ML17342A339
| ML17342A339 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, Watts Bar  |
| Issue date: | 12/08/2017 |
| From: | Jo Bridge NRC/NRR/DIRS/IRAB |
| To: | Gregory Bowman NRC/NRR/DIRS/IRAB |
| Bridge J, NRR/DIRS, 301-415-4052 | |
| Shared Package | |
| ML17342A333 | List: |
| References | |
| Download: ML17342A339 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 8, 2017 MEMORANDUM TO: Gregory T. Bowman, Chief Reactor Oversight Process Assessment Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation FROM:
Joanna L. Bridge, Reactor Operations Engineer /RA/
Reactor Oversight Process Assessment Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE REACTOR OVERSIGHT PROCESS WORKING GROUP PUBLIC MEETING HELD ON NOVEMBER 16, 2017 On November 16, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff hosted a Reactor Oversight Process (ROP) Working Group (WG) public meeting with the Nuclear Energy Institutes (NEIs) ROP Task Force and other industry representatives. A summary of the discussion topics is provided below.
contains the meeting attendance list.
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML17342A364) contains the presentations and handouts discussed during the meeting.
(ADAMS Accession No. ML17342A393) contains the Performance Indicator (PI)
Frequently Asked Questions (FAQs) Log and the FAQs discussed during the meeting.
Frequently Asked Questions In the area of the PI program, FAQs 17-04 and 17-05 were the only FAQs that were open at the
Enclosures:
- 1. Attendance List
- 2. Presentations and handouts
- 3. FAQs CONTACT:
Joanna Bridge, NRR/DIRS/IRAB 301-415-4052
time of this meeting. NRC staff will review them and provide a response to the industry at the next ROP public meeting in January 2018.
Criteria for Closure of Inspection Procedure (IP) 95001 A brief discussion was held on the criteria for successful completion of Inspection Procedure (IP) 95001, Supplemental Inspection Response to Action Matrix Column 2 Inputs, based on recent examples where these inspections were not completed successfully the first time. The NRC and the industry plan to have further dialog on this topic at a public meeting in 2018.
Significance Determination Process (SDP) Topics The NRC summarized and provided feedback on an NEI letter on SDP updates and prioritization. The NEI letter was provided on October 12, 2017, and can be found via ADAMS Accession No. ML17338A031.
Industry is reviewing a revision to Inspection Manual Chapter (IMC) 0609, Appendix F, Fire Protection Significance Determination Process. This revision was made publicly available in October 2017 (ADAMS Accession No. ML17089A411) to support discussion at this meeting.
Industry representatives indicated that they intend to complete their review the revised document and provide the NRC with any feedback in mid-December.
The Divisions of Risk Assessment (DRA) and Inspection and Regional Support (DIRS) in the NRCs Office Nuclear Reactor Regulation (NRR) discussed a revision to IMC 0609, Appendix O, Significance Determination Process for Mitigating Strategies and Spent Fuel Pool Instrumentation. The purpose of this revision is to address comments from the ROP feedback forms, with a goal of enhancing clarity of the screening questions in the SDP to reduce the number of cases where the SDP unnecessarily directs the inspector to IMC 0609, Appendix M, Significance Determination Process Using Qualitative Criteria.
Consequential-Steam Generator Tube Rupture (C-SGTR)
The staff informed the public that they are updating the guidance in the Risk Assessment Standardization Project (RASP) Handbook for this area. Upon finishing its internal review to remove proprietary information, the staff will provide the ADAMS accession numbers of the guidance documents to the public and the industry.
Licensee Event Reporting The Operating Experience Branch (IOEB) in the NRR is working to improve the licensee event report (LER) submission process under Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.73 through the use of a voluntary online LER submittal tool. IOEB briefed industry on the potential benefits of this initiative, including better capture of structured data, improved searchability and data accessibility for all users, consistent document quality, and reduced cost and burden to the NRC and licensees. Staffs presentation included a demonstration of a developmental version of the online LER submittal tool. Industry provided some initial feedback on the tool. At a future public meeting, staff hopes to learn more about licensees internal LER review and submittal processes in order to determine what improvements can be made to the online LER submittal tool.
Engineering Inspections The engineering inspection working group (EIWG) continues to make progress with both internal and external stakeholders and have obtained alignment on number of key points:
- 1) the heat sink and boric acid inspections can be accomplished as a focused sample during another inspection,
- 2) the in-service inspection can be improved by modifying both focus areas and agility,
- 3) the engineering design inspections can be improved by modifying both focus areas and
- agility,
- 4) the fire protection inspection can be improved by modifying both focus areas and agility,
- 5) the 10 CFR 50.59 inspection can be accomplished as a focused sample during a comprehensive engineering inspection, and
- 6) licensee activities that could result in the introduction of latent conditions should be inspected or assessed annually.
The next EIWG public meeting is scheduled on December 12, 2017, and is focused on addressing a number of important open items. The open items include:
- 1) the length of the inspection cycle or frequency of certain inspections,
- 2) how fire protection inspections should be accomplished in the future,
- 3) future comprehensive engineering inspections,
- 4) industry self-assessment initiative,
- 5) pilot of industry proposed self-assessment process,
- 6) measurement of effectiveness of changes to engineering inspection procedures, and
- 7) details and descriptions on what current industry performance indicators/practices could be used to reliably track engineering performance, as well as identify latent conditions
Working Group to Update the ROP for Regulatory Actions Taken Following the Fukushima Dai-ichi Accident The ROP Inspection Branch (IRIB) in the NRR/DIRS shared with stakeholders that an NRC working group has been established to consider how to integrate oversight of regulatory actions taken by the NRC following the Fukushima Dai-ichi accident into the ROP. The charter for this working group can be found via ADAMS Accession No. ML17164A285. IRIB discussed the charters scope, key expectations, communications, and milestones. The goal is to begin implementation of any new ROP program documents by January 1, 2020. As a minimum, communications with external stakeholders will occur upon commencement and completion of key milestones. Additional communication opportunities can be scheduled if desired.
