ML093360229
| ML093360229 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/04/2009 |
| From: | Orf T Plant Licensing Branch II |
| To: | |
| Orf, T J, NRR/DORL/301-415-2788 | |
| References | |
| FOIA/PA-2010-0116, TAC ME2372 | |
| Download: ML093360229 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 4, 2009 LICENSEE: FLORIDA POWER CORPORATION, DOING BUSINESS AS PROGRESS ENERGY (PGN)
FACILITY: CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
SUBJECT:
SUMMARY
OF NOVEMBER 20, 2009, MEETING WITH PGN REGARDING THE CRYSTAL RIVER UNIT 3 CONTAINMENT BUILDING CONCRETE DELAMINATION (TAC NO. ME2372)
On November 20,2009, a Category 1 public meeting was held between the U.S. Nuclear RegulatorY Commission (NRC) and representatives of PGN at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the recently identified containment building concrete delamination. A list of attendees is provided as an enclosure.
The presentation started with opening remarks from Eric Leeds, Director, NRC Office of Nuclear Regulation; Luis Reyes, Administrator, NRC Region II, and Jim Scarola, PGN Senior Vice President and Chief Nuclear Officer. Eric Leeds emphasized that the purpose of this presentation was for PGN to provide a status of their investigation of the recently identified containment building concrete delamination; although, the investigation was not yet complete.
Luis Reyes briefly discussed the ongoing Special Inspection at Crystal River that began on October 13. The purpose of the Special Inspection is to help the NRC better understand the issue and to independently assess PGN's actions to address it.
Jim Scarola outlined the presentation (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093240292), which included an analysis of extent of condition, a design basis analysis, root cause, and repair options. He then yielded the floor to Jon Franke who discussed the analysis of extent of condition.
Jon Franke, Vice President, Crystal River Nuclear Plant, discussed some of the current refueling activities, especially those related to the extended power uprate and the steam generator replacement (SGR). He continued his presentation, describing general dimensions of the reactor building and its design features. Next he discussed some activities involving the steam generator replacement, which included creating a 25 feet by 27 feet opening in the side of the containment building. A water jet generating approximately 25,000 pounds per square inch of pressure was used in the concrete removal process. The delamination was found during this concrete removal process approximately 9 to 10 inches from the outside surface, the depth of the horizontal tendons.
Garry Miller, Manager, PGN Containment Project, a new PGN organization created specifically to manage the containment delamination issue, continued the presentation by describing various analyses involved in the investigation of the issue. Joe Donahue, Vice President, PGN Nuclear Oversight, described changes made to the nuclear oversight organization to support the issue as well. A special subcommittee of the Nuclear Safety Oversight Committee was
-2 convened to provide an independent review of activities associated with the containment concrete delamination.
Next in the presentation was Paul Fagan of PGN, who discussed the assessment of extent of condition. Various tests were performed on the containment structure. The majority of the external structure of containment and accessible containment wall surfaces in adjacent buildings were sUbject to impulse response testing (IR). This type of testing is useful for plate like structures in determining delamination. Ground penetrating radar was used to locate tendons beneath the surface of the concrete before obtaining core bore samples.
The core bores were used to confirm the IR results; and the samples were also sent to multiple labs for petrographic and other analysis. The holes left by the core bores were inspected using a boroscope to view the inside of the concrete and confirm whether or not delamination was present. Impact echo testing may also be used in the future to further confirm these results.
The results of the test to date show that the delamination is limited to the area between buttresses 3 and 4 and centered on the SGR opening.
Garry Miller continued discussing the results of the investigation to date; although, it must be emphasized that at the time of the presentation, no root cause determination had been made.
Mr. Miller discussed the shape of the delamination and the apparent relation to energized and de-energized tendons. He also discussed different structural features that probably served to limit propagation of the delamination.
At this point, questions were taken from members of the audience. A member of the NRC asked if there was a correlation between the results of the core bores and the IR testing. The answer was that the IR testing predicted with 100 percent accuracy the delamination confirmed by the core bores. The NRC staff member also asked about the strength of the concrete. The answer was that the strength was less than expected but still above design parameters.
Another NRC staff member asked about the limitations of the IR testing method. The answer received was that IR testing determines the existence of delamination, but not at what depth the delamination occurs. In order to determine the depth of the delamination, impact echo testing or core bores, as was done, is needed.
Paul Gunter of Beyond Nuclear asked questions next. His first question related to the square footage of the exterior of the containment building and the coverage of the core bores. He next asked if the containment building was "sub-atmospheric", which it is not. His third question related to inspection of the steel liner for corrosion. The answer was that liner corrosion inspection was not the subject of this effort, but is covered in inservice inspections.
After a 10 minute break, Dr. Chong Chiu of Performance Improvement International, discussed the different failure modes that his company was investigating. Through reviewing construction and operational history of the containment building, 74 different failure modes were hypothesized. His job is to refute those failure modes that did not occur or could not have contributed to the delamination of the concrete. These failure modes were grouped into nine different categories. As of the date of the presentation, 47 failure modes had been eliminated.
