IR 05000390/2020011
| ML20294A260 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/20/2020 |
| From: | James Baptist NRC/RGN-II/DRS/EB1 |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2020011 | |
| Download: ML20294A260 (11) | |
Text
October 20, 2020
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000390/2020011 AND 05000391/2020011
Dear Mr. Barstow:
On September 24, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar Nuclear Plant, Units 1 and 2 and discussed the results of this inspection with Mr. Anthony Williams 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. 05000390 and 05000391 License Nos. NPF-90 and NPF-96
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000390 and 05000391
License Numbers:
Report Numbers:
05000390/2020011 and 05000391/2020011
Enterprise Identifier: I-2020-011-0042
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar Nuclear Plant, Units 1 and 2
Location:
Spring City, TN
Inspection Dates:
August 31, 2020 to September 24, 2020
Inspectors:
P. Carman, Senior Reactor Inspector
M. Greenleaf, Reactor Inspector
N. Morgan, 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 design basis assurance inspection (programs) inspection at Watts Bar Nuclear Plant, Units 1 and 2, 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
71111.21N.02 - Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements POV Review (IP Section 03)
The inspectors:
a. Evaluated whether the sampled POVs are being tested and maintained in accordance with NRC regulations along with the licensees commitments and/or licensing bases.
b. Evaluated whether the sampled POVs are capable of performing their design-basis functions.
c. Evaluated 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)1-FCV-1-51-S, Turbine-Driven Auxiliary Feedwater Pump Trip and Throttle Valve (2)1-FCV-67-67-B, Diesel Generator Heat Exchanger 1B1/1B2 Essential Raw Cooling Water Supply Header 1B Isolation Valve (3)1-FCV-72-2-B, Containment Spray Header (Train B) Isolation Valve (4)2-FCV-63-93-A, Residual Heat Removal to Cold Leg 2 & 3 Injection Isolation Valve (5)2-FCV-68-332-B, Pressurizer Power-Operated Relief Valve (PORV) Block Valve (6)2-LCV-62-135-A, Refueling Water Storage Tank Chemical and Volume Control System Supply Header Isolation Valve (7)1-FCV-1-22-T, Main Steam Loop 3 Isolation Valve (8)1-PCV-1-5-T, Steam Generator Loop 1 PORV Valve (9)2-FCV-1-25-B, Steam Generator 3 Blowdown Isolation Valve
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 24, 2020, the inspectors presented the design basis assurance inspection (programs) inspection results to Mr. Anthony Williams and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.02 Calculations
048-018-MSS
System Level Review for Watts Bar Main Steam
Supply System Air Operated Valves
Rev. 1
048-018-PIL
Evaluation of Required Thrust for MSIVs and SG-
PORVs (Pilot-Operated Balanced Disk Globe
AOVs) at Watts Bar Nuclear Power Station
Rev. 1
25402-011-V1E-SS00-
00001-002
EPRI MOV PPM Analysis for 4 Butterfly MOVs for
Compliance with GL 89-10 MOV Program
Requirements for Units 1 and 2, Document No.
2914C
Rev. 2
CGACQ1304
Weak Link Analysis for 8-150# Posi Seal Butterfly
Valves Mark# 17W586-1
Rev. 1
EDQ00099920070002
AC Auxiliary Power System Analysis
Rev. 73
EPMCPH060292
Documentation of MOV Design Basis Review and
Thrust/Torque Requirements and Valve and
Actuator Capability Assessment for Valve 1-FCV-
2-2
Rev. 6
EPMDTN051192
Documentation of Design Basis Review, Required
Torque Calculations, and Valve and Actuator
Capability Assessment for Valve 1-FCV-67-67
Rev. 6
EPMTSS117091
Generic Letter 89-10 MOV Population at Watts Bar
(Unit 1)
Rev. 28
EPTMSS100292
Documentation of Design Basis Review, Required
Thrust/Torque Calculations, and Valve and Actuator
Capability Assessment for Valve 1-FCV-01-051
Rev. 7
MDN-000-999-2011-
0178
WBN Probabilistic Risk Assessment - Risk Ranking
of Motor Operated Valves
Rev. 2
MDN-000-999-2011-
0179
WBN Probabilistic Risk Assessment - Risk Ranking
of Air Operated Valves (AOV)
Rev. 1
MDQ00099920010063
Categorization of the Air Operated Valves (AOVs)
Rev. 7
MDQ00100120020072
Component Level Review Calculation for Watts Bar
Main Steam Supply (MSS) System Pilot-Operated
Balanced Disk Globe Air Operated Valves (AOVs)
Rev. 5
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
MDQ00199920100167
Watts Bar Nuclear Plant JOG MOV Periodic
Verification Classification
Rev 5
MDQ0020622008-0226
Documentation of Design Basis Review Required
Thrust/Torque Calculations and Valve and Actuator
Capability Assessment for Valve 2-LCV-62-135
Rev. 5
MDQ0020632008-0244
Documentation of Design Basis Review, Required
Thrust/Torque Calculations and Actuator Capability
Assessment for Valve 2-FCV-63-093
Rev. 9
MDQ0020682008-0274
Documentation of Design Review Basis Review,
Required Thrust/Torque Calculations and Valve and
Actuator Capability Assessment for Valve 2-FCV-
68-332
Rev. 4
MDQ0029992009-0310
Generic Letter 89-10 MOV Population for Watts Bar
(Unit 2)
Rev. 10
MDQ0029992015000687 Watts Bar Nuclear Plant Unit 2 JOG MOV Periodic
Verification Classification
Rev. 0
QDC0029992014000504
Material Aging Calculation for Unit 1 and 2
Mechanical Equipment Qualification (Binder WBN-
MEQ-001)
Rev. 11
WAT-D-8584
Maximum Allowable Thrusts
06/25/1991
WBN-EM-59
Essentially Mild Calculation for Limitorque Actuators Rev. 9
WBNOSG4159
Thermal Transient of Target Rock Solenoid Valves
Located in the Valve Vaults During a MSLB
Rev. 6
WBT-D-4037
Summary of Seismic Analysis of 8GM78FN Built to
Drawing 115E012 at Watts Bar Unit 2
08/29/2012
Corrective Action
Documents
CRs 1093165, 1195979,
1601458, 1624132,
25963
Corrective Action
Documents
Resulting from
Inspection
CR 1639485
20 NRC POV Inspection - PM frequency change
needed
09/23/2020
CR 1634592
20 NRC POV Inspection - procedure typo in
rev.log reference
09/03/2020
CR 1634666
20 NRC POV Inspection - Correct reference in
Section 7.1.9 of calculation EPMDTN051192
09/03/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR 1634871
20 NRC POV Inspection - Administrative Error in
EDQ00099920070002 Appendix 10.9
09/03/2020
CR 1635223
20 NRC POV Inspection - Calculation
EPMTSS100292 reference omission and input
clarification
09/08/2020
CR 1636100
20 POV NRC Inspection - Correct typographical
error for Reference 3 on pdf page 730 (actual calcul
09/08/2020
CR 1636444
20 NRC POV Inspection - Document critical
thinking associated with Section XI repairs
09/14/2020
CR 1637673
20 NRC POV Inspection - Additional
Documentation of Critical Thinking for Section XI
Repairs.
