ML18248A105

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Presentation Slides - Watts Bar Nuclear Plant Units 1 and 2 Adoption of TSTF-425 Initiative 5b - Surveillance Frequency Control Program - September 6, 2018
ML18248A105
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 09/05/2018
From:
Tennessee Valley Authority
To: Shea J W, Skaggs M D
Office of Nuclear Reactor Regulation
Jordan N J
References
Download: ML18248A105 (25)


Text

Watts Bar Nuclear Plant Units 1 and 2 Adoption of TSTF

-425Initiative 5b

-Surveillance Frequency Control ProgramSeptember 6, 2018

  • Meeting Purpose
  • License Amendment Request (LAR) Overview
  • Probabilistic Risk Assessment (PRA) Model Considerations
  • Variations from TSTF

-425 Template

  • LAR Schedule
  • ConclusionsAgendal 2WBN Units 1 and 2 Adoption of TSTF-425 Meeting Purpose
  • Provide an overview of the proposed Watts Bar Nuclear Plant (WBN) TSTF-425 License Amendment Request (LAR) *Describe the Internal Events and Seismic PRA models that will be used as a basis for controlling surveillance frequencies
  • Discuss any unique variations on the TSTF

-425 template that will be included in the LAR as WBN Technical Specification (TS) changes*Discuss the proposed LAR submittal, review, and implementation

schedulel 3WBN Units 1 and 2 Adoption of TSTF-425 LAR Overview

-425 model application provided in the Federal Register dated July 6, 2009 (74 FR 31996) *Nine attachments

1 -Description and Assessment 2 -PRA Adequacy3.1 and 3.2

-WBN Units 1 and 2 TS markup pages4.1 and 4.2

-WBN Units 1 and 2 Retyped TS pages 5 -WBN Unit 1 Bases markup 6 -No Significant Hazards Consideration 7 -WBN TS to TSTF

-425 Cross Reference l 4WBN Units 1 and 2 Adoption of TSTF-425 LAR Overview

  • Content informed by most recent precedents
  • Over 250 Surveillance Requirement (SR) Frequencies are being changed for each WBN unit*Justifies use of the WBN PRA for use in this risk

-informed application

  • Variations are identified for changes not specifically addressed in TSTF-425l 5WBN Units 1 and 2 Adoption of TSTF-425 TVA SFCP Process
  • Follows the industry guidance document, NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies"
  • The TVA SFCP process has been in effect for about three years at the Sequoyah Nuclear Power Plant (SQN)
  • SQN-specific implementation procedures will inform the implementation of the SFCP at WBN l 6WBN Units 1 and 2 Adoption of TSTF-425 PRA Technical Adequacy ReviewInternal Events with Internal Flooding PRA Model

-Full Scope Peer Review against the ASME/ANS 2008 PRA Standard Addendum a, Endorsed by RG 1.200 R2

-Underwent Facts and Observation (F&O) Closure

Process-Seven Open F&Os (Finding Level) which were assessed

against the SFCP application l 7WBN Units 1 and 2 Adoption of TSTF-425 PRA Technical Adequacy ReviewSeismic PRA Model

-Full Scope Peer Review against Part 5 (seismic) of Addendum b of the 2008 ASME/ANS PRA Standard

-Underwent F&O Closure Process

-One Open F&O (Finding Level), which was assessed against the SFCP application l 8WBN Units 1 and 2 Adoption of TSTF-425 Model Update & MaintenanceTVA procedures ensure or provide:

-Model configuration, fidelity and realism

-Periodic update requirements

-Living model requirements

-PRA model updates

>PRA Maintenance

>PRA Upgrade

-Peer Review requirements l 9WBN Units 1 and 2 Adoption of TSTF-425 Non-Modeled HazardsInternal Fire Hazards

-Qualitative evaluation

-Progressive screening approach using the Fire Induced Vulnerability Evaluation (FIVE) from the docketed Individual Plant Examination of External Events (IPEEE) l 10WBN Units 1 and 2 Adoption of TSTF-425 Non-Modeled HazardsOther External Hazards

  • Screening results from the IPEEE for evaluations
  • SSCs credited in the IPEEE Other External Hazards Evaluation to allow the hazard to screen is qualitatively evaluated in the SFCP evaluation
  • External hazard screening was reviewed against the current as

-built, as-operated plant l 11WBN Units 1 and 2 Adoption of TSTF-425 Shutdown EventsShutdown risk management in accordance with NUMARC 91-06 which includes a qualitative process

  • TVA process assesses the potential impact on shutdown risk

-focus on planning, conservative decision-making and maintaining defense

-in-depth-assessment of plant shutdown configurations for impact on Key Safety Functions l 12WBN Units 1 and 2 Adoption of TSTF-425 Cumulative Risk

  • The cumulative risk analysis compares the change in risk for all previously approved Surveillance Test Interval extensions and the extension(s) under consideration that have not been rolled into the model of record*The delta from the baseline model represents the cumulative risk effect *Limits for Core Damage Frequency and Large Early Release Frequency are consistent with those limits given in NEI 04-10l 13WBN Units 1 and 2 Adoption of TSTF-425 Variations from TSTF

-425 Template

  • TSTF-425 is based on a markup of NUREG

-1431 Rev. 3.0 and 3.1*The WBN Technical Specifications are based on NUREG-1431 Rev. 1

  • This difference has resulted in numerous variations, most of which are administrative in nature
  • SR that are unique to WBN were screened against the criteria

of the model safety evaluation

  • None of the variations affect the model safety evaluation provided in the Federal Register Notice for TSTF-425l 14WBN Units 1 and 2 Adoption of TSTF-425 VariationsSR 3.7.5.2This SR is currently performed every 31 days on a Staggered Test Basis
  • TSTF-425 removes the definition of "Staggered Test Basis"
  • TSTF-101 revised the Frequency to "In accordance with the InserviceTesting Program

"*NUREG-1431 Rev. 4 includes this change

  • TVA proposes to be consistent with the Improved Standard Technical Specifications and refer to the InserviceTesting Program l 15WBN Units 1 and 2 Adoption of TSTF-425 AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path.and in both steam supply flow paths to the steam turbine driven pump, that is not locked. sealed. or otherwise secured in position, is in the correct position.SR 3.7.5.2 -------------------

NOTE------------------

Not required to be performed for the turbine driven AFW pump until

24 hours
2.777778e-4 days
0.00667 hours
3.968254e-5 weeks
9.132e-6 months

after 2 1092 psig in the steam generator.

