IR 05000390/2020011

Design Basis Assurance Inspection (Programs) Inspection Report 05000390/2020011 and 05000391/2020011

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

ber 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: NPF-90 and NPF-96 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.21N.02 Calculations 048-018-MSS System Level Review for Watts Bar Main Steam Rev. 1

Supply System Air Operated Valves

048-018-PIL Evaluation of Required Thrust for MSIVs and SG- Rev. 1

PORVs (Pilot-Operated Balanced Disk Globe

AOVs) at Watts Bar Nuclear Power Station

25402-011-V1E-SS00- EPRI MOV PPM Analysis for 4 Butterfly MOVs for Rev. 2

00001-002 Compliance with GL 89-10 MOV Program

Requirements for Units 1 and 2, Document No.

2914C

CGACQ1304 Weak Link Analysis for 8-150# Posi Seal Butterfly Rev. 1

Valves Mark# 17W586-1

EDQ00099920070002 AC Auxiliary Power System Analysis Rev. 73

EPMCPH060292 Documentation of MOV Design Basis Review and Rev. 6

Thrust/Torque Requirements and Valve and

Actuator Capability Assessment for Valve 1-FCV-

2-2

EPMDTN051192 Documentation of Design Basis Review, Required Rev. 6

Torque Calculations, and Valve and Actuator

Capability Assessment for Valve 1-FCV-67-67

EPMTSS117091 Generic Letter 89-10 MOV Population at Watts Bar Rev. 28

(Unit 1)

EPTMSS100292 Documentation of Design Basis Review, Required Rev. 7

Thrust/Torque Calculations, and Valve and Actuator

Capability Assessment for Valve 1-FCV-01-051

MDN-000-999-2011- WBN Probabilistic Risk Assessment - Risk Ranking Rev. 2

0178 of Motor Operated Valves

MDN-000-999-2011- WBN Probabilistic Risk Assessment - Risk Ranking Rev. 1

0179 of Air Operated Valves (AOV)

MDQ00099920010063 Categorization of the Air Operated Valves (AOVs) Rev. 7

MDQ00100120020072 Component Level Review Calculation for Watts Bar Rev. 5

Main Steam Supply (MSS) System Pilot-Operated

Balanced Disk Globe Air Operated Valves (AOVs)

Inspection Type Designation Description or Title Revision or

Procedure Date

MDQ00199920100167 Watts Bar Nuclear Plant JOG MOV Periodic Rev 5

Verification Classification

MDQ0020622008-0226 Documentation of Design Basis Review Required Rev. 5

Thrust/Torque Calculations and Valve and Actuator

Capability Assessment for Valve 2-LCV-62-135

MDQ0020632008-0244 Documentation of Design Basis Review, Required Rev. 9

Thrust/Torque Calculations and Actuator Capability

Assessment for Valve 2-FCV-63-093

MDQ0020682008-0274 Documentation of Design Review Basis Review, Rev. 4

Required Thrust/Torque Calculations and Valve and

Actuator Capability Assessment for Valve 2-FCV-

68-332

MDQ0029992009-0310 Generic Letter 89-10 MOV Population for Watts Bar Rev. 10

(Unit 2)

MDQ0029992015000687 Watts Bar Nuclear Plant Unit 2 JOG MOV Periodic Rev. 0

Verification Classification

QDC0029992014000504 Material Aging Calculation for Unit 1 and 2 Rev. 11

Mechanical Equipment Qualification (Binder WBN-

MEQ-001)

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 Rev. 6

Located in the Valve Vaults During a MSLB

WBT-D-4037 Summary of Seismic Analysis of 8GM78FN Built to 08/29/2012

Drawing 115E012 at Watts Bar Unit 2

Corrective Action CRs 1093165, 1195979,

Documents 1601458, 1624132,

25963

Corrective Action CR 1639485 2020 NRC POV Inspection - PM frequency change 09/23/2020

