IR 05000313/2020011

Design Basis Assurance Inspection (Programs) Inspection Report 05000313/2020011 and 05000368/2020011

ML20196L755
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/15/2020
From:	Vincent Gaddy Region 4 Engineering Branch 1
To:	Dinelli J Entergy Operations
References
IR 2020011
Download: ML20196L755 (14)

Text

July 15, 2020

SUBJECT:

ARKANSAS NUCLEAR ONE - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000313/2020011 AND 05000368/2020011

Dear Mr. Dinelli:

On June 26, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Arkansas Nuclear One and discussed the results of this inspection with Mr. J. Sullivan, General Manger, Plant Operations, 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, Vincent G. Digitally signed by Vincent G. Gaddy Gaddy Date: 2020.07.15 14:34:08 -05'00'

Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000313 and 05000368 License Nos. DPR-51 and NPF-6

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000313 and 05000368 License Numbers: DPR-51 and NPF-6 Report Numbers: 05000313/2020011 and 05000368/2020011 Enterprise Identifier: I-2020-011-0015 Licensee: Entergy Operations, Inc Facility: Arkansas Nuclear One Location: Russellville, AR Inspection Dates: June 8, 2020 to June 26, 2020 Inspectors: J. Braisted, Reactor Inspector D. Reinert, Reactor Inspector W. Sifre, Senior Reactor Inspector Approved By: Vincent G. Gaddy, 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 design basis assurance inspection (programs) inspection at Arkansas Nuclear One, 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 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), regional inspectors were directed to begin telework. The inspection documented below was determined that the objectives and requirements stated in the IP could be completed remotely.

REACTOR SAFETY

71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)

The inspectors:

a. Determined whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.

Specific Guidance b. Determined whether the sampled POVs are capable of performing their design-basis functions c. Determined 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) CV-1404 - Low Pressure Injection to Reactor Coolant System (Unit 1)

(2) CV-1407 - Borated Water Storage Tank to Low Pressure Injection A suction header (Unit 1)

(3) CV-2691 - Main Steam Isolation valve (unit 1)

(4) CV-3640 - B train discharge to loop II Service Water (Unit 1)

(5) CV-3646 - Service Water system crossover (Unit 1)

(6) CV-3811 - Service Water System (Unit 1)

(7) CV-3840 - Service Water to Pump P34A (Unit 1)

(8) 2CV-5103-1 - High Pressure Safety Injection (Unit 2)

(9) 2CV-5631-2 - Reactor Building Spray (Unit 2)

(10) 2CV-5649-1 - Train A High Pressure Injection outbound sump isolation (Unit 2)

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

On June 26, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. J. Sullivan, General Manger, Plant Operations, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations 1104.029 Service Water and Auxiliary Cooling 120

91-E-0091-01 Design Control Logic Review of Unit 1 Motor Operator 001

Valves

2-R-0017-02 Rotork Valve Actuator Thrust Testing for the Nuclear 0

Industry

94-R-0011-01 ANO MOV Program Design Criteria Valve Factor Keport 7

95-R-0011-07 ANO-1 GL 89-10 MOV Safety Significance Determination 07/30/1997

A-EP-2003-004 ANO MOV Program-Rate of Loading (ROL) 12

CALC- V-1081 Differential Pressure and Line Pressure Review Valve 2

No(s): CV-3640, CV-3642, CV-3644 & CV-3646

CALC-2CV-5631 The purpose of this calculation is to evaluate the 5

-10 capability of the CSS RWT 2T3 DISCH TO 2P-

35B, 2CV-5631-2, to function under the worst case design

basis conditions. This is a 20 inch flexwedge

gate valve manufactured by Crane Aloyco, with a

ROTORK 40NA actuator mounted to

operate the valve.

CALC-91-R- Service Water Performance Testing Methodology 29

2013-01

CALC-92-E- AC-Motor Operated Valve Terminal Voltage 12

0009-01

CALC-93-0010- Evaluation of Safety Related, Power Operated Gate 1

001 Valves for Susceptibility to Hydraulic or Pressure Locking

and Thermal Binding

CALC-A-CV- The purpose of this calculation is to evaluate the 3

2691-02 capability of the of the Unit 1 Main Steam

Isolation Valve CV-2691 to function under the worst case

design basis conditions in the

performance of the ADVs safety related function of

isolating the steam generators upon

receiving an EFIC close signal.

