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
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 Enterprise Identifier: I-2020-010-0042 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations 13075.58-NPB-1- Pressurizer Vent System - Stress Analysis Rev. 001

X6

13075.58-NPB-1- Evaluation of Replacement Solenoid Valves per DC NA-10- 10/27/2010

X6 Addendum 00152

00B

13929.08-NPB-1- Replacement of the 1" pressurizer head vent solenoid 05/16/2019

X6 Addendum operated valves 2-RC-SOV-202A1, 202A2, 202B1 and

00B 202B2 per DC NA-17-00158

CE-1641 Analysis of the As-Built Configuration of the Piping and Pipe Rev. 0

Supports of the Reactor Vessel Head Vent Line at North

Anna Power Station Unit 1

CEM-0199 Evaluation of PORV Nitrogen Accumulator Installed Per DC Rev. 0

NA-17-00257

DAR-ME-14-9 Qualification Summary Report for the Core Exit Rev. 0

Thermocouple System Flexible Mineral Insulated Support

Tray Cable Assemblies at North Anna Units 1 and 2

Corrective Action CR1151192 2020 NRC 10CFR50.59 Inspection-Incorrect Calc Identified 07/08/2020

Documents in DC NA-17-00158

Resulting from

Inspection

Drawings 1700112-11715- Semi-Vital Buses and Panel 1-EP-CB-16D North Anna Rev. 1

FE-1W Power Station Unit 1

59-2-S935- Sectional Assembly 8"-150R Rev. 0

2441

59-2-S935- Dimensional Arrangement 8"-150R Rev. 0

2442

Engineering 14-3188 Replacement of CRDM, RPI and Core Exit Thermocouple 09/02/2014

Changes Cable Sections / North Anna 1 & 2

14-3194 Replacement of CRDM, RPI and Core Exit Thermocouple 09/19/2014

Cable Sections / North Anna 1 & 2

15-3010 Replacement of CRDM, RPI and Core Exit Thermocouple 01/13/2015

Cable Sections / North Anna 1 & 2

Inspection Type Designation Description or Title Revision or

Procedure Date

18-0140 Replacement of CROM, RPI and Core Exit Thermocouple 03/31/2018

Cable Sections / North Anna 1 & 2

NA-11-01082 Main Steam Radiation Monitor Replacement 12/10/2013

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 8/27/15

System Replacement

NA-14-00032 EDG Standby Jacket Cooling Circulating Pump Replacement 3/10/15

NA-14-01024 Replacement of CRDM, RPI and Core Exit Thermocouple 08/05/2014

Cable Sections / North Anna 1 & 2

NA-15-00050 Local Control Room Data Acquisition System 05/03/2016

NA-15-00058 Solid State Protection System Digital Card Replacement - 12/15/2015

Unit 1

NA-15-00061 Installation of Voltage Unbalance Protection (1H) 06/06/2017

NA-15-00071 Unit 2 Main Turbine Controls Replacement 12/15/16

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 Rev. 1

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

NA-17-00112 Semi-Vital Bus Uninterruptible Power Supply Rev. 5

NA-17-00158 Pressurizer Head Vent Equivalent Solenoid Valves / NAPS / Rev. 1

Unit 2

NA-17-00166 Pressurizer Steam Space Small Branch Lines Safety Class Rev. 1

Changes

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 - Rev. 2

Piping Replacements

NA-17-00257 PORV N2 Supply Upgrade Rev. 1

NA-18-00026 Auxiliary Feedwater Pump Steam Turbine Upgrade (1-FW-T- Rev. 0

2)

Engineering CA7907881 Substantial Safety Hazard Evaluation - CR1144961 05/12/2020

Evaluations ETE-NAF-2017- Technical and Regulatory Basis for the Revision of VEP- Rev. 0

Inspection Type Designation Description or Title Revision or

Procedure 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- Allowed CMS 5 Software Versions and Model Options for Rev. 0

0009 Use in Production Reload Nuclear Design Activities

Miscellaneous DOWG 16-01 Resource Manual for IP-ENG-001, Standard Design Process March 1,

2017

EPRI 1011881 Nuclear Maintenance Applications Center: Westinghouse 04/01/2006

Full-Length Rod Control System - Life Cycle Management

Planning Sourcebook

G-955186 Equipment Specification: Solenoid Operated Globe and Rev. 1

Throttle Valves ASME Boiler and Pressure Vessel Code

Section III Class 1, 2 and 3

ML14260A143 FINAL SAFETY EVALUATION BY THE OFFICE OF 09/19/2014

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

PO 4500320548- Westinghouse Repair & Replacement 10/24/2017

00001-

000000263403

SDBD-NAPS-EV System Design Basis Document for Emergency Power and Rev. 19

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

SS-14-P01/028- Generic Application of the Studsvik Scandpower Core Rev. 0

TR-P-A Management System to Pressurized Water Reactors

Procedures CM-AA-400 10 CFR 50.59 and 10 CFR 72.48 - Changes, Tests, and Rev. 13

Experiments

CM-AA-DDC-201 Design Changes Rev. 22

CM-AA-SDP-201 Standard Design Process Interface Rev. 2

DNES-AA-GN- Design Effects and Considerations Rev. 21

1003

DNES-AA-GN- Digital Modification Considerations Rev. 4

1007

Inspection Type Designation Description or Title Revision or

Procedure Date

DNES-VA-GN- Seismic Qualification of Equipment Rev. 0

0038

IP-ENG-001 Standard Design Process Rev. 1

NF-AA-PRA-410 Probabilistic Risk Assessment Procedures and Methods: Rev. 10

PRA Configuration Control Program

Work Orders 59203140109 Damaged RPI coils Rev. 0

203140118 Damaged RPI coils Rev. 0

8