Safety Culture Monitoring The industry provided a brief on the updates being made to improve safety culture across the industry. Slides from this presentation can be found in Enclosure 2.
Actions from this Meeting:
- 1) Sunil Weerakkody (NRR/DRA) will provide the expected publication date of Regulatory Guide (RG) 1.174.
- a. Answer: The estimated publication date for RG 1.174, Revision 3, is late-February/early-March 2018.
- 2) Sunil Weerakkody (NRR/DRA) will provide an update on RASP.
- a. Answer: Once the draft RASP guidance on C-SGTR is made publicly available, the staff will make the ADAMS accession number available. The NRC will provide an update on this action at the next ROP public meeting.
- 3) Alex Garmoe (NRR/DIRS) will provide a status update on revisions to the IMC 0609 appendixes.
- a. Answer:
SDP Appendix Revision Currently in Progress?
Status/Notes Appendix A - At Power SDP No Will need to be considered for new reactor revisions.
Appendix B - Emergency Preparedness SDP No Awaiting upcoming letter from NEI with industry perspectives on revising this Appendix.
Appendix C - Occupational Radiation Safety SDP Yes Draft update in progress - update was previously discussed at a public meeting, staff plans to solicited public feedback in early 2018.
Appendix D - Public Radiation Safety SDP Yes Draft update in progress - update was previously discussed at a public meeting, staff plans to solicited public feedback in early 2018.
Appendix E - Security SDP Yes Draft update in progress - closed meeting in December 2017 to discuss ongoing revision with industry.
Appendix F - Fire Protection SDP Yes Awaiting industry comments on draft revision, which was made publicly available in October 2017.
Appendix G - Shutdown SDP No Will need to be considered for new reactor revisions.
Consider future revision to resolve numerous feedback forms.
Appendix H - Containment Integrity SDP No Will need to be considered for new reactor revisions.
Consider future revision to disposition a feedback form on defining close in population.
Appendix I - Operator Requalification SDP No Draft update in progress - no change to content but Appendix will be reorganized to better sync with an upcoming IP 71111.11 update.
No update needed for new reactors.
Appendix J - Steam Generator Tube Integrity SDP No None currently identified.
Appendix K - Maintenance Risk SDP No None currently identified.
Appendix L - B.5.b SDP No Consider whether this could be combined with the new mitigating strategies SDP.
Appendix M - Qualitative Criteria SDP Yes Staff working to clearly define the scope of the recommended update.
Update will be provided as an option in response to SRM-SECY-13-0137 direction on considering use of qualitative factors for operating reactors.
Will need to be considered for new reactor revisions.
Appendix O - Mitigating Strategies and Spent Fuel Pool SDP Yes Staff revising earlier draft to preclude premature entry into Appendix M.
Will need to be considered for new reactor revisions.
- 4) NEI will send updated FAQs with serialized numbers.
- a. Answer: FAQs with serial numbers are included in Enclosure 3.
- 5) NEI will coordinate with NRC to establish 2018 ROP public meeting dates.
- a. Answer: In progress. An update will be provided at the next ROP public meeting
G. Bowman DISTRIBUTION:
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- concurred via email OFFICE NRR/DIRS/IRAB BC:NRR/DIRS/IRIB BC:NRR/DIRS/IRAB NRR/DIRS/IRAB NAME JBridge SAnderson GBowman JBridge DATE 12/4/17 12/7/17 12/7/17 12/8/17 OFFICIAL RECORD COPY
REACTOR OVERSIGHT PROCESS PUBLIC MEETING ATTENDANCE LIST November 16, 2017 Steve Alferink NRC Munehisa Iwamoto Japanese Electric Power Information Center Eric Bowman NRC Eric Katzman Next Era Energy Gregory Bowman NRC Roy Linthicum Exelon Joanna Bridge NRC Daniel McGinnis Dominion Energy Robert Dexter NRC Larry Parker STARS Alex Garmoe NRC Deann Raleigh Curtiss Wright Tony Gody NRC Richard Rasmussen Conger & Elsea Jim Isom NRC Mark Reidmeyer Certrec Molly Keefe-Forsyth NRC Robin Ritzman First Energy Robert Krsek NRC Jim Slider NEI Michael Levine NRC Lenny Sueper Xcel Energy Benjamin Mabbott NRC Ryan Treadway Duke Energy Chris Miller NRC Steve Vaughn NEI Daniel Merzke NRC Andy Vomastek Dominion Energy Michael Montcalvo NRC Ching Ng NRC Caty Nolan NRC William Orders NRC Jesse Robles NRC Kevin Roche NRC Shane Sandal NRC Stu Sheldon NRC Eric Thomas NRC Sunil Weer NRC Diane Aitken Dominion Energy Erin Anners Southern Nuclear Rob Burg EMP Christopher E. Earls NEI Adam Goodman Duke David Gudger Exelon Lori Hayes Duke Erin Henderson TVA Greg Halnon First Energy Please note that the attendance list may not include all attendees.