IR 05000327/2018010

NRC Evaluation of Changes, Tests, and Experiments Report Number 05000327/2018010 and 05000328/2018010

ML18170A074
Person / Time
Site:	Sequoyah
Issue date:	06/19/2018
From:	Marvin Sykes NRC/RGN-II
To:	James Shea Tennessee Valley Authority
References
IR 2018010
Download: ML18170A074 (7)

Text

June 19, 2018

SUBJECT:

SEQUOYAH NUCLEAR PLANT - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS REPORT NUMBER 05000327/2018010 AND 05000328/2018010

Dear Mr. Shea:

On June 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Plant, Units 1 and 2, and the NRC inspectors discussed the results of this inspection with Chris Reneau and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Marvin D. Sykes, Chief Engineering Branch 1 Division of Reactor Safety

Docket Nos. 50-327, 50-328 License Nos. DPR-77 and DPR-79

Enclosure:

Inspection Report 05000327/2018010 and 05000328/2018010

Inspection Report

Docket Numbers:

050000327, 05000328

License Numbers:

DPR-77 and DPR-79

Report Numbers:

05000327/2018010, 05000328/2018010

Licensee:

Tennessee Valley Authority

Facility:

Sequoyah Nuclear Plant Units 1 and 2

Location:

Soddy Daisy, TN

Inspection Dates:

June 4-8, 2018

Inspectors:

Bradley Davis, Reactor Inspector (Team Lead)

Marcus Riley, Reactor Inspector

Nadiyah Morgan, Reactor Inspector

Approved By:

M. Sykes, Chief

Engineering Branch 1

Division of Reactor Safety

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Tennessee Valley

Authoritys performance by conducting a 10 CFR 50.59 inspection at Sequoyah 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.

No findings or more than minor violations were identified.

INSPECTION SCOPE

Inspections were conducted using the appropriate portions of the inspection procedure (IP) 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, conducted walkdowns 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

The inspectors evaluated the following samples for compliance with Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, from June 4, 2018, to June 8, 2018:

10 CFR 50.59 Evaluations - 71111.17T

1. Design Change Notice (DCN) 23343, Identify Design Basis Flood Barriers for the Shield

Buildings

3. DCN 23396, Issue Design Output Portion of the Emergency Operating Procedure

Setpoint Calculation SQS20110

5. DCN 23364, Replace Obsolete parts of Exo Sensor Incore Thermocouple Monitoring

System

6. DCN 23527, Replacement of 125V DC Vital Battery Charges II, III, and IV

10 CFR 50.59 Screening/Applicability Determinations - 71111.17T

7. DCN 23234, Replace Relief Valves for Essential Raw Cooling Water, Component

Cooling, and Containment Spray Systems

8. DCN 23623, Degraded Non-Conforming Motor Operated Valve (MOV) Modifications -

Gears/Actuator/Motor/Cables Reroute

9. DCN 21192, Generic ASCO Solenoid Valve Replacement

10. DCN 22778-01, Install Motor Driven Auxiliary Feedwater Pump 1A-A Relief Valve (SQN-1-VLV-003-0908-A) and Motor Driven Auxiliary Feedwater Pump 18-B Relief Valve ( SQ N-1 -VL V-003-0909-B)11. DCN 22778-02, Install Turbine Driven Auxiliary Feedwater Pump 1A-S Relief Valve (SQN-1-VLV-003-0910)12. DCN 23353, Replacement of Penetration 1-PENE-302-0009-B and Removal from Equipment Qualification (EQ) Program of Penetrations 1-PENE-302-0226-S and 1-PENE-302-0040-S 13. DCN 23056, Mark Emergency Diesel Generator (EDG) Lube Oil Dipstick to Indicate 6-Day & 7-Day Volumes 14. DCN 21892-03, Install a Current Control Unit on 2-FSV-43-61 15. DCN 23270, Replace MOV Motors for 1-FCV-3-47, 1-FCV-3-87, 1-FCV-3-100 & 2-FCV-3-33 16. DCN 23372, Replace Unit 2 Pressurizer Heater Transformers 17. DCN 23609, Replacement of EQ Containment Sump Level Transmitters 18. DCN23733, Remove Crankcase Pressure Switch Trip Function from EDGs 1A-A, 1B-B, 2A-A, 2B-B

EXIT MEETINGS AND DEBRIEFS

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

On June 8, 2018, the inspectors presented the inspection results to Mr. Chris Reneau, and other members of the licensee staff.

DOCUMENTS REVIEWED

Procedures

IP-ENG-001, Nuclear Standard Design Process, Rev. 0

0-SI-SXV-000-264.0, Testing Setpoint of ASME Code Class 2 & 3 Safety and Relief Valves and

Vacuum Breakers, Rev. 15

0-AR-DG-1A-LCL, Diesel Generator 1A-A Local Panel, Rev. 22

0-SI-SLT-000-257.0, Type B Local Leak Rate Test, Rev. 15

ES-1.3, Transfer to RHR Containment Sump, Rev. 23

NPG-SPP-03.15, FSAR Management, Rev. 2

NPG-SPP-09.4, 10 CFR 50.59 Evaluations of Changes Tests and Experiments, Rev. 12

NPG-SPP-09.3, Plant Modifications and Engineering Change Control, Rev. 28

NPG-SPP-09.5, Temporary Modifications and Temporary Configuration Changes, Rev. 13

NPG-SPP-12.7, Computer Software Control, Rev. 8

Drawings

1,2-47W450-3, Mechanical - Essential Raw Cooling Water, Rev. 23

1,2-45N703-2, 125 VDC Vital Battery Board II Single Line - Sheet 2, Rev. 42

1,2-45N767-10, Schematic Alarm for Engine 1A1, Rev. 6

1,2-45N767-2, 6900V Diesel Generators Schematic Diagram - Sh 2, Rev. 35

1,2-45N767-9, Schematic Alarm for Engine 1A2, Rev. 8

1,2-47W803-1, Feedwater Flow Diagram, Rev. 116

1,2-47W881-5-1, Mechanical Flow Diagram Water Quality and Sampling System, Rev. 15

2-45N724-3, 6900V Shutdown Board 2A-A Single Line Wiring Diagrams, Rev. 28

Calculations

03D53EPMRJP030491, Documentation of Design Bases Review, Required Thrust Calc and

Valve and Actuator Capability Assessment for 1-FCV-03-047, Rev. 8

03D53EPMRJP030591, Documentation of Design Bases Review, Required Thrust Calc and

Valve and Actuator Capability Assessment for 1-FCV-03-087, Rev. 8

03D53EPMRJP030691, Documentation of Design Bases Review, Required Thrust Calc and

Valve and Actuator Capability Assessment for 1-FCV-03-100, Rev. 8

B87150730001, Purge Air Ductwork Qualification for Hydrostatic Pressure, Rev. 2

B8790051027, Compute the Blowout Capacity of Blowout Plugs in the West Steam Valve

Room, Rev. 1

B87900822005, Blow-out Plugs - West Main Steam Valve Room - Reliability Study of as Built

Condition and Mod. Recommendations

B87910809021, Dynamic Analysis of Blow-Away Roofs and Hatches of East and West Main

Steam Valve Vault Panels

B87930202006, Main Steam Valve Vault Subcompartment Pressure Analysis, Rev. 2

E31880203208, Shutdown Board 1A-A 480V Transformers (500KVA), Rev. 2

EDQ0000942016000322, Incore Thermal Monitoring System Software Quality Assurance

Documentation, Rev. 1

EDQ0002502013000067, 125V DC Vital Battery Charger I, II, III, IV - Power Relays, Rev. 1

MDQ0000032015000278, Auxiliary Feedwater Pump Alternative Min-flow Relief Valve Sizing,

