ML14099A469

Summary of 4/2/2014 Pre-Application Meeting with Arizona Public Service Company to Discuss Extension of Authorized Repair to Palo Verde, Unit 3, Bottom Mounted Instrumentation to End-of-Unit Life (TAC MF3520)

ML14099A469
Person / Time
Site:	Palo Verde
Issue date:	04/21/2014
From:	Rankin J K Plant Licensing Branch IV
To:
Rankin J K
References
TAC MF3520
Download: ML14099A469 (4)

Text

LICENSEE:

Arizona Public Service Company FACILITY:

Palo Verde Nuclear Generating

Station, Unit 3

SUBJECT:

SUMMARY OF APRIL 2, 2014, PREAPPLICATION PUBLIC MEETING WITH ARIZONA PUBLIC SERVICE COMPANY REGARDING RELIEF REQUEST 52 TO EXTEND AUTHORIZED REPAIR TO PALO VERDE NUCLEAR GENERATING

STATION, UNIT 3, BOTTOM-MOUNTED INSTRUMENT FOR REMAINDER OF LICENSED OPERATING LIFE (TAC NO. MF3520) On April 2, 2014, a 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, Rockville, Maryland.

The purpose of the meeting was for APS to discuss its forthcoming Relief Request 52, which will seek authorization to operate Palo Verde Nuclear Generating Station (PVNGS),

Unit 3, with the bottom-mounted instrument (BMI) nozzle penetration 3 half-nozzle repair for the duration of the facility operating license.

In November 2013, the NRC granted verbal authorization to APS for Relief Request 51, the proposed alternative half-nozzle repair and flaw evaluation of BMI nozzle penetration 3, for the duration of the current fuel operating cycle (U3C18).

The meeting notice and agenda are publicly available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 14077A371.

The licensee's meeting slide presentation is available at ADAMS Accession No. ML 14098A 183. A list of attendees is provided in the Enclosure.

The licensee's presentation began with an overview of the BMI nozzle 3 flaw discovery and repairs.

The licensee then described the boat sample location and collection, which attempted to capture the reactor coolant system (RCS) leak entrance point, weld defect, known axial cracks, and unaffected weld and nozzle material for analysis.

During the destructive evaluation of the boat sample, the licensee noted a void inside the sample, which appeared to be the source of one solidification crack and multiple primary water stress-corrosion cracking (PWSCC)-indicative cracks. However, the through-wall crack from the RCS pressure boundary was not found in the boat sample. The licensee continued the presentation with an overview of the methods and analysis used to evaluate the remnant flaw propagation and acceptability for the duration of the Unit 3 facility operating license.

Analyses presented included stress and fatigue analysis, welding residual stress analysis, remnant flaw growth analysis, remnant nozzle structural integrity and dynamic analysis, a corrosion assessment, and a loose parts evaluation.

Additionally, the licensee discussed its schedule for submitting Relief Request 52 to the NRC staff for review. The NRC staff asked the licensee numerous questions during the presentation regarding analysis

methods, bases for calculations, model types used, and proposed schedule for submitting the request.

The NRC suggested that APS consider the following as it develops the Relief Request 52 submittal:

• Provide sufficient detail and information regarding the plant-specific models, analyses, and data used to support extended operation with the remnant flaw and half-nozzle repair.

• Include identification of excitation frequencies and natural frequencies for the remnant nozzle (slide 23 of the licensee's presentation).

During the meeting, the licensee noted that the detailed metallurgy report regarding the cracking in BMI nozzle 3 was expected to be shared with the NRC Resident Inspectors.

The NRC staff noted that information contained in the metallurgy report may be of use during the review of Relief Request 52. Subsequent to the meeting, the NRC Resident Inspectors at PVNGS confirmed that they have received the referenced metallurgy report. One Public Meeting Feedback Form was received for this meeting.

Please direct any inquiries to me at 301-415-1530 or at Jennivine.Rankin@nrc.gov.

Docket No. 50-530

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

(\<cVY\ GLA__, Yennie K. Rankin, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LIST OF ATTENDEES APRIL 2, 2014. PUBLIC MEETING WITH ARIZONA PUBLIC SERVICE COMPANY REGARDING RELIEF REQUEST 52 TO EXTEND REPAIR TO PALO VERDE NUCLEAR GENERATING

STATION, UNIT 3, BOTTOM-MOUNTED INSTRUMENT FOR REMAINDER OF LICENSED OPERATING LIFE NAME Delbert Elkinton Tom Weber Ed Fernandez Ken House Michael Hooshmand Doug Hansen Gene Montgomery Winston Borrero Mike DiLorenzo*

Robert Roehler*

Mark McGhee

• Paul Hom* Douglas Berg* Matthew Glenn* Rex Meeden* Carl Stephenson*

David Kelsey* Doug Killian Ashok Nana Sarah Davidsaver*

Steve Fyfitch*

DOCKET NO. 50-530 ORGANIZATION Arizona Public Service Company (APS) APS APS APS APS APS APS APS APS APS APS APS APS APS APS APS APS AREVA AREVA AREVA AREVA MPR Associates, Inc. JNES Dave Rackiewicz*

Kensaku Arai Robert Hardies Jay Collins U.S. Nuclear Regulatory Commission (NRC) NRC Andrea George Jennie Rankin Carol Nove* Mike Markley Stacey Rosenberg Simon Sheng Ganesh Cheruvenki Steven Vitto David Alley

• participated via telephone NRC NRC NRC NRC NRC NRC NRC NRC NRC Enclosure submitting the request.

The NRC suggested that APS consider the following as it develops the Relief Request 52 submittal:

• Provide sufficient detail and information regarding the plant-specific models, analyses, and data used to support extended operation with the remnant flaw and half-nozzle repair.

• Include identification of excitation frequencies and natural frequencies for the remnant nozzle (slide 23 of the licensee's presentation).

During the meeting, the licensee noted that the detailed metallurgy report regarding the cracking in BMI nozzle 3 was expected to be shared with the NRC Resident Inspectors.

The NRC staff noted that information contained in the metallurgy report may be of use during the review of Relief Request 52. Subsequent to the meeting, the NRC Resident Inspectors at PVNGS confirmed that they have received the referenced metallurgy report. One Public Meeting Feedback Form was received for this meeting.

Please direct any inquiries to me at 301-415-1530 or at Jennivine.Rankin@nrc.gov.

Docket No. 50-530

Enclosure:

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 LPL4-1 Reading RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDorl Resource RidsNrrDorllpl4-1 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMPaloVerde Resource RidsOpaMail Resource RidsRgn4MaiiCenter Resource JNick, EDO RIV NTaylor, RIV RHardies, NRR/DE SRosenberg, NRR/DE/EVIB

JCollins, NRR/DE/EPNB SSheng, NRR/DE/EVIB GCheruvenki, NRR/DE/EVIB ADAMS Accession No.: ML14099A469 OFFICE NRRIDORULPL4-1/PM N RR!DORULPL4-1/PM NRR!DORU

/LPL4-1/LA NRRIDE/EPNB/BC NAME A George JRankin JBurkhardt SRosenberg DATE 4/15/14 4/15/14 4/15/14 4/18/14 OFFICE NRR!DORULPL4-1/BC NRRIDORULPL4-1/PM NAME MMarkley JRankin DATE 4/21/14 4/21/14 OFFICIAL RECORD COPY