IR 05000280/2021010

Design Basis Assurance Inspection (Programs) Inspection Report 05000280/2021010 and 05000281/2021010

ML21228A225
Person / Time
Site:	Surry
Issue date:	08/16/2021
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2021010
Download: ML21228A225 (16)

Text

August 16, 2021

SUBJECT:

SURRY POWER STATION - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000280/2021010 AND 05000281/2021010

Dear Mr. Stoddard:

On July 30, 2021, 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, Surry 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 Branch 1 Division 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:

05000280/2021010 and 05000281/2021010

Licensee:

Virginia Electric and Power Company

Facility:

Surry Power Station

Location:

Surry, VA

Inspection Dates:

July 12, 2021 to July 30, 2021

Inspectors:

S. Campbell, Senior Reactor Systems Engineer

P. Carman, Senior Reactor Inspector

M. Schwieg, Reactor Inspector

Approved By:

James B. Baptist, 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 (programs) 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 a 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

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements

POV Review (IP Section 03) (9 Samples 1 Partial)

The inspectors:

a. Evaluated whether the sampled power-operated valves (POVs) are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.

c. Evaluated whether testing of the sampled POVs is adequate to demonstrate the capability of the POVs to perform their safety functions under design-basis conditions.

d. Evaluated maintenance activities including a walkdown of the sampled POVs (if accessible).

(1)1-CC-TV-140B, Component Cooling (CC) Return from Reactor Coolant Pump Thermal Barriers, Outside Containment Isolation Valve (2)1-MS-PCV-102A, Main Steam Supply Trip Valve to Turbine Driven Auxiliary Feedwater Pump (3)1-RC-MOV-1535, Block Valve for Pressurizer Power Operated Relief Valve (4)1-RC-PCV-1455C, Pressurizer Power Operated Pressure Control Valve Discharge to Pressurizer Relief Tank (5)2-CH-MOV-2115E, Charging Pump Supply Isolation Valve from Volume Control (6)2-CW-MOV-206D, Condenser Inlet Isolation Valve (7)2-FW-MOV-251F, Standby Auxiliary Feedwater Supply to "A" Steam Generator (8)2-SI-MOV-2867D, Boron Injection Tank Outlet to Reactor Coolant System (RCS)

Cold Leg Isolation Valve (9)2-SI-MOV-2890C, Low Head Safety Injection (SI) Pumps Cold Leg Discharge Stop Isolation Valve (10)

(Partial)2-SI-MOV-2860A/B, Low Head SI Pump 'A' & 'B' Suction Isolation from Containment Sump

• Safety Injection MOV Valve Pressure Locking Modifications (SU-10-01041)

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 30, 2021, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Doug Lawrence, Surry Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21N.02 Calculations

14937.07-M-8

Maximum Differential Pressure Across Safety Injection

System MOVs to Determine Torque and Overload Setting

Rev. 0 with

Addendums

A through H

2044498-C-003

Seismic/Weak Link Thrust Calculation for MOV(s): 1-CH-

MOV-1115C, 1-CH-MOV-1115E, 1-CH-MOV-2115C & 2-

CH-MOV-2115E at Surry

Rev. 1

2044498-C-034A

Analysis of Various Components for SPS Replacement

Valve 38-02-CH-MOV-2289A

Rev. 2

2044498-C-036

Seismic / Weak Link Thrust Calculation for MOVs

Rev. 0 with

Addendums

A through H

2044498-C-048

Seismic / Weak Link Calculation for MOVs: 1-FW-MOV-

151A to F at Surry Unit 1, 2-FW-MOV-251A to F at Surry

Unit 2, Addendum A, Rev 0

05/01/2014

CT-SPEC-000-

676270

Control Valve Specification

06/11/1968

ME-0113

Performance Review Pressurizer Power Operated Relief

Valves North Anna and Surry Power Stations

09/30/1997

ME-0288

Maximum Differential Pressure Across Feedwater System

MOVs (keywords: Auxiliary Feedwater, MOV, Pressure

Differential)

