ML21047A290
| ML21047A290 | |
| Person / Time | |
|---|---|
| Issue date: | 02/16/2021 |
| From: | Tekia Govan NRC/NRR/DRO/IRAB |
| To: | Masters A NRC/NRR/DRO/IRAB |
| Govan T | |
| References | |
| Download: ML21047A290 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 16, 2021 MEMORANDUM TO:
Anthony D. Masters, Chief Reactor Assessment Branch Division of Reactor Oversight Office of Nuclear Reactor Regulation FROM:
Tekia V. Govan, Project Manager /RA Reactor Assessment Branch Division of Reactor Oversight Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE REACTOR OVERSIGHT PROCESS MONTHLY PUBLIC MEETING HELD ON JANUARY 27, 2021 On January 27, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff hosted a public meeting with the Nuclear Energy Institutes (NEIs) Reactor Oversight Process (ROP) Task Force executives, and other senior industry executives, to discuss the staffs progress on the ROP initiatives. The topics discussed during this teleconference are described below.
Performance Indicator (PI) Frequently Asked Questions (FAQ)
FAQ 20-03: Restoration of Train Monitoring After PRA Model Changes (ADAMS as Accession No. ML21021A090)
This FAQ was submitted to propose that when restoring trains/segments to mitigating system performance index (MSPI) monitoring, unavailability data be required only moving forward (including the quarter in which monitoring is restored) and not for the 12 preceding quarters.
After the review of the proposed change, the NRC staff agreed to the proposed language to modify guidance in NEI 99-02, Revision 7, "Regulatory Assessment Performance Indicator Guideline. The FAQ status was transitioned to Tentatively Approved and will be transitioned to Final Approved at the February 2021 ROP meeting.
FAQ 20-05: River Bend Station (RBS) Unplanned Scram May 2019 (ADAMS as Accession No. ML21028A347)
This FAQ is associated with an RBS feedwater heater tube leak that required a rapid shutdown for repair on May 31, 2019. RBS believed that this event should be counted as an unplanned scram per 7,000 Critical Hours (IE01). After the staffs review of this FAQ and other documents CONTACT: Tekia V. Govan, NRR/DRO 301-415-6197
Related to the event, it was determined that the event that occurred on May 31, 2019, should be classified as an unplanned scram with complications (IE03). The FAQ status was transitioned to Tentatively Approved and will be transitioned to Final Approved at the February 2021 ROP meeting.
FAQ 20-06: Grand Gulf Nuclear Station (GGNS) Turbine Controls Upgrade Scrams One-Time Exemption (ADAMS as Accession No. ML21028A387)
GGNS submitted this PI FAQ requesting that only the first of two scrams that were associated with a turbine controls upgrade project (on May 25, 2020 and August 8, 2020) be counted as one scram, with the basis that the design errors that contributed to both scrams were the result of the same vendor not validating assumptions as part of the Turbine Controls Upgrade Project.
Based on the staffs review of the information provided within the FAQ and information gathered during a December 29, 2020 public meeting (ADAMS as Accession No. ML21013A550), the staff determined that both scrams should be counted in the IE01 PI. The FAQ status was transitioned to Tentatively Approved and will be transitioned to Final Approved at the February 2021 ROP meeting.
FAQ 21-01: Unplanned Scrams with Complications AP1000 (ADAMS as Accession No. ML21028A391)
This FAQ was submitted by NEI to seek implement changes to NEI 99-02 that were proposed in a whitepaper approved by the NRC at an ROP public meeting on November 18, 2020 (ADAMS Accession Nos. ML20322A339 and ML20339A592). After the staffs review of the propose changes, this FAQ status was transitioned to Tentatively Approved and will be transitioned to Final Approved at the February 2021 ROP meeting.
Lessons Learned and Best Practices on Reactor Oversight During the COVID 19 Pandemic The NRC staff briefed industry representatives and members of the public on the initial lessons learned and best practices identified on the regulatory oversight of operating power reactors during the COVID-19 public health emergency (ADAMS Accession No. ML21022A200). The lessons learned and best practices are documented in the report entitled, Initial Report on Challenges, Lessons Learned and Best Practices from the 2020 COVID-19 Public Health Emergency - Focus on Regulatory Oversight of Operating Nuclear Reactors, (ADAMS Accession No. ML20308A389).
A 17-member team of NRC staff primarily used the results of a 24-question survey that was sent to all NRC inspectors, staff and managers involved in the oversight of operating power reactors.
The survey results were evaluated and used to develop recommendations to improve oversight during the current and future public health emergencies and non-emergency conditions.
The recommendations, which have not been decided upon, focus on three major areas which include:
Information Technology Capability and Reliability Remote Inspection Practices Inspection Guidance Enhancements
External stakeholders, including industry representatives and a member of the public commented on the following areas:
use of quantitative measures for the lessons learned and best practices effort value of in-person inspections versus remote inspections need for standardized approaches on preparations for team inspections whether lessons learned identified in the report should apply to non-emergency conditions potential cyber concerns for NRC remote access to plant information and licensee programs whether increased remote oversight had caused an apparent reduction in number of inspection findings The staff discussed these areas during the meeting with no additional follow-up questions. An industry representative stated that the industry was performing a lessons-learned initiative and would present the results at a future public meeting.
