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| number = ML13053A342
| number = ML13053A342
| issue date = 02/22/2013
| issue date = 02/22/2013
| title = Cooper Nuclear Station - E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation (TAC No. ME8992)
| title = E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
| author name = Wilkins L E
| author name = Wilkins L
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = McCutchen E L
| addressee name = Mccutchen E
| addressee affiliation = Nebraska Public Power District (NPPD)
| addressee affiliation = Nebraska Public Power District (NPPD)
| docket = 05000298
| docket = 05000298
| license number = DPR-046
| license number = DPR-046
| contact person = Wilkins L E
| contact person = Wilkins L
| case reference number = TAC ME8992
| case reference number = TAC ME8992
| document type = E-Mail, Request for Additional Information (RAI)
| document type = E-Mail, Request for Additional Information (RAI)
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=Text=
=Text=
{{#Wiki_filter:Lent, Susan From: Wilkins, Lynnea Sent: Friday, February 22,20131:29 PM To: McCutchen, Edward L. Cc; Lent, Susan; Burkhardt, Janet  
{{#Wiki_filter:Lent, Susan From:                       Wilkins, Lynnea Sent:                       Friday, February 22,20131:29 PM To:                         McCutchen, Edward L.
Cc;                         Lent, Susan; Burkhardt, Janet


==Subject:==
==Subject:==
DRAFT: RAls for Cooper Nuclear Station Re: Fuel Handling Accident Dose Assessment (ME8992) Attachments:
DRAFT: RAls for Cooper Nuclear Station Re: Fuel Handling Accident Dose Assessment (ME8992)
ME8992 RAls Email.docx Ed, By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number NIL 121850025), Nebraska Public Power District (NPPD), requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment.
Attachments:                 ME8992 RAls Email.docx Ed, By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS)
The NRC staff has determined that additional information specified in the attached Request for Additional Information (RAI) is needed for the staff to complete its evaluation.
Accession Number NIL121850025), Nebraska Public Power District (NPPD), requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment.
Please contact me if a clarifying teleconference is needed for the attached RAI. Thanks Lynnea Lynnea Wi(/(ins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1
The NRC staff has determined that additional information specified in the attached Request for Additional Information (RAI) is needed for the staff to complete its evaluation. Please contact me if a clarifying teleconference is needed for the attached RAI.
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR REVISIONS TO THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT TAC NO. ME8992 By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 121850025), Nebraska Public Power District (NPPD), requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment.
Thanks Lynnea Lynnea Wi(/(ins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1
Section 2.5, "Atmospheric Dispersion (X/Q) Factors," of Attachment 4 to the application states, in part: "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.  
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR REVISIONS TO THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT TAC NO. ME8992 By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML121850025), Nebraska Public Power District (NPPD),
'The control room intake X/Q values were taken from reference 23 for a release emanating from the Reactor Building.
requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment.
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.  
Section 2.5, "Atmospheric Dispersion (X/Q) Factors," of Attachment 4 to the application states, in part:
... 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 CNS Amendment 222 dated September 5, 2006 (ADAMS Accession Number ML062260239).}}
    "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 in flow rates, etc.) which would alter the NPPD X/Q assessment in support of CNS Amendment 222 dated September 5, 2006 (ADAMS Accession Number ML062260239).
ENCLOSURE}}

Latest revision as of 22:52, 4 November 2019

E-mail, Draft Request for Additional Information, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
ML13053A342
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/22/2013
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Mccutchen E
Nebraska Public Power District (NPPD)
Wilkins L
References
TAC ME8992
Download: ML13053A342 (2)
v • d • e


Text

Lent, Susan From: Wilkins, Lynnea Sent: Friday, February 22,20131:29 PM To: McCutchen, Edward L.

Cc; Lent, Susan; Burkhardt, Janet

Subject:

DRAFT: RAls for Cooper Nuclear Station Re: Fuel Handling Accident Dose Assessment (ME8992)

Attachments: ME8992 RAls Email.docx Ed, By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS)

Accession Number NIL121850025), Nebraska Public Power District (NPPD), requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise the Cooper Nuclear Station (CNS) Updated Safety Analysis Report to reflect changes to the Fuel Handling Accident (FHA) dose assessment.

The NRC staff has determined that additional information specified in the attached Request for Additional Information (RAI) is needed for the staff to complete its evaluation. Please contact me if a clarifying teleconference is needed for the attached RAI.

Thanks Lynnea Lynnea Wi(/(ins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST FOR REVISIONS TO THE FUEL HANDLING ACCIDENT DOSE ASSESSMENT TAC NO. ME8992 By application dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML121850025), Nebraska Public Power District (NPPD),

requested an amendment to Facility Operating License DPR-46 under the provisions of 10 CFR 50.4 and 10 CFR 50.90 to revise 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 Attachment 4 to the application states, in part:

"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 in flow rates, etc.) which would alter the NPPD X/Q assessment in support of CNS Amendment 222 dated September 5, 2006 (ADAMS Accession Number ML062260239).

ENCLOSURE

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