IR 05000338/2020010

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000338/2020010 and 05000339/2020010

ML20209A007
Person / Time
Site:	North Anna   (NPF-004, NPF-007)
Issue date:	07/27/2020
From:	James Baptist NRC/RGN-II/DRS/EB1
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
IR 2020010
Download: ML20209A007 (10)

Text

July 27, 2020

SUBJECT:

NORTH ANNA POWER STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000338/2020010 AND 05000339/2020010

Dear Mr. Stoddard:

On July 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at North Anna Power Station and discussed the results of this inspection with Mr. Jim Jenkins 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. 05000338 and 05000339 License Nos. NPF-4 and NPF-7

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000338 and 05000339

License Numbers:

NPF-4 and NPF-7

Report Numbers:

05000338/2020010 and 05000339/2020010

Licensee:

Virginia Electric & Power Company

Facility:

North Anna Power Station

Location:

Mineral, VA

Inspection Dates:

July 06, 2020 to July 10, 2020

Inspectors:

P. Carman, Senior Reactor Inspector

B. Collins, Senior Reactor Inspector

M. Greenleaf, 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 triennial inspection of evaluation of changes, tests and experiments baseline inspection at North Anna 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.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from May 1, 2017 to July 10, 2020.

(1)50.59 Evaluation: NA-11-01082, Main Steam Radiation Monitor Replacement (2)50.59 Evaluation: NA-12-00106, Fuel Oil Pump House High Pressure CO2 Fire Protection System Replacement (3)50.59 Evaluation: NA-15-00050, Local Control Room Data Acquisition System (4)50.59 Evaluation: NA-15-00058, Solid State Protection System Digital Card Replacement - Unit 1 (5)50.59 Evaluation: NA-15-00061, Installation of Voltage Unbalance Protection (1H)

(6)50.59 Evaluation: NA-15-00071, Unit 2 Main Turbine Controls Replacement (7)50.59 Evaluation: NA-16-00013, Unit 1 SOLA Regulator Removal (8)50.59 Evaluation: NA-16-00014, Instrument Air Compressor (2-IA-C-1) Digital Timing Relays (9)50.59 Evaluation: NA-16-00047, Unit 2 Feedwater Bypass NTD Dual Circuit Cards (10)50.59 Evaluation: ETE-NAF-2017-0122, Technical and Regulatory Basis for the Revision of VEP-FRD-42A to Revision 2, Minor Revision 2, Including the Basis for the Addition of the CMS5 Topical Report SSP-14-P01/028-TR Into the Reload Nuclear Design Methodology (11)50.59 Screen: NA-12-00096, Repair Reactor Coolant Loop Stop Valve 1-RC-MOV-1595 (12)50.59 Screen: NA-14-00032, Emergency Diesel Generator Standby Jacket Cooling Circulating Pump Replacement (13)50.59 Screen: NA-16-00058, Removal of Weko Pipe Seals in the "B" Service Water Supply Header (36"-WS-2-151-Q3)

(14)50.59 Screen: NA-17-00112, Semi-Vital Bus Uninterruptible Power Supply (15)50.59 Screen: NA-17-00158, Pressurizer Head Vent Equivalent Solenoid Valves (16)50.59 Screen: NA-17-00166, Pressurizer Steam Space Small Branch Lines Safety Class Changes (17)50.59 Screen: NA-17-00194, 2-SW-TV-201A Valve Replacement (18)50.59 Screen: NA-17-00195, Vital Bus 1-I Non-Safety Branch Circuit Fuse Installation (19)50.59 Screen: NA-17-00220, Unit 1 2018 Flow-Accelerated Corrosion (FAC) Program Piping Replacements (20)50.59 Screen: NA-17-00257, PORV N2 Supply Upgrade (21)50.59 Screen: NA-18-00026, Auxiliary Feedwater Pump Steam Turbine Upgrades (1-FW-T-2)

(22)50.59 Screen: ETE-NAF-2018-0009, Allowed CMS5 Software Versions and Model Options for Use in Production Reload Nuclear Design Activities (23)50.59 Equivalency: NA-14-01024, Replacement of CRDM, RPI, and Core Exit Thermocouple Cable Sections / North Anna 1 &

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 triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. Jim Jenkins and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.17T Calculations