09/22/1992

ME-0379

Evaluation of Relief Lines to Pressurizer Relief Tank

2/12/1993

and

05/23/1997

ME-0498

Pressure Locking and stem Effect and Thermal Binding

Analysis for Generic Letter 95-07,

Rev. 0 with

Addendums

A through H

ME-0597

Minimum Delivered AFW Flow and Acceptance Criteria

for AFW Pump Operability Verification Testing

Rev. 4

including

Addendums

4B through

4E

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ME-0631

Addendum A, System Level Calculation

03/28/2005

ME-0727

MOV Differential Pressure (DP) Calculation for the

Charging Pump Supply Valves for the Volume Control

Tank (VCT)

Rev. 0

ME-0738

MOV Differential Pressure (DP) Calculation for the

Auxiliary Feedwater Steam Generator Supply Valves

Calculation Coversheet,

2/15/2009

ME-3367

JOG Calculation of Required Thrust Settings for MOV 2-

CH-MOV-2115E

Rev. 1

ME-3412

JOG Calculation of Required Thrust Settings for MOV 2-

FW-MOV-251 F, Rev. 0

09/23/2010

ME-3441

JOG Calculation of Required Thrust and Design Margin

for SPS 2-SI-MOV-2867D

Rev. 3

ME-3450

JOG Calculation of Required Thrust Settings for MOV 2-

SI-MOV-2890C

Rev. 2

MEC-14937.07-

M-2

Maximum Differential Pressure Across Feedwater System

MOVs to Determine Proper Torque and Overload Settings

03/21/1994

MEC-2044498-C-

050B

Seismic / Weak Link Calculation for MOVs: X-RC-MOV-

X535 & 1-RC-MOV-1536 at North Anna X-RC-MOV-X535

& X-RC-MOV-X536 at Surry

06/06/2011

SM-0945

Revised Heatup and Cooldown Curves and LTOPS

Setpoints

Rev. 0 and

Addendum A

SM-1001

Effect of Backup Air System AOT on Pressurizer PORV

Reliability for Surry

05/17/1996

SM-1002

Surry PORV Cycle Study

05/08/2006

SM-1476

Surry GOTHIC analysis of NPSH Available for the LHSI

and RS Pumps

Rev. 1

SU-CALC-MEC-

DEO-0096

PORV Redundant Bottled Air System Capacity

Revs. 0 and

SU-CALC-SPC-

14937.07-M-6

Maximum Differential Pressure Across 1/2-RC-MOV-X535

and 1/2-RC-MOV-X536

05/24/1994

Corrective Action

Documents

CA263793

CA to Corporate Engineering to complete the design

review of the air supplies to the Pressurizer PORVs and

initiate necessary actions to assess and improve design

06/13/2013

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

margin

Category 3 Root

Cause Evaluation

Response -S-

2003-07

2/24/2003

CR579848,

CR579849,

CR100174,

CR1052589,

CR1058901,

CR1061142,

CR1111182,

CR1111273,

CR1146451,

CR1147013,

CR1155555,

CR1164618

Plant Issues - S-

2002-0612, S-

2002-1623 and

S-2002-0496

Corrective Action

Documents

Resulting from

Inspection

CR1176854

NRC Identified - Substance on bonnet of 1-MS-11

Rev. 0

CR1176861

2-DRP-014 Revision 38 Motor Operated Valves

Engineering Data needs to be revised

Rev. 0

CR1177242

Calculation ME-3367, Revision 1 for 2-CH-MOV-2115E

contains typographical errors

Rev. 0

CR1177735

