IR 05000313/2020011
| 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. 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:
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
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
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
1104.029
Service Water and Auxiliary Cooling
20
91-E-0091-01
Design Control Logic Review of Unit 1 Motor Operator
Valves
001
2-R-0017-02
Rotork Valve Actuator Thrust Testing for the Nuclear
Industry
94-R-0011-01
ANO MOV Program Design Criteria Valve Factor Keport
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)
CALC-V-1081
Differential Pressure and Line Pressure Review Valve
No(s): CV-3640, CV-3642, CV-3644 & CV-3646
CALC-2CV-5631
-10
The purpose of this calculation is to evaluate the
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-
2013-01
Service Water Performance Testing Methodology
CALC-92-E-
0009-01
AC-Motor Operated Valve Terminal Voltage
CALC-93-0010-
001
Evaluation of Safety Related, Power Operated Gate
Valves for Susceptibility to Hydraulic or Pressure Locking
and Thermal Binding
CALC-A-CV-
2691-02
The purpose of this calculation is to evaluate the
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
10-00001
CALC-V-1010
Pressure Analysis for CV-1407
CALC-V-1015
Pressure Analysis for CV-1404
CALC-V-1015
Pressure Analysis for CV-1404
CALC-V-1081
Pressure Analysis for MOVs CV-3640, CV-3642, CV-
3644,and CV-3646
CALC-V-1082
Pressure Analysis for MOV CV-3811
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
CALC-V-2CV-51
03-10
The purpose of this calculation is to evaluate the
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-
5649-05
Seismic/Weak Member, and Minimum Required Thrust
Report
CALC-V-2CV-
5649-10
MOV Torque Switch Setpoints for 2CV-5649-1
CALC-V-3001
Thrust, Torque, and Limiting Component Report of BWIP
Gate Valves
09/01/1989
CALC-V-CV-
1407-05
Seismic/Weak Member, and Minimum Required Thrust
Report
CALC-V-CV-
3640-10
MOV Torque Switch Setpoints for CV-3640
CALC-V-CV-
3646-10
MOV Torque Switch Setpoints for CV-3646
CALC-V-CV-381
1-10
MOV Torque Switch Setpoints for CV-3811
CALC-V-CV-56-
Seismic/Weak Member, and Minimum Required Thrust
Report
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EES-12
Motor Operated Valve (MOV) Electrical Evaluation
NES-13
Environmental Qualification - Environmental Service
Conditions
PSA-ANO1-06-02 MOV PSA Risk Ranking for Arkansas Nuclear One, Unit 1
PSA-ANO1-06-03 AOV PSA Risk Ranking for Arkansas Nuclear One, Unit 1
PSA-ANO2-06-03 AOV PSA Risk Ranking for Arkansas Nuclear One, Unit 2
TDN383 0100
Operation and Maintenance Instructions for High Pressure
Stainless Steel and Carbon Steel Gate Valves
V--3001
Thrust, Torque, and Limiting Component Report of BWIP
Gate Valves
09/01/1989
V-2043-00
Pressure Analysis for 2-CV-5103-1
07/15/1987
V-CV-1407-05
Seismic/Weak Member, and Minimum Required Thrust
Report
V-CV-3646-05
Seismic/Weak Member & Minimum Required Torque for
Valve Assembly CV-3646
Corrective Action
Documents
1-2017-03067,
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
Procedure
Type
Designation
Description or Title
Revision or
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
Procedure
Type
Designation
Description or Title
Revision or
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
Documents
Resulting from
Inspection
1-2020-01045,
1-2020-01806,
1-2020-01815,
1-2020-01052,
1-2020-01070,
C-2020-01782,
1-2020-01057
Drawings
M-206, Sheet 2
Piping & Instrument Diagram MSIV Operator Controls
M-2232, Sheet 1
Piping & Instrument Diagram Safety Injection System
2
M-2257-BC-5
As-Built: DCP 90-2017
M-2257-BC-5,
Sheet 1
EC 5000112949, 50001068
Engineering
Changes
0000026154
Upgrade 2P-89A to a Precision Pump Elemenl
000
0000044627
Evaluation of Enertech Valves in U1 Service Water
System
0000044627
Evaluation of Enertech Valves in U1 Service Water
System
0000044915
CV-3640 / 3644 Valve Rotation 180 Degrees
000
0000065760
CR-ANO-1-2015-02032 CA-20 EVAL EC to Allow for
Machining Clearance on Covers of SMB 000 MOV'S as
an Alternative Configuration
991802
Change valve stroke time or modify actuator logic on
2CV-5630-1 and 2CV-5631-2 to decrease the time
required to complete transfer of ECCS pump suctions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Evaluations
MES-03
Pressure Evaluation of Motor Operated Valves
Miscellaneous
Evaluation Guide for Valve Thrust and Torque
Requirements
01/24/2018
Nuclear Maintenance Applications Center: Application
Guide for Main Steam Isolation Valves
October,
2017
Request for Relief VRR-ANO2-2009-1 Frequency of Leak
Rate Testing of the Service Water Boundary Isolation
Valves
10/16/2009
LO-ALO-2019-
00085
ANO Power Operated Valve Focused Self-Assessment
03/05/2020
OCAN059906
Response to NRC Request for Additional Information on
GL 96-05; Periodic Verification of MOVs (NRC
TAC Nos. M97013 and M97014)
05/28/1999
STM 1-15
Arkansas Nuclear One Unit 1 System Training Manual,
STM 1-42
Arkansas Nuclear One Unit 1 System Training Manual,
Service & Auxiliary Cooling Water
STM 2-05
Arkansas Nuclear One Unit 2 System Training Manual,
STM 2-08
Arkansas Nuclear One Unit 2 System Training Manual,
Containment Spray System
TD L200.0030
Instruction and Maintenance Manual Limitorque Type
SMB
V-EC-1658-A
Risk Ranking Approach for Motor-Operated Valves in
Response to Generic Letter 96-05
Operability
Evaluations
Overhaul of Limitorque SMB 000 & SB/SMB 00 Actuators
Procedures
Limitorque Valve Operator Model SMB/SB/SBD-000
014
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
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
20
202.012
Repetitive Tasks
2
203.031
Reactor Coolant Pump and Motor
030
2104.039
HPSI System Operation
089
Air Operated Valve Program
PRA Maintenance and Update
008
System and Component Monitoring
AOV Setpoint Control, Signature Analysis and Trending
Evaluation
Engineering Methodologies for Design Basis Review
(DBR) of Air Operated Valves (AOV)
MOV Thrust / Torque Setpoint Calculations
MOV Periodic Verification
006
Motor Operated Valve (MOV) Test Data Review
Component Performance Monitoring
EN-FAP-OM-023
Entergy Nuclear Change Management
Use of Viper or Votes Infinity Air Operator Valve
Diagnostics
Use of VIPER or VOTES Infinity Motor Operated Valve
Diagnostics
Overhaul of Limitorque SMB/SB 0 through 4 Actuators
EN-NE-G-026
Probabilistic Safety Assessment Applications
Time Critical Action/Time Sensitive Action Program
Standard
003
SEP-ANO-AOV-
001
ANO Air Operated Valve (AOV) Program
003
Work Orders
00191635,
00305896,
2747407,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2788661,
2503522,
2734618,
00351269,
2844560,
2847673,
2776215,
00469259,
2508165,
00487569,
2579157,
2770428,
00409632,
2874938,
00345709,
2485066,
2805186