ML21221A156

Summary of Quarterly Meeting with Technical Specifications Task Force

ML21221A156
Person / Time
Site:	Technical Specifications Task Force
Issue date:	08/23/2021
From:	Michelle Honcharik NRC/NRR/DSS/STSB
To:	Natreon Jordan NRC/NRR/DSS/STSB
Honcharik M, NRR/DSS, 301-415-1774
Shared Package
ML21221A158	List: ML21217A069 ML21221A156
References
Download: ML21221A156 (6)

Text

N. Jordan August 23, 2021 MEMORANDUM TO: Natreon J. Jordan, Acting Branch Chief Technical Specifications Branch Division of Safety Systems Office of Nuclear Reactor Regulation Signed by Honcha FROM: Michelle C. Honcharik, Senior Project Manager on 08/23/21 Technical Specifications Branch Division of Safety Systems Office of Nuclear Reactor Regulation

SUMMARY

OF AUGUST 5, 2021, QUARTERLY MEETING WITH THE TECHNICAL SPECIFICATIONS TASK FORCE On August 5, 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. ML21203A015. The TSTF provided one handout for the meeting, which is available at ADAMS Accession No. ML21217A069. A list of attendees is enclosed.

Due to higher priority items, the Revision 5 of the Standard TSs (STS) is now scheduled to be issued by the end of August 2021.

It was agreed that for the six licensees that have not yet adopted TSTF-566, they could submit one license amendment request to adopt both TSTF-566 and TSTF-580.

The status of active traveler reviews prepared by the TSTF is in ADAMS at Accession No. ML21217A069.

The TSTF submitted its response to NRC staffs request for additional information (RAI) and Revision 1 of TSTF-576, "Revise Safety/Relief Valve Requirements (ADAMS Accession No. ML21174A109). The NRC staff is reviewing the RAI responses and revision to the traveler. The NRC anticipates providing feedback and/or additional RAI questions by the end of August.

CONTACT: Michelle C. Honcharik, NRR/DSS 301-415-1774

N. Jordan The NRC staff and the TSTF will hold a second public teleconference to discuss draft traveler TSTF-585, "Revise LCO [Limiting Condition for Operation] 3.0.3, in September.

The NRC staff provided feedback on draft traveler TSTF-588, "Remove List of COLR

[Core Operating Limits Report] Methods," via e mail (ADAMS Accession No. ML21218A089). The TSTF will let the NRC know when they are ready to discuss it.

NRC discussed the allowance of normal/expected leakage from isolation devices with respect to drain time calculations; industry agreed to discuss it during their next Boiling Water Reactor Owners' Group (BWROG) meeting. Traveler TSTF-542 focuses the operator's attention on water inventory during shutdown and reduces the likelihood of having a draining event that could impact plant safety. When required by TSs, the operators verify drain time 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Implementation details for calculating drain time are contained in STS SR 3.5.2.1 Bases. The STS SR 3.5.2.1 Bases state in part, Normal or expected leakage from closed systems or past isolation devices is permitted. The NRC sought clarification regarding the consistent application of this STS Bases statement. The NRC provided the following scenario to facilitate the discussion: if the recirculation system isolation valves are being used as a maintenance boundary with leak-by directed to the sump and that quantified leak-by would result in a drain down time less than 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, then should that actual leakage be factored into required compensatory measures? The industry shared that the drain time calculation focused on flow paths that are assumed to open instantaneously and are not subsequently isolated and that normal or expected leakage would be addressed by LCO 3.5.2 requirements to have one lower pressure emergency core cooling system (ECCS) injection/spray subsystem operable.

The industry agreed to discuss this issue during their next BWROG meeting. .

NRC discussed the need for more clarity in the applications to adopt travelers, specifically for plants with shared systems and design differences. The TSTF agreed to work with the NRC staff on improvements to the model applications. NRC staff will provide specific examples to the TSTF.