Incorrect Weak Link Limit in Calculation ME-3450 Rev 2

Rev. 0

CR1177822

NRC Identified Performance Deficiency during POV

Inspection

Rev. 0

CR1177878

NRC Identified Observation during POV Inspection

Rev. 0

CR1177879

NRC identified Performance Deficiency during POV

inspection for failure to perform 10 CFR 50.59 eval

Rev. 0

Drawings

11448-FM-075C

Flow/Valve Operating Diagram Compressed Air System

Surry Power Station Unit 1

Rev. 35

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

11548-FM-083A

Flow/Valve Operating Numbers Diagram Vents and

Drains System Surry Power Station Unit 2

Rev. 34

11548-FM-089A

Safety Injection System Surry Power Station Unit 2 Sheet

Rev. 54

11548-FP-60D

Containment Recirculation Spray & Low Head Safety

Injection Pimp Piping Surry Power Station - Unit 2

Rev. 16

11548-FS-14AV

Containment Sump Strainer Mark No. Locations Surry

Power Station - Unit 2

Rev. 0

88405-1

Velan Engineering Companies, Forged Bolted Bonnet

Primary Nuclear Motor Operated Gate Valve: Motor

Operated Gate Valve For ASA 1500 LB. 3

11/7/1966

93-12860

10x8x10 No. S350 WDDASA Series 1500, Welding Ends

Outside Screw & Yoke Gate Valve with Lip Seal and

SMB-2-60 Limitorque Valve Control

Rev. H

D-338840

Copes-Vulcan Series D Valve Assembly With Model

1000-160 RA Actuator 2" Class 1500

Rev. 3

L-138088

Copes-Vulcan Model D-100 160-2 1/2 OPERATOR 2"-

1500 LB U.S.A STD Valve Assembly with 3" Inlet & Outlet

07/01/1972

SU-11548-FM-

088B

Flow/Valve Operating Numbers Diagram Chemical and

Volume Control System Surry Power Station Unit 2

Virginia Power, Sheet 1 of 3

Rev. 43

SU-11548-FM-

089A

Flow/Valve Operating Numbers Diagram Safety Injection

System Surry Power Station Unit 2 Virginia Power, Sheet

of 3

Rev. 55

SU-DWG-000-

11448-ESK-63B1

Elementary Diagram 1-RC-PCV-1455C, Sheet 1 of 1

Rev. 5

SU-DWG-000-

11448-ESK-6BL2

Elementary Diagram 480V Circuit Motor Operated Valves

01-Rc-MOV-1535 & 1536 Surry Power Station - Unit 1,

Rev 4, Sheet 5 of 5

03/23/1997

SU-DWG-000-

11448-FM-075E

Compressed Air System for 1-RC-PCV-1455C, Sheet 2

of 2

Rev. 12

SU-DWG-000-

11448-FM-075E

Compressed Air System for 1-RC-PCV-1455C, Sheet 1 of

Rev. 12

SU-DWG-000-

Flow/Valve Operating Numbers Diagram Reactor Coolant

05/20/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

11448-FM-086B

System Surry Power Station Unit 1, Sheet 1 of 3

SU-DWG-000-

11548-ESK-6BY

SH-003

Elementary Diagram 480V Circuits Motor Operated Vales

FW-MOV-251E & F, Surry Power Station, Unit 2, Sheet 3

of 3

Rev. 25

SU-DWG-000-

11548-FM-068A

SH-001

Flow/Valve Operating Numbers Diagram Feedwater

System Surry Power Station Unit 2 Virginia Power, Sheet

of 4

2/26/2014

SU-EDWG-000-

11448/11548-

6.43-15B

150#, SS Motor Operated Gate Valve, Sheet 1

Rev. 2

SU-EDWG-000-

P2-71424-K1

