IR 05000327/2024010
| ML24352A161 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/19/2024 |
| From: | Masters A NRC/RGN-II/DORS |
| To: | Erb D Tennessee Valley Authority |
| References | |
| IR 2024010 | |
| Download: ML24352A161 (1) | |
Text
SUBJECT:
SEQUOYAH UNITS 1 AND 2 - DESIGN BASIS ASSURANCE INSPECTION (PROGRAMS) INSPECTION REPORT 05000327/2024010 AND 05000328/2024010
Dear Delson Erb:
On November 20, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Sequoyah Units 1 and 2 and discussed the results of this inspection with Tom Marshall, Site Vice President 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, Anthony D. Masters, Chief Engineering Branch 1 Division of Operating Reactor Safety Docket Nos. 05000327 and 05000328 License Nos. DPR-77 and DPR-79
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000327 and 05000328
License Numbers:
Report Numbers:
05000327/2024010 and 05000328/2024010
Enterprise Identifier:
I-2024-010-0048
Licensee:
Tennessee Valley Authority
Facility:
Sequoyah Units 1 and 2
Location:
Soddy-Daisy, TN
Inspection Dates:
November 04, 2024 to November 20, 2024
Inspectors:
P. Braxton, Reactor Inspector
J. Copeland, Reactor Inspector
A. Ruh, Senior Resident Inspector
Approved By:
Anthony D. Masters, Chief
Engineering Branch 1
Division of Operating 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 Sequoyah 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.
REACTOR SAFETY
===71111.21N.03 - Commercial Grade Dedication The inspectors reviewed the implementation of the licensees processes for dedicating commercial-grade items/services as basic components and/or for procuring safety-related structures, systems, and components for the following samples:
Commercial Grade Dedication===
- (1) Thermal overload relay, safety injection pump flow control valve (CAA979N) (QA2),
- (2) Drive belt, control room air handling unit (CAM866B) (QA2), WO 123172639
- (3) Flexible coupling, essential raw cooling water strainer (DAY447A, DAY446C, DAX918D) (QA2), WO 122596737
- (4) Terminal board, main steam header isolation (CBD133T) (QA2), WO 121952165
- (5) Thermostatic expansion valve, electric board room chiller (DAC624B) (QA2), WO 120284596
- (6) Capacitor, Eagle 21 process protection system power supply (CHP955N) (QA2), WO 122408274
- (7) Fast acting fuse, Spare 120V AC Vital Inverter 0-II (BVM483R) (QA2), WO 122503134
- (8) Pneumatic damper actuator, electric board room air handling unit (DAL895D) (QA2),
- (9) Lubricating oil (CAT418D) (QA2), WO 117812721
- (10) Circuit breaker, 120V AC vital instrument power board 1-IV (CNF467E) (QA1), WO 122167444
- (11) Fuse block holder, reactor vessel head vent throttle valve (DAL875K) (QA1), WO 120662966
- (12) Solenoid valve, main steam header isolation (CBC720V) (QA1), WO 120831726
- (13) Temperature transmitter, auxiliary building high energy line break detection (CYX872B) (QA1), WO 119350135
- (14) Cap screw, auxiliary feedwater flow control valve diaphragm screw (DBG631K)
(QA1), WO
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 20, 2024, the inspectors presented the design basis assurance inspection (programs) inspection results to Tom Marshall, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
1817497,
1818804,
1836301,
1876471,
1494054,
1592594,
1818920,
1631916,
1661993
1970989
SQN CGDI 2024010: Selection of M&TE with Appropriate
Ranges
1972101
WO 119350135 administrative issues
1973677
NRC Observation on Appropriate CCs for Setscrews
Provided with Other Components
Corrective Action
Documents
Resulting from
Inspection
1973778
NRC SQN CGDI 2024010: PD V-Belt Critical
Characteristic Tolerances
011507-225
Control Valve 4" Model 37-20721 ANSI Class 900 Flanged
Ends #24 Direct Actuator
C
1,2-014D17734
KVA Inverter, 100-140VDC, 120VAC, 60 Hz, 1Ø
1,2-21245H-3
Cylinder Mounted Panel Board for 32' Mian Steam Bore
Isolation Valve
1,2-45N601-5
Wiring Diagrams-Main Steam System, Sheet 5
1,2-45N601-6
Wiring Diagram Main Steam, Sheet 6
1,2-45N706-4
Wiring Diagram 120V AC Vital Instrument Power Boards 1-
IV & 2-IV Connection Diagram Sheet-Sheet 4
1,2-45N751-5
Wiring Diagram-480V Reactor MOV BD 1B1-B, Single
Line, Sheet 1
1,2-47W865-7
Flow Diagram Air Conditioning Refrigerant Flow
1-45B793-60
Non-1E Loads Powered from Class 1 E Ac/DC Power
Systems
71111.21N.03
Drawings
1-45N1630-59
Wiring Diagram Miscellaneous Valves Connection
Diagram, Sheet 59
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
SQN-23-054
Allow Installation of Larger Actuator Stem Nut Washer for
the 4" Motor Driven Auxiliary Feedwater - Steam
Generator Level Control Valves
07052400M3
Safety Related Molded Case circuit Breakers
16904M0
Moore Industries RTD transmitters for MCR Panel 2-M-23,
with seismic, mild environment, and EMI/RFI qualification
requirements, third party qualification
19801-SQNM0
Valve, expansion, QA 2
29690M0
Bussman Time delay fuse and fuse block
29715-SQNM0
ACTUATOR, PISTON TYPE, PNEUMATIC,
CONDITIONALLY DEDICATED
CAP-EAGLE-21
Capacitor
2/07/2019
CPEGM-2-00048
Fuse Cartridge 1E
CPEGM-2-00071
Relay, (All Types)- General Purpose
CPEGM-2-
VBELT
V-belts from Carlisle / Timken-By Method-1 dedication
G5305-1-1263
Fasteners to various material specifications (AISI)
excluding ASME and ASTM specifications
G5940-2-046EQ
Terminal Blocks & Strips
G5945-1-641
MSIV Pilot Control Solenoid
G6105-2-1338A
Components for flexible coupling
G9150-2-065
GENERIC TE FOR INDUSTRIAL OILS/LUBRICANTS
(NON 10CFR50.49)
Engineering
Evaluations
SCRs 101841,
104440, 124791,
24807, 124844,
24855, 127053,
27069, 124974,
110777, 97954,
103662, 104230,
106041, 125179,
101879, 100170
Miscellaneous
4405934
Purchase Order: TRANSMITTER,TEMPERATURE, QA 1,
RTD, 117 V/ 50/60 HZ, 3 WIRE
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5669998
Purchase Order: LUBRICANT,OIL, QA 2, SYNTHESIZED
GAS TURBINE, DRUM, ISO VG-32
26479
Purchase Order: ACTUATOR,PNEUMATIC, QA 2,
6814210
Board, Terminal
7031586
Material Inspection Form: Capacitor
2/14/2022
7031586
TVA Purchase Order: CAPACITOR,ELECTRICAL
DEVICE, QA 2, ELECTROLYTIC, 33 MFD, (2) RADIAL
LEADS
10/17/2021
7362469,
7500762,
7384145,
7362469,
7598927,
5492515,
26479,
7031586,
5669998,
4405934
Material Inspection Form
7401043
Relay, Thermal, Overload
7475763
Fuse, One-Time, QA 2, Cartridge, Fast Acting, 250, 400,
10.6 K, 1-1/2 IN, 3-27/32 IN
5/22/2023
LIT-2681054P
Product Bulletin: D-3153 Pneumatic Actuator
03/12/2015
SQN-VTD-G080-
1150
General Electric Terminal Boards
SQN-VTD-M120-
1610
Masoneilan International Spring-Diaphragm Actuator
Instructions
SQN-VTD-S250-
0040
Parts Lists and Drawings for Solidstate Controls, Inc.
Inverters 0-I, 0-III, and 0-IV
NDE Reports
240425-082017,
230615-150900,
200424-131915
Lab Test Reports
Procedures
0-TI-PMT-000-
000.0
Pre-Post Maintenance Testing Matrices
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NEDP-8.0
Evaluations for Procurement of Materials, Items, and
Services
NPG-SPP-06.3
Pre-/Post-Maintenance Testing
P.S.4.M.1.5
CLASSIFICATION, PROCUREMENT, RECEIPT AND
USE OF LUBRICANTS
SQN-DC-V-
11.4.1
Normal and Emergency AC Auxiliary Power Systems
SQN-DC-V-27.3
Safety Injection System
SQN-DC-V-4.1.1
Main Steam System
SQN-DC-V-40.0
Seismic/Structural Qualification of Seismic Category I,
Electrical and Mechanical Equipment
SQN-DC-V.11.6
20 -V AC Vital Instrument Power System
1912037
Self-Assessment for the NRC CGD Inspection at SQN
03/28/2024
2018N-46
TVA Audit/Survey: Nuclear safety-related commercial-
grade dedication, product qualification, manufacturing and
supporting engineering services.
08/16/2018
Self-
Assessments
Audit Report
SSA2403
Materials Management and Procurement Engineering
Sequoyah Nuclear Plant (SQN)
06/11/2024
117812721
Replace Motor with refurbished spare to support Long
Range Outage Plan
09/23/2021
Work Orders
21543475
SQN-0-FCO-311-0028 will not open on fan start
05/19/2021