NRC issued Regulatory Guide (RG) 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities, on December 31, 2020 (ADAMS Accession No. ML20238B871). RG 1.200 created the possibility for licensees to develop revised language for TS 5.5.[20] paragraph (e), that would differ from that which was approved in TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b(ADAMS Accession No. ML18183A493). During a public meeting on June 3, 2021 (ADAMS Accession No. ML21131A244), the NRC staff and industry discussed TS language that could be used to leverage flexibilities relating to the newly developed method in RG 1.200, Revision 3. The language discussed during the June 3, 2021, meeting was of draft form and not approved by the NRC staff. It would need to be reviewed and approved via a license amendment in order for a licensee to adopt it. The information in RG 1.200, Revision 3, and the June 3, 2021, meeting summary can be used by licensees or the TSTF for any future actions in this area. The NRC does not plan to issue any additional written guidance concerning this. The TSTF said they may pursue a traveler to revise TS 5.5.[20] paragraph (e) related to PRA methods.

On July 8, 2021, the NRC issued Draft Version 1.2 of Project Plan to Prepare the U. S. Nuclear Regulatory Commission for Efficient and Effective Licensing of Accident Tolerant Fuels [ATF]

(ADAMS Accession No. ML21188A117). NRC staff noted that the project plan is still open for comments and provided the email address to send comments on the draft. Page 52 of the pdf in ADAMS (page A-7), contained several items related to potential changes needed in design features sections of the STS to accommodate fuel changes such as enrichment beyond

N. Jordan 5 percent, chromium coated cladding, and doped pellets. NRC staff did not have any new information to present to the TSTF, but reiterated the intent to maintain an open dialog on the subject as it evolves. The TSTF commented that they will be voting on whether to start a project on improving the design features section of the STS, which would include fuel designs and may address this.

The TSTF informed Joe Donoghue that the Owners Groups (OGs) have had several meetings on possible improvements to the topical report review process. The OGs will engage with the licensing process branch to discuss further.

Traveler TSTF-584, BWR RWCU Isolation on SLC [Standby Liquid Control] Initiation Removal, will be discussed at OG meeting to decide if they will submit it to the NRC.

A traveler to eliminate PWR TS requirement for automatic diesel generator (DG) start during shutdown (likely TSTF-589) is on track to be submitted by the end of the calendar year. The traveler would remove the TS requirement for an automatic DG start in Modes 5 and 6, similar to the TS change approved in TSTF-582. The TSTF will provide a draft traveler, but they do not plan on requesting a pre-submittal meeting because the change is nearly identical that approved in TSTF-582.

No public comments were received.

The next meeting will be November 18, 2021.

Project No. 753

Enclosure:

As stated cc: See next page

Package: ML21221A158, Meeting summary: ML21221A156; Meeting notice: ML21203A015; Meeting handout ML21217A069

• via Email NRR-106 OFFICE NRR/DSS/STSB* NRR/DSS/STSB/Acting BC NRR/DSS/STSB NAME MHoncharik NJordan MHoncharik DATE 8/12/2021 8/23/2021 8/23/2021 LIST OF ATTENDEES NRC Staff Honcharik, Michelle Scarbrough, Thomas Donoghue, Joseph Smith, Steve Ashley, Clinton Sweat, Tarico West, Khadijah Hughey, John Tilton, Caroline Scott, Christian Hamm, Matthew Tseng, Ian Grover, Ravi Krepel, Scott Wilson, Joshua Weerakkody, Sunil TSTF Mann, Brian (TSTF, EXCEL Services)

Joyce, Ryan (TSTF)

Miksa, Jim (TSTF, LSC Chair - Entergy)

Vaughan, Jordan L (TSTF)

Industry/Public Bergman, Jana (Scientech)

Gross, Karl (NuScale Power)

Mahan, Howard (Entergy)

Linthicum, Roy R.:(Exelon Nuclear)

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@duke-energy.com Ryan M. Joyce Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-274-EC Birmingham, AL 35243 E mail: rmjoyce@southernco.com David M. Gullott Exelon Generation 4300 Winfield Road Warrenville, IL 60555 E mail: David.Gullott@exeloncorp.com Wesley Sparkman Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-274-EC Birmingham, AL 35242 E mail: wasparkm@southernco.com