IR 05000390/2021012

Biennial Problem Identification and Resolution Inspection Report 05000390/2021012 and 05000391/2021012

ML21182A036
Person / Time
Site:	Watts Bar
Issue date:	07/01/2021
From:	Tom Stephen NRC/RGN-II/DRP/RPB5
To:	Jim Barstow Tennessee Valley Authority
References
IR 2021012
Download: ML21182A036 (13)

Text

July 1, 2021

SUBJECT:

WATTS BAR NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000390/2021012 AND 05000391/2021012

Dear Mr. Barstow:

On May 21, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Watts Bar Nuclear Plant. On May 20, 2021 the NRC inspectors discussed the results of this inspection with Mr. Tony Williams and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.

Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.

Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.

Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

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/

Thomas A. Stephen, Chief Reactor Projects Branch #5 Division of Reactor Projects

Docket Nos. 05000390 and 05000391 License Nos. NPF-90 and NPF-96

Enclosure:

As stated

ML21182A036 X

SUNSI Review

X Non-Sensitive Sensitive

X Publicly Available Non-Publicly Available

OFFICE RII/DRP RII/DRP RII/DRP RII/DRP RII/DRP NAME S. Ninh R. Taylor K. Miller N. Childs T. Stephen DATE 6/29/2021 6/29/2021 6/29/2021 6/30/2021 7/1/2021

Enclosure

U.S. NUCLEAR REGULATORY COMMISSION

Inspection Report

Docket Numbers:

05000390 and 05000391

License Numbers:

NPF-90 and NPF-96

Report Numbers:

05000390/2021012 and 05000391/2021012

Licensee:

Tennessee Valley Authority

Facility:

Watts Bar Nuclear Plant

Location:

Spring City, TN

Inspection Dates:

May 03, 2021 to May 21, 2021

Inspectors:

N. Childs, Resident Inspector

K. Miller, Resident Inspector

S. Ninh, Senior Project Engineer

R. Taylor, Senior Project Engineer

Approved By:

Thomas A. Stephen, Chief

Reactor Projects Branch #5

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution inspection at Watts Bar Nuclear Plant, 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

Type Issue Number Title Report Section Status URI 05000391/2021012-01 2A-A CCS Pump Seal Bolting Failure 71152B Open

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 a 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.

OTHER ACTIVITIES - BASELINE

71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)

(1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.

• Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted an in-depth CAP review of the component cooling system (CCS), residual heat removal (RHR)system, and control room emergency ventilation system (CREVS).

• Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.

• Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.

INSPECTION RESULTS

Assessment 71152B Based on the samples reviewed, the team determined that the licensees corrective action program (CAP) complied with regulatory requirements and self-imposed standards. The licensees implementation of the CAP adequately supported nuclear safety.

1. Corrective Action Program Effectiveness

Problem Identification: The team determined that the licensee was generally effective in identifying problems and entering them into the CAP at the appropriate threshold. This conclusion was based on a review of the requirements for initiating condition reports (CRs) as described in licensee procedure NPG-SPP-22.300, Corrective Action Program, and the site's management expectation that employees were encouraged to initiate condition reports.

Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.

Problem Prioritization and Evaluation: Based on the review of CRs sampled by the inspection team during the onsite period, the inspectors concluded that problems were prioritized and evaluated in accordance with the CAP requirements described in procedure NPG-SPP-22.300. The inspectors determined that adequate consideration was given to system or component operability and associated plant risk. The inspectors determined that plant personnel had generally conducted cause evaluations in compliance with the licensees CAP procedures, including appropriate cause determinations, and performed adequate levels of analysis based on the significance of the issues being evaluated.

Effectiveness of Corrective Actions: Based on a review of corrective action documents, interviews with licensee staff, and verification of completed corrective actions, the inspectors determined that corrective actions were effective, timely, and commensurate with the safety significance of the issues. For significant conditions adverse to quality, the corrective actions directly addressed the cause and effectively prevented recurrence. The inspectors reviewed performance indicators, CRs, and effectiveness reviews, as applicable, to verify that the significant conditions adverse to quality had not recurred. Effectiveness reviews for corrective actions to preclude repetition (CAPRs) were sufficient to ensure corrective actions were properly implemented and were effective.

2. Use of Operating Experience (OE)

Based on a review of selected documentation related to OE issues, the team determined that the licensee was effective in screening operating experience for applicability to the plant.

Industry OE was evaluated at either the corporate or plant level depending on the source and type of document. Relevant information was then forwarded to the applicable department for further action or informational purposes. Operating Experience issues requiring action were entered into the CAP for tracking and closure. The team determined that the licensees use of industry and NRC OE was effective, and the program adequately supported nuclear safety.

3. Self-Assessments and Audits

The team determined that the scopes of assessments and audits were adequate. Self-assessments were generally detailed and critical. The team verified that CRs were created to document areas for improvement and findings resulting from self-assessments and verified that actions had been completed consistent with those recommendations. Audits of the quality assurance program appropriately assessed performance and identified areas for improvement. Generally, the licensee performed evaluations that were technically accurate.

4. Safety Conscious Work Environment (SCWE)

Based on interviews with plant staff and reviews of the employee concerns program, CRs, and the latest safety culture survey results, the inspectors found no evidence of challenges to the safety conscious work environment. It should be noted that this was the first biennial Problem Identification and Resolution (PI&R) inspection at Watts Bar since closure of the Chilling Effect Letter and the SCWE cross cutting issue. The safety culture appeared to be improved since the last PI&R and employees appeared willing to raise nuclear safety concerns through at least one of the several means available.

Unresolved Item (Open)2A-A CCS Pump Seal Bolting Failure URI 05000391/2021012-01 71152B

Description:

On May 5, 2021, during the CCS walkdown with the system engineer for the PI&R inspection, the inspector identified abnormal leakage coming from the 2A-A CCS pump inboard mechanical seal. Upon further investigation, the licensee identified that one of two inboard seal bolts was sheared/missing from the seal housing. The bolt was observed to be lying in the seal leak off catch basin. As a result of this observation, the licensee declared the 2A-A CCS pump inoperable at 5:10 p.m. on May 5, 2021 and entered technical specification (TS) limiting condition for operation (LCO) 3.7.7 which requires restoration of the pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. An unresolved item (URI) is opened for additional review to determine if appropriate regulatory requirements or self-imposed standards were followed for the maintenance of the 2A-A CCS pump (i.e., to determine the performance deficiency).

Planned Closure Actions: The Watts Bar resident inspectors will review the licensees evaluation of the issue and document the results in the quarterly integrated inspection report.

Licensee Actions: Work Order (WO) 122102466 replaced the sheared inboard seal bolt and the 2A-A CCS pump was declared operable at 1844 on May 6 after the work was completed. The licensee is currently evaluating the issue and extent of condition via CR 1701046.

Corrective Action References: CRs 1692049, 1692589, 1695509,

EXIT MEETINGS AND DEBRIEFS

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

• On May 20, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Tony Williams and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152B

Corrective Action

Documents

233275; 1244275; 1244348; 1244398; 1245056;

1332863; 1353102; 1413807; 1434751; 1446383;

1450336; 1450338; 1454882; 1474341; 1476614;

1482137; 1483352; 1486878; 1486882; 1487830;

1488848; 1488684; 1492565; 1498928; 1498934;

1499812; 1501943; 1501994; 1501945; 1507301;

1508964; 1510237; 1501946; 1502448; 1502633;

1502915; 1504014; 1504499; 1504520; 1506037;

1506341; 1510056; 1513326; 1515204; 1515390;

1516431; 1516485; 1516492; 1516494; 1516841;

1517359; 1520769; 1521049; 1521069; 1521317;

21319; 1521497; 1525654; 1525982; 1526540;

27359; 1527618; 1548617; 1549553; 1549554;

29382; 1531046; 1534909; 1540594; 1540598;

1540601; 1540603; 1542419; 1548549; 1555701;

1557359; 1558324; 1563492; 1566193; 1579238;

1571100; 1579250; 1585826; 1595410; 1597523;

1594403; 1602934; 1607003; 1608135; 1608980;

1609457; 1610611; 1612542; 1615444; 1616077;

1616698; 1618074; 1618544; 1620816; 1622991;

24008; 1636072; 1629687; 1631948; 1634062;

1634387; 1637007; 1640749; 1640903; 1641030;

1642981; 1643336; 1634387; 1644412; 1644413;

1647007; 1647416; 1653024; 1653032; 1654084;