CALC-ANOC-EP- ANO MOV Program - JOG Categorization Report 1

Inspection Type Designation Description or Title Revision or

Procedure Date

10-00001

CALC-V-1010 Pressure Analysis for CV-1407 3

CALC-V-1015 Pressure Analysis for CV-1404 1

CALC-V-1015 Pressure Analysis for CV-1404 3

CALC-V-1081 Pressure Analysis for MOVs CV-3640, CV-3642, CV- 2

3644,and CV-3646

CALC-V-1082 Pressure Analysis for MOV CV-3811 2

CALC-V-2043-00 Pressure Analysis for 2CV-5103-1 07/15/1985

CALC-V-2152-0 Pressure Evaluation for MOV 2CV-5631-2 08/24/1992

CALC-V-2154 Pressure Evaluation for 2CV-5649-l 0

CALC-V-2CV-51 The purpose of this calculation is to evaluate the 6

03-10 capability of the SIS HPSI HEADER NO. 1

ORIFICE BYPASS VALVE 2CV4698-1 to function

under the worst case design basis conditions.

This is a 4 inch Flex Wedge Gate valve manufactured by

Borg/Warner Valve Company, with a

LIMITORQUE SMBD0 actuator mounted to operate the

valve.

CALC-V-2CV- Seismic/Weak Member, and Minimum Required Thrust 3

5649-05 Report

CALC-V-2CV- MOV Torque Switch Setpoints for 2CV-5649-1 6

5649-10

CALC-V-3001 Thrust, Torque, and Limiting Component Report of BWIP 09/01/1989

Gate Valves

CALC-V-CV- Seismic/Weak Member, and Minimum Required Thrust 6

1407-05 Report

CALC-V-CV- MOV Torque Switch Setpoints for CV-3640 8

3640-10

CALC-V-CV- MOV Torque Switch Setpoints for CV-3646 8

3646-10

CALC-V-CV-381 MOV Torque Switch Setpoints for CV-3811 9

1-10

CALC-V-CV-56- Seismic/Weak Member, and Minimum Required Thrust 3

Report

Inspection Type Designation Description or Title Revision or

Procedure Date

EES-12 Motor Operated Valve (MOV) Electrical Evaluation 5

NES-13 Environmental Qualification - Environmental Service 13

Conditions

PSA-ANO1-06-02 MOV PSA Risk Ranking for Arkansas Nuclear One, Unit 1 1

PSA-ANO1-06-03 AOV PSA Risk Ranking for Arkansas Nuclear One, Unit 1 1

PSA-ANO2-06-03 AOV PSA Risk Ranking for Arkansas Nuclear One, Unit 2 1

TDN383 0100 Operation and Maintenance Instructions for High Pressure 1

Stainless Steel and Carbon Steel Gate Valves

V--3001 Thrust, Torque, and Limiting Component Report of BWIP 09/01/1989

Gate Valves

V-2043-00 Pressure Analysis for 2-CV-5103-1 07/15/1987

V-CV-1407-05 Seismic/Weak Member, and Minimum Required Thrust 6

Report

V-CV-3646-05 Seismic/Weak Member & Minimum Required Torque for 3

Valve Assembly CV-3646

Corrective Action 1-2017-03067,

Documents 1-2018-02590,

1-2017-00324,

1-2018-01425,

1-2018-02690,

1-2017-00711,

1-2018-01542,

1-2018-02822,

1-2017-01536,

1-2018-02478,

1-2015-02371,

1-2018-04359,

1-2017-02414,

1-2018-02582,

1-2017-00270,

1-2018-02892,

1-2015-02032,

1-2018-03082,

1-2015-02710,

Inspection Type Designation Description or Title Revision or

Procedure Date

1-2019-01712,

1-2016-01003,

1-2019-04390,

1-2017-01171,

2-2015-01729,

1-2015-01729,

1-2015-01952,

1-2016-03564,

1-2018-02706,

2-2015-03716,

2-2019-03151,

2-2015-03729,

2-2020-01594,

2-2018-01370,

2-2019-00566,

2-2010-02248,

2-2019-02655,

20-00608,

1-2016-01004,

1-2019-02851,

2019-02851,

1-2017-03067,

1-2020-00608,

1-2018-01703,

1-2019-00281,

1-2019-01125,

1-2013-01261,

1-2011-00039,

1-2013-00545,

1-2019-02852,

1-2019-02946,

1-2016-04302,

2015-02395,

1-2018-00155,

Inspection Type Designation Description or Title Revision or

Procedure Date

2016-04193,

1-2019-02559,

2019-00026,

2015-01952,

2016-03564,

1-2018-00951,

1-2020-00866,

1995-00122,

1995-00633,

1995-00466

Corrective Action 1-2020-01045,

Documents 1-2020-01806,

Resulting from 1-2020-01815,

Inspection 1-2020-01052,

1-2020-01070,

C-2020-01782,

1-2020-01057

Drawings M-206, Sheet 2 Piping & Instrument Diagram MSIV Operator Controls 24

M-2232, Sheet 1 Piping & Instrument Diagram Safety Injection System 122

M-2257-BC-5 As-Built: DCP 90-2017 10

M-2257-BC-5, EC 5000112949, 50001068 10

Sheet 1

