ML21127A275

Summary of Quarterly Meeting with Technical Specifications Task Force

ML21127A275
Person / Time
Site:	Technical Specifications Task Force
Issue date:	06/10/2021
From:	Michelle Honcharik NRC/NRR/DSS/STSB
To:	Natreon Jordan NRC/NRR/DSS/STSB
Honcharik M, NRR/DSS, 301-415-1774
Shared Package
ML21126A068	List: ML21126A071 ML21126A072 ML21126A073 ML21127A275
References
Download: ML21127A275 (6)

Text

N. Jordan June 10 , 2021 MEMORANDUM TO: Natreon J. Jordan, Acting Branch Chief Technical Specifications Branch Division of Safety Systems Office of Nuclear Reactor Regulation FROM: Michelle C. Honcharik, Senior Project Manager Technical Specifications Branch Michelle C. Digitally signed by Michelle C. Honcharik Division of Safety Systems Honcharik Date: 2021.06.10 Office of Nuclear Reactor Regulation 08:01:13 -04'00'

SUMMARY

OF MAY 6, 2021, QUARTERLY MEETING WITH THE TECHNICAL SPECIFICATIONS TASK FORCE On May 6, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff held a public teleconference with members of the Technical Specifications Task Force (TSTF). The purpose of the meeting was for the NRC staff and the TSTF to discuss technical issues and administrative processes related to technical specifications (TSs) and travelers. The meeting notice is available in the Agencywide Document Access and Management System (ADAMS) at Accession No. ML21118A814. The TSTF provided three handouts for the meeting, which are available in ADAMS Package Accession No. ML21126A068. A list of attendees is enclosed.

Revision 5 of the Standard TSs (STS) are on schedule to be issued by the end of June 2021.

The revision will include travelers TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections, and TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR

[Residual Heat Removal] Shutdown Cooling.

After the meeting, the TSTF provided, for information only, TSTF-GG-21-01, Technical Requirements Manual and Operational References (TRM) Format and Content Guideline (ADAMS Accession No. ML21137A033).

Since the NRC approved traveler TSTF-577, "Revised Frequencies for Steam Generator Tube Inspections, ahead of schedule, licensees will be able to adopt it in time for Fall 2021 and Spring 2022 outages, without expedited review requests. The TSTF provided a schedule of expected license amendment request (LAR) submittals to adopt TSTF-577 (ADAMS Accession No. ML21126A072).

NRC staff discussed improvements to the NRC staffs model safety evaluation (SE) of TSTF-505, Risk-Informed Completion Times. The revised model SE does not change the NRC staffs findings. The SE will better document the NRC staff review and will be more streamlined.

The status of active traveler reviews prepared by the TSTF is in ADAMS at Accession

N. Jordan No. ML21126A073.

• NRC staff and the TSTF will hold a public teleconference on May 13, 2021, to discuss the review of TSTF-576, "Revise Safety/Relief Valve Requirements. A revised schedule will be set after the teleconference.

• NRC staff review of TSTF-580, "Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, is ahead of schedule.

• The NRC staff and the TSTF will hold a public teleconference to discuss draft traveler TSTF-585, "Revise LCO [Limiting Condition for Operation] 3.0.3, on June 10, 2021.

• The NRC staff and the TSTF will hold a public teleconference to discuss draft traveler TSTF-588, "Remove List of COLR [Core Operating Limits Report] Methods." No date has been set yet, but it will likely be in June 2021.

NRC staff and the TSTF are continuing to search for an old memorandum related to the evaluation of LCOs included under the regulation at Title 10 of the Code of Federal Regulations (10 CFR) Paragraph 50.36(c)(2)(ii). The document is: AIF/TSIP Criteria Trial Application -

Wolf Creek/Limerick TS Split, dated March 21, 1986, to Edward J. Butcher, Chief, Technical Specification Coordination Branch, from Kulin D. Desai, Technical Specification Coordination Branch, Division of Human Factors Technology, Office of Nuclear Regulation, U.S. NRC, Washington, D.C.

The NRC staff and the TSTF discussed the adequacy of the current STS for use of Accident Tolerant Fuels (ATF) and/or High Burnup (HBU) Fuels. STS changes to Section 4.2 (Fuel Design) may be needed to permit use of these fuels. The TSTF is also considering a project to review the design features section of the STS.

The TSTF gave a presentation on the interaction of TS surveillances and 10 CFR 50.69 (ADAMS Accession No. ML21126A071). The TSTF is developing guidance for licensees to address their TSs when implementing, or planning to implement, 10 CFR 50.69. After the meeting, the TSTF provided a draft of their guidance (ADAMS Accession No. ML21155A160).

