ML14170B220: Difference between revisions
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{{#Wiki_filter: | {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Wednesday, June 18, 2014 8:37 PM To: medwards@oppd.com; BHansher@oppd.com | ||
==Subject:== | ==Subject:== | ||
Acceptance Review - Fort Calhoun LAR - Revi se Surveillance Frequency for the Pressurizer Safety Valves (MF3466)Mr. Hansher and Mr. Edwards, | Acceptance Review - Fort Calhoun LAR - Revi se Surveillance Frequency for the Pressurizer Safety Valves (MF3466)Mr. Hansher and Mr. Edwards, By letter dated February 10, 2014, as supplemented June 9, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML14041A408 and ML14163A417, respectively), Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would revise the surveillance fre quency for the pressurizer safety valves from a refueling frequency to be consistent with the Inservice Testing Program. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (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. | ||
By letter dated February 10, 2014, as supplemented June 9, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML14041A408 and ML14163A417, respectively), Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would revise the surveillance fre quency for the pressurizer safety valves from a refueling frequency to be consistent with the Inservice Testing Program. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (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 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 NRC staff to complete 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. 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. If additional information is needed, you will be advised by separate correspondence. | 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 NRC staff to complete 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. 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. If additional information is needed, you will be advised by separate correspondence. | ||
Revision as of 14:26, 9 July 2018
| ML14170B220 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/18/2014 |
| From: | Jennivine Rankin Plant Licensing Branch IV |
| To: | Edwards M, Hansher B Entergy Nuclear Operations |
| References | |
| MF3466 | |
| Download: ML14170B220 (2) | |
Text
1 NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Wednesday, June 18, 2014 8:37 PM To: medwards@oppd.com; BHansher@oppd.com
Subject:
Acceptance Review - Fort Calhoun LAR - Revi se Surveillance Frequency for the Pressurizer Safety Valves (MF3466)Mr. Hansher and Mr. Edwards, By letter dated February 10, 2014, as supplemented June 9, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML14041A408 and ML14163A417, respectively), Omaha Public Power District (OPPD) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would revise the surveillance fre quency for the pressurizer safety valves from a refueling frequency to be consistent with the Inservice Testing Program. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (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 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 NRC staff to complete 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. 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. If additional information is needed, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1530.
- Thanks, Jennie Jennie Rankin, Project Manager Palo Verde Nuclear Generating Station Fort Calhoun Station
Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Jennie Rankin, Project Manager Palo Verde Nuclear Generating Station
Fort Calhoun Station Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier: NRR_PMDA Email Number: 1389 Mail Envelope Properties (E85CAE0ED2FC5449B808712D77E97576B5E9DF238C)
Subject:
Acceptance Review - Fort Calhoun LAR - Revise Surveillance Frequency for the Pressurizer Safety Valves (MF3466) Sent Date: 6/18/2014 8:37:27 PM Received Date: 6/18/2014 8:37:00 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients: "medwards@oppd.com" <medwards@oppd.com> Tracking Status: None "BHansher@oppd.com" <BHansher@oppd.com> Tracking Status: None
Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 2895 6/18/2014 8:37:00 PM
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: