ML13059A345

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Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
ML13059A345
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/08/2013
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Limpias O
Nebraska Public Power District (NPPD)
Wilkins L
References
TAC ME8992
Download: ML13059A345 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 8, 2013 Mr. Oscar A. Limpias Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT (TAC NO. ME8992)

Dear Mr. Limpias:

By application dated June 25,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121850025\ Nebraska Public Power District requested a license amendment to revise the licensing and design basis as documented in the Cooper Nuclear Station Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident dose assessment.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the application and determined that additional information is required in order to complete the review and approval of the changes. The questions were provided to Mr. E. McCutchen of :Iour staff bye-mail on February 22,2013. Mr. McCutchen replied via email on February 25,2013, stating that a clarifying call was not needed and that a response would be provided for the enclosed request for additional information (RAI) within 30 days of the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient tir,',e is available for staff review and contribute toward the NRC's goal of efficient and effective i..I~;e ()~ NRC staff resources. If circumstances result in the need to revise the requ'3sted response clAte, please contact me at 301-415-1377 or via e-mail at Lynnea.Wilkins@nr:",!,gov.

Sincere~y,

~d.

Lynnea E Wilkins, Project Manager Plant Licensing Branch IV DivIsion of Operat'ng Reactor licensing Office of Nuclear R.6actor Regulation Docket No. 50-298

Enclosure:

Request for Additional Information cc w/encl: Distribution via Ustserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR REVISIONS TO THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT COOPER NUCLEAR STATION DOCKET NO. 50-298 By application dated June 25.2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121850025). Nebraska Public Power District (NPPD). requested a license amendment to revise the licensing and design basis as documented in the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment. Section 2.5, "Atmospheric Dispersion (X/Q) Factors," of to the application states. in part. that:

The X/Q values are taken from existing eNS calculations developed specifically for various Control Room Intake, Exclusion Area Boundary (EAB). and Low Population Zone (LPZ) receptor points for use in the development of the bounding Design Basis Accidents (DBA) Radiological Analysis. These receptor locations were previously determine to be the most limiting in determining compliance with the dose criteria established.

The control room intake X/Q values were taken from reference 23 for a release emanating from the Reactor Building. The reactor building vent release case was analyzed as a ground release for three release rates through the reactor building vent. The lowest release flow which coincides with the highest X/Q values was chosen for the most conservative approach .... The EAB and LPZ Atmospheric Dispersion X/Q values were taken from reference 25 for a ground release emanating from the Reactor Building.

Section 2.5 cites the "lowest release flow" and references 23 and 25, which are both dated September 23. 2009. Please confirm that this lowest flow is 1780 cubic feet per minute and that there are not any changes in the FHA release scenario (e.g., changes in potential source/receptor locations, changes in flow rates. etc.) which would alter the NPPD X/Q assessment in support of Amendment No. 222. dated September 5, 2006 (ADAMS Accession No. ML062260239).

Enclosure

March 8, 2013 Mr. Oscar A. Limpias Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO REVISE THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT (TAC NO. ME8992)

Dear Mr. Limpias:

By application dated June 25,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121850025), Nebraska Public Power District requested a license amendment to revise the licensing and design basis as documented in the Cooper Nuclear Station Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident dose assessment.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in the application and determined that additional information is required in order to complete the review and approval of the changes. The questions were provided to Mr. E. McCutchen of your staff bye-mail on February 22, 2013. Please respond to the enclosed request for additional information (RAI) within 30 days of the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of NRC staff resources. If circumstances result in the need to revise the requested response date, please contact me at 301-415-1377 or via e-mail at Lynnea.Wilkins@nrc.gov.

Sincerely, IRAI Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

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