ML110420201: Difference between revisions

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| number = ML110420201
| number = ML110420201
| issue date = 02/11/2011
| issue date = 02/11/2011
| title = Cooper Nuclear Station - Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
| title = Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
| author name = Wilkins L E
| author name = Wilkins L E
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV

Revision as of 01:26, 13 April 2019

Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
ML110420201
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/11/2011
From: Wilkins L E
Plant Licensing Branch IV
To: McCutchen E L
Nebraska Public Power District (NPPD)
Wilkins, L E, NRR/DORL/LPL4, 415-1377
References
TAC ME5287
Download: ML110420201 (1)


Text

From: Wilkins, Lynnea Sent: Friday, February 11, 2011 9:25 AM To: McCutchen, Edward L. Cc: Burkhardt, Janet; Lent, Susan

Subject:

Acceptance of LAR for Reducing the Number of TS 3.4.3 Required Safety Relief Valves (ME5287)

Ed, By letter dated January 5, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110100291), Nebraska Public Power District requested an amendment to the Facility Operating License for the Cooper Nuclear Station. The proposed amendment would modify Technical Specification 3.4.3, "Safety/Relief Valves (SRVs) and Safety Valves (SVs)," by reducing the number of SRVs required to be OPERABLE for over-pressure protection from eight to five. The purpose of this letter 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 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