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| {{#Wiki_filter:July 1, 2021 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| WATTS BAR NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000390/2021012 AND 05000391/2021012
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| ==Dear Mr. Barstow:==
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| 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.
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| 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.
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| 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.
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| Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
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| 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.
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| Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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| 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.
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| Sincerely,
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| /RA/
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| 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:
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| As stated
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| ML21182A036 X Non-Sensitive X Publicly Available X SUNSI Review Sensitive 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
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| U.S. NUCLEAR REGULATORY COMMISSION
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| ==Inspection Report==
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| Docket Numbers: 05000390 and 05000391 License Numbers: NPF-90 and NPF-96 Report Numbers: 05000390/2021012 and 05000391/2021012 Enterprise Identifier: I-2021-012-0017 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 Enclosure
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| =SUMMARY=
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| 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.
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| ===List of Findings and Violations===
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| No findings or violations of more than minor significance were identified.
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| ===Additional Tracking Items===
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| Type Issue Number Title Report Section Status URI 05000391/2021012-01 2A-A CCS Pump Seal 71152B Open Bolting Failure
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| =INSPECTION SCOPES=
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| 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.
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| 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.
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| ==OTHER ACTIVITIES - BASELINE==
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| ===71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04) ===
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| {{IP sample|IP=IP 71152|count=1}}
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| : (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.
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| * 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).
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| * Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
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| * Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
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| ==INSPECTION RESULTS==
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| 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.
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| 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.
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| Additionally, site management was actively involved in the corrective action program and focused appropriate attention on significant plant issues.
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| 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.
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| 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.
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| 2. Use of Operating Experience (OE)
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| 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.
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| 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.
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| ===3. Self-Assessments and Audits===
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| 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.
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| 4. Safety Conscious Work Environment (SCWE)
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| 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.
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| Unresolved Item 2A-A CCS Pump Seal Bolting Failure 71152B (Open) URI 05000391/2021012-01
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| =====Description:=====
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| 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 hours. 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).
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| 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.
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| 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.
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| Corrective Action References: CRs 1692049, 1692589, 1695509,
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| ==EXIT MEETINGS AND DEBRIEFS==
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| The inspectors verified no proprietary information was retained or documented in this report.
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| * 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.
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| =DOCUMENTS REVIEWED=
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| 71152B Corrective Action 1233275; 1244275; 1244348; 1244398; 1245056;
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| Documents 1332863; 1353102; 1413807; 1434751; 1446383;
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| 1450336; 1450338; 1454882; 1474341; 1476614;
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| 1482137; 1483352; 1486878; 1486882; 1487830;
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| 1488848; 1488684; 1492565; 1498928; 1498934;
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| 1499812; 1501943; 1501994; 1501945; 1507301;
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| 1508964; 1510237; 1501946; 1502448; 1502633;
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| 1502915; 1504014; 1504499; 1504520; 1506037;
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| 1506341; 1510056; 1513326; 1515204; 1515390;
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| 1516431; 1516485; 1516492; 1516494; 1516841;
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| 1517359; 1520769; 1521049; 1521069; 1521317;
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| 21319; 1521497; 1525654; 1525982; 1526540;
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| 27359; 1527618; 1548617; 1549553; 1549554;
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| 29382; 1531046; 1534909; 1540594; 1540598;