13075.58-NPB-1-

X6

Pressurizer Vent System - Stress Analysis

Rev. 001

13075.58-NPB-1-

X6 Addendum

00B

Evaluation of Replacement Solenoid Valves per DC NA-10-

00152

10/27/2010

13929.08-NPB-1-

X6 Addendum

00B

Replacement of the 1" pressurizer head vent solenoid

operated valves 2-RC-SOV-202A1, 202A2, 202B1 and

2B2 per DC NA-17-00158

05/16/2019

CE-1641

Analysis of the As-Built Configuration of the Piping and Pipe

Supports of the Reactor Vessel Head Vent Line at North

Anna Power Station Unit 1

Rev. 0

CEM-0199

Evaluation of PORV Nitrogen Accumulator Installed Per DC

NA-17-00257

Rev. 0

DAR-ME-14-9

Qualification Summary Report for the Core Exit

Thermocouple System Flexible Mineral Insulated Support

Tray Cable Assemblies at North Anna Units 1 and 2

Rev. 0

Corrective Action

Documents

Resulting from

Inspection

CR1151192

20 NRC 10CFR50.59 Inspection-Incorrect Calc Identified

in DC NA-17-00158

07/08/2020

Drawings

1700112-11715-

FE-1W

Semi-Vital Buses and Panel 1-EP-CB-16D North Anna

Power Station Unit 1

Rev. 1

59-2-S935-

2441

Sectional Assembly 8"-150R

Rev. 0

59-2-S935-

2442

Dimensional Arrangement 8"-150R

Rev. 0

Engineering

Changes

14-3188

Replacement of CRDM, RPI and Core Exit Thermocouple

Cable Sections / North Anna 1 & 2

09/02/2014

14-3194

Replacement of CRDM, RPI and Core Exit Thermocouple

Cable Sections / North Anna 1 & 2

09/19/2014

15-3010

Replacement of CRDM, RPI and Core Exit Thermocouple

Cable Sections / North Anna 1 & 2

01/13/2015

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

18-0140

Replacement of CROM, RPI and Core Exit Thermocouple

Cable Sections / North Anna 1 & 2

03/31/2018

NA-11-01082

Main Steam Radiation Monitor Replacement

2/10/2013

NA-12-00096

Repair Reactor Coolant Loop Stop Valve 1-RC-MOV-1595

11/27/12

NA-12-00106

Fuel Oil Pump House High Pressure CO2 Fire Protection

System Replacement

8/27/15

NA-14-00032

EDG Standby Jacket Cooling Circulating Pump Replacement 3/10/15

NA-14-01024

Replacement of CRDM, RPI and Core Exit Thermocouple

Cable Sections / North Anna 1 & 2

08/05/2014

NA-15-00050

Local Control Room Data Acquisition System

05/03/2016

NA-15-00058

Solid State Protection System Digital Card Replacement -

Unit 1

2/15/2015

NA-15-00061

Installation of Voltage Unbalance Protection (1H)

06/06/2017

NA-15-00071

Unit 2 Main Turbine Controls Replacement

2/15/16

NA-16-00013

Unit 1 SOLA Regulator Removal

03/15/2016

NA-16-00014

Instrument Air Compressor (2-IA-C-1) Digital Timing Relays

11/9/16

NA-16-00047

Unit 2 Feedwater Bypass NTD Dual Circuit Cards

03/10/2017

NA-16-00058

Removal of Weko Pipe Seals in the B Service Water

Supply Header (36-WS-2-151-Q3)

Rev. 1

NA-17-00112

Semi-Vital Bus Uninterruptible Power Supply

Rev. 5

NA-17-00158

Pressurizer Head Vent Equivalent Solenoid Valves / NAPS /

Unit 2

Rev. 1

NA-17-00166

Pressurizer Steam Space Small Branch Lines Safety Class

Changes

Rev. 1

NA-17-00194

2-SW-TV-201A Valve Replacement

Rev. 1

NA-17-00195

Vital Bust 1-I Non Safety Branch Circuit Fuse Installation

Rev. 6

NA-17-00220

Unit 1 2018 Flow Accelerated Corrosion (FAC) Program -

Piping Replacements

Rev. 2

NA-17-00257

PORV N2 Supply Upgrade

Rev. 1

NA-18-00026

Auxiliary Feedwater Pump Steam Turbine Upgrade (1-FW-T-

2)

Rev. 0

Engineering

Evaluations

CA7907881

Substantial Safety Hazard Evaluation - CR1144961

05/12/2020

ETE-NAF-2017-

Technical and Regulatory Basis for the Revision of VEP-

Rev. 0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

22

FRD-42-A to Revision 2, Minor Revision 2, Including the

Basis for the Addition of CMS5 Topical Report SSP-14-

P01/028-TR Into the Reload Nuclear Design Methodology

ETE-NAF-2018-

0009

Allowed CMS 5 Software Versions and Model Options for

Use in Production Reload Nuclear Design Activities

Rev. 0

Miscellaneous

DOWG 16-01

Resource Manual for IP-ENG-001, Standard Design Process

March 1,

2017

EPRI 1011881

Nuclear Maintenance Applications Center: Westinghouse

Full-Length Rod Control System - Life Cycle Management

Planning Sourcebook

04/01/2006

G-955186

Equipment Specification: Solenoid Operated Globe and

Throttle Valves ASME Boiler and Pressure Vessel Code

Section III Class 1, 2 and 3

Rev. 1

ML14260A143

FINAL SAFETY EVALUATION BY THE OFFICE OF

NUCLEAR REACTOR REGULATION TOPICAL REPORT

WCAP-17867-P, REVISION 1, WESTINGHOUSE SSPS

BOARD REPLACEMENT LICENSING SUMMARY

REPORT PRESSURIZED WATER REACTOR OWNERS

GROUP TAC NOS. MF3550 AND MF4655

09/19/2014

PO 4500320548-

00001-

000000263403

Westinghouse Repair & Replacement

10/24/2017

SDBD-NAPS-EV

System Design Basis Document for Emergency Power and

Vital Bus (120-240V) System North Anna Power Station

Rev. 19

SS-14-P01/028-

TR-P-A

Generic Application of the Studsvik Scandpower Core

Management System to Pressurized Water Reactors

Rev. 0

Procedures

CM-AA-400

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

Experiments

Rev. 13

CM-AA-DDC-201

Design Changes

Rev. 22

CM-AA-SDP-201

Standard Design Process Interface

Rev. 2

DNES-AA-GN-

1003

Design Effects and Considerations

Rev. 21

DNES-AA-GN-

1007

Digital Modification Considerations

Rev. 4

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

DNES-VA-GN-

0038

Seismic Qualification of Equipment

Rev. 0

IP-ENG-001

Standard Design Process

Rev. 1

NF-AA-PRA-410

Probabilistic Risk Assessment Procedures and Methods:

PRA Configuration Control Program

Rev. 10

Work Orders

203140109

Damaged RPI coils

Rev. 0

203140118

Damaged RPI coils

Rev. 0