IR 05000395/2020010

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NRC Design Bases Assurance Inspection (Team) Report 05000395/2020010
ML20356A295
Person / Time
Site: Summer 
Issue date: 12/21/2020
From: James Baptist
NRC/RGN-II/DRS/EB1
To: Lippard G
Dominion Energy
References
IR 2020010
Download: ML20356A295 (14)


Text

December 21, 2020

SUBJECT:

VIRGIL C. SUMMER - DESIGN BASIS ASSURANCE INSPECTION (TEAMS)

INSPECTION REPORT 05000395/2020010

Dear Mr. Lippard III:

On November 19, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Virgil C. Summer 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/

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

Docket No. 05000395 License No. NPF-12

Enclosure:

As stated

Inspection Report

Docket Number:

05000395

License Number:

NPF-12

Report Number:

05000395/2020010

Enterprise Identifier: I-2020-010-0047

Licensee:

Dominion Energy

Facility:

Virgil C. Summer

Location:

Jenkinsville, SC

Inspection Dates:

October 26, 2020 to November 20, 2020

Inspectors:

P. Braxton, Reactor Inspector

J. Hamman, Reactor Inspector

S. Ninh, Senior Project Engineer

R. Patterson, Senior Reactor Inspector

M. Riley, Reactor Inspector

T. Su, Reactor Inspector

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 Virgil C.

Summer, 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)480V MCC (XMC1DA2Y)

  • Compliance with Updated Final Safety Analysis (UFSAR), Technical Specifications (TS), and TS Bases
  • Conformance with manufacturer instructions for installation, maintenance, and operation
  • Material condition and configuration
  • Environmental Conditions
  • Design requirements (loading, short circuit analysis, etc.)
  • Verification that System Health Reports accurately reflect current system conditions
  • Protective device settings
  • Circuit breaker preventive maintenance inspection and testing procedures

(2)1A EDG and Support Systems

  • Compliance with UFSAR, including applicable design and licensing basis requirements
  • Material condition and configuration
  • Maintenance effectiveness
  • System health reports
  • Surveillance test results
  • Calculations verifying system design requirements (e.g., loading and fuel tank capacity)
(3) DC Battery Bus (1HA9B)
  • Battery and bus material condition and configuration
  • Battery and bus maintenance effectiveness
  • System health reports
  • Worked maintenance and surveillance test reviews
  • Calculations verifying system design requirements
(4) MDEFW Pump (XPP-21A)
  • Compliance with UFSAR, TS, and Design Basis Document (DBD)
  • Material condition and configuration (e.g., visual inspection during a walkdown)
  • Consistency between station documentation (e.g. procedures) and Vendor Specifications
  • Operating, Abnormal and Emergency Procedures
  • Training Manual and System Description
  • Operator Critical Actions
  • Maintenance effectiveness
  • Component Health System reports, corrective maintenance records, and corrective action history
  • Consistency between design bases calculations and test procedure acceptance criteria
  • Surveillance Test results
  • Operating Industry Experience

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

(1) Steam Generator (SG) Power Operated Relief Valve (PORV) IPV-2000
  • UFSAR, including applicable design and licensing basis requirements
  • Material condition and configuration
  • Maintenance effectiveness, including review of maintenance procedures
  • Surveillance test results
  • Review of related condition reports (CR)
  • System review of the supporting instrument air system
  • Verification that the Equipment Reliability (ER) tracking list accurately reflects current system configuration

Modification Review - Permanent Mods (IP Section 02.03) (4 Samples)

(1)

===50883A - Safety Related Inverter Replacement (2)50567S - Major Revision - XVB3107A/B Closing Time Watchdog Permissive (3)70290C - Steam Generator Tube Rupture (SGTR) Enhancements (4)50933G - Component Cooling Heat Exchanger Service Water Return Throttle Valve Installation - B Train

Review of Operating Experience Issues (IP Section 02.06)===

(1) NRC Information Notice 2019-02, Emergency Diesel Generator Excitation System Diode Failures

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On November 19, 2020, the inspectors presented the design basis assurance inspection (teams) inspection results to George Lippard III and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.21M Calculations

DC09610-056

Assessment of Instrument Error Flow Measurement in SW

Pump IST

Rev. 2

0.13.10

Review of Skew Hilti Bolt Non-Conformance on Pipe

Support Anchors

Rev. 0

DC0011A-012

Qualified Life of Rosemount 1153 Series A Transmitters

(Qual Key 309)

