ML13311B183

From kanterella
Revision as of 11:03, 30 March 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search

11/04/13 Summary of Meeting with Arizona Public Service Company to Discuss Non-destructive Examination Efforts, Repairs, and Progress on Root Cause Identified During Inspection of Bottom-Mounted Instrumentation Nozzles at Palo Verde, Unit 3
ML13311B183
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 11/18/2013
From: Rankin J K
Plant Licensing Branch IV
To:
Rankin J K
References
TAC MF2922
Download: ML13311B183 (5)


Text

LICENSEE: Arizona Public Service Company FACILITY: Palo Verde Nuclear Generating Station, Unit 3 SUBJECT: SUMMARY OF NOVEMBER 4, 2013, PUBLIC MEETING WITH ARIZONA PUBLIC SERVICE COMPANY TO DISCUSS THE CURRENT STATUS OF THE NON-DESTRUCTIVE EXAMINATION EFFORTS, REPAIRS, AND PROGRESS ON THE ROOT CAUSE DETERMINATION INVOLVING REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAKAGE ON THE BOTTOM MOUNTED INSTRUMENTATION NOZZLES (TAC NO. MF2922) On November 4, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Arizona Public Service Company (APS, the licensee) at NRC Headquarters, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss the current status of the non-destructive examination (NDE) efforts, repairs, and progress on the root cause determination involving reactor coolant system pressure boundary leakage identified during visual inspections on the reactor vessel bottom mounted instrumentation (BMI) nozzles at Palo Verde Nuclear Generating Station, Unit 3. The meeting notice and agenda are publicly available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 13294A373. The licensee's meeting slide presentation is available at ADAMS Accession No. ML 13308B332. A list of attendees is provided in the Enclosure. APS representatives described its initial discovery and response to the leakage on the BMI nozzles, the NDE action plan and results, the causal evaluation, the repair plan, and the proposed relief requests. APS's NDE efforts concluded that BMI nozzle #3 was the only visually leaking nozzle and that there are multiple axial ultrasonic indications. The licensee stated that other 60 BMI nozzles did not have any unacceptable indications. The licensee's causal evaluation determined the probable cause of crack initiation likely occurred at a weld defect that was exposed to the primary water environment resulting in primary water stress-corrosion cracking (PWSCC). The licensee plans to perform a boat sample and metallurgical analysis and testing to confirm the probable cause. The licensee noted that the boat sample is expected to be performed on approximately November 7, 2013. In addition, the licensee described the qualification and performance of the half-nozzle repair which is estimated to be completed on approximately November 7, 2013. Lastly, the licensee discussed two proposed relief requests pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations that are being developed. The first proposed relief request will be submitted and request relief from sections of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the duration of one operating cycle. The licensee stated that authorization for this relief request will be needed prior to entering MODE 2, which is estimated to occur on approximately November 24, 2013. The second relief request will include more detailed analysis including fatigue crack growth and request relief from certain sections of the ASME

-2-Code for operation beyond the next operating cycle. The licensee expects to submit this relief request in the April or May 2014 timeframe. The NRC suggested that APS consider the following as it proceeds in the recovery efforts:

