ML12366A032

Summary of Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1

ML12366A032
Person / Time
Site:	Fort Calhoun
Issue date:	01/25/2013
From:	Lynnea Wilkins Plant Licensing Branch IV
To:	Plant Licensing Branch 1
Wilkins L
References
TAC MF0307
Download: ML12366A032 (5)

Text

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LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1

SUMMARY

OF MEETING HELD ON DECEMBER 12,2012, WITH OMAHA PUBLIC POWER DISTRICT TO DISCUSS CONTAINMENT INTERNAL STRUCTURES ISSUES AT FORT CALHOUN STATION, UNIT 1 (TAC NO. MF0307)

On December 12,2012, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Omaha Public Power District (OPPD, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss topics concerning containment internal structures for Fort Calhoun Station, Unit 1 (FCS). The meeting notice and agenda, dated November 30,2012, is available in the Agencywide Documents Access and Management System at Accession No. ML12345A270. The licensee's presentation slides are available at ADAMS Accession No. ML12349A151.

During the meeting on December 12, 2012, the licensee presented information on the following topics:

• History and Identification of Containment Internal

• Structures (Containment Internal Structures (CIS>> Issue

• Discovery Process and Extent of Condition

• Modeling Methodology, Inputs and Assumptions

• Licensing Basis and Operability Criteria

• Planned Actions for Restart

• Support for NRC Inspection Activities

• Post-Restart Actions As a follow-up action to the meeting, the NRC staff requested that the licensee provide the following additional information:

• Please describe internal missile loads on operating floor. State if these loads need to be considered per the Updated Safety Analysis Report (USAR).

• The design basis for the intake structure was reconstituted in 2007, with similar walkdown procedures that are currently being used for reconstitution of the containment internal structures. The anchors securing the raw water pumps does not appear to have been installed according to the original design specifications and that error was not discovered by the 2007 reconstitution.

Please describe the procedures being used to validate the design basis.

-2 Determine if some items may not be identified by a visual, line of sight walkdown.

In addition, please state if there are other technologies available for walkdowns.

• The proposed structural changes may affect the containment volume. Please describe what the current and the new margin is between the containment peak pressure (Pa) and design pressure during a design basis accident.

• Describe the methodology and number of samples used for determining concrete strength for operability evaluation.

• Please clarify if there are any changes to methodologies that may require a license amendment.

• Please describe, conceptually, how the new columns will be attached to the foundation base mat. Please describe the load path to the foundation base mat and the effects on the base mat liner plate. Also, please identify columns requiring modification prior to restart.

The public was invited to observe the meeting and was given an opportunity to communicate with the NRC after the business portion, but before the meeting was adjourned. Members of the public were present. No Public Meeting Feedback forms were received. Comments received included the following:

• Were the defects present during original licensing? Would the defects preclude licensing if they were identified at that time?

NRC Response: Yes, the NRC would have expected the defects to be corrected or justified during the initial licensing process.

• What weight are the beams supporting?

NRC Response: Some support ventilation systems, tanks, etc. No specific weight value was identified for components or zones.

• It is rumored that a cold joint is present on one particular side of containment.

Has FCS considered these cold joints?

NRC Response: The NRC requested information* regarding the individual's concerns.

• Considering the 2010 finding and the 2011 flood, it is apparent that OPPD omits information. What difference has been made in the believability of OPPD?

NRC Response: The NRC has numerous upcoming inspections to verify information received from OPPD and to examine areas of concerns independently.

-3

• NRC will not issue new licenses until long term fuel storage has been reviewed.

This decision does not affect operating plants. How does this affect FCS if it is redesigning its license?

NRC Response: The NRC routinely reviews existing licenses, including those that have been granted extended operation through license renewal. The FCS license has been renewed for continued operation through August 9,2033. Additional information regarding the Waste Confidence Act can be found on the NRC website.

• How is the Reactor Vessel Stand affected?

NRC Response: The loading margin is reduced but the licensee has determined that it is still operable for outage conditions.

Please direct any inquiries to me at 301-415-1377 or Lynnea.Wilkins@nrc.gov.

ciLynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

LIST OF ATTENDEES U.S. NUCLEAR REGULATORY COMMISSION DECEMBER 12,2012, PUBLIC MEETING WITH OMAHA PUBLIC POWER DISTRICT REGARDING CONTAINMENT INTERNAL STRUCTURES AT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Name qrganization I Bruce Rash OPPD Bernie Van Sant OPPD Brian Davis OPPD Russ Placke OPPD Terry Simpkin OPPD Thomas Dailey OPPD Andrew Carmean Automated E/'1gineering Services Eric Halverson ~omated Engineering Services Jack Grobe elon Nuclear Partners Caroline Schlaseman MRP Associates Tsiming Tseng Sargent and Associates P.K. Agrawal Sargent and Lund~

Michael Allison Stevenson and Associates Douglas Seymour Stevenson and Associates i Farhad Farzam NRC/NRRlDE/EMCB ~

• Pat Hiland NRC/NRR/DE

. Bryce Lehman N RC/NRRIDLR/RASB i Kamal Manoly NRC/NRR/DE I Martin Murphy NRRIDE/EMCB Michael Balazik INRC;NRRlDIRSIIPAB Lousie Lund NRC/NRRlDORL Lynnea Wilkins NRC/NRR/NRRlDORULPL4 Michael Markley NRC/NRR/NRR/DORULPL4 Matthew Hamm N RC/NRRIDSS/STSB Ahsan Sallman NRC/N RR/DSS/SCVB Mike Hay NRC/RIVIDRP/FCS  !

Chris Smith NRC/RIVIIDRP/FCS

• Megan Williams NRC/RIVlDRS/EB1

• Donald Ferraro Exelon i Wallace Taylor Iowa Sierra Club Lisa Olsen OPPD Public Affairs Mike Ryan Clean Connection  !

Brian Jelke LaVerne Thorin Charles Osten i Enclosure

Meeting Notice ML 12345A27 , Meetina ummary ML1236M03, 2 SIides ML12349A151 *via

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