Documents needed

Resulting from CR 1634592 2020 NRC POV Inspection - procedure typo in 09/03/2020

Inspection rev.log reference

CR 1634666 2020 NRC POV Inspection - Correct reference in 09/03/2020

Section 7.1.9 of calculation EPMDTN051192

Inspection Type Designation Description or Title Revision or

Procedure Date

CR 1634871 2020 NRC POV Inspection - Administrative Error in 09/03/2020

EDQ00099920070002 Appendix 10.9

CR 1635223 2020 NRC POV Inspection - Calculation 09/08/2020

EPMTSS100292 reference omission and input

clarification

CR 1636100 2020 POV NRC Inspection - Correct typographical 09/08/2020

error for Reference 3 on pdf page 730 (actual calcul

CR 1636444 2020 NRC POV Inspection - Document critical 09/14/2020

thinking associated with Section XI repairs

CR 1637673 2020 NRC POV Inspection - Additional 09/17/2020

Documentation of Critical Thinking for Section XI

Repairs.

CR 1638837 2020 NRC POV Inspection - MOV PV thrust test 09/21/2020

data for 1-FCV-1-51 suspected unreliable

CR 1639066 2020 NRC POV Inspection - missing 09/21/2020

evaluation/justification of not obtaining AF torque

values

CR 1639626 2020 NRC POV Inspection - QMDS requirements 09/23/2020

do not match Vendor Manual

CR 1639697 2020 NRC POV Inspection Performance Deficiency 09/24/2020

CR 1639749 2020 NRC POV Inspection - Delete o-ring 09/24/2020

replacement

Drawings 0-47W845-1 Mechanical Flow Diagram-Essential Raw Cooling Rev. 19

Water System

1-47A595-3 Set-Up Parameters for Air Operated Valves Setup Rev. 2

Box for 1-FCV-001-0022-T

1-47A8910-72-01 Mechanical Table of Motor-Operated Valve Rev. 3

Requirements

1071240-7 Solenoid Operated Valve Energize to Open (FC) - Rev. G

ON/OFF 2 1/2 - 4 Inch

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 Type Designation Description or Title Revision or

Procedure Date

Miscellaneous ESBU/WOG-96-022 Summary of January 4 & 5, 1996 Pressure Locking 01/19/1996

& Thermal Binding (PLTB) Task Team Meeting

(MUHP-6050)

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 Reactor Coolant System Rev. 43

WB-DC-30-15 Motor Operated Valve Thermal Overload and Rev. 6

Torque Switch Bypass

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 Rev. 7

Operated Valves

WBN-VTD-T020-0520 Target Rock Technical Manual for Calve Models Rev. 1

2AB-001-4BB, 82AB-001-5BB

WBN-VTD-T401-0010 Teledyne Test Services Quiklook II Valve Rev. 1

Diagnostic Test Equipment Description, Safety

Related Status, Accuracy & Calibration Periodicity

Summary

WBNEQ-MOV-003 Limitorque Actuators with Class B Motors Rev. 37

WBNEQ-SOL-002 Target Rock Solenoid Valves Rev. 40

WBNMEQ-001-53006 Mechanical Equipment Qualification Package Rev. 2

WOG-05-87 Addendum to Verification of Pressure Locking 02/28/2005

Analysis Program - PRESLOK (CN-SEE-01-141)

Procedures 0-TI-100.006 Inservice Testing Program Rev. 9

1-SI-1-906-A Main Steam Valves Position Indication Verification - Rev. 13

Train A

1-SI-3-902 Turbine Driven Auxiliary Feedwater Pump 1A-S Rev. 59

Quarterly Performance Test

2-SI-68-901-B Valve Full Stroke Exercising During Plant Rev. 3

Operation: Reactor Coolant B-Train

2-TRI-0-4 18 Month B Train MOV Thermal Overload Relay Rev. 7

Bypass Circuit Functional Test

DS-M18.2.21 Motor Operated Valve Thrust and Torque Rev. 25

Inspection Type Designation Description or Title Revision or

Procedure Date

Calculations

G-50 Torque, Thrust and Control Switch Settings for Rev. 12

Motor-Operated Valves

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

9