Velan Bolted Bonnet Needle Valve (Forged), Rev B,

Sheet 1

06/03/1988

SU-EDWG-0000-

11448-656-3A

2-SI-MOV-2860A

Engineering

Changes

DCP 02-031

Pressurizer PORV Backup Air Sys Pressure Regulator

Setpoint Change - Unit 1

10/14/2002

DCP 04-033

Scaling Changes for SGLCS, Pressurizer Pressure, and

Lvl Control Systems and RWST Level

10/19/2004

DCP 77-008

RCS Overpressure Mitigation

03/22/1978

DCP 79-037

ASCO SOV Replacement

11/19/1980

DCP 79-054

Direct Indication of PORV and Safety Valves

10/29/1980

DCP 79-53

Emergency Power Supply PORV

08/06/1980

DCP 92-083

Standing DCP, Misc Limitorque Operator Modifications/

Surry/ Units 1 & 2

04/30/1996

SU-10-01041

SAFETY INJECTION MOV VALVE PRESSURE

LOCKING MODIFICATIONS

Rev. 2

SU-17-00139

Unit 2 Stem and Pin Replacement on Anchor Darling

Double Disc Gate Valves

Rev. 1

Engineering

Evaluations

EE-0306

Evaluation of MOV Thermal Overload Settings

Rev. 0 with

Addendums

A through D

EE-0501

Motor Terminal Voltage for Motor-Operated Valves

Addendum A

and

Addendum

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

A, Rev. 2

ET CME-07-0035

Review of Potential Surry PORV Backup Air Supply

Isolation Valve

08/29/2007

ET S 02-0208

Review Adequacy of PORV Backup Air Supply and Alarm

Setpoint In Support of PORV Stroke Time Change Surry

Power Station, Unit 1 and 2

03/03/2003

ET-NAF-970094

Relaxation of Przr PORV Stroke Time Criterion

05/05/1997

ETE-CME-2011-

0001

Implementation of Motor Operated Valve Setup Windows

for SPS Unit 2 Valves

Rev. 5

ETE-CME-2013-

25

Design Basis COF for Gate Valves With Stellite-Stellite

Disc/Seat Material Pairs

Rev. 0

ETE-CME-2021-

0003

Impact of Masoneilan EDA Changes on Surry AOV

Program

Rev. 1

ETE-SU-2011-

0094

GL 96-05 Motor Operated Valve Risk Ranking

Rev. 1

EWR 93-021 IA

PORV Back-up Bottled Air Supply

05/04/1993

ME-3915

JOG Calculation of Required Thrust Settings for MOV 1-

RC-MOV-1535

10/29/2015

NE-1050

Addendum 1, Reanalysis of Pressurizer PORV Air Bottles

Minimum Pressure Limit

05/16/2006

P-SURR-332601

Change MPM frequency on CW MOVs in the MOV

program.

Rev. 0

Miscellaneous

MOV - Program Health Report Scorecard, 2020, 2Q

1-RC-PCV-1455C Strokes Times on Backup Air Since

2002

07/27/2021

Maintenance Strategy: 01-RC-MOV-1535-VALVOP

07/12/2021

Performance Criteria Basis Document

04/15/2019

Maintenance Strategy: 02-FW-MOV-251F-VALVOP

07/12/2021

38-F264-00010

Vender Manual Fisher 471 Actuator

Rev. 6

80058

Limitorque Valve Actuator Qualification For Nuclear

Power Station Service Report 80058 Tests Conducted

Per IEEE 382-1972, 323-1974, 244-1975

01/11/1980

AFW02

Function Basis Document

04/15/2019

B0003

Qualification Type Test Report Limitorque Actuators for

06/2/1976

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Class 1E Service Outside Primary Containment

