NLS2013035, Response to Request for Additional Information Regarding License Amendment Request to Revise the Fuel Handling Accident Dose Assessment
| ML13094A370 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/27/2013 |
| From: | Limpias O Nebraska Public Power District (NPPD) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NLS2013035, TAC ME8992 | |
| Download: ML13094A370 (4) | |
Text
N Nebraska Public Power District Always there when you need us 50.90 NLS2013035 March 27, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
Reference:
Response to Request For Additional Information Regarding License Amendment Request to Revise the Fuel Handling Accident Dose Assessment Cooper Nuclear Station, Docket No. 50-298, DPR-46
- 1. Letter from Lynnea E. Wilkins, U.S. Nuclear Regulatory Commission, to Oscar A. Limpias, Nebraska Public Power District, dated March 8, 2013, "Cooper Nuclear Station - Request For Additional Information Re: License Amendment Request To Revise the Fuel Handling Accident Dose Assessment (TAC No. ME8992)"
- 2. Letter from Brian J. O'Grady, Nebraska Public Power District, to U.S.
Nuclear Regulatory Commission, dated June 25, 2012, "License Amendment Request for Revisions to the Fuel Handling Accident" (NLS2012045)
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District to provide the response to a Nuclear Regulatory Commission Request for Additional Information (Reference 1) related to the Cooper Nuclear Station (CNS) License Amendment Request to revise the CNS Fuel Handling Accident (Reference 2). This response is attached. There are no commitments made in this submittal.
Should you have any questions concerning this matter, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com
NLS2013035 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on 03/Z.7/15 (Date) /
Si Vice President - ?lUucle Chief Nuclear Officer and OAL/wv
Attachment:
Response to Cooper Nuclear Station Request For Additional Information Regarding License Amendment Request to Revise the Fuel Handling Accident Dose Assessment cc:
Regional Administrator w/ Attachment USNRC - Region IV Cooper Project Manager w/ Attachment USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/ Attachment USNRC - CNS Nebraska Health and Human Services w/ Attachment Department of Regulation and Licensure NPG Distribution w/o Attachment CNS Records w/ Attachment
NLS2013035 Attachment Page 1 of 2 Attachment Response to Cooper Nuclear Station Request For Additional Information Regarding License Amendment Request to Revise the Fuel Handling Accident Dose Assessment The Nuclear Regulatory Commission Request for Additional Information regarding the Fuel Handling Accident License Amendment Request is shown in italics. The Nebraska Public Power District (NPPD) response to the RAI is shown in block font.
Request:
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 CNS 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 inflow rates, etc.) which would alter the NPPD X/Q assessment in support ofAmendment No. 222, dated September 5, 2006 (ADAMS Accession No. ML062260239).
NLS2013035 Attachment Page 2 of 2 NPPD Response:
NPPD confirms that 1780 cfm remains the lowest release flow that is appropriate for the Control Room X/Q. The EAB and LPZ X/Q values are based on the methodologies described in Regulatory Guides 1.3 and 1.25, which are independent of the release flow rate. NPPD also confirms that there are not any changes in the FHA release scenario which would alter the X/Q assessment in support of License Amendment 222.