As more data is gathered from the field, the number of failure modes will be narrowed further.
Any repair model will encompass all supported or unrefuted failure modes, and the schedule for repair will be driven by the technical analysis.
-3 Ed Bird of MPR Associates, Inc. continued the presentation discussing detailed finite element analyses (FEA) that model the forces within the structure of the containment building.
Afterwards, Mr. Miller provided a walkthrough of the different repair options that PGN is considering. Ultimately, the final repair option will be to remove and replace the delaminated material, restoring the applicable design basis margin.
At this point, additional questions were taken from members of the audience. One NRC staff member asked about asymmetries of the structure compared to the FEA model. Another NRC staff member asked how rebar was included in the FEA model, and the answer was that it was not, and did not need to be modeled explicitly. A staff member from NRC's Region I office asked if differences in containment structures from other plants had been included in the root cause analysis where SGRs had taken place without delamination, and the answer was yes.
Mr. Reyes summarized the presentation, and stated that the special inspection of the Crystal River Unit 3 was still active and after PGN presents their root cause analysis, then a public meeting will be held to present the results of the inspection. Another public meeting may be held before the unit is placed back in service. The NRC staff is also investigating generic implications.
Mr. Scarola then presented his closing remarks, stating that PGN respects and appreciates the expertise and openness of the NRC. He also stated PGN's commitment that energy production is second to its top priority of safety.
Mr. Gunter asked that the licensee's root cause analysis be made public.
Thomas Saporito of Saporito Energy Consultants then commented that in his opinion the licensee's design and testing methods were insufficient and that impact echo testing and destructive testing of the containment building needed to be performed. He also asked that the other reactor units on site be shut down until the root cause analysis is finished. However, there is only one reactor on site. Further, he asked that a formal hearing be convened before the repair is completed and questioned whether generic correspondence would be forthcoming.
With that the meeting was adjourned.
Members of the public were in attendance, however no Public Meeting Feedback forms were received. Please direct any inquiries to me at 301-415-1447, or Farideh.Saba@nrc.gov.
-r~~(}+-
Tracy J. Orf, Project Manager Plant Licensing Branch, 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATTENDEES NOVEMBER 20,2009, MEETING WITH PROGRESS ENERGY CONTAINMENT BUILDING CONCRETE DELAMINATION Attending in person: Luis Reyes, NRC/RII Dan Fisher, Areva INL LaDonna Suggs, NRC/RII Paul Gunter, Beyond Nuclear Paul Jacques, Nuclear Electric Insurance Ron Burg, CTL Group Limited Honggang Cao, CTL Group William Freebairn, Nucleonics Week Pam Cowan, Exelon Nuclear Joe Donahue, PGN John Piazza, Exelon Nuclear Robert Duncan, PGN Dave Crabtree, INPO Paul Fagan, PGN Edward Bird, MPR Jon Franke, PGN Jim Riley, NEI Mike Heath, PGN Nikki Gilanshahi, NRC/NRO Mike Hughes, PGN Vaughn Thomas, NRC/NRO Ernest Kapopoulos, PGN Hans Ashar, NRC/NRR Ron Knott, PGN Rajender Auluck, NRC/NRR Brian McCabe, PGN Peter Bamford, NRC/NRR Garry Miller, PGN Robert Bernardo, NRC/NRR Sid Powell, PGN Jerome Bettie, NRC/NRR Jim Scarola, PGN Eva Brown, NRC/NRR Chong Chiu, PII Nick DiFrancesco, NRC/NRR Anand Singh, Sargent & Lundy Farhad Farzam, NRC/NRR Tom Spink, TVA Dave Garmon, NRC/NRR W. Jay Leininger, Unistar Nuclear Brian Hollian, NRC/NRR Mark Beaumont, URS Meena Khanna, NRC/NRR Nathan Kyle, URS, Washinton Div.
Rob Kuntz, NRC/NRR Eric Leeds, NRC/NRR Bryce Lehman, NRC/NRR Kamal Manoly, NRC/NRR Carol Nove, NRC/NRR Trace Orf, NRC/NRR Daniel Santos, NRC/NRR Abdul Sheikh, NRC/NRR Wilkins Smith, NRC/NRR George Thomas, NRC/NRR Alexander Tsirigotis, NRC/NRR John Monninger, NRC/OCM Herman Graves, NRC/RES Jose Pires, NRC/RES Mary Wegner, NRC/RES Robert Carrion, NRC/RII Mark Franke, NRC/RII Enclosure
-2 Attending via telephone: Digna Alvarez, Senator Bill Nelson Staff Robert Oliveira, American Nuclear Insurers Susie PerezQuinn, Senator Bill Nelson Staff Alan, Anbex Rudy Alvarado, Sigma, LLC Nawar Alchaar, Areva NP Greg Lang, SNC Licensing Michael Hoskins, Areva NP Ted Koser, South Texas Project Bill Hovis, Areva NP Dennis Swann, Southern Nuclear Operating Ronda Pederson, Areva NP Company Mark Van Nay, Areva NP Keith Axler, Southwest Research Institue Jack Dambach, Bay News Lietai Yang, Southwest Research Institute Amanda Mims, Citrus County Chronicle Rick Danielson, St. Petersburg Times Mark Rigsby, Manager - Support Services Don Morris, St. Petersburg Times Nuclear, Crystal River Dave Schafer, Steam Generator John MacCrimmon, Dominion Replacement Project, Southern Franklin Hope, Enercon Services, Inc. California Edison Eddie Rodriguez, Engineering Codes Shari Day, Structural Integrity Program, Entergy Services, Inc. Associates, Inc.