10 CFR Part 50.55a/Power-Operated Valve (POV)
The NRC staff provided an overview of the first year of implementing POV inspections. This overview prompted a discussion on the 2017 rule change in which the NRC incorporated by reference the 2012 Edition of the ASME OM Code in 10 CFR 50.55a. The NRC staff answered three questions from industry regarding that rule and POV inspections:
- 1. What requirement will inspectors verify regarding supplemental valve position indication requirements?
NRC Staff Response: Inspectors would inspect to 10 CFR 50.55a(b)(3)(xi), and paragraph ISTC-3700 of the ASME OM Code. NRC staff also added that inspectors will verify that the licensees have performed the testing in accordance with the ISTC-3700 schedule of two years since the previous testing and if licensees use the 6 month grace period they will need to have justified the reason in accordance with the ASME OM Code.
- 2. Is concurrent testing for supplemental valve position indication testing required?
NRC Staff Response: No, concurrent testing is not required as allowed by ISTC-3700.
- 3. When is compliance with 10 CFR 50.55a(b)(3)(xi) required and what is the frequency of the supplemental testing?
NRC Staff Response: The rule condition to become effective when updating to the 2012 Edition of the OM Code and that ISTC-3700 requires valve position testing every 2 years and the (b)(3)(xi) condition applies when the ISTC-3700 test is performed (2 years from the previous test).
Industry representatives stated that they did not agree with the NRC staff position, and that they believed the next ISTC-3700 test was to be performed within 2 years from updating to the 2012 Edition of the OM code. The NRC staff shared that this question and answer was specifically addressed in the rulemaking process and package and can be found on pages 37-38 (ADAMS Accession No. ML16130A531), which specifically stated the 2 year performance did not begin after updating to the 2012 Edition of the Code and therefore the NRC position was finalized in the 2017 rulemaking. The NRC
staff and industry representatives discussed a few examples of when testing was required. A visual representation of what is acceptable can be found at under ADAMS Accession No. ML21032A238. The NRC staff also discussed with industry that the NRC is open to the option of requesting relief to extend testing beyond the 2 years and grace period if that was in the best interest of safety of the plant and valves in question.
Inspection Procedure (IP) 370060 - Enhancement Working Group Updates The NRC staff provided an update on working group activities associated with enhancement of IP 37060, 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components Inspection (ADAMS Accession No. ML20182A687). Stakeholders were informed of the development of IP 37060 Potential Enhancement Items (ADAMS Accession No. ML20345A122) which will used to develop draft recommendations for enhancing IP 37060.
Independent Spent Fuel Storage Installation (ISFSI) Enhancement Update The NRC staff provided an update on the overall status of the ISFSI inspection program enhancement activities. As background, the staff discussed that during the last update the NRC was performing implementation activities for the final approved recommendations. This included revisions to the ISFSI inspection program documents as well as a new inspection manual chapter for the ISFSI inspection program technical basis. The staff then discussed that at this time, the NRC has completed the revisions to the ISFSI inspection program documents, specifically the suite of ISFSI inspection procedures, ISFSI inspection program manual chapter, and new ISFSI inspection program technical basis document. All of these program documents have been issued as of late December 2020 and went into effect on January 1, 2021. The staff also noted that three ISFSI IPs (IP 60854.1, IP 60855.1, and IP 60856.1) are planned to be retired in the near future but are still available and on the NRC inspection manual public webpage so that inspections can be closed out from 2020.
NEI Reactor Oversight Process Whitepaper - Counting of DEP Opportunities from an Actual Emergency Following a Retraction of the Emergency Declaration The NRC staff re-opened NEI White Paper, Counting of DEP Opportunities from an Actual Emergency Following a Retraction of the Emergency Declaration, (ADAMS Accession No. ML19339H435) to provide an opportunity to further enhance the language to ensure consistent understanding of the issue.
Meeting Action Items NEI has committed to providing a revision to the White Paper, Counting of DEP Opportunities from an Actual Emergency Following a Retraction of the Emergency Declaration.
Communicating with the NRC staff At the start of all ROP public meetings, the project manager provides contact information for the public to use to provide their name as a participant in the meeting. This contact information is also provided for submitting questions and comments to the NRC technical staff. Please note that any questions and/or comments pertaining to the ROP project can be sent to Tekia.Govan@nrc.gov. Questions and/or comments will be forward to the appropriate NRC staff. The staff also mentioned the role out of the Contact Us about ROP page on the new ROP website, which can also be used to submit questions and comments regarding the ROP initiative (https://www.nrc.gov/reactors/operating/oversight/contactus.html).
