ML12222A266: Difference between revisions

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| number = ML12222A266
| number = ML12222A266
| issue date = 08/08/2012
| issue date = 08/08/2012
| title = Cooper Nuclear Station - Acceptance Review Email, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation (TAC No. ME8992)
| title = Acceptance Review Email, 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
| document type = E-Mail
| page count = 1
| page count = 1
| project = TAC:ME8992
| project = TAC:ME8992
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:From:Wilkins, LynneaTo:"McCutchen, Edward L."Subject:Acceptance of Cooper LAR To Revise the Fuel Handling Accident (ME8992)Date:Wednesday, August 08, 2012 5:34:00 PMEd, By letter dated June 25, 2012 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML121850025), Nebraska Public Power District (NPPD)requested an amendment to the Facility Operating License for the Cooper Nuclear Station(CNS). The proposed amendment would revise the CNS Updated Safety Analysis Report(USAR) to reflect changes to the Fuel Handling Accident (FHA) dose calculation.
{{#Wiki_filter:From:           Wilkins, Lynnea To:             "McCutchen, Edward L."
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), anamendment to the license (including the technical specifications) must fully describe thechanges requested, and following as far as applicable, the form prescribed for originalapplications. Section 50.34 of 10 CFR addresses the content of technical informationrequired. This section stipulates that the submittal address the design and operatingcharacteristics, unusual or novel design features, and principal safety considerations.
 
The NRC staff has reviewed your application and concluded that it does provide technicalinformation in sufficient detail to enable the staff to proceed with its detailed technicalreview and make an independent assessment regarding the acceptability of the proposedamendment in terms of regulatory requirements and the protection of public health andsafety and the environment. If additional information is needed for the staff to complete itstechnical review, you will be advised by separate correspondence.
==Subject:==
If you have any questions, please contact me at (301) 415-1377. Lynnea Wilkins, Project ManagerFort Calhoun Station, Unit 1Plant Licensing Branch IVDivision of Operating Reactor Licensing Office of Nuclear Reactor RegulationUS Nuclear Regulatory CommissionPhone: 301-415-1377  
Acceptance of Cooper LAR To Revise the Fuel Handling Accident (ME8992)
}}
Date:           Wednesday, August 08, 2012 5:34:00 PM Ed, By letter dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121850025), Nebraska Public Power District (NPPD) requested an amendment to the Facility Operating License for the Cooper Nuclear Station (CNS). The proposed amendment would revise the CNS Updated Safety Analysis Report (USAR) to reflect changes to the Fuel Handling Accident (FHA) dose calculation.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1377.
Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377}}

Latest revision as of 23:55, 11 November 2019

Acceptance Review Email, License Amendment Request to Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation
ML12222A266
Person / Time
Site: Cooper Entergy icon.png
Issue date: 08/08/2012
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Mccutchen E
Nebraska Public Power District (NPPD)
Wilkins L
References
TAC ME8992
Download: ML12222A266 (1)


Text

From: Wilkins, Lynnea To: "McCutchen, Edward L."

Subject:

Acceptance of Cooper LAR To Revise the Fuel Handling Accident (ME8992)

Date: Wednesday, August 08, 2012 5:34:00 PM Ed, By letter dated June 25, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML121850025), Nebraska Public Power District (NPPD) requested an amendment to the Facility Operating License for the Cooper Nuclear Station (CNS). The proposed amendment would revise the CNS Updated Safety Analysis Report (USAR) to reflect changes to the Fuel Handling Accident (FHA) dose calculation.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1377.

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