IR 05000390/2019003

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Integrated Inspection Report 05000390/2019003 and 05000391/2019003
ML19303A006
Person / Time
Site: Watts Bar  Tennessee Valley Authority icon.png
Issue date: 10/30/2019
From: Omar Lopez-Santiago
Division Reactor Projects II
To: Jim Barstow
Tennessee Valley Authority
Reeder D
References
IR 2019003
Download: ML19303A006 (12)


Text

{{#Wiki_filter:ber 30, 2019

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000390/2019003 AND 05000391/2019003

Dear Mr. Barstow:

On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Watts Bar, Units 1 and 2. On October 17, 2019, 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.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Omar R. López-Santiago, Chief Reactor Projects Branch 5 Division of Reactor Projects 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: 05000390/2019003 and 05000391/2019003 Enterprise Identifier: I-2019-003-0024 Licensee: Tennessee Valley Authority Facility: Watts Bar, Units 1 and 2 Location: Spring City, TN 37381 Inspection Dates: July 01, 2019 to September 30, 2019 Inspectors: N. Childs, Senior Resident Inspector W. Deschaine, Senior Resident Inspector J. Hamman, Resident Inspector S. Janicki, Resident Inspector R. Mathis, Test Inspector J. Nadel, Senior Resident Inspector Approved By: Omar R. López-Santiago, Chief Reactor Projects Branch 5 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Watts Bar, 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.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power. On August 31, 2019, the unit was manually tripped due to a main feedwater regulating valve (MFRV) failure. Repairs were made to the MFRV and on September 3, 2019, the unit reached 12%. On September 5, 2019, the licensee noted some turbine repairs that were necessary and shutdown the unit. The unit remained offline for the remainder of the inspection period.

Unit 2 operated at or near rated thermal power for the entire inspection period.

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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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

71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) 1B train charging system while 1A centrifugal charging pump (CCP) was out of service (OOS) for a component outage on July 8, 2019
(2) 2B train of containment spray while 2A train was OOS for planned maintenance on July 9, 2019
(3) 1A-A emergency diesel generator (EDG) while 1B-B EDG was OOS for planned maintenance
(4) 1A, 1B and 2A 480V electric board room (EBR) chillers while 2B EBR chiller was OOS for repairs on August 22, 2019

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

(1) Inspectors observed an announced fire drill for a fire in the 1B-B containment spray pump room on August 14, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Control building elevation 741', Unit 1 and 2 cable spreading rooms on August 20, 2019.

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Unit 1 and 2 auxiliary building elevation 757', shutdown board rooms

==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during a Unit 1 start-up following a forced outage due to the failure of the #2 main feedwater regulating valve on September 2, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02)==

(1) The inspectors observed simulator scenario 3-OT-SRT-H1-6, Revision 2, for a loss of ultimate heat sink following a rapid load reduction due to high turbine bearing temperature on September 19, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Condition Report (CR) 1526540, A and B Emergency Gas Treatment System functional failure due to a tear in penetration seal 0-SLV-304-R2S065

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Risk assessment for week of August 12, 2019 with 1B-B emergency diesel generator OOS for planned maintenance
(2) Risk assessment for August 29, 2019, with the 2B-B emergency diesel generator OOS for planned maintenance
(3) Risk assessment for September 9, 2019, with Unit 1 shutdown for a forced outage
(4) Risk assessment for September 25, 2019 with 2B-B emergency diesel generator OOS due to load swings during a surveillance

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Operability determination for CR 1539213, auxiliary building gas treatment system 1A-A fan motor high vibrations
(2) Operability determination for CR 1534088, Engineering Work Request EWR-19-ELE-030-284, low margin to maximum limit for Unit 1 lower containment temperature.

==71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample) The inspectors evaluated the following temporary or permanent modifications:

(1) Temporary Modification WBN-0-2019-031-004, temporary chillers installed to provide chilled water to the B-B shutdown board room chiller loads on August 22, 2019

71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)

[[IP sample::=

=IP 71111.18|count=2}}

The inspectors evaluated the following post maintenance tests:

(1) Post maintenance test of 1A-A auxiliary building gas treatment system exhaust fan motor after preventive maintenance on August 8, 2019
(2) WO 120614655, 0-SI-82-12-B, Monthly Diesel Start and Load Test DG 2B-B, following 2B-B emergency diesel generator repairs on September 25, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Inservice Testing (IP Section 03.01)

(1) Work Order (WO) 120163013, 1-SI-3-901-B, Motor Driven Auxiliary Feedwater Pump 1B-B Quarterly Performance Test on August 2,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below: MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===

(1) Unit 1 (July 1, 2018 - June 30, 2019)
(2) Unit 2 (July 1, 2018 - June 30, 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (July 1, 2018 - June 30, 2019)
(2) Unit 2 (July 1, 2018 - June 30, 2019)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (July 1, 2018 - June 30, 2019)
(2) Unit 2 (July 1, 2018 - June 30, 2019)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (July 1, 2018 - June 30, 2019)
(2) Unit 2 (July 1, 2018 - June 30, 2019)

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more safety significant issue.

