IR 05000390/2021010

NRC Inspection Report 05000390/2021010 and 05000391/2021010

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: NPF-90 and NPF-96 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 Enclosure

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 Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations EPMWJK041592 Instrument Safety Limits, Analytical Limits and Setpoints for Rev. 17

the Auxiliary Building HVAC System

WBNAPS2022 WBN Fluid Transient Event Identification for the Residual Rev. 5

Heat Removal System (74)

WBNAPS3078 Offsite and Control Room Dose due to a ECCS Leak Rev. 10

Outside Containment Following A LOCA

WCG11816 Design Criteria Document for Watts Bar Rerack Project Rev. 2

Corrective Action 1681585

Documents

Resulting from

Inspection

Miscellaneous NRC Safety Evaluation, Watts Bar Nuclear Plant, Units 1 05/22/2019

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)

Westinghouse Westinghouse Recommendation to set Valve Stroke at 60 11/16/1990

Letter WAH-825 degrees

27-6513-MTB-R- Failure Mode, Effects and Criticality Analysis Report Rev. 0

MTF

DCN 66397 Replace Unit 1 CRD Equipment Room Unitary Air Rev. A

Conditioning Units 1A and 1B

Holtec Report No: Licensing Report for the Criticality Safety Analysis of the Rev. 1

2177876 Watts Bar Nuclear Plant Spent Fuel Pool

NISP-IP-ENG-001 Resource Manual for Standard Design Process Rev. 0

SDD-N3-30AB- Auxiliary Building Heating Ventilation Air Conditioning Rev. 47

4001 System

SDD-N3-79-4001 Fuel Handling and Storage System Rev. 24

SDD-NE-74-4001 Residual Heat Removal System Rev. 20

Inspection Type Designation Description or Title Revision or

Procedure Date

SP-65847-002 Annunciator Replacement System Procurement Rev. 0

Specification

TVAWBN00085- Watts Bar Nuclear (WBN) TDAFW Pump Room DC Rev. 0

REPT-001 Fan Setpoint Evaluation

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 Rev. 15

Experiments

Work Orders 114522058

116154307

116550503

119077439,

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