Some licensees have TSs that reference the Inservice Testing (IST) Program to meet the surveillance requirements for specific components. Following the TSTF presentation, the NRC staff agreed that the relationship between 10 CFR 50.69 and the TSs might be a challenge for specific nuclear power plants where the TSs reference the IST Program for certain surveillance requirements. When implementing 10 CFR 50.69, licensees are allowed to apply alternative treatment rather than the IST requirements specified in 10 CFR 50.55a(f) for safety-related structures, systems and components (SSCs) with low safety significance (RISC-3 SSCs) and non-safety-related SSCs with low safety significance (RISC-4 SSCs). Safety-related SSCs with high safety significance (RISC-1 SSCs) and non-safety-related SSCs with high safety significance (RISC-2 SSCs) continue to be required to meet the applicable IST requirements specified in 10 CFR 50.55a(f). When 10 CFR 50.69 was issued, the Commission stated in the Federal Register notice for the final rule that TSs are not within the scope of 10 CFR 50.69.

During the public meeting, the TSTF suggested that the definition of IST Program in the TSs for some nuclear power plants might be sufficiently broad to allow the use of the alternative treatment of the 10 CFR 50.69 program to meet surveillance requirements for RISC-3 and RISC-4 SSCs within the scope of 10 CFR 50.69. The NRC staff indicated that it would need to discuss this interpretation of the definition of IST Program in the TSs with appropriate NRC staff members. In the interim, the NRC staff recommended that licensees who are planning to

N. Jordan submit a LAR to implement 10 CFR 50.69, or have received a license amendment to implement 10 CFR 50.69, discuss the specific language of their TSs with the applicable NRC staff to determine whether any changes are needed to the TSs to ensure that appropriate surveillance requirements continue to be required for components that are within the scope of the alternative treatment allowed by 10 CFR 50.69.

Previously Joe Donoghue, Director of the Division of Safety Systems, had asked the TSTF members if there were any other NRC/Industry interactions that a process like the NRC/TSTF could be beneficial. The TSTF members stated that they are evaluating the topical report process for possible inclusion. The goal for both programs is to find the best generic solution to a problem and both are lower priority in Office of Nuclear Reactor Regulation (NRR) workload.

Vic Cusumano, Chief of the Technical Specifications Branch, suggested that industry evaluate other processes where a Consolidated Line Item Improvement Process (CLIIP) approach could be used.

Joe Donoghue also commented that the ATF and/or HBU fuel are important areas for NRC. He is glad to see we are opening a dialogue. The goal is to have batch loads of HBU fuel by 2025.

The TSTF plans to submit traveler TSTF-584, BWR RWCU Isolation on SLC [Standby Liquid Control] Initiation Removal, by the end of 2021.

Industry is planning coordinated licensee submittals to adopt TSTF-501, Revision 1, "Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control, and TSTF-547, Revision 1, "Clarification of Rod Position Requirements.

No public comments were received.

The next meeting will be August 5, 2021. There is uncertainty as to whether it will be a teleconference or an in-person meeting. The final meeting for 2021 is planned for November 18.

Project No. 753

Enclosure:

As stated cc: See next page CONTACT: Michelle C. Honcharik, NRR/DSS 301-415-1774

Package: ML21126A068, Meeting summary: ML21127A275; Meeting notice: ML21118A814; Meeting handouts ML21126A071, ML21126A072, ML21126A073

• via Email NRR-106 OFFICE NRR/DSS/STSB* NRR/DSS/STSB/Acting BC NRR/DSS/STSB NAME MHoncharik NJordan MHoncharik DATE 6/4/2021 6/9/2021 6/10/2021 LIST OF ATTENDEES NRC Staff Honcharik, Michelle Russell, Andrea Donoghue, Joseph Green, Kimberly Harbuck, Craig Wilson, Joshua Ashley, Clinton Scarbrough, Thomas West, Khadijah Smith, Steve Cusumano, Victor Kuntz, Robert Tilton, Caroline Sweat, Tarico Hamm, Matthew Harvey, Jackie Grover, Ravi Industry/Public Kusumawatimurray, Putri (Exelon Nuclear)

Mann, Brian (TSTF, EXCEL Services)

Joyce, Ryan (TSTF)

Sparkman, Wesley (TSTF)

Holderbaum, Chad Miksa, Jim (TSTF, LSC Chair - Entergy)

Gross, Karl (NuScale Power)

Vaughan, Jordan L (TSTF)

Couture, Phil Enclosure

Technical Specifications Task Force Project No. 753 cc:

Technical Specifications Task Force c/o EXCEL Services Corporation 11921 Rockville Pike, Suite 100 Rockville, MD 20852 Attention: Brian D. Mann E mail: brian.mann@excelservices.com James P. Miksa Entergy Nuclear Operations, Inc.

Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043 E mail: jmiksa@entergy.com Jordan L. Vaughan Duke Energy EC07C / P.O. Box 1006 Charlotte, NC 28202 E mail: jordan.vaughan@dukeenergy.com Ryan M. Joyce Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-274-EC Birmingham, AL 35243 E mail: rmjoyce@southernco.com Dwi Murray Exelon Generation 4300 Winfield Road Warrenville IL 60555 E mail: Putri.Kusumawatimurray@exeloncorp.com Wesley Sparkman Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-274-EC Birmingham, AL 35242 E mail: wasparkm@southernco.com