ML16243A366

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Acceptance of Requested Licensing Action Measurement Uncertainty Recapture
ML16243A366
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/01/2016
From: John Klos
Plant Licensing Branch IV
To: Reddemann M
Energy Northwest
Klos L
References
CAC MF8060
Download: ML16243A366 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 1, 2016 Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)

Richland, WA 99352-0968

SUBJECT:

COLUMBIA GENERATING STATION-ACCEPTANCE OF REQUESTED LICENSING ACTION RE: MEASUREMENT UNCERTAINTY RECAPTURE (CAC NO. MF8060)

Dear Mr. Reddemann:

By letter dated June 28, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16183A365) as supplemented by letter dated August 18, 2016 (ADAMS Accession No. ML16231A511), Energy Northwest submitted a license amendment for Columbia Generating Station. The proposed amendment would revise the operating license and technical specification to implement an increase in rated thermal power from the current licensed thermal power of 3486 megawatts thermal (MWt) to a measurement uncertainty recapture thermal power of 3544 MWt. The purpose of this letter 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. During the acceptance review process insufficiencies were identified by the NRC staff which were submitted in the supplemental letter dated August 18, 2016 stated above.

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. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

M. Reddeman If you have any questions, please contact me at (301) 415-5136 or via e-mail at John.Klos@nrc.gov.

J n los, Project Manager Plan Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397 cc: Distribution via Listserv

ML16243A366 OFFICE NRR/DORL/LPL4-1/PM NRR/DORL/LPL4-1/LA NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME JKlos JBurkhardt(PBlechman for) BPascarelli JKlos DATE 8/31/16 8/31/16 8/31/16 9/1 /16