ML20247A424

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Safety Evaluation Accepting Revised Process Control Program Re General Methods of Sampling,Processing,Analysis & Waste Formulation During Solidification of Radwaste
ML20247A424
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/20/1989
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247A399 List:
References
NUDOCS 8903290120
Download: ML20247A424 (2)


Text

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5 E WASHINGTON, D. C. 20666

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SOLID WASTE PROCESS CONTROL PROGRAM REVIEW NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298

1.0 INTRODUCTION

By letter dated October 28, 1988 Nebraska Public Power District (NPPD) submitted a revised Process Control Program outlining the general methods of sampling, processing, analysis and waste formulation during solidification of radioactive waste. Prior to this, the basis for waste solidification had been the Cooper Nuclear Station Process Control Program submitted to the NRC by letter dated June 8,1982. In addition, by letter dated May 24, 1988, the licensee submitted information regarding testing of the processed waste for conformity with the waste stability requirements of 10 CFR 61.56 for disposal of the waste.

2.0 EVALUATION The licensing guidance regarding process control programs is contained in NUREG-0800, " Standard Review Plan for the Review of Safety Analysis  ;

Reports for Nuclear Power Plants," Section 11.4, " Solid Waste Management Systems," Revision 2, July 1981, and in the staff document " Guidelines for Preparation of a Solid Waste Process Control Program." The staff has completed its review of the revised Process Control Program for the Cooper Nuclear Station and finds that it is in conformance with this licensing guidance and, therefore, is acceptable.

Guidance to waste generators on test methods and results for implementing 10 CFR 61.56 waste stability requirements is contained in the technical position paper sent to all Comission licensees in s letter dated May 11, l' 1983. The staff has not completed its review of the licensee's submittal regarding testing of the processed waste for conformity with the waste stability requirements of 10 CFR 61.56. However, our preliminary assessment i of this submittal has indicated no non-conformities with the guidance on j waste stability as contained in the technical position paper identified J above. j

3.0 CONCLUSION

The acceptance of the Cooper Process Control Program and the above preliminary assessment of the licensee's 10 CFR 61.56 submittal are the bases, during the interim period until the staff review of the 10 CFR 61.56 submittal is completed, for our conclusion that reasonable assurance 8103290120 890320 N ua ADOCK0500ggy8 p i

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O i 2 has been provided that the waste solidified at the Cooper Nuclear Station in accordance with the Cooper Nuclear Station Technical Specifications j will be in conformance with the waste stability requirements of 10 CFR 61.56.

Principal Contributor: C. Nichols M. Tokar P. O'Connor Dated: March 20, 1989

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