IR 05000390/2021010
| ML21130A034 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/06/2021 |
| From: | James Baptist Division of Reactor Safety II |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2021010 | |
| Download: ML21130A034 (8) | |
Text
May 6, 2021
SUBJECT:
WATTS BAR - NRC INSPECTION REPORT 05000390/2021010 AND 05000391/2021010
Dear Mr. Barstow:
On April 1, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar. On April 1, 2021, the NRC inspectors 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:
05000390/2021010 and 05000391/2021010
Enterprise Identifier: I-2021-010-0037
Licensee:
Tennessee Valley Authority
Facility:
Watts Bar
Location:
Spring City, TN
Inspection Dates:
March 29, 2021 to April 1, 2021
Inspectors:
P. Braxton, Reactor Inspector
C. Even, Sr. Construction 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 NRC inspection at Watts Bar, 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 teleworking. 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
71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)
The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from March 29-April 1, 2021.
(1)50.59 Evaluation: DCN 59007 - Replace 1-PCV-003-0122 and -0132 with a Cavitating Venturi, 08/2018 (2)50.59 Screening: 0-SOI-24.01, Procedure Change Evaluation, 04/2016 (3)50.59 Evaluation: DCN 60696, Replace Pressurizer Power Operated Relief Valves, 01/2018 (4)50.59 Screening: DEC 66688-02, Emergency Diesel Generator Jacket Water Heat Exchanger Replacement, 02/2020 (5)50.59 Screening: DCN 66592, Raise Turbine-Driven Auxiliary Feedwater Pump Room DC Exhaust Fan Setpoints, 01/2018 (6)50.59 Screening: DCN 64545, Replace Obsolete Westinghouse Supplied 8" Fisher Butterfly Valve/Actuator for FCV-074-0016/-0028/-0032, 10/2015 (7)50.59 Screening: DECP 100447-02, Neutron Absorber Material Extraction and Coupon Tree Installation, 10/2019 (8)50.59 Evaluation: DCN 65847, Replace Obsolete Unit 1 Ronan Main Control Room Annunciator System, 07/2018 (9)50.59 Screening: DCN 63209, EQ Containment Sump Transmitters, 08/2017 (10)50.59 Evaluation: DCN 66360, Replace Aux Building Vent, Upper and Lower Containment Radiation Monitors, 11/2018 (11)50.59 Screening: DCN 65893, Replace ESF Room Cooler Coils, 12/2016 (12)50.59 Screening: SCN 66388, Modify Damper to Add Access Openings for Inspection/Repair, 09/2016 (13)50.59 Screening: WBN-19-298, Unit 2 Containment Purge Isolation Logic Train B, 03/2019 (14)50.59 Screening: 0-SI-82-3, Procedure Change, 05/2020 (15)50.59 Screening: 2-ARI-131-137, Procedure Change, 04/2016 (16)50.59 Screening: WBN-18-016, Revise Calculation 2-LT-003-0043, 02/2019 (17)50.59 Screening: 0-SOI-264, Procedure Change, 10/2019 (18)50.59 Screening: 2-IMI-72.034, Procedure Change, 06/2019
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 1, 2021, the inspectors presented the NRC 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
71111.17T Calculations
EPMWJK041592
Instrument Safety Limits, Analytical Limits and Setpoints for
the Auxiliary Building HVAC System
Rev. 17
WBNAPS2022
WBN Fluid Transient Event Identification for the Residual
Heat Removal System (74)
Rev. 5
WBNAPS3078
Offsite and Control Room Dose due to a ECCS Leak
Outside Containment Following A LOCA
Rev. 10
WCG11816
Design Criteria Document for Watts Bar Rerack Project
Rev. 2
Corrective Action
Documents
Resulting from
Inspection
1681585
Miscellaneous
NRC Safety Evaluation, Watts Bar Nuclear Plant, Units 1
and 2-Issuance of Amendment
Regarding Revision to Watts Bar Nuclear Plant, Unit 2,
Technical Specification 4.2.1, "Fuel
Assemblies," and Watts Bar Nuclear Plant, Units 1 and 2,
Technical Specifications Related to Fuel
Storage (EPID L-2017-LLA-0427)
05/22/2019
Letter WAH-825
Westinghouse Recommendation to set Valve Stroke at 60
degrees
11/16/1990
27-6513-MTB-R-
MTF
Failure Mode, Effects and Criticality Analysis Report
Rev. 0
DCN 66397
Replace Unit 1 CRD Equipment Room Unitary Air
Conditioning Units 1A and 1B
Rev. A
Holtec Report No:
2177876
Licensing Report for the Criticality Safety Analysis of the
Watts Bar Nuclear Plant Spent Fuel Pool
Rev. 1
NISP-IP-ENG-001 Resource Manual for Standard Design Process
Rev. 0
SDD-N3-30AB-
4001
Auxiliary Building Heating Ventilation Air Conditioning
System
Rev. 47
SDD-N3-79-4001
Fuel Handling and Storage System
Rev. 24
SDD-NE-74-4001
Residual Heat Removal System
Rev. 20
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Annunciator Replacement System Procurement
Specification
Rev. 0
TVAWBN00085-
REPT-001
Watts Bar Nuclear (WBN) TDAFW Pump Room DC
Fan Setpoint Evaluation
Rev. 0
Procedures
0-SI-82-3
Loss of Offsite Power with Safety Injection-DG 1A-A
Rev. 73
0-SI-82-3
Loss Of Offsite Power with Safety Injection - DG 1A-A
Rev.74
0-SI-82-3
Loss Of Offsite Power with Safety Injection - DG 1A-A
Rev.75
0-SOI-24.01
Raw Cooling Water System
Rev. 16
2-ARI-131-137
Unit 2 Annunciator Response Instruction
Rev. 1
2-ARI-131-137
Unit 2 Annunciator Response Instruction
Rev. 2
2-ARI-131-137
Unit 2 Annunciator Response Instruction
Rev. 3
BTI-EEB-TI-28
Setpoint Calculations
Rev. 12
NPG-SPP-09.03
Plant Modifications and Engineering Change Control
Rev. 35
NPG-SPP-09.4
10.CFR 50.59 Evaluations of Changes, Tests, and
Experiments
Rev. 15
Work Orders
114522058
116154307
116550503
119077439,