Rev. 0

MDQ0000822014000219, Diesel Generator Lube Oil Volume for 6 and 7 Days of Operation,

Rev. 0

NDQ0063980038, RWST and Containment RHR Sump Safety and Operational Limits, RWST

Setpoint Required Accurary and LBLOCA Sump Minimum Levels, Rev. 17

OE2-DS196RP, Containment, Electrical Penetration Protection Analysis, Rev. 29

SQEQ-PENE-004, Westinghouse Canister Electrical Penetrations (LVP/C&I), Rev. 60

SQEQ-PENE-005, Conax Electrical Penetrations (LVP/C&I), Rev. 40

SQN-APS-003, 480VAC APS Class 1E Load Coordination Study, Rev. 100

SQN-CPS-051, Circuit Protection Device Evaluation, Rev. 65

SQN-EEB-MS-TI28-0010, Instrument Accuracy Calc 1-LT-63-176, 177, 178, 179 Containment

Sump Level Indication, Rev. 11

SQN-EEB-MS-TI28-0013, Instrument Accuracy Calc 1-LT-63-176, 177, 178, 179 Containment

Sump Switchover, Rev. 15

SQNETAPAC, Auxiliary Power System, Rev. 84

SQS20110, Emergency and Abnormal Operating Procedure Setpoints, Rev. 27

CRs (Condition Reports)

117027

655763

934663

217684

Design Basis Documents

SQN-DC-V-13.9.8, Sequoyah Nuclear Plant - Auxiliary Feedwater System, Rev. 28

SQN-DC-V-13.9.9, Component Cooling Water System, Rev. 28

SQN-DC-V-21.0, Environmental Design, Rev. 27

SQN-DC-V-27.5, Containment Spray System, Rev. 18

SQN-DC-V-3.0, The Classification of Piping, Pumps, Valves, and Vessels, Rev. 21

Work Orders

05-780558-004

05-780558-003

113312349

113312355

113312383

114611700

115790860

116101146

116690396

117063742

117063744

117094249

117214605

117214614

117214618

117214627

117918755

117918862

117918863

117918865

118175904

118514454

Miscellaneous Documents

Critical Digital Review Fisher DVC6000 Series Digital Valve Controller for TVA 025-

N230353335, Rev. A

DG-E18.1.25, Digital System Develop System Development, Procurement, and Implementation,

Rev. 4

DS-E18.1.25.4, Design for Simple Digital Device Determination, Rev. 3

DS-E18.1.25.8, Cyber Hardening for Digital Devices, Rev. 1

Engineering Change Turnover Package for ECP 23234-07, Replace 1-VLV-067-01590A,

2/29/2015

Engineering Change Turnover Package for ECP 23623-04, RHR HTX B to SIS Pumps,

4/26/2018

EQ14-0774, Evaluation of Conduit Plug Kits and Materials, 2/2/2015

LTR-SCS-17-2, Sequoyah Units 1&2 Main Feedwater Valve Stroke Time Increase - NSSS

Design Transients and Plant Operability Evaluation, 1/6/2017

NPG-SPP-09.2, Equipment Environmental Qualification Program, Rev. 10

PIC 23687, Sleeve #106 Seal Detail Change, Rev. 0

SQN Auxiliary Feedwater System Feasibility Study for Min-Flow Design Pressure Increase,

11/11/2015

SQNEQ-XMTR-009, Rosemount Model 3155N Transmitters Tab D, Rev. 0

SS-E18.15.01, Requirement for Digital Systems (Real-Time Data Acquisition and Control

Computer Systems), Rev. 8

Triconex Approved Topical Report 7286-545-1-A, Rev. 4

Corrective Action Documents Written as a Result of the Inspection

CR 1421144, Vital Charger Maintenance Strategy Gap

CR 1421232, Drawing Note Discrepancy for Battery Charger Limiting Amperage