ML20010H689

Clarifies to Jr Miller Re Dismantling Plan.Areas Covered by License R-47 Will Be Transferred to License SNM-778 by Separate Action to Be Taken Subsequent to Final IE Insp.Requested Environ Info Encl

ML20010H689
Person / Time
Site:	Lynchburg Research Center, 07000824
Issue date:	09/23/1981
From:	Olsen A BABCOCK & WILCOX CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8109290120
Download: ML20010H689 (3)

Text

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o Rose.rcn & Developm.nt Division Babcock & Wilcox tynennor. R r.n c.ni.,

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License R-4 7, docket 50-99 Reference (a) Letter to Mr. James R. Miller from A. F. Olsen, July 23, 1981.

(b) Dismantling Plan for the Lynchburg Pool Reactor, July,1981, Liccase R-47 docket 50-99.

Gentlemen:

This is to provide additional information and clarifications to the above references.

In the first paragraph of reference (a), I made mention of material license SNM-778.

It was not my intent to request NRR to take any action regsrding our material license, which is clearly a matter for the attention of NMSS.

My intent was to inform you that the areas covered by license R-47 would be transferred to license SNM-778 by separate action to be taken by me subse-quent to final inspection by I&E.

I regret the confusion and hope this will serve to clarify the point.

Mr. Peter Erickson (N.R.R.) phoned me to ask for environmental information that would be pertinent to the dismantling of the Lynchburg Pool Reactor.

In response to his request, I have attached an addendum to reference (b).

If you require any additional information, please call me at (804) 522-5174.

Yours very truly,

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Arne F. Olsen Sr. License Administrator AFO:ccf gQ Attachment 5

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g Environmental Considerations Radioactive material produced during the dismantling process will be sent to a licensed burial ground.

The reactor will be dismantled in accordance with the dismantling plan.

Dismantling will consist primarily of removal of activated reactor internal components, beam ports and autoclave. The reactor has only operated 35 MW days in 22 years and the 1972 cleaning of the pool inoicated that the activity Icvel in the walls was very low. Therefore, only minor decontamina-tion effort is expected.

If any decontamination liquids are generated, they will be handled in accordance with 10 CFR Part 20 requirements and procedures presently in existence at the Lynchburg Research Center (LRC).

It is the intention of B&W te decontaminate t' a LPR to meet the criteria below.

However, these decontamination limits were developed for the release of facili-ties to unrestricted access.

B&W is not releasing the LPR facility for unre-stricted access but transferring the entire area to the control cf the Special Nuclear Material License (SNM-778).

Therefore, if B&W is unable to decontaminate to reach the criteria below, the SNM-778 license will allow a transfer of radioactiva material of higher radia-tion levels.

(B&W has transferred radioactive material with radiation levels up to 55 mrad /hr to the control of license SNM-778 - see letter dated 8/31/72 from A. F. Olsen to R. B. Chitwood (Fuel Fabrication and Reprocessing Branch -

NRC).

Also see letter dated 9/20/72 from R. B. Chitwood to A. F. Olsen).

Su_rface Contamination Surfaces decontaminated to levels consistent with Table 1 or Reg. Ouide 1.86.

Radioactive Material Other Than Surface Contamination (Co 60, Eu 152, Cs 137)

Co 60. Eu 152 and Cs 137 that may exist in concrete, components, struc-tures and soil removed such that the radiation level from these isotopes is less than SUR/hr above natural background (1) as measured at one meter from surface.

(1)

Radiation from naturally occurring radioisotopes as measured at a comparable uncontaminated structure or exterior soil surface.

Therefore, dismantling will cause no significant environmental impact because of the low residual activity and the controls and criteria established.

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2-gernativos to Dismantling of Reactor and Disposal of Compraents The reactor is of no present or future use to the LRC.

It occupies space which can be used by the LRC for other purposes. There are no reasontble alternatives to dismantling.

Long Term Effects of Dismantling and Disposal of Reactor Components Upon removal of reactor components, the facility will be transferred to the license SNM-778 and the facility rooms can be used for other purposes or the facility can be changed into a laboratory.

The reactor fuel will be repro-cessed at the dot, Savannah River Plant.

Reactor components that are radio-active will be disposed of as radioactive waste or transferred to.the license SNM-778 for further use. Nonradioactive omponents will be either disposed of as a clean vaste or retained for further use.

Since the dismantled LPR area will be useful for possible future work under the SNM license, it is.wre bene-ficial to decontaminate to levels as low as reasonably possible and transfer the area to license SNM-778 than attempting to decontaminate to levels for unre-stricted access.

Costs and Benefits of Reactor Dismantling The costs of dismantling the facility and disposal of its components is'esti-mated to be about $125,000. Dismantling is preferable to remaining in its present status where it serves no useful purpose. No benefits would be served by not dismantling the reactor.

Conclusions The LRC concludes that there will be no significant environmental impact associated with the dismantling of the facility and dispcsal of its component ports and that no environmental-impact statement is required to be written for dismantling of the facility and disposal of the component ports.

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