Core

Uprate and Turbine Retrofit Projects

Revision 0

SM-796

Surry SGTR Analysis for Core Uprate Condition

Revision 0

SU-CALC-EEP-

EE-0336

Protective Relay Setting

Revision 0

SU-CALC-EEP-

EE-0336

Protective Relay Settings

Revision 0

Corrective Action

Documents

CRs 570285,

1098552,

1109856,

1148513, 360054,

518985

Various Corrective Action Reports

Various

Corrective Action

Documents

Resulting from

Inspection

CR 1155555

JOG Classification Documented in a Superseded

Engineering Technical Evaluation (ETE)

09/16/2020

CR 1155602

Error in Calculation SU-CALC-ICC-EE-0111

09/17/2020

CR 1156028

Calculation Error in PQE

09/22/2020

CR 1156261

PQE Review for 3152N Rosemount Transmitter

09/24/2020

CR 1156667

Non-Safety Classification of Backflow Preventers

09/29/2020

CR 1156851

Periodic Testing of Circuit Breaker 25J3 Undervoltage Relay

10/01/2020

Drawings

11448-FE-1A2

Electrical Power Distribution - One Line Integrated

Revision 44

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Schematic

SU-DWG-000-

11448-FM-068A

AFW System Flow Diagrams

Revision 65

SU-DWG-000-

11448-FM-089A

Safety Injection Flow Diagram

Revision 54

SU-DWG-000-

11448-FM-089B

Safety Injection Flow Diagram

Revision 35

Engineering

Changes81-050

EDG Transfer Bus Mod 2 Second Delay

10/09/81

DCP 00-049

EDG Output Breaker Circuit Modification and Relay Setpoint

Change/Surry/Unit 1 & 2

07/12/01

SU-19-00113

1-RC-P-1A Abeyance Seal Upgrade

08/29/2019

SU-19-01001

Replacement of Service Water Flow Transmitters

Revision 1

SU-19-01068

Replacement of 01-FW-LT-1495-IXMITR

Revision 0

SU-PTE-000

Fuel Oil Day Tank ASCO SOV Series 8210

Version 01

Engineering

Evaluations

CT-EQUAL-000-

PQE-08.27-P01

3154N Pressure Transmitters

Revision 2

D2013003

IEEE Qualification Report of Rosemount 3154N Pressure

Transmitters

Revision B

EE-0116

Allowable Custom Values for North Anna Improved

Technical Specifications (ITS) Tables 3.3.1-1 and 3.3.2-1

and Setting Limits for Surry Technical Specifications (CTS),

Sections 2.3 and 3.7

Revision 17

EE-0432

CSA Calculation for Surry Power Station, Steam Generator

Narrow Range Level, Units 1 & 2

Revision 5

ET-NAF-07-0092

Evaluation of Main Steam Exhaust Piping Vulnerability to

Tornado Generated Missiles at North Anna and Surrv

Revision 0

ETE-CEE-2016-

0006

Performance Specification for Rosemount 3153N and

3154N Series Transmitters

Revision 0

ETE-SU-2015-

0069

Design Basis for Backflow Preventers in Charging Pump

Cubicles, MER 3, MER 4, and MER 5

Revision 0

ETE-SU-2020-

0037

Main Steam Safety Valves and Pressurizer Safety Valves

repaired/refurbished without SCM Vendor Surveillance

Revision 0

PA3035300

Evaluate IN 16-08

08/21/16

SU-EQUAL-000-

3154N Pressure Transmitters EQ Evaluation

Revision 2

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

PQE-08.27-P01

Miscellaneous

Surry EQML

09/17/2020

CT-EQUAL-000-

GQE-08.27-G01

3154N Series Transmitters Rosemount Report

Revision 0

D2013003

IEEE Qualification Report for Rosemount 3154N Pressure

Transmitters

Revision B

ET-CEM-99-0009

Spectral Peaks and Zero Period Accelerations (ZPA) - OBE

and DBE Surry Power Station - Units 1 and 2

Revision 0

ME-0009

Design Specification for Reactor Coolant Pump N-9000 Seal

Assembly

Revision 001

OEE000707

OPEX002248: IN 2009-11 Configuration Control Errors

04/05/2010

PI-AA-100-1007-

Attachmentt 9

NRC Information Notice 2016-08

08/10/16

PIR 1040648

IN 16-08, Inadequate Work Practices Resulting in Faulted

Circuit Breaker Connections

06/30/16

SDBD-SPS-EG

System Design Basis Document for Emergency Diesel

Generator System, Surry Power Station

Revision 24

SDBD-SPS-FW

System Design Basis Document for Feedwater System

Surry Power Station

Revision 18

SU-EQUAL-000-

38-EZD

Surry Environmental Zone Description Units 1 & 2

Revision 29

Procedures

0-AP-13.00

Turbine Building or MER 3 Flooding

Revision 33

0-AP-13.01

Uncontrollable Turbine Building Flooding

Revision 10

0-AP-13.02

Loss of ESGR Cooling

Revision 11

0-DRP-049

Time Critical Operator Actions

Revision 19

0-OSP-TCA-001

Time Critical Operator Action Validation

Revision 22

1-AP-9.02

Loss of RCP Seal Cooling

Revision 14

1-AP-9.02

Loss of RCP Seal Cooling

Revision 14

2-DRP-006

Protective Relay Setpoints

Revision 28

2-MPT-0427-02

Main Steam Safety Setpoint Verification

Revision 12

CM-AA-400

CFR 50.59 and 10 CFR 72.48 - Changes, Tests, and

Experiments

Revision 13

DNES-AA-MEL-

4001

Determining the Safety Classification of Structures,

Systems, and Components

Revision 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ER-AA-IST-103

ASME IST Program - Inservice Testing of Pressure Relief

Devices

Revision 3

ER-AA-IST-PRD-

103

ASME IST Program - Inservice Testing of Pressure Relief

Devices Implementation

Revision 1

PI-AA-100-1007

Operating Experience Program

Revision 2

Work Orders

203877019,

38103441574,

38103791010,

204185642,

204185670,

204209440,

204209678,

204210949,

38102151703,

204036719,

203920040,

38103690022,

381021411743,

38102166449,

38103724130,

203871047