09/17/2020
CR 1638837
20 NRC POV Inspection - MOV PV thrust test
data for 1-FCV-1-51 suspected unreliable
09/21/2020
CR 1639066
20 NRC POV Inspection - missing
evaluation/justification of not obtaining AF torque
values
09/21/2020
CR 1639626
20 NRC POV Inspection - QMDS requirements
do not match Vendor Manual
09/23/2020
CR 1639697
20 NRC POV Inspection Performance Deficiency
09/24/2020
CR 1639749
20 NRC POV Inspection - Delete o-ring
replacement
09/24/2020
Drawings
0-47W845-1
Mechanical Flow Diagram-Essential Raw Cooling
Water System
Rev. 19
1-47A595-3
Set-Up Parameters for Air Operated Valves Setup
Box for 1-FCV-001-0022-T
Rev. 2
1-47A8910-72-01
Mechanical Table of Motor-Operated Valve
Requirements
Rev. 3
1071240-7
Solenoid Operated Valve Energize to Open (FC) -
ON/OFF 2 1/2 - 4 Inch
Rev. G
1167E80
Motor Op Gate Valve, MOD 10000GM82FBB00B
Rev. 903
2-47W813-1
Flow Diagram Reactor Coolant System
Rev. 39
2607
Electrical Assy
Rev. E
O-47W803-2
Rev. 9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
ESBU/WOG-96-022
Summary of January 4 & 5, 1996 Pressure Locking
& Thermal Binding (PLTB) Task Team Meeting
(MUHP-6050)
01/19/1996
SDD-N3-1-4002
Main Steam System
Rev. 22
SDD-N3-15-4002
Steam Generator Blowdown System Unit 1 / Unit 2
Rev. 19
SDD-N3-3B-4002
Auxiliary Feedwater System
Rev. 30
SDD-N3-68-4001
Rev. 43
WB-DC-30-15
Motor Operated Valve Thermal Overload and
Torque Switch Bypass
Rev. 6
WBN-SDD-N3-63-4001
Safety Injection System (Unit 1 / Unit 2)
Rev. 36
WBN-SDD-N3-67-4002
Essential Raw Cooling Water System, System 67
Rev. 38
WBN-VTD-C994-0010
Equipment Inaccuracy Summary for Motor
Operated Valves
Rev. 7
WBN-VTD-T020-0520
Target Rock Technical Manual for Calve Models
Rev. 1
WBN-VTD-T401-0010
Teledyne Test Services Quiklook II Valve
Diagnostic Test Equipment Description, Safety
Related Status, Accuracy & Calibration Periodicity
Summary
Rev. 1
WBNEQ-MOV-003
Limitorque Actuators with Class B Motors
Rev. 37
WBNEQ-SOL-002
Rev. 40
WBNMEQ-001-53006
Mechanical Equipment Qualification Package
Rev. 2
WOG-05-87
Addendum to Verification of Pressure Locking
Analysis Program - PRESLOK (CN-SEE-01-141)
2/28/2005
Procedures
0-TI-100.006
Inservice Testing Program
Rev. 9
1-SI-1-906-A
Main Steam Valves Position Indication Verification -
Train A
Rev. 13
1-SI-3-902
Turbine Driven Auxiliary Feedwater Pump 1A-S
Quarterly Performance Test
Rev. 59
2-SI-68-901-B
Valve Full Stroke Exercising During Plant
Operation: Reactor Coolant B-Train
Rev. 3
2-TRI-0-4
Month B Train MOV Thermal Overload Relay
Bypass Circuit Functional Test
Rev. 7
DS-M18.2.21
Motor Operated Valve Thrust and Torque
Rev. 25
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
G-50
Torque, Thrust and Control Switch Settings for
Motor-Operated Valves
Rev. 12
NPG-SPP-09.26.13
Air Operated Valve Program
Rev. 0
NPG-SPP-09.26.14
Motor Operated Valve Program
Rev. 4
Work Orders
114900760, 115264274,
116646007, 116986101,
117325065, 117404329,
117758092, 117625369,
117943531, 118294730,
118720661, 119064218,
119064767, 119473916,
119475391, 119526855,
119528673, 120241095,
20241347, 120295031,
20295726, 120498998,
20555952, 120557231,
20850611, 120850804,
21027350