ML19164A091
| ML19164A091 | |
| Person / Time | |
|---|---|
| Issue date: | 06/18/2019 |
| From: | Tekia Govan NRC/NRR/DIRS/IRGB |
| To: | Ami Agrawal NRC/NRR/DIRS/IRGB |
| Govan T, 415-6197, NRR/DIRS | |
| References | |
| Download: ML19164A091 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 18, 2019 MEMORANDUM TO: Ami R. Agrawal, Chief Reactor Inspection Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation FROM: Tekia V. Govan, Project Manager /RA/
ROP Support and Generic Communication Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE REACTOR OVERSIGHT PROCESS MONTHLY PUBLIC MEETING HELD ON MAY 22, 2019 On May 22, 2019, 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 enhancement initiative and other ROP topics.
Updates to Changes to the Engineering Inspection Program The NRC staff provided a brief update on the proposed changes to the engineering inspection program (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19141A219). The update included the plan for implementation of the new procedures, when to expect publicly available drafts of the procedures, and when the NRC inspectors will be trained on the changes. The NRC staff also provided a review of how the focused engineering inspection (FEI) topics were selected. The staff answered questions from industry on how operating experience was used in determining FEI topics, and how the NRC would incorporate lessons learned from the current environmental qualification inspections. The NRC staff committed to making the training presentation provided to NRC staff inspectors, available to the public.
The NRC staff is currently drafting new inspection procedures and will make the completed procedures publicly available in June 2019. The staff is considering additional FEI topics, should the Commission approve the proposed engineering inspection program cycle. The staff will provide the Commission with the additional topics through a Commissions Assistant Note.
CONTACT: Tekia V. Govan, NRR/DIRS (301) 415-6197
A. Agrawal Operating Experience - Brunswick Cryofit Coupling Failure The NRC staff discussed recent operating experience involving the failure of a one-inch diameter cryogenic coupling at Brunswick Nuclear Generating Station (Brunswick; licensee),
Unit 1 (ADAMS Accession No. ML19141A219). On March 28, 2019, Brunswick, Unit 1, was operating at 100 percent power and declared a notice of unusual event (NOUE) for a leak rate greater than 10 gallons per minute for 15 minutes. Operators received indications of narrow range reactor water level instrument failing high. The licensee cooled the reactor down to Mode 4 and terminated the NOUE when the leak rate fell below 10 gallons per minute.
The licensee identified that the leak was a result of the failure of a one-inch CryoFit coupling, which is a cryogenic coupling. The coupling was located on reactor vessel level reference leg and had been installed as part of a post-Three Mile Island plant modification made in 1989. The coupling had experienced a 360-degree circumferential failure in what appeared to be the center of the coupling where the two connected pipe ends meet.
The NRC staff performed a search of relevant operating experience for these couplings. In 1991, Seabrook Station (Seabrook) experienced the 360-degree circumferential fracture at the midpoint of a CryoFit coupling on a pressurizer gas space sampling line. A second CryoFit coupling in the same line fractured in a similar manner after an accidental physical impact. In response to the Seabrook event, the NRC issued Information Notice 91-87, Hydrogen Embrittlement of Raychem CryoFit Couplings. There have been no known failures of CryoFit couplings since.
The NRC staff continues to seek additional information from industry and NEI on extent of condition (e.g., how many other plants have similar couplings) and failure mechanism (e.g.,
possible material aging component related to coupling failure).
Reactor Oversight Process Performance Indicator Program Frequently Asked Question (FAQ)
FAQ 19-02, Brunswick reactor coolant system leakage was presented by NEI (ADAMS Accession No. ML19141A149). The NRC will review the submitted FAQ 19-02 and discuss the topic during the next ROP public meeting on June 19, 2019.
FAQ 19-01, Change to NEI 99-02 Text for the Drill/Exercise Performance Indicator - Initial Notification Form Accuracy Criteria (ADAMS Accession No. ML19119A304) was transitioned from tentatively approved to final approval by the NRC staff.
NEIs Response Letter to the March 27, 2019 ROP Public Meeting On May 20, 2019, NEI submitted a letter to the NRC, Proposed SECY on ROP Enhancement (ADAMS Accession No. ML19141A143). This letter was submitted by NEI to provide a written summary of key comments that the nuclear industry would like considered in the June 2019 ROP enhancement SECY paper that will be submitted to the NRC Commission. The NRC staff acknowledge receipt of this letter and will continue to develop the SECY paper for submittal to the Commission by June 2019.
A. Agrawal Next Steps - ROP Enhancement The NRC staff provided an overview of longer term ROP enhancement activities (ADAMS Accession No. ML19141A219), as follows:
- Perform holistic review of problem identification and resolution inspections
- Examine effectiveness of the cross-cutting issues program
- Evaluate significance determination process decision-making to improve efficiency and effectiveness
- Evaluate changes to supplemental inspection for White findings (Inspection Procedure 95001)
- Optimize independent spent fuel storage installation and radiation protection inspections
- Evaluate crediting licensee performance in other safety cornerstones for emergency preparedness inspection findings 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, even in areas where NRC staff and industry may not be aligned. The NRC management stressed the importance of 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
ML19164A091 OFFICE NRR/DIRS/IRGB/PM NRR/DIRS/IRGB/OLA* NRR/DIRS/IRAB/BC*
NAME TGovan IBetts AAgrawal DATE 06/13/2019 06/18/2019 06/18/2019 LIST OF ATTENDEES REACTOR OVERSIGHT PROCESS MONTHLY PUBLIC MEETING May 22, 2019, 10:00 AM to 12:15 PM NRC One White Flint North 11555 Rockville Pike O-11B04 Rockville, MD Name Organization Name Organization Carlos Sisco Winston and Strawn Chris Miller NRC Mark DeWire Duke Energy Billy Dickson NRC Jim Slider NEI Greg Bowman NRC Bryan Wooten Duke Energy Jason Carneal NRC Larry Parker STARS Alliance Alex Garmoe NRC Jerry Oierce Duke Energy Russ Gibbs NRC Laura Schwartz International Technology and Doug Bollock NRC Trade Associates David Gudger Exelon Ami Agrawal NRC Jean Fleming PSEG Nuclear C.J. Fong NRC Steve Catron NextEra Joylynn Quinones NRC Ken Heffner Certrec Mike Montecalvo NRC Tony Zimmerman Duke Energy Don Helton NRC Robin Ritzman FENOC Julio Lara NRC Rob Burg EPM, Inc. Dan Merzke NRC Mohammed Shaubi NRC David Garmon NRC Annie Mayer NRC Anthony Masters NRC Robert Orlikowski NRC Robert Kahler NRC Derek Widmayer NRC Enclosure