Ken Canavan, EPRI Terry Herrmann, Structural Integrity Maria Guimaraes, EPRI Associates, Inc.
John Lindberg, EPRI Howard Hill, TMI Leonard Loflin, EPRI Sri Dodeja, URS Nuclear Center David Modeen, EPRI Mike Thumm, URS Washington Division Greg Selby, EPRI Dale Krause, V.C. Summer Nuclear Station Henry Stephens, EPRI Raffi Shahabian, WorleyParsons James Wall, EPRI Richard lonelli, no affiliation cited Dean Galanis, Exelon Rhonda Roff, no affiliation cited Michael Younger, Florida Division of Emergency Management Allen Hiser, NRC/NRR Billy Jessup, NRC/NRR Marlayna Vaaler, NRC/NRR John White, NRC/RI John Bozga, NRC/Rill David Hills, NRC/Rill Jason Redd, Nuclear Development, Southern Nuclear Operating Company Betsy Cox, Nuclear Plant Development, Progress Energy Tony Zimmerman, Nuclear Regulatory Affairs, Progress Energy Bob Munger, Nuclear Service Organization Kevin Spear, Orlando Sentinel Gary Little, Progress Energy Jim Breman, PSC, Florida Mike Clary, Resident (retired Progress Energy)
Gary Sanford, Resident, Crystal River Judy Prantl, Resident, St. Petersburg Lisa Senesac, Sargent & Lundy, LLC
-3 Ed Bird of MPR Associates, Inc. continued the presentation discussing detailed finite element analyses (FEA) that model the forces within the structure of the containment building.
Afterwards, Mr. Miller provided a walkthrough of the different repair options that PGN is considering. Ultimately, the final repair option will be to remove and replace the delaminated material, restoring the applicable design basis margin.
At this point, additional questions were taken from members of the audience. One NRC staff member asked about asymmetries of the structure compared to the FEA model. Another NRC staff member asked how rebar was included in the FEA model, and the answer was that it was not, and did not need to be modeled explicitly. A staff member from NRC's Region I office asked if differences in containment structures from other plants had been included in the root cause analysis where SGRs had taken place without delamination, and the answer was yes.
Mr. Reyes summarized the presentation, and stated that the special inspection of the Crystal River Unit 3 was still active and after PGN presents their root cause analysis, then a public meeting will be held to present the results of the inspection. Another public meeting may be held before the unit is placed back in service. The NRC staff is also investigating generic implications.
Mr. Scarola then presented his closing remarks, stating that PGN respects and appreciates the expertise and openness of the NRC. He also stated PGN's commitment that energy production is second to its top priority of safety.
Mr. Gunter asked that the licensee's root cause analysis be made public.
Thomas Saporito of Saporito Energy Consultants then commented that in his opinion the licensee's design and testing methods were insufficient and that impact echo testing and destructive testing of the containment building needed to be performed. He also asked that the other reactor units on site be shut down until the root cause analysis is finished. However, there is only one reactor on site. Further, he asked that a formal hearing be convened before the repair is completed and questioned whether generic correspondence would be forthcoming.
With that the meeting was adjourned.
Members of the public were in attendance, however no Public Meeting Feedback forms were received. Please direct any inquiries to me at 301-415-1447, or Farideh.Saba@nrc.gov.
IRA!
Tracy J. Orf, Project Manager Plant Licensing Branch, 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
List of Attendees cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 r/f RidsAersAenw_MailCTR RidsNrrDorlLpl2-2 RidsNrrPMCrystalRiver RidsNrrLASola RidsOgeRp RidsRgn2MailCenter CTuea, NRR CRegan, EDO Regionll LReyes, Rgn II RidsNrrOd RidsNrrDorl MSykes, NRR MFranke, Rgnll LLake, Rgn II MKhanna, NRR TChan, NRR JPaige. NRR TOrt, NRR ADAMS Accession No. PKG ML093020101 Meeting Notice ML093020101 Meeting Summary MLO93360229 Handouts MLO93240292 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC DORULPL2-2/PM NAME TOrt CSoia TBoyee TOrt DATE 12/04/09 12/04/09 12/04/09 12/04/09 OFFICIAL RECORD COpy