  • Evaluate the need to harvest additional indications and additional weld material when collecting the boat sample or samples.
  • Evaluate the need in the metallurgical analysis and test plan for using additional or different surface analytical techniques or other metallurgical analysis methods to characterize fracture or defect surfaces.
  • Evaluate if a relief request is required to address ASME Code requirements for allowing flaws to remain in the nozzle. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at 301-415-1530 or at Jennivine.Rankin@nrc.gov. Docket No. 50-530 Enclosures: List of Attendees cc w/encl: Distribution via Listserv K. Rankin, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES NOVEMBER 4. 2013. MEETING WITH ARIZONA PUBLIC SERVICE COMPANY REGARDING PALO VERDE NUCLEAR GENERATING STATION. UNIT 3 BOTTOM MOUNTED INSTRUMENTATION LEAKAGE DOCKET NO. 50-530 NAME Dwight Mims Jack Cadogan Ron Barnes Ken House Mike Mclaughlin Mark Fallon Tom Weber Mike Dilorenzo Brian Cable Doug Hansen Ed Fernandez Gene Montgomery Jacquelyn Koessel ** Robert Roehler ** Tom Hook** R. C. Foley ** Mark McGhee ** Michael Hooshmand ** Dominic Macedonia ** Mike Powlikosky ** Sabrina Ireland** Chris Wax** Paul Hom** Jenny Tolar** Jennifer Cox ** Winston Borrero ** Doug Berg** Delbert Elkinton ** Donald Buth ** David Medek ** Maria Lacal ** Mark Radspinner ** Don Wheeler ** Scott Bauer *** Dave Waskey *** Doug Killian *** ORGANIZATION Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company Arizona Public Service Company STARS AREVA AREVA Enclosure NAME Michael Lashley *** James Axline
  • Chris Lohse
  • Anthony Giannuzzi
  • Bud Auvil* Paul Sullivan
  • Ron Payne* Nick Pappas Bernie Rudell Jim Cirilli Aubrey Godwin Akihiro Kanno James Clark
  • Kensaku Arai Eric Shouse
  • Suzuki Harutaka
  • participated via telephone -2-ORGANIZATION Structural Integrity Associates, Inc. Structural Integrity Associates, Inc. Structural Integrity Associates, Inc. Structural Integrity Associates, Inc. Structural Integrity Associates, Inc. Structural Integrity Associates, Inc. WSI/AZZ NEI CENG Exelon Arizona Radiation Regulatory Agency Hitachi -GE Nuclear Energy GE -Hitachi Nuclear Energy JNES El Paso Electric Site Mitsubishi Heavy Industries U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission ** participated via telephone and represented APS *** represented APS

-2-Code for operation beyond the next operating cycle. The licensee expects to submit this relief request in the April or May 2014 timeframe. The NRC suggested that APS consider the following as it proceeds in the recovery efforts:

  • Evaluate the need to harvest additional indications and additional weld material when collecting the boat sample or samples.
  • Evaluate the need in the metallurgical analysis and test plan for using additional or different surface analytical techniques or other metallurgical analysis methods to characterize fracture or defect surfaces.
  • Evaluate if a relief request is required to address ASME Code requirements for allowing flaws to remain in the nozzle. No Public Meeting Feedback Forms were received for this meeting. Please direct any inquiries to me at 301-415-1530 or at Jennivine.Rankin@nrc.gov. Docket No. 50-530 Enclosures: List of Attendees IRA/ Jennie K. Rankin, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC RidsNrrLAJBurkhardt Resource RidsNrrPMDiabloCanyon Resource RidsOpaMail Resource RidsRgn4MaiiCenter Resource DRich, EDO RIV VDricks, OPA RIV TWertz, NRR WMaier, RIV RHardies, NRRIDE SRosenberg, NRRIDE/EVIB JCollins, NRRIDE/EPNB SSheng, NRRIDE/EVIB GCheruvenki, NRR/DE/EVIB LPLIV-1 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDorl Resource RidsNrrDoriLp14-1 Resource ADAMS Accession Nos. Meeting Notice ML 13294A373; Meeting Summary ML 13311 B 183; Slides ML 13308B332
  • via email OFFICE NRRIDORULPL4-1/PM NRRIDORU/LPL4-1/LA NRRIDE/EPNB* NRRIDE* NAME JRankin JBurkhardt JCollins RHardies DATE 11/13/13 11/13/13 11/6/13 11/5/13 OFFICE NRRIDORULPL4-1/BC NRRIDORULPL4-1/PM NAME MMarkley JRankin DATE 11/15/13 11/18/13 OFFICIAL RECORD COPY