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| 1540601; 1540603; 1542419; 1548549; 1555701;
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| 1557359; 1558324; 1563492; 1566193; 1579238;
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| 1571100; 1579250; 1585826; 1595410; 1597523;
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| 1594403; 1602934; 1607003; 1608135; 1608980;
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| 1609457; 1610611; 1612542; 1615444; 1616077;
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| 1616698; 1618074; 1618544; 1620816; 1622991;
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| 24008; 1636072; 1629687; 1631948; 1634062;
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| 1634387; 1637007; 1640749; 1640903; 1641030;
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| 1642981; 1643336; 1634387; 1644412; 1644413;
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| 1647007; 1647416; 1653024; 1653032; 1654084;
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| 1654091; 1660933; 1660938; 1661691; 1667128;
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| 1667314; 1668321; 1669936; 1670127; 1670136;
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| 1670795; 1670878; 1670960; 1670969; 1672352;
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| 1672356; 1672357; 1672359; 1672462; 1672644;
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| 1672655; 1673877; 1675314; 1677763; 1677999;
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| 1679707; 1681286; 1688163; 1690437; 1690827;
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| 1691621; 1691824; 1692049; 1693132; 1693260;
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| 1693651; 1695509;
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| Corrective Action 1692049 WBN PI&R inspection - 2A CCS pump inboard mechanical 05/05/2021
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| Documents seal leakage
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| Resulting from 1693132 WBN PI&R Inspection - P&IR Walkdown CREVs - Loose 05/11/2021
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| Inspection Door Seal C50
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| 1693260 WBN P&IR Walkdown CREVs - Loose Door Seal C36 05/11/2021
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| 1693624 WBN PI&R Inspection - Issues with CR summaries in CRs 05/12/2021
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| 1540603 and 1540601
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| 1695079 WBN PI&R Inspection - Page numbering issue with WBN- 05/19/2021
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| VTD-D088-0020
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| 1695509 WBN PI&R Inspection - Legacy error in calculation 05/20/2021
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| EPMDWP070594 for CCS Pump Seal Bolts
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| 1695529 WBN PI&R Inspection - URI on 2A CCS pump issues 05/20/2021
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| 1695591 WBN PI&R Inspection - NRC Observation regarding EWR 05/20/2021
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| associated with CR 292049
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| Miscellaneous Equipment Failure Investigation Checklist for CR 1597523, 05/14/2020
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| Turbine Driven Auxiliary Feedwater Level Control Valve
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| Failed Quarterly Stroke Time Test
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| Watts Bar Nuclear (WBN) Nuclear Safety Culture 09/01/2019
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| Evaluation
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| 21 WBN Problem Identification and Resolution Self- Rev. 2
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| Assessment
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| Organizational Effectiveness and Programmatic Checklist, 06/28/2019
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| Potential non-compliance with NERC Standard VAR-002 -
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| 4.1 Requirements
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| Organizational Effectiveness and Programmatic Checklist, 03/26/2020
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| Streaming Analysis of 2019 WBN Performance Based
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| Evaluation (PBE)
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| Root Cause Analysis Report, Risk Management of the 2C Rev. 0
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| Unit Board Loss
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| Root Cause Analysis Report, Unit 2 Turbine Generator Rev. 0
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| Exciter Failure
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| Equipment Failure Investigation Checklist for CR 1669936, 05/17/2020
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| Water in Upper Bearing Oil of ERCW Pump Motor
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| Audit Report Chemistry, Effluent, and Environmental Monitoring Watts
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| SSA1906 Bar (WBN), June 03 - June 13, 2019
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| Engineering Work Evaluation for Loss of CRE Safety Function Due to MCR 6/18/2018
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| Request no. Doors Open,
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| EWR18MEC030278
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| Health Report Air Conditioning/CREVS, Reporting Period: October 2018 -
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| Scorecard March 2019
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| Health Report Air Conditioning/CREVS, Reporting Period: Reporting
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| Scorecard Period: April 2019 - September 2019
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| Health Report Air Conditioning/CREVS, Reporting Period: Oct 1, 2019 to
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| Scorecard March 31, 2020)
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| Health Report Air Conditioning/CREVS, Reporting Period: April 1, 2020 to
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| Scorecard Sept 30, 2020
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| Health Report Component Cooling Water System (CCS): Fall 2019 -
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| Scorecards Spring 2021
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| Pressure Boundary Door C036 Data Sheet 5/11/2021
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| Door Smoke Test
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| Pressure Boundary Door C0350 Data Sheet 5/11/2021
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| Door Smoke Test
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| SDD-N3-30CB- Control Building Heating, Ventilating, Air Conditioning, and Rev. 21
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| 4002 Air Cleanup System Unit 1/Unit 2
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| Site Audit Report, Radiation Protection and Radwaste Watts Bar Nuclear
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| SSA1907 Plant (WBN), July 15 - 25, 2019
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| SSA2101 Audit Report - Emergency Preparedness Watts Bar 02/18/2021
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| Nuclear Plant (WBN)