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample) The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) The inspectors conducted safety culture interviews in the Watts Bar Site Projects organization as a result of several safety culture related condition reports. The inspectors concluded that individuals in the Watts Bar Site Projects organization understood the various methods of reporting safety concerns and were willing to use them without fear of retaliation.

INSPECTION RESULTS

Observation: Review of Condition Reports Related to Tritium Production in Unit 71152 1 Reactor During their regular review of the licensees corrective action program, the inspectors identified eleven condition reports written between February and September 2019 relating to tritium production using tritium producing burnable absorber rods (TPBAR) in the Unit 1 reactor. The inspectors evaluated this as a possible trend. The technical issues described in ten of the condition reports had insignificant impact on plant operations. Condition report 1521541, related to airborne tritium concentration in lower containment, received a detailed review by the inspectors. Specifically, increased tritium concentration in unit 1 reactor coolant sometimes resulted in increased airborne tritium in lower containment. This is because reactor coolant is collected in the reactor building equipment drain system, which is open to the lower containment atmosphere, and is present in the reactor coolant drain tank, which is vented to the lower containment atmosphere. The inspectors found that the licensee had procedures in place to monitor lower containment tritium concentrations and to ensure protection for personnel working in lower containment. Additionally, the licensee monitored gaseous releases from Unit 1 containment to ensure that those releases are below regulatory requirements. Overall, the inspectors concluded that none of the condition reports reviewed were indicative of a more significant safety issue.

EXIT MEETINGS AND DEBRIEFS

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

  • On October 17, 2019, the inspectors presented the integrated 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 71111.04Q Drawings 2-47W812-1 36 Miscellaneous SDD-N3-30AB- Auxiliary Building Heating, Ventilation, Air Conditioning 45 4001 System (30, 31, 44) Unit1/Unit 2 Procedures 0-SI-82-2 8 Hour Diesel Generator AC Power Source Operability 27 Verification 1-PI-OPS-PE Protection Equipment 21 2-PI-OPS-1-PE Protected Equipment 7 71111.05A Fire Plans AUX-0-676-01 WBN Prefire Plan 3 Miscellaneous Watts Bar Nuclear Plant Fire Protection Report 55 71111.05Q Corrective Action CR 1542582 Documents Fire Plans CON-0-729-01 Pre-Fire Plan 2 71111.06 Calculations Flooding Calculation WBN0SG4009, Appendix J, Backflow 09/25/1987 Through Floor Drains MDN-000-999- WBN Probabilistic Risk Assessment - Internal Flooding 3 2008-0146 Analysis Notebook WBN-DC-40- Evaluating the Effects of Flooding due to Moderate Energy 5 31.51 Pipe Failures Inside and Outside of Containment WBN-DC-40-61 Equipment and Floor Draining System 5 Corrective Action CR 1542885, 1539120 Documents 71111.11Q Corrective Action CR 1526540 Documents Miscellaneous 1-GO-2 Reactor Startup 19 1646, 1647 Cause Determination Evaluation Procedures 0-TI-119 Maintenance Rule Performance Indicator Monitoring, 6 Trending, and Reporting - 10CFR50.65 Work Orders 120536836 71111.13 Miscellaneous Operator's Risk Report 08/12/2019 WBN Defense in Depth Assessment 09/09/2019 Operator's Risk Report 09/25/2018 Procedures 0-SI-82-2 8 Hour Diesel Generator AC Power Source Operability 27 Inspection Type Designation Description or Title Revision or Procedure Date Verification 71111.15 Corrective Action CR 1534088, 1535612, 1536108, 1539213 Documents Miscellaneous EWR-19-ELE- Evaluate the impact of one or more failed temperature 07/23/2019 030-284 sensors on the determination of the average lower containment temperature for WBN 1 Procedures 0-TI-31.02 Plant Equipment Monitoring & Vibration Diagnostics 2 Program 1-T-30-210 Setpoint and Scaling Document 2 NEDP-10, Site Engineering Setpoint and Scaling Documents 23 NEDP-2 Safety/Quality-Related Setpoint Establishment and 23 Validation Process NEDP-4, Quality-related Processes-Augmented QA 26 NPG-SPP-06.7 Instrumentation Setpoint, Scaling, and Calibration Program 4 NPG-SPP-09.0 Conduct of Engineering 10 Work Orders 119904284 71111.18 Miscellaneous C19-0447, C19- Fire Protection Impairment Permit 0454 WBN-0-2019- Temporary Chiller to Support Replacement of B-Train 031-004 Shutdown Board Room (SDBR) Chiller 71111.19 Corrective Action CR 1539213 Documents Procedures 0-SI-82-12-B Monthly Diesel Start and Load Test B2-B 57 0-TI-31.02 Plant Equipment Monitoring & Vibration Diagnostics 2 Program Work Orders 119904284 0 71111.22 Procedures 1-SI-3-901-B Motor Driven Auxiliary Feedwater Pump 1B-B Quarterly 34 Performance Test 71152 Corrective Action 1494503, Condition Reports Documents 1521541, 22992, 24508, Inspection Type Designation Description or Title Revision or Procedure Date 26913, 29480, 1531261, 1533009, 1549445, 1549467, 1549912 10| ]]