Verify the developed head of each AFW pump 31 days on a at the flow test point is greater than or STAGGERED TEST equal to the required developed head. BASISSR 3.7.5.3


NOTE-------------------

Not applicable in MODE 4 when steam generator is relied upon for heat removal.Verify each AFW automatic valve that is not 18 months locked, sealed, or otherwise secured in position.

actuates to the correct positionon an actual or simulated actuation signal.(continued)

Watts Bar-Unit 1 3.7-13 Anwxient Nb. 13 OCT 2 6 1998 VariationsSRs 3.8.1.2 and 3.8.1.3These SRs surveil the diesel generators with a Frequency "As specified in Table 3.8.1

-1." *Table 3.8.1

-1 establishes frequencies based on failures of valid tests per RG 1.9*TSTF-37 deleted Table 3.8.1

-1 and changed the Frequencies for SRs 3.8.1.2 and 3.8.1.3 to 31 days (based on implementation of the Maintenance Rule and GL 94-01)*TSTF-425 changed those Frequencies to be included in the SFCP*TVA proposes to delete Table 3.8.1

-1 and state that the SRs 3.8.1.2 and 3.8.1.3 Frequencies will be in accordance with the SFCP l 16WBN Units 1 and 2 Adoption of TSTF-425

VariationsSR 3.8.3.7This SR requires a 10

-year inspection of the fuel oil storage tank per RG 1.137.*TSTF-2 transferred this SR to licensee control

  • TVA is not adopting TSTF

-2 as part of the TSTF

-425 LAR*TVA proposes to apply the SFCP to this SR Frequency (meets criteria for inclusion contained in the model safety evaluation) l 17WBN Units 1 and 2 Adoption of TSTF-425 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)

-SURVEILLANCE FREQUENCYSR 3.8.3.2 Verify lubricating oil inventory is 31 days 2 287 gal per engine.SR 3.8.3.3 Verify fuel oil properties of new and In accordance stored fuel oil are tested in accordance with the Diesel with, and maintained within the limits of, Fuel Oil the Diesel Fuel Oil Testing Program. Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure 31 daysis 2 190 psig.SR 3.8.3.5 Check for and remove accumulated water from 31 days each of the four interconnected tanks which constitute the 7 day fuel oil storage tank.SR 3.8.3.6 Perform a visual inspection for leaks in 18 months the exposed fuel oil system piping while the DG is running.SR 3.8.3.7 For each of the four interconnected tanks 10 yearswhich constitute the 7 day fuel oil storage tank: a. Drain the fuel oil;b. Remove the sediment; and c. Clean the tank.Watts Bar-Unit 1 3.8-23 VariationsSR 3.8.4.13 Note 1This Note allows the performance of SR 3.8.4.14 modified discharge test in lieu of the battery service test once per 60 months.

  • The phrase "Once per 60 months" is being deleted, which is consistent with the SR 3.8.4.14 Frequency being changed to the SFCP
  • This change is technically justified by IEEE 450

-1995 and has been accepted by recent precedent (Cooper -ML17061A050) l 18WBN Units 1 and 2 Adoption of TSTF-425 DC Sources -Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)-SURVEILLANCE FREQUENCY SR 3.8.4.12 -------------------

NOTE--------------------

Credit may be taken for unplanned events that satisfy this SR.Verify each diesel generator battery charger is 18 months capable of recharging its associated battery from a service or capacity discharge test while supplying normal loads.SR 3.8.4.13 -------------------

NOTES-------------------

1. The modified performance discharge test in SR 3.8.4.14 may be performed in lieu of the service test in SR 3.8.4.13 once per 60 months.2. This Surveillance is not performed in MODE 1, 2. 3, or 4 for required vital batteries.

Credit may be taken for unplanned events that satisfy this SR.Verify battery capacity is adequate to supply, 18 months and maintain in OPERABLE status, the required emergency loads and any connected nonsafety loads for the design duty cycle when subjected to a battery service test.(continued)

I Watts Bar-Unit 1 3.8-28 Ahndwent W.12 11^ I" 1i2 LAR Schedule l 19*Coordination with 10 CFR 50.69 Submittal

-It is expected that there will be review efficiencies gained because of the common PRA usage

-Both the TSTF-425 LAR and 10 CFR 50.69 LAR submittals are planned for 9/28/18*A one-year NRC review is requested

  • Upon approval, the TSTF

-425 License Amendment will be implemented within 60 daysWBN Units 1 and 2 Adoption of TSTF-425 Conclusions

  • TSTF-425 LAR is scheduled to be submitted by September 28, 2018
  • LAR is consistent with Model Application and Safety Evaluation, and informed by precedent
  • SFCP Process will follow NEI 04

-10*Internal Events PRA meets RG 1.200 Rev. 2

requirements and Seismic PRA Model meets the requirements of Addendum b to the PRA Standardl 20WBN Units 1 and 2 Adoption of TSTF-425