Engineering 0000026154 Upgrade 2P-89A to a Precision Pump Elemenl 000

Changes 0000044627 Evaluation of Enertech Valves in U1 Service Water 0

System

0000044627 Evaluation of Enertech Valves in U1 Service Water 0

System

0000044915 CV-3640 / 3644 Valve Rotation 180 Degrees 000

0000065760 CR-ANO-1-2015-02032 CA-20 EVAL EC to Allow for 0

Machining Clearance on Covers of SMB 000 MOV'S as

an Alternative Configuration

991802 Change valve stroke time or modify actuator logic on 0

2CV-5630-1 and 2CV-5631-2 to decrease the time

required to complete transfer of ECCS pump suctions

Inspection Type Designation Description or Title Revision or

Procedure Date

from RWT to containment sump. This modification

is to prevent the RWT level from falling below the top of

the vortex breaker following RAS

initiation. Reference CR-ANO-2-1998-0405.

CRN-97-314 Revision of Assumptions. 01/21/1998

Engineering MES-03 Pressure Evaluation of Motor Operated Valves 1

Evaluations

Miscellaneous Evaluation Guide for Valve Thrust and Torque 01/24/2018

Requirements

Nuclear Maintenance Applications Center: Application October,

Guide for Main Steam Isolation Valves 2017

2CAN100901 Request for Relief VRR-ANO2-2009-1 Frequency of Leak 10/16/2009

Rate Testing of the Service Water Boundary Isolation

Valves

LO-ALO-2019- ANO Power Operated Valve Focused Self-Assessment 03/05/2020

00085

OCAN059906 Response to NRC Request for Additional Information on 05/28/1999

GL 96-05; Periodic Verification of MOVs (NRC

TAC Nos. M97013 and M97014)

STM 1-15 Arkansas Nuclear One Unit 1 System Training Manual, 13

Main Steam

STM 1-42 Arkansas Nuclear One Unit 1 System Training Manual, 26

Service & Auxiliary Cooling Water

STM 2-05 Arkansas Nuclear One Unit 2 System Training Manual, 34

Emergency Core Cooling System

STM 2-08 Arkansas Nuclear One Unit 2 System Training Manual, 24

Containment Spray System

TD L200.0030 Instruction and Maintenance Manual Limitorque Type 4

SMB

V-EC-1658-A Risk Ranking Approach for Motor-Operated Valves in 2

Response to Generic Letter 96-05

Operability EN-MA-151 Overhaul of Limitorque SMB 000 & SB/SMB 00 Actuators 1

Evaluations

Procedures EN-MA-141 Limitorque Valve Operator Model SMB/SB/SBD-000 014

Inspection Type Designation Description or Title Revision or

Procedure Date

Through 5 MOV and HBC

Periodic Inspection

1015.002 Decay Heat Removal and LTOP System Control 067

1104.004 Decay Heat Removal Operating Procedure 131

1104.029 Service Water and Auxiliary Cooling System 120

202.012 Repetitive Tasks 022

203.031 Reactor Coolant Pump and Motor 030

2104.039 HPSI System Operation 089

EN-DC-140 Air Operated Valve Program 9

EN-DC-151 PRA Maintenance and Update 008

EN-DC-159 System and Component Monitoring 16

EN-DC-196 AOV Setpoint Control, Signature Analysis and Trending 6

Evaluation

EN-DC-302 Engineering Methodologies for Design Basis Review 4

(DBR) of Air Operated Valves (AOV)

EN-DC-304 MOV Thrust / Torque Setpoint Calculations 3

EN-DC-311 MOV Periodic Verification 006

EN-DC-312 Motor Operated Valve (MOV) Test Data Review 6

EN-DC-325 Component Performance Monitoring 9

EN-FAP-OM-023 Entergy Nuclear Change Management 8

EN-MA-143 Use of Viper or Votes Infinity Air Operator Valve 10

Diagnostics

EN-MA-148 Use of VIPER or VOTES Infinity Motor Operated Valve 4

Diagnostics

EN-MA-152 Overhaul of Limitorque SMB/SB 0 through 4 Actuators 0

EN-NE-G-026 Probabilistic Safety Assessment Applications 5

EN-OP-123 Time Critical Action/Time Sensitive Action Program 003

Standard

SEP-ANO-AOV- ANO Air Operated Valve (AOV) Program 003

001

Work Orders 00191635,

00305896,

2747407,

Inspection Type Designation Description or Title Revision or

Procedure Date

2788661,

2503522,

2734618,

00351269,

2844560,

2847673,

2776215,

00469259,

2508165,

00487569,

2579157,

2770428,

00409632,

2874938,

00345709,

2485066,

2805186

8