Rev. 5

DC04330-085

Sizing of SW Throttle Valves

Rev. 0

DC05220-083

MDEFW Pump Surveillance Test Requirements

Rev. 2

DC05220-091

EF Hydraulic Analyses

Rev. 3

DC06630-001

EDG Fuel Oil Consumption

Rev. 14

DC08040-012

Protective Device Coordination

Rev. 8

DC08050-002

Load Study of ESF 7.2KV and 480V

Rev. 8

DC08200-001

ESF Degraded Voltage Logic and Settings

Rev. 29

DC082220-010

1E Fault Current Study

Rev. 6

DC08240-003

480V System Protection

Rev. 4

DC08320-005

ESF Battery 1A & 1B Capacity

Rev. 14

DC08320-005

ESF Battery 1A & 1B Capacity

10/16/2015

DC08320-010

Class 1E 125 Volt DC System Voltages & Voltage Drop

Rev. 18

DC09310-066

Service Water from CC Heat Exchanger B Flow (IFT04490)

Rev. 1

DC09610-001

Accuracy of Totalized Service Water System Flow

Rev. 2

DC09610-048

IFE04460/04490 SW Scaling for CCW Heat Exchanger

Thermal Performance (GL 89-13)

Rev. 3

EF-000-2

Piping: Emergency Feedwater Flow Control Valve

04/17/1987

SW002

Pipe Analysis SW002

Rev. 6.2

Sw008

SW008 Piping Analysis

10/14/2014

Corrective Action

Documents

17-02093, 17-

2586, 17-05464,

17-05877, 20-

2840, 16-00972,

17-05464,17-

05526,17-05530,

17-05588,17-

Various

Various

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

05877, 18-

208,18-

05853,19-00223,

19-04060,19-

222, 20-01075,

20-01115, 20-

01791, 20-02840,

20-03029, 14-

03039

17-04148, 18-

01032, 18-01033,

20-01681, 20-

2394

CR-19-02065,

CR-17-05376,

CR-17-05224,

CR-17-03153

Various

Various

Corrective Action

Documents

Resulting from

Inspection

20-03588

The cover band assembly for the B MDEFW pump flow

control valve is loose and resting circumferentially around

the valve body.

11/02/2020

CR-20-03529

PM Not Generated Per Plant Procedure

10/26/2020

CR-20-03546

A computational error for dead weight associated with

W6x15.5 (GA-W6) beams

10/28/2020

CR-20-03591

There was no grout beneath the support (Hanger ID:

EFH2007) for XVR03531-EF Air Supply Relief Valve for

IFV03531-EF

11/03/2020

CR-20-03630

AGASTAT Catalog Pages Included in Error

11/05/2020

CR-20-03674

Discrepancy between UFSAR Table 8.3-3 Part A1 and

Design Calculation DC08360-006

11/10/2020

CR-20-03676

During extent of condition review for CR-20-03591, which

identified base plate for support EFH2007 was missing

grout, it was identified that the condition was typical for 5

additional supports.

11/12/2020

CR-20-03725

Discrepancy between UFSAR Table 8.3-3 Part A2 and

11/16/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Design Calculation DC08360-006

Drawings

21-085-

EFH2007A

Piping Support

Rev. 0

04-4461-SS-200-

27

480V Load Centers Relay and Breaker Settings

Rev 10

1MS-50-161

8X6 Body 80 Actuator 667-EWP Diaphragm Actuated

Control Valve

21-085-

EFH2007B

Piping Support,

Rev. 0

D-302-011

Main Steam Nuclear

Engineering

Changes

290

Steam Generator Tube Rupture Procedure Enhancements

Rev. D

ECR 50933G

CC HX SW Return Throttle Valve Installation - B Train

Rev. 6

ECR50965M

EF Flow Margin Improvement

Rev. 5

Miscellaneous

0310-0025-

MEMO-006

Power & Rectifier Chassis Temperature Rise Test Results

Rev. 0

10CFR50.59

Review

10CFR50.59 Review for ECR-70290

05/23/2012

1MS-94B-0390

Vendor Manual-Model 4 Motor Control Center

Design Basis

Document

Diesel Generator Engine Support and Control Systems (DG)

Rev. 15

Design Basis

Document

Main Steam (MS)

Rev. 12

ECR 50733, Att. I

Replace the Emergency Diesel Generator Excitation System

Rev. 4

ECR 50933G -

Technical Work

Record -ES-104

XVA43182B-SW Status Indication Discussion

Rev. 3

Enhanced Design

Basis Document,

Emergency Feedwater System

Rev. 17

Health System

Report

Emergency Feedwater System Health Report 2nd Half-2019

03/13/2020

Health System

Reports

Emergency Feedwater System (EF) Health Report 1st Half-

20

08/12/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RPM 2015624

XVB3107A Lockout Control Panel

10/29/2020

System Health

Report

Emergency Diesel Generator 2020 Period 1

08/12/2020

Time Critical

Action Validation

Scenario Form

Steam Line Break Outside RB with Loss of Bus 1HA and

Offsite Power 05/02/18

05/02/2018

Time Critical

Action Validation

Scenario Form S

Steam Generator Tube Rupture Dated 02/26/19

2/26/2019

VCSNS - DBD

25 Volt DC

Electrical System

VCSNS - DBD 125 Volt DC Electrical System

Rev. 6

Vendor Manual

Bingham Emergency Feedwater Pump

Rev. 5

Vendor Manual

Number 1MS-

94B-1425

BNL Industries. Inc.: Operating and Maintenance

Instructions for 3/4-inch. 1-inch, and 2-inch (reduced port )

