ML24264A023

RAI TSTF-600, Rev. 0, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency

ML24264A023
Person / Time
Site:	Technical Specifications Task Force
Issue date:	09/20/2024
From:	Michelle Honcharik NRC/NRR/DSS/STSB
To:	Technical Specifications Task Force
References
EPID L 2024-PMP-0005
Download: ML24264A023 (4)

Text

September 20, 2024 Technical Specifications Task Force 11921 Rockville Pike, Suite 100 Rockville, MD 20852

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RE: TRAVELER TSTF-600, REVISION 0, "REVISE THE REACTOR COOLANT SYSTEM (RCS)

PRESSURE ISOLATION VALVE (PIV) LEAKAGE TESTING FREQUENCY" (EPID: L-2024-PMP-0005)

Dear Members of the Technical Specifications Task Force:

By letter dated April 22, 2024 (Agencywide Documents Access and Management System (Accession No. ML24113A002), you submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to incorporate Traveler TSTF-600, "Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency," into the standard technical specifications.

Upon review of the information provided, the NRC staff has determined that additional information is needed to complete the review. Mr. Brian Mann, Vice President of Licensing, EXCEL Services Corporation, agreed that the NRC staff will receive your response to the enclosed request for additional information questions within 90 calendar days of the date of this letter.

The review schedule that was provided in the acceptance letter dated June 20, 2024 (ADAMS ML24172A054), has not changed.

MILESTONE SCHEDULE DATE Issue Draft Safety Evaluation June 16, 2025 Issue Final Safety Evaluation October 14, 2025

If you have any questions, please contact me at (301) 415-1774 or via email to Michelle.Honcharik@nrc.gov.

Sincerely,

/RA/

Michelle C. Honcharik, Senior Project Manager Technical Specifications Branch Division of Safety Systems Office of Nuclear Reactor Regulation

Project No. 753

Enclosure:

Request for Additional Information cc: See next page

cc:

Technical Specifications Task Force c/o EXCEL Services Corporation 11921 Rockville Pike, Suite 100 Rockville, MD 20852 Attention: Brian D. Mann Email: brian.mann@excelservices.com

Drew Richards STP Nuclear Operating Company 12090 FM 521 Mail Code: N5016 Wadsworth, TX 77483 Email: amrichards@stpegs.com

Kevin Lueshen Constellation Energy Generation 4300 Winfield Road Warrenville IL 60555 Email: kevin.lueshen@constellation.com

Jordan L. Vaughan Duke Energy EC07C / P.O. Box 1006 Charlotte, NC 28202 Email: jordan.vaughan@duke-energy.com

Shane Jurek 2818 Provin Oaks Ct NE Grand Rapids, MI 49525 Email: Shane.Jurek@pseg.com

Wesley Sparkman Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-226-EC Birmingham, AL 35242 Email: wasparkm@southernco.com

ML24264A023

• via email NRR-106 OFFICE NRR/DSS/SCPB/BC* NRR/DEX/EMIB/BC* NRR/DSS/STSB/BC* NRR/DSS/STSB/PM*

NAME MValentin SBailey SMehta MHoncharik DATE 9/20/2024 9/20/2024 9/20/2024 9/20/2024 REQUEST FOR ADDITIONAL INFORMATION

TECHNICAL SPECIFICATIONS TASK FORCE

TRAVELER TSTF-600, REVISION 0, "REVISE THE REACTOR COOLANT SYSTEM (RCS)

PRESSURE ISOLATION VALVE (PIV) LEAKAGE TESTING FREQUENCY"

(EPID: L-2024-PMP-0005)

By letter dated April 22, 2024, the Technical Specifications Task Force (TSTF) submitted Revision 0 of Traveler TSTF-600, "Revise t he Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency" (ML24113A002). The U.S. Nuclear Regulatory Commission (NRC) staff requires the following additional information complete our review of the traveler.

1) The NRC understands that the term valve integrity is associated with the pressure boundary of the valve body as used in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section III. In the traveler the term valve integrity is used with respect to valve leak tightness. Provide a definition for valve integrity as used in the traveler. Revise the traveler to differentiate between valve pressure boundary integrity, leak tightness, and ability to stroke closed.

2) The ASME Operations and Maintenance (OM) Code and technical specifications (TS) are separate requirements. Before a licensee eliminates fixed and event driven PIV test frequencies from the TS in lieu of ASME OM Code frequency requirements, the licensee should verify that there are no licensing basis requirements that would require additional consideration of frequencies that may be time or event driven. Licensees should review their licensing bases to ensure that the inservice testing (IST) Program frequencies adequately cover all licensing basis requirements. A statement specific to this issue should be added to the model application. This will facilitate the traveler being reviewed under the consolidated line item im provement process (CLIIP).

3) The traveler states that all boiling water reactor (BWR) plants with an RCS PIV TS have a surveillance requirement (SR) frequency that references the IST Program and not the surveillance frequency control program (SFCP). The NRC identified at least two BWR plants that have maintenance-or SFCP-based frequencies. The traveler should address the actual TS throughout the fleet.

4) ASME OM Code Case OMN-23, Alternative Rules for Testing Pressure Isolation Valves, allows sample testing of PIVs rather than individual testing of PIVs every two years. The traveler should address the acceptability of TSTF-600 in light of the alternative testing approach of PIVs allowed by OMN-23.