Qualification Report

B0212

Nuclear Power Station Qualification Type Test Report

Limitorque Valve Actuators

4/12/1985

CT-EQUAL-000-

CT-EQUAL-000-

GQE-09.01-G01

Namco Limit Switch Test Report

04/26/2017

CT-EQUAL-000-

CT-EQUAL-000-

PQE-09.01-P01

Namco Limit Switch Qualification Report

2/1/2020

CT-EQUAL-000-

CT-EQUAL-000-

PQE-35.01-P02

SOV Qualification Report

07/30/2020

CT-EQUAL-000-

GQE-03.01-G01

EQ File for SMB-0 Limitorque Actuator with a 25 ft-lb 1.6

HP Reliance AC Class B Motor

01/24/2019

CT-EQUAL-000-

GQE-03.01-G02

EQ File for Series SB, SBD, SMB, and SMB/HBC Motor

Operators

1/23/2019

CT-EQUAL-000-

PQE-03.01-P01

EQ File for SMB Series Actuator, Class RH, H motors -

Inside Containment

01/23/2019

CT-EQUAL-000-

PQE-03.02-P01,

EQ File for Motor Operators

1/23/2019

CT-PO-000-

45467730 SD-

PO107927-SDO-

SU

Framatome ANP Actuator Purchase Order

10/02/2006

CT-PO-000-

45576213 SD-

PO272962-SDO-

SU

Areva NP Purchase Order No. 455762213

03/24/2008

Diagnostic

Summary 1-MS-

PCV-102A

Rev. 0

E-676270

SPS Valve Data Sheets

07/7/1970

ME-0658

Addendum A DBRs for X-RC-PCV-X455C & 456

03/11/2014

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ME-0658

Addendum B DBRs for X-RC-PCV-X455C & 456

05/20/2015

NCRODP-38

Nuclear Control Room Document: Reactor Coolant

System

08/15/2019

PO 45652371

Areva NP Purchase Order No. 45652371

03/17/2009

RC002

Function Basis Document

04/15/2019

RC006

Function Basis Document

07/14/2021

RC017

Function Basis Document

04/15/2019

S1PVI5

Surry Unit 1 Inservice Testing Program Plan For Pumps

and Valves Fifth Interval

Rev. 1

S2PVI5

Surry Unit 2 Inservice Testing Program Plan For Pumps

and Valves Fifth Interval

Rev. 1

SDBD-SPS-AFW

AFW Design Basis Document

11/5/2020

SDBD-SPS-RC

System Design Basis Document for Reactor Coolant

System Surry Power Station

2/22/2006

Serial No. 446

Original Przr PORV Design Letter to NRC

10/14/1977

Serial Number

6710-55155-555-

1-RC-PCV-1455C Valve Data Sheet

05/03/2021

SPS AOV

Program Health Report Scorecard, 2020, Q2

SPS-IST-BASIS-

INT-5

Surry Nuclear Plant, Units 1 & 2 Inservice Testing (IST)

Program/IST Program Basis Interval 5

Rev. 1

SSY-320516

Velan Purchase Order No. 320516

2/05/1991

SU-VTM-000-38-

C432-00017

Copes Vulcan 2 Inch D-100 Control Valve

Revs. 3 and

SU-VTM-000-38-

C432-00029

Copes D-1000 Upgrade Manual

Rev. 3

US-2099

Standard Specification for Safety-Related Motor Operated

Valves Surry Nuclear Station Units 1 And 2

Rev. 0 with

Addendums

through 2A

White paper 2-SI-

MOV-2860A

Rev. 0

Procedures

0-MPM-0300-10

LIMITORQUE QUARTER TURN OPERATOR TYPE SMB

AND HBC LUBRICATION AND INSPECTION

Rev. 4

0-NSP-VE-001

Stroke Time Reference Change for Valves in the In-

Rev. 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Service Testing Program

1-OPT-RC-001

PRZR PORV REFUELING TEST

05/27/2003

2-DRP-014

Motor Operated Valves Engineering Data

Rev. 38

2-ECA-1.1

Loss of Emergency Coolant Recirculation

Rev. 45

2-PT-25.1

Quarterly Testing of CW and SW System Valves

Rev. 21

2B-F3

SFGDS Area Sump HI LVL

Rev. 1

DNES-AA-GN-

1005

Failure Modes and Effects Analysis (FMEA)

Rev. 5

DNES-AA-

ME/MOV-1001

Motor-Operated Valves

Rev. 8

DNES-AA-MEL-

4001

Determining the Safety Classification of Structures,

Systems, and Components

Rev. 3

DNES-AA-MOV-

1001

Motor-Operated Valve Diagnostic Test Preparation and

Evaluation

Rev. 4

EPM-1503-01

Electrical Preventive Maintenance

Rev. 9

ER-AA-MOV-10

Motor-Operated Valve Program

Rev. 3

ER-AA-MOV-101

Motor-Operated Valve Program Process

Rev. 4

ER-AA-PRS-

1010

Preventive Maintenance Task Basis and Maintenance

Strategy

Rev. 13

Work Orders

38077670801,

38102114458,

38102334667,

38103182787,

38103225214,

38103278666,

38103312556,

38103432967,

38103500426,

38103522463,

38103623243,

38103666321,

38103738692,

38103792407,

38103819350,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

38103826394,

204179462,

204179474,

204180114,

204190637,

204205069,

204209011,

204209244,

204209264,

204210027,

204217634,

204224254,

204233807,

204241075,

204241671