Conclusion At the end of the meeting, NRC and industry management gave closing remarks. NEI expressed appreciation for the open dialogue and willingness of NRC staff to hear industry views. The NRC management stressed the importance of the NRC being focused on providing reasonable assurance of public health and safety when considering changes to the ROP.
The enclosure provides the attendance list for this meeting.
Enclosure:
As stated
- = via email OFFICE NRR/DRO/IRAB/PM NRR/DRO/IRSB NRR/DRO/IRAB/BC NRR/DRO/IRAB/PM NAME TGovan*
BCurran*
AMasters*
TGovan*
DATE 02/16/2021 02/16/2021 02/16/2021 02/16/2021
Enclosure LIST OF ATTENDEES REACTOR OVERSIGHT PROCESS MONTHLY PUBLIC MEETING January 27, 2021, 9:30 AM to 12:00 PM Name Organization1 Name Organization James Gilbert Unknown Alex Garmoe NRC Ken Heffner Certrec Kevin Hsueh NRC Jim Slider NEI Jason Drake NRC Matthew Euten Unknown Julio Lara NRC Marcellus Ruff Exelon Nuclear Heather Jones NRC Tim Riti NEI Rick Deese NRC Robin Ritzman Curtiss Wright Antonios Zoulis NRC Martin Murphy Xcel Energy Mike King NRC John Giddens Entergy Tekia Govan NRC Steve Catron Next Era Daniel Merzke NRC Joe Cole Vogtle Licensing Todd Keene NRC Tony Zimmerman Duke Energy Shakur Walker NRC William Reynolds Exelon Angela Buford NRC Carlos Sisco Winston Strawn LLC Anthony Masters NRC Christopher Pendleton Southern Nuclear Thomas Hipschman NRC Daniel McGinnis Dominion Energy Gurjendra Bedi NRC Keith Brown Unknown Charles Murray NRC Rob Burg EPM Christopher Cauffman NRC Roy Linthicum Exelon Paula Cooper NRC Larry Nicholson Certrec Eric Duncan NRC Tom Basso Unknown Scott Burnell NRC Bill Doody PSEG Nuclear Mike Montecalvo NRC David Young NEI Russell Gibbs NRC Ray Kellar Unknown Manuel Crespo NRC Greg Holmes GE Hitachi Billy Gleaves NRC Cheryl Gayheart Southern Nuclear Bill Maier NRC Curt Reynolds Exelon David Garmon-Candelaria NRC Steve Sayovitz Unknown Joylynn Quinones-Navarro NRC Maggie Staiger Unknown Ravi Grover NRC Chris Nolan Unknown Michael Webb NRC Mandy Halter Entergy Russell Felts NRC David Dobson Unknown Marc Ferdas NRC Adam Goodman Unknown Ken Kolaczyk NRC Kevin Walden Unknown John Hughey NRC 1 Unknown organization indicates that the participants affiliation was not provided by the issuance of this meeting summary.
Name Organization Name Organization Jack Hicks Unknown Thomas Fredette NRC Rodney Vickers Exelon Aron Lewin NRC Justin Bresson Unknown Dave Werkheiser NRC Michael Ellett Indian Michigan Power Gregory Suber NRC Marty Phalen Unknown Douglas Bollock NRC Ashley Burress Exelon Jason Kozal NRC Shannon Rafferty-Czincila Exelon Robert Krsek NRC Nicholas Hansing Unknown Thomas Scarbrough NRC Pamela Frazier Unknown Don Johnson NRC Wesley Sparkman Unknown Derek Widmayer NRC David Gudger Exelon Ross Telson NRC Isaac Mulhern Unknown Coleman Curran NRC Ron Gaston Unknown Michael McCoppin NRC James Love Unknown Rodney Clagg NRC Jonathan Hartman Southern Co.
Kent Chambliss NRC Enrique Melendez Asensio CSN, Spanish Nuclear Regulator Chris Kline NRC James Pak Dominion Energy Juan Arellano NRC Casey Smith Unknown Andy Rosebrook NRC David Barrow Unknown Kevin Fay NRC Jared Smith Exelon Steve Smith NRC Denver Atwood Unknown David Rivard NRC Fredrick Sarantakos Exelon Deann Raleigh NRC Brad Bishop Unknown Megan Gangewere NRC Eric Magnuson NRC Michael Hay NRC Muzammil Siddiqui NRC Timothy Steadham NRC Jeff Mitman NRC Nick Smalley NRC Chris Miller NRC Rayo Kumana NRC Raymond Trelka NRC Karla Stoedter NRC Laura Kozak NRC Robert Vadella NRC Michael Farnan NRC Cheryl Khan NRC Dariusz Szwarc NRC Dong Park NRC Ed Miller NRC Eli Garcia NRC Jeremy Tapp NRC Julie Kulik NRC Nicole Fields NRC Tyler Beck NRC Bridget Curran NRC Audrey Klett NRC Amber Donley NRC Lisa Regner NRC Larry Grimes NRC Steve Campbell NRC Matthew Leech NRC