ML17037D162

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Supplemental Information Needed for Acceptance of Requested Licensing Action - Request for Exemptions from 10 CFR 50.47 and 10 CFR 50 Appendix E, Reduce Emergency Planning Requirements for Permanently Defueled Condition (MF9067)
ML17037D162
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/07/2017
From: James Kim
Special Projects and Process Branch
To: Fisher M
Omaha Public Power District
Kim J
References
CAC MF9067
Download: ML17037D162 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ms. Mary J. Fisher Senior Director for Decommissioning Omaha Public Power District Fort Calhoun Station 9610 Power Lane, Mail Stop FC-2-4 Blair, NE 68008 February 7, 2017

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE:

EXEMPTIONS FROM 10 CFR 50.47 AND 10 CFR PART 50, APPENDIX E (CAC NO. MF9067)

Dear Ms. Fisher:

By letter dated December 16, 2016 (ADAMS Accession No. ML16356A578), Omaha Public Power District (OPPD, the licensee) requested exemptions from portions of Sections 50.47(b) and 50.47(c)(2) of Title 10 of the Code of Federal Regulations (10 CFR), and 10 CFR Part 50, Appendix E for the Fort Calhoun Station, Unit No. 1 (FCS). The proposed exemptions would allow FCS to reduce emergency planning requirements consistent with the permanently defueled condition of the station.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of the exemption 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.

The NRC staff has reviewed your application and concluded that the following information is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed exemptions request in terms of regulatory requirements and the protection of public health and safety and the environment.

The licensee stated that the justification for the requested exemptions was based on Interim Staff Guidance (ISG) NSIR/DPR-ISG-02, "Emergency Planning Exemption Requests for Decommissioning Nuclear Power Plants," dated May 11, 2015 (ADAMS Accession No. ML14106A057). The ISG indicated that expected analyses completed by the licensee include an adiabatic heatup analysis. This analysis is determined by the ratio of the heat capacity to the decay heat rate for the limiting assembly. Information about decay heat of the limiting assembly in of the exemption request consisted of Table 2-4, "Heat Generated by the Highest Heat Load Fuel Assembly (DD07)," which listed the maximum fuel assembly heat generation rate for several different times after shutdown.

The NRC staff found Table 2-4 provided insufficient information to support the adiabatic heatup time analysis. Specifically, the provided information did not indicate the methodology used to calculate the decay heat rate, the input values used in the methodology, and how the input values were established. This information should be provided to enable a complete review of the adiabatic heatup analysis.

In order to make the application complete, the NRC staff requests that OPPD supplement the application to address the information requested as stated above by February 17, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter were discussed with Mr. Erick Matzke of your staff on February 6, 2017.

If you have any questions, please contact me at (301) 415-4125 or e-mail at James.Kim@nrc.gov.

Docket No. 50-285 cc: Listserv Sincerely,

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James Kim, Project Manager Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ML17037D162 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LSPB/LA NAME JKim JBurkhardt DATE 2/07/2017 2/07/2017 OFFICE NRR/DORL/LSPB/BC NRR/DORL/LSPB/PM NAME DBroaddus JKim DATE 2/07/2017 2/07/2017