1654091; 1660933; 1660938; 1661691; 1667128;

1667314; 1668321; 1669936; 1670127; 1670136;

1670795; 1670878; 1670960; 1670969; 1672352;

1672356; 1672357; 1672359; 1672462; 1672644;

1672655; 1673877; 1675314; 1677763; 1677999;

1679707; 1681286; 1688163; 1690437; 1690827;

1691621; 1691824; 1692049; 1693132; 1693260;

1693651; 1695509;

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Corrective Action

Documents

Resulting from

Inspection

1692049

WBN PI&R inspection - 2A CCS pump inboard mechanical

seal leakage

05/05/2021

1693132

WBN PI&R Inspection - P&IR Walkdown CREVs - Loose

Door Seal C50

05/11/2021

1693260

WBN P&IR Walkdown CREVs - Loose Door Seal C36

05/11/2021

1693624

WBN PI&R Inspection - Issues with CR summaries in CRs

1540603 and 1540601

05/12/2021

1695079

WBN PI&R Inspection - Page numbering issue with WBN-

VTD-D088-0020

05/19/2021

1695509

WBN PI&R Inspection - Legacy error in calculation

EPMDWP070594 for CCS Pump Seal Bolts

05/20/2021

1695529

WBN PI&R Inspection - URI on 2A CCS pump issues

05/20/2021

1695591

WBN PI&R Inspection - NRC Observation regarding EWR

associated with CR 292049

05/20/2021

Miscellaneous

Equipment Failure Investigation Checklist for CR 1597523,

Turbine Driven Auxiliary Feedwater Level Control Valve

Failed Quarterly Stroke Time Test

05/14/2020

Watts Bar Nuclear (WBN) Nuclear Safety Culture

Evaluation

09/01/2019

21 WBN Problem Identification and Resolution Self-

Assessment

Rev. 2

Organizational Effectiveness and Programmatic Checklist,

Potential non-compliance with NERC Standard VAR-002 -

4.1 Requirements

06/28/2019

Organizational Effectiveness and Programmatic Checklist,

Streaming Analysis of 2019 WBN Performance Based

Evaluation (PBE)

03/26/2020

Root Cause Analysis Report, Risk Management of the 2C

Unit Board Loss

Rev. 0

Root Cause Analysis Report, Unit 2 Turbine Generator

Exciter Failure

Rev. 0

Equipment Failure Investigation Checklist for CR 1669936,

Water in Upper Bearing Oil of ERCW Pump Motor

05/17/2020

Audit Report

Chemistry, Effluent, and Environmental Monitoring Watts

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SSA1906

Bar (WBN), June 03 - June 13, 2019

Engineering Work

Request no.

EWR18MEC030278

Evaluation for Loss of CRE Safety Function Due to MCR

Doors Open,

6/18/2018

Health Report

Scorecard

Air Conditioning/CREVS, Reporting Period: October 2018 -

March 2019

Health Report

Scorecard

Air Conditioning/CREVS, Reporting Period: Reporting

Period: April 2019 - September 2019

Health Report

Scorecard

Air Conditioning/CREVS, Reporting Period: Oct 1, 2019 to

March 31, 2020)

Health Report

Scorecard

Air Conditioning/CREVS, Reporting Period: April 1, 2020 to

Sept 30, 2020

Health Report

Scorecards

Component Cooling Water System (CCS): Fall 2019 -

Spring 2021

Pressure Boundary

Door Smoke Test

Door C036 Data Sheet

5/11/2021

Pressure Boundary

Door Smoke Test

Door C0350 Data Sheet

5/11/2021

SDD-N3-30CB-

4002

Control Building Heating, Ventilating, Air Conditioning, and

Air Cleanup System Unit 1/Unit 2

Rev. 21

Site Audit Report,

SSA1907

Radiation Protection and Radwaste Watts Bar Nuclear

Plant (WBN), July 15 - 25, 2019

SSA2101

Audit Report - Emergency Preparedness Watts Bar

Nuclear Plant (WBN)

