ML20057E620

Forwards Amend 4 to License SNM-7,authorizing Lower Possession Limit & Possession & Use of Small Piece of Spent Fuel

ML20057E620
Person / Time
Site:	07000008
Issue date:	10/05/1993
From:	Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Fess G BATELLE-INSTITUTE, E.V.
Shared Package
ML20057E622	List: ML20057E620 ML20057E637 ML20057E641
References
TAC-L30564, TAC-L30612, NUDOCS 9310120386
Download: ML20057E620 (3)

Text

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License SNM-7 Amendment 4 f

Mr. Gregory Fess L

NRC Licensing Coordinator Battelle Memorial Institute 505 King Avenue Columbus, Ohin 43201-2693 b

Dear Mr. Fess:

SUBJECTS: (1) LOWER POSSESSION LIMITS, AND (2) AUTHORIZATION TO POSSESS AND USE A SMALL PIECE OF SPENT FUEL (TAC NOS. L30564 AND L30612) l

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This is in response to your letters dated June 1,1993, and September 7,1993, in which you requested license amendments to (1) lower your existing possession limits for special nuclear material (SNM), source material, and by-i product material; (2) modify License Condition 9 to reflect current limited l

operations; (3) delete Conditions 15,16 and 17; (4) extend the applicability of Condition 18 to also apply at the West Jefferson facility; (5) delete Condition 26; and (6) authorize the receipt and analysis of a small (less than 50 ' milligrams) piece of irradiated spent fuel.

Items (1) through (5) pertain to your June 1st letter, while item (6) is related to your September 7th letter.

-l We are hereby revising Conditions 6, 7 and 8 of your License SNM-7 to lower the maximum authorized quantities that can be possessed, as requested. We have determined that your request for deleting Conditions 15, 16 and 17 is appropriate in view of the lower possession limits (i.e., the criticality control requirements of 10 CFR 70.24 no longer apply to Battelle). Your request to extend the exemption stated in Condition 18 to also apply to the t

West Jefferson site (rather than just the King Avenue facility) is