ML20045G701

TS Change Request 54 to License DPR-4,including Facility Characterization as Activity Permissible in TS

ML20045G701
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	06/23/1993
From:	Hildebrand J SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20045G700	List: ML20045G699 ML20045G701 ML20045G703
References
NUDOCS 9307150065
Download: ML20045G701 (5)

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION SAXTON NUCLEAR FACILITY Operating License No. DPR-4 Docket No. 50-146 Technical Specification Change Request No. 54 1

This Technical Specification Change Request is submitted in support of Lice e's request to change Appendix A to Operating License No. DPR-4 for Saxton Nuclear Facility. As a part of this request, proposed replacement pages for Appendix A are also included.

t SAXTON NUCLEAR EXPERIMENTAL CORPORATION BY: 4% E / NL[6 l

President SNEC Sworn and subscribed

<IJrd to before me t day of d u o ;his , 1993. '

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DIANA M, DeBLASIO

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF SAXTONNUCLEAREXPERIMEh$$LCORPORATION DOCKET NO. 50-146 LICENSE N0. DPR-4 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 54 to Attachment A of the Operating License for the Saxton Nuclear Facility has, on the date given below, been filed with the executives of Liberty Township, Bedford County Pennsylvania; Bedford County Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

Mr. Donald Weaver, Chairman Mr. Richard Rice, Chairman Liberty Township Supervisors Bedford County Commissioners R.D. #1 County Courthouse Saxton, PA 16678 203 South Juliana Street Bedford, PA 15522 Mr. William Dornsife, Director SAXTON NUCLEAR EXPERIMENTAL CORP.

PA Dept. of Environmental Resources Bureau of Radiation Protection BY: /s/ J. E. Hildebrand l

P.O. Box 2063 President, SNEC Harrisburg, PA 17120 DATE: 07/08/93 l

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C301-93-2005 Page 1 of 3

1. Technical Soecification Chanae Reouest No. 54 The Saxton Nuclear Experimental Corporation (SNEC) requests that the following revision be made to the SNEC Technical Specifications (TS):

Replace page A-1.

II. Reason for the Chance ,

This Technical Specification Change Request (TSCR) requests NRC approval i to allow facility characterization at Saxton. The change is necessary to- l allow the collection of radiological data to support best estimates of i manpower, equipment and services, radwaste volumes and types, radiation exposure and costs associated with the decommissioning of the facility to be reflected in the Decommissioning Plan.

Characterization activities will consist of:

1) Direct radiation measurements using conventional survey instruments. Survey activities will be performed in accordance with the guidance in NUREG/CR-5849, " Manual for Conducting Radiological Surveys in Support of License Termination."

2) Removal of samples (concrete cores, insulation, paint, smears of removable contamination and scrapings of corrosion film from the inside surfaces of plant systems) for detailed radiological analysis.

3) Component disassembly and shield block removal to permit access for the sample / survey activities described above. No dismantlement or component removal will occur beyond that required to permit--

characterization. No permanent changes or modifications to the facility, except for the core bores and the addition of equipment to support rigging activities, will take place.

4) Inspection and evaluation of the material / physical condtion of the facility (i.e. Containment Vessel and overhead crane to permit conceptual design modification engineering and refurbishment planning) activities in support of decommissioning.

5) Toxic / hazardous material evaluation will be performed in addition to the radiological characterization. -The materials to be evaluated include lead, lead based paints and asbestos.

III. Safety Evaluation  :

Power operation at the SNEC facility was concluded in May 1972 and l shortly afterward all systems, components and areas presently requiring  !

characterization were drained and vented. Decommissioning and/or i maintenance of the facility has continued since that time. Planning for ,

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1 C301-93-2005 Page 2 of 3 decommissioning the SNEC facility in support of license termination is in progress. Extensive radiological and toxic / hazardous material characterization, as described above, is required to provide data indicative of current plant conditions relative to these concerns. The resulting data will be used in evaluating appropriate work practices and determining the extent of the contaminated / radioactive waste resulting from the decommissioning activity. The information is key to the i development of a practical decommissioning plan for SNEC.

Routine quarterly surveillances performed from mid 1975 to the present i have identified no evidence of any remaining liquids and no change in the radiological condition of the containment vessel and its contents with the exception of natural radiological decay. The characterization activities delineated above will not produce any effect which would cause a release of radiological material in excess of 10 CFR 20 limits.

The activities permitted by this revision to the TS do not differ substantively from the routine activities performed under sections 4.b.,

4.c., and 4.d. of the current TS. The characterization activities will be performed in accordance with TS sections 4.c. and 4.d. requirements as implemented by procedures. Based on the procedural control of the activities, the stable radiological condition of the containment vessel and the knowledge that the delineated activities will not disrupt that stability, it has been concluded that characterization activities will have no adverse impact on the health and safety of the public.

IV. No Sionificant Hazards Consideration SNEC has determined that this TSCR poses no significant hazards as defined in 10 CFR 50.92. Allowing the performance of characterizction activities enhances the success of the decommissioning effort by i

permitting effective evaluation of the radiological condition of the facility. Characterization of the facility will not:

1. As previously identified, power generation at the SNEC facility was terminated in May 1972. The unit has been defueled and the reactor coolant system drained. Since activities associated with characterization of the facility are not operational in nature and the equipment remaining at the facility is non-functional, there will be no significant increase in the probability or consequences of an accident previously evaluated.

2. For the reasons provided in 1 above, the possibility of a new or different type of accident previously evaluated in the FSAR will not be created by the implementation of activities permitted by the approval of this TSCR.  ;

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3. No margins of safety exist that are relevant to the equipment remaining at the facility. As a result, activities involved in characterization will not involve a significant reduction in a margin of safety.

V. ImplementatiqD It is requested that the amendment authorizing this TSCR be issued i expeditiously and be effective upon issuance. Completion and submittal of the Decommissioning Plan for SNEC is dependent on data obtained during facility characterization. ,

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