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| Procedures 0-TI-119 Maintenance Rule Performance Indicator Monitoring, Rev. 11
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| Trending, and Reporting - 10CFR50.65
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| 1-FOR-304-1 Visual Inspection of Fire-Rated Assemblies Located in Unit Rev. 19
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| Reactor Building
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| 2-FOR-304-1 Visual Inspection of Fire-Rated Assemblies Located in Unit Rev. 5
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| Reactor Building
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| 0-FOR-304-1 Fire Barrier/Mechanical, Conduit, Cable Tray, and Fire Rev. 20
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| Damper (External) Penetration Visual Inspection- Auxiliary,
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| Control Diesel
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| Fire Protection Fire Protection Fire Barrier/Mechanical, Conduit, and Cable Rev. 3
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| Training Procedure Tray Penetration Seals and Radiant Energy Shields
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| - FPT 358.304.000 Qualification Card
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| NEDP-22 Operability Determinations and Functional Evaluations Rev. 21
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| NEDP-27 Past Operability Evaluations Rev. 5
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| OPDP-8 Operability Determination Process and Limiting Conditions Rev. 27
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| for Operation Tracking
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| NPG-SPP-18.4.6 Control of Fire Protection Impairments Rev. 18
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| NPG-SPP-22.300 Corrective Action Program Rev. 20
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| NPG-SPP-01.7.1 Employee Concerns Program Rev. 5
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| NPG-SPP-03.19 Conduct of Quality Assurance Internal Audits Rev. 13
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| NPG-SPP-03.28 Conduct of the Quality Assurance Organization Rev. 0
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| NPG-SPP-22.000 Performance Improvement Program Rev. 12
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| NPG-SPP-22.000 NPG Self-Assessment and Benchmarking Programs Rev. 11
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| NPG-SPP-22.300 Corrective Action Program Rev. 21
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| NPG-SPP-22.500 Operating Experience Program Rev. 13
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| NPG-SPP-22.600 Issue Resolution Rev. 12
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| NPG-SPP-22.600 Issue Resolution Rev. 11
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| OPDP-8 Operability Determination Process and Limiting Conditions Rev. 8
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| for Operation Tracking
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| Technical Breaching Hazard Barriers Rev. 14
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| Instruction (TI)-64
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| TI-65 Breaching the Containment Annulus, ABSCE, or MCRHZ Rev. 9
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| Pressure Boundaries
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| TVA-NQA-PLN89-A Nuclear Quality Assurance Plan (NQAP) (Quality Rev. 9
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| Assurance Program Description)
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| WBN-RP-SA-19- Self-Assessment Report, Occupational Exposure Control
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| 001 Effectiveness
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| WBN-RP-SA-19- Self-Assessment Report, Radiation Monitoring
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| 005 Instrumentation
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| Self-Assessments SA/BM Report Control Room Envelope(CRE) Habitability Program Self- 01/15/2020
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| Assessment
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| SA/BM Report Gamma spectroscopy report review 9/16/2019
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| SA/BM Report Closed cooling water 8/31/2020
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| WBN-CEM-SA-18- Self-Assessment Report, Pre-NRC Public Radiation
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| 2 Safety/Effluents & REMP & GW
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| WBN-CEM-SA-19- Self-Assessment Report, QA/QC Crosscheck Program
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| 001
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| WBN-CEM-SA-19- Self-Assessment Report, Chemistry Level B Technician
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| 003 Class 1604 improvement opportunities
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| WBN-RP-SA-19- Self-Assessment Report, Radiological Hazard Assessment
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| 2 and Exposure Controls
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| WBN-RP-SA-19- Self-Assessment Report, Pre-NRC Inspection Occupational
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| 003 ALARA Planning and Controls
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| WBN-RP-SA-19- Self-Assessment Report, Occupational Dose Assessment
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| 004
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| WBN-RP-SA-19- Self-Assessment Report, In Plant Airborne Radioactivity
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| 006 Control and Mitigation
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| Work Orders 115628962; 119335861; 119348959; 119585026;
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| 119585030; 119637745; 119638587; 119700865;
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| 119723972; 119891929; 119891939; 119965129;
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| 20016807; 120031097; 120308867; 120346965;
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| 20371218; 120410551; 120449610; 120524675;
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| 20537041; 120550272; 120550341; 120550342;
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| 20593488; 120774110; 120860846; 120918377;
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| 20967368; 120967370; 120967384; 120968563;
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| 21056541; 121056931; 121102181; 121121004;
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| 21264623; 121292587; 121344438; 121377748;
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| 21399972; 121399973; 121424581; 121443542;
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| 21469082; 121509038; 121590361; 121590359;
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| 21597109; 121590361; 121544716; 121658780;
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| 21663792; 121752447; 121752449; 121799971;
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| 21834547; 121834548; 121892180; 121912949;
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| 21922757; 122000228; 122014474; 122102466;
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| 2102469;
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| 10
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| }} | | }} |