Ball Valves

Rev. 5

Vendor Manual

Number 1MS-

94B-1870

Fisher Vee-Ball V150 Rotary Control Valves

Rev. 0

Procedures

STP-123.001

Service Water System Valve Lineup Verification

Rev. 7

AOP-112.2

ARG-3, Steam Generator Tube Leak not Requiring SI

Rev. 7

ARP-001-XCP-

605 Revision 7

Main Control Board

Rev. 7

EC-03

Processing Engineering Change Packages

Rev. 6

EMP 280.004

Molded Case Circuit Breaker Testing

Rev. 22

EMP 280.006

Molded Case Circuit Breaker and Controller Inspection and

Preventative Maintenance

Rev. 8

EMP-115.029

Battery Main Distribution Panel Inspection

Rev. 1

EMP-295.011

Motor Rotor Bar Check,

Rev. 4

EOP-1.0

E-1, Reactor Trip or Safety Injection

Rev. 0

EOP-3.0, E-2

Faulted Steam Generator Isolation

Rev. 13

EOP-4.0

E-3, Steam Generator Tube Rupture

Rev. 26

EOP-4.0

E-3, Steam Generator Tube Rupture

Rev. 26

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

ES-0120

Operability or Functionality Recommendation Development

Rev. 1

ICP-345.064

Functional Test and Replacement of Train A SW to EF

Cross Connect Time Delay Relays,

Rev. 0

ICP-345.065

Functional Test and Replacement of Train B SW to EF

Cross Connect Time Delay Relays

Rev. 0

ICP-400.004

Service Water from CC HX B FlowIFT04490

Rev. 9

MMP-300.013

Main Steam Power Relief Valve and Actuator Maintenance

Rev. 12

Change A

MMP-300.022

General Air Actuator Diaphragm and O-Ring Replacement

Rev. 7

Change C

MMP-300.033

Changing Oil in Pumps Equipped With TRICO OPTO-

MATIC oilers,

Rev. 8

PTP-173.001

Backflushing Service Water side of Component Cooling

Heat Exchanger A(B),

Rev. 3

SAP-0133

Design Control /Implementation and Interface

Rev. 16

SAP-0999

Correction Action Program

Rev. 19,

Change A

SAP-0999B

CR Review Team (CRRT)

Rev. 1.

Change D

SAP-0999C

Management Review Team (MRT)

Rev. 1,

Change G

SAP-0999E

Corrective Action Review Board (CARB)

Rev. 5

SAP-143

Preventive Maintenance Program

Rev. 16,

Change B

SOP-211

Emergency Feedwater System

Rev. 14

STP-0220.001A

Motor Driven Emergency Feedwater Pump and Valve Test

Rev. 2

STP-0220.008

Motor Driven Emergency Driven Feedwater Pump Full Flow

Test

Rev. 7

STP-120.005A

Motor Driven Emergency Feedwater Pump A Actuation Test

Rev. 1

STP-121.002A

Steam Generator PORV Operability Test

Rev. 0

Change D

STP-223.003

Service Water Pump Performance Test Flow vs Differential

Pressure

Rev. 1

Work Orders

1706308,

Various

Various

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1711623,

1711906,

1716342,

1716679,

1717001,

1802065,

1808781,

1813048,

1817424,

1900454,

1903296,

1903353,

1903712,

1903717,

1904607,

1905905,

1910786,

1912131,

1913504,

1913702,

1917892,

1918061,

2000979,

2006228,

2008938,

2012520,

2012524,

2012525,

2015732

1706952-001,

1708804-001,

1712322-001,

1717581-001,

1717582-001,

Various

Various

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

1718241-001,

1800393-001,

1808401-001,

1809718-001,

1812287-001,

1815929-001,

20606-001,

1903132-001,

1904919-001,

1909684-001,

1911168-001,

1913117-001,

1913131-001,

1914543-001,

1915269-001,

1915269-002,

1916648-001,

2001053-001,

2004941-001,

2006059-001

1903851-001,

1903852-001,

1711884-001,

1718225-001,

1903133-001,

1903136-001,

0105321-001,

1611168-001,

1611168-002,

1710182-001,

1710182-002,

1900232-001

Various

Various