ML20008F608

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Forwards Safety Evaluation of Modified Radwaste Solidification Sys Per IE Circular 80-18.Process Control Program Encl
ML20008F608
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/15/1981
From: Baynard P
FLORIDA POWER CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20008F609 List:
References
3-041-22, 3-41-22, IEC-80-18, NUDOCS 8104210372
Download: ML20008F608 (3)


Text

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. P- 9 Florida Power C O a ao e a i so e.

April 15, 1981

  1. 3-041 -22 File: 3-B-14-f bf Mr. Darrell G. Eisenhut Director 'y ApR 2 01981 > C Division of Licensing - -9 U.S. Nuclear Regulatory Comission Q f y ou Washington, D.C. 20555 gs

Subject:

Crystal River Unit 3 /g v Docket No. 50-302 Operating License No. DPR-72 Process Control Program and 10 CFR 50.59 Safety Evaluation for the Radwaste Solidification System

Dear Mr. Eisenhut:

Florida Power Corporation has modified the Crystal River Unit 3 Radwaste Solidification System. The modified radwaste solidification system employs CNSI Cement Solidification Units from Chem-Nuclear Systems, Inc. The modified solidification system became operational effective March 28, 1981.

In accordance with 10 CFR 50.59 and IE Circular 80-18, FPC has performed a safety evaluation of the modified radwaste solidification system.

This safety evaluation did not result into any "unreviewed safety ques-tion."

l The enclosed Process Control Program and a summary of 10 CFR 50.59 l Safety Evaluation are for your information. Mr. Richard Bangard of yt :r office has advised us that an approved Process Control Program is not required prior to the operation of tne modified system, since FPC main-l tains a Certificate of Compliance at the waste processing site (CR-3) placed on the waste burial fi rm, Chem-Nuclear Systems, Inc. by the agreement State of South Carolina.

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-810.4210 378 f g a

General Office 3201 Tn nv cunn street soutn . P O Box 14042. st Petermurg. Flor ca 33733 813 - 866-5151

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i Mr. Darrell G. Eisenhut Director April 15, 1981 Page 2 Should you have any questions regarding the above subject, please con-tact this office.

Very truly yours, FLORIDA POWER CORPORATION

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P. Y. Baynard Manager Nuclear Support Services i

Lobo (T02)D3-2 Enclosure cc: Director Office of Inspection and Enforcement "

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. J. P. O'Deilly

( Director

! Office of Inspection and Enforcement

! Suite 3100 101 Marietta Street Atlanta, GA 30303 Mr. T. F. Stetka NRC Resident Inspector, CR-3 x,c __,

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SUMMARY

OF 10 CFR 50.59 SAFETY EVALUATION FOR THE MODIFIED RADWASTE SOLIDIFICATION SYSTEM PROPOSED MODIFICATIONS Effective January 1,1981, no waste packages shall contain more than trace quantities of non-corrosive free liquids upon arrival at the burial site. Prt:sent methods of waste solidification by Urea Formalde-hyde (UF) Systems do not provide assurance that the waste packages on arrival at the burial site contain no more than trace quantities of non-corrosive free liquids. The CANSI cement mobile and portable solidifi-cation system from Chem-Nuclear Systems, Inc. is the most readily avail-able and approved by the State of South Carolina to replace UF System.

The CANSI cement solidification system provides assurance that waste packages upon arrival at the burial site contain no more than trace quantities of non-corrosive free liquids.

The CANSI cement mobile and portable solidification system will be temporarily connected to the existing CR-3 radwaste system using Chem-Nuclear approved hoses. This portable system will utilize the berm area located near the guard shed, outside the drummir.; room and drumming storage area. The rig of the portable system will reside in the berm area until the proposed waste building is completed.

10 CFR 50.59 SAFETY EVALUATION In accordance with 10 CFR 50.59, IE Bulletin 80-10, IE Circulars 80-18 i and 80-14, FPC has performed a safety evaluation of the proposed modifi-cation to the radwaste solidification system. This proposed modifica-l tion neither involves any change in Safety Technical Specifications nor I increases the probability of an occurrence or the consequences of an accident or malfunction of equipment to safety previously evaluated in the FSAR. Also, the margin of safety, as defined in the basis for any Safety Technical Specification, is not reduced. A review of the pro-posed modification did not result in any "unreviewed safety question."

CONCLUSION t

i NRC approval is not required prior to the modification of the radwaste system. Also, FPC maintains a Certificate of Compliance at CR-3 placed on Chem-Nuclear System, Inc. by the agreement State of South Carolina.

This Certificate of Compliance indicates that CANSI cement solidifica-tion system meets the objective for solid radioactive waste leaving the reactor site for burial as defined in the Appendix 2 of ANSI /ANS 55.1-1979.

l Lobo (T03)D3-2 l

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