ML16005A552: Difference between revisions

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| document type = E-Mail
| document type = E-Mail
| page count = 1
| page count = 1
| project = CAC:MF7144, CAC:MF7143
| project = CAC:MF7143, CAC:MF7144
| stage = Acceptance Review
| stage = Acceptance Review
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Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) 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 request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1420.  
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) 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 request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1420.  


Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing  Office of Nuclear Reactor Regulation
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing  Office of Nuclear Reactor Regulation}}
 
}}

Revision as of 20:46, 20 May 2018

Acceptance Review - Peach Bottom Units 2 and 3 - Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements (CACs MF7143 and MF7144)
ML16005A552
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/05/2016
From: Richard Ennis
Plant Licensing Branch 1
To: Hanson S
Exelon Generation Co
Ennis R B
References
CAC MF7143, CAC MF7144
Download: ML16005A552 (1)


Text

From: Ennis, Rick Sent: Tuesday, January 05, 2016 3:58 PM To: Stephanie.Hanson@exeloncorp.com Cc: David Helker

Subject:

Acceptance Review - Peach Bottom Units 2 and 3 - Emergency Diesel Generator Fuel Oil Transfer Surveillance Requirements (CACs MF7143 and MF7144) Stephanie, By letter dated December 3, 2015 (ADAMS Accession No. ML15337A413), Exelon Generation Company, LLC submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would revise the surveillance requirements associated with the emergency diesel generator (EDG) fuel oil transfer system. Specifically, the amendment would allow for the crediting of manual actions, in lieu of automatic actions, without having to declare the EDGs inoperable.

The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs) 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 request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1420.

Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation