ML20134M960

Amend 91 to License DPR-40,adding New Tech Specs Addressing Surveillance Requirements Re Solid Radwaste Process Control Program

ML20134M960
Person / Time
Site:	Fort Calhoun
Issue date:	08/22/1985
From:	Butcher E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20134M957	List: ML20134M954 ML20134M960 ML20134N025
References
NUDOCS 8509040358
Download: ML20134M960 (4)

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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION,-UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE  !

Amendment No.91 License No. DPR-40

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated June 6, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended

.(the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the

. Comission; C. There is reasonable assurance (1) that the activities authorized i by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. ,

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of October 3,1985.

FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 22, 1985

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ATTACHMENT TO LICENSE AMENDMENT NO.91 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise the Appendix "A" Technical Specifications as indicated below. The revised page is identified by amendment number and contains vertical lines indicating the area of change.

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3.0 SURVEILLANCE REQUIREMENTS 3.12 Radiological Waste Sampling and Monitoring (Continued) 3.12.2 Solid Radioactive Waste Applicability Applies to the sampling, testing, and analysis of the wet radioactive waste.

Objective To ensure that the solid radioactive wastes meet the limits specified in Section 2.9.2 of these Specifications. .

Specifications (1) The Process Control Program (PCP) shall be used to verify the solidification of at laast one representative test specimen (drum) from at least every twelfth batch of wet radioactive waste (e.g., evaporator concentrates).

A. If any test specimen fails to terify solidification, the following actions shall be taken:

(i) Verify solidification of all other drums from the batch under test.

(ii) Review the adequacy of the solidification parameters defined in the PCP and develop / verify alternative solidifiestion parameters, if required, in accordance with the PCP. -

t In the event the solidification parameters are altered:

(a) Select one representative drum from each consecutive batch to verify solidification until at least 3 consecutive drums verify solidification. The surveil-lance schedule defined in Specification 3.12.2(1),

above, may be resumed after 3 consecutive drums verify solidification.

'(b) Modify the PCP as required and report the changes to the NRC in accordance with Specification 5.9.4.a.

Basis This. specification was developed to ensure the requirements of 10 CFR Parts 20 and 71 for solid radioactive waste are met. The purpose of placing wet radioactive wastes in a solid, dry form is to limit dispersion of radioactive material to the environs in the event of failure of a o disposal container (drum) before, during or after disposal. These require-

, ments provide periodic documentation that solidified wet radioactive waste materials are in suitable form for transportation and. disposal.

, .3-71a Amendment No. SS, 91

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