2/18/2021

Procedures

0-TI-119

Maintenance Rule Performance Indicator Monitoring,

Trending, and Reporting - 10CFR50.65

Rev. 11

1-FOR-304-1

Visual Inspection of Fire-Rated Assemblies Located in Unit

Reactor Building

Rev. 19

2-FOR-304-1

Visual Inspection of Fire-Rated Assemblies Located in Unit

Reactor Building

Rev. 5

0-FOR-304-1

Fire Barrier/Mechanical, Conduit, Cable Tray, and Fire

Damper (External) Penetration Visual Inspection-Auxiliary,

Control Diesel

Rev. 20

Fire Protection

Fire Protection Fire Barrier/Mechanical, Conduit, and Cable

Rev. 3

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Training Procedure

- FPT 358.304.000

Tray Penetration Seals and Radiant Energy Shields

Qualification Card

NEDP-22

Operability Determinations and Functional Evaluations

Rev. 21

NEDP-27

Past Operability Evaluations

Rev. 5

OPDP-8

Operability Determination Process and Limiting Conditions

for Operation Tracking

Rev. 27

NPG-SPP-18.4.6

Control of Fire Protection Impairments

Rev. 18

NPG-SPP-22.300

Corrective Action Program

Rev. 20

NPG-SPP-01.7.1

Employee Concerns Program

Rev. 5

NPG-SPP-03.19

Conduct of Quality Assurance Internal Audits

Rev. 13

NPG-SPP-03.28

Conduct of the Quality Assurance Organization

Rev. 0

NPG-SPP-22.000

Performance Improvement Program

Rev. 12

NPG-SPP-22.000

NPG Self-Assessment and Benchmarking Programs

Rev. 11

NPG-SPP-22.300

Corrective Action Program

Rev. 21

NPG-SPP-22.500

Operating Experience Program

Rev. 13

NPG-SPP-22.600

Issue Resolution

Rev. 12

NPG-SPP-22.600

Issue Resolution

Rev. 11

OPDP-8

Operability Determination Process and Limiting Conditions

for Operation Tracking

Rev. 8

Technical

Instruction (TI)-64

Breaching Hazard Barriers

Rev. 14

TI-65

Breaching the Containment Annulus, ABSCE, or MCRHZ

Pressure Boundaries

Rev. 9

TVA-NQA-PLN89-A

Nuclear Quality Assurance Plan (NQAP) (Quality

Assurance Program Description)

Rev. 9

WBN-RP-SA-19-

001

Self-Assessment Report, Occupational Exposure Control

Effectiveness

WBN-RP-SA-19-

005

Self-Assessment Report, Radiation Monitoring

Instrumentation

Self-Assessments SA/BM Report

Control Room Envelope(CRE) Habitability Program Self-

Assessment

01/15/2020

SA/BM Report

Gamma spectroscopy report review

9/16/2019

SA/BM Report

Closed cooling water

8/31/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

WBN-CEM-SA-18-

2

Self-Assessment Report, Pre-NRC Public Radiation

Safety/Effluents & REMP & GW

WBN-CEM-SA-19-

001

Self-Assessment Report, QA/QC Crosscheck Program

WBN-CEM-SA-19-

003

Self-Assessment Report, Chemistry Level B Technician

Class 1604 improvement opportunities

WBN-RP-SA-19-

2

Self-Assessment Report, Radiological Hazard Assessment

and Exposure Controls

WBN-RP-SA-19-

003

Self-Assessment Report, Pre-NRC Inspection Occupational

ALARA Planning and Controls

WBN-RP-SA-19-

004

Self-Assessment Report, Occupational Dose Assessment

WBN-RP-SA-19-

006

Self-Assessment Report, In Plant Airborne Radioactivity

Control and Mitigation

Work Orders

115628962; 119335861; 119348959; 119585026;

119585030; 119637745; 119638587; 119700865;

119723972; 119891929; 119891939; 119965129;

20016807; 120031097; 120308867; 120346965;

20371218; 120410551; 120449610; 120524675;

20537041; 120550272; 120550341; 120550342;

20593488; 120774110; 120860846; 120918377;

20967368; 120967370; 120967384; 120968563;

21056541; 121056931; 121102181; 121121004;

21264623; 121292587; 121344438; 121377748;

21399972; 121399973; 121424581; 121443542;

21469082; 121509038; 121590361; 121590359;

21597109; 121590361; 121544716; 121658780;

21663792; 121752447; 121752449; 121799971;

21834547; 121834548; 121892180; 121912949;

21922757; 122000228; 122014474; 122102466;

2102469;