ML16054A531

TSTF Quarterly Meeting Handout Proposed Reactor Coolant Leakage Requirements Traveler

ML16054A531
Person / Time
Site:	Technical Specifications Task Force
Issue date:	02/18/2016
From:	Office of Nuclear Reactor Regulation, Technical Specifications Task Force
To:
Honcharik M
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ML16054A498	List: ML16054A503 ML16054A505 ML16054A527 ML16054A531 ML16054A533 ML16054A709 ML16056A251
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Download: ML16054A531 (6)

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity TSTF / NRC Meeting February 18, 2016 Proposed Reactor Coolant Leakage Requirements Traveler 1

Technical Specifications Task Force TSTF A Joint Owners Group Activity TSTF-554, Revise Reactor Coolant Leakage Requirements

• The TSTF is creating TSTF-554, which will revise the leakage related definitions and specifications to improve clarity and to provide Actions commensurate with the level of degradation.

• The following discussion reflects the current state of the proposed traveler.

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity Definitions

• The definition title is changed from LEAKAGE to REACTOR COOLANT LEAKAGE.

• The subdivisions of LEAKAGE in the existing definition are made separate defined terms, IDENTIFIED LEAKAGE, UNIDENTIFIED LEAKAGE, TOTAL LEAKAGE, and MATERIAL FAULT LEAKAGE, all listed under the REACTOR COOLANT LEAKAGE title.

• The proposed definitions define the systems to which they apply. The PWROG and BWROG definitions are different to reflect system differences.

3 Technical Specifications Task Force TSTF A Joint Owners Group Activity Definitions

• PWR REACTOR COOLANT LEAKAGE introductory paragraph

- Proposed

• REACTOR COOLANT LEAKAGE shall be leakage of reactor coolant, excluding reactor coolant pump seal water injection or leakage, from any pressure-containing components that are part of the reactor coolant system (RCS) and up to and including the second of two isolation valves of connections to the RCS.

• The introduction includes the PWR identified and unidentified LEAKAGE exception for reactor coolant pump (RCP) seal water injection and leakoff in order to eliminate duplication.

• The system boundary is the RCS and any connected systems (such as ECCS injection lines) up to the second isolation valve.

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity Definitions

• BWR REACTOR COOLANT LEAKAGE introductory paragraph

- Proposed

• REACTOR COOLANT LEAKAGE shall be leakage of reactor coolant into the drywell from any pressure-containing components that are part of the reactor coolant system (RCS) or connected to the RCS.

• The introduction includes the existing BWR identified LEAKAGE qualification as leakage into the drywell.

• The system boundary is the RCS and any connected systems within the drywell.

5 Technical Specifications Task Force TSTF A Joint Owners Group Activity Definitions

• The existing definitions of identified LEAKAGE, unidentified LEAKAGE, and total LEAKAGE (BWR only) are reworded for clarity with no change in intent. For example:

PWR Identified LEAKAGE PWR IDENTIFIED LEAKAGE

1. LEAKAGE, such as that from pump seals or 1. leakage that is captured and conducted to valve packing (except reactor coolant pump collection systems or a sump or collecting (RCP) seal water injection or leakoff), that is tank, such as that from pump seals or valve captured and conducted to collection packing; systems or a sump or collecting tank, 2. leakage from sources that are specifically

2. LEAKAGE into the containment atmosphere located and known to not interfere with the from sources that are both specifically operation of leakage detection systems; or located and known either not to interfere 3. leakage into the secondary system through with the operation of leakage detection a steam generator.

systems or not to be pressure boundary LEAKAGE, or

3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity Pressure Boundary LEAKAGE Definition Replaced with MATERIAL FAULT LEAKAGE PWR Pressure Boundary LEAKAGE PWR MATERIAL FAULT LEAKAGE LEAKAGE (except primary to secondary IDENTIFIED LEAKAGE or UNIDENTIFIED LEAKAGE) through a nonisolable fault in an LEAKAGE through a material fault in a RCS component body, pipe wall, or vessel component body, pipe wall, or vessel wall, wall. excluding leakage into the secondary system through a steam generator. Leakage past seals and gaskets is not MATERIAL FAULT LEAKAGE.

BWR Pressure Boundary LEAKAGE BWR MATERIAL FAULT LEAKAGE LEAKAGE through a nonisolable fault in a IDENTIFIED LEAKAGE or UNIDENTIFIED Reactor Coolant System (RCS) component LEAKAGE through a material fault in a body, pipe wall, or vessel wall. component body, pipe wall, or vessel wall. Leakage past seals and gaskets is not MATERIAL FAULT LEAKAGE.

7 Technical Specifications Task Force TSTF A Joint Owners Group Activity Specifications

• PWR TS 3.4.14 and BWR TS 3.4.4 are renamed from "RCS Operational LEAKAGE" to "REACTOR COOLANT LEAKAGE."

• The LCOs and SRs are unchanged except to use the new defined terms.

• The existing TS Actions on UNIDENTIFIED LEAKAGE, IDENTIFIED LEAKAGE, TOTAL LEAKAGE and UNIDENTIFIED LEAKAGE increase have no technical changes except to use the new defined terms.

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity PWR Actions for MATERIAL FAULT LEAKAGE

• Required Action B.1: Close the associated isolation valve immediately.

- A note provides an exception:

• Not applicable to MATERIAL FAULT LEAKAGE in a component body, pipe wall, or vessel wall with an [inner] diameter [XX] inches.

• We are still developing criteria for the component size.

- If the note does not apply and there is no isolation valve, the default (shutdown) Action applies.

9 Technical Specifications Task Force TSTF A Joint Owners Group Activity BWR Actions for MATERIAL FAULT LEAKAGE

• Required Action B.1: Close the associated isolation valve immediately.

- There is no Note.

• BWR licensees don't enter the drywell during plant operation, so there is no opportunity to determine the location of a leak and the size of the leaking component.

- If there is no isolation valve, the default (shutdown) Action applies.

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2/22/2016 Technical Specifications Task Force TSTF A Joint Owners Group Activity PWR & BWR Actions for MATERIAL FAULT LEAKAGE

• Required Action B.2: Determine system is acceptable for continued operation in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

- Applies whether or not the isolation valve is closed.

- Bases require considering:

• the effect of the flaw on the material strength of the affected component, such as seismic response, thermal cycling, and flaw propagation;

• the effect of continued degradation of the affected component during reactor operation prior to repair due to leakage through the fault, including leakage past any closed isolation valve;

• the potential for interference with leakage detection systems;

• the quality of the water passing through the flaw (liquid versus steam);

and

• (PWRs) the effect of any boric acid deposition on the affected component or other systems.

11 Technical Specifications Task Force TSTF A Joint Owners Group Activity Schedule

• Complete traveler and distribute for industry 3-week review End of April

• Resolve industry comments and provide draft to NRC Early June

• TSTF/NRC Presubmittal meeting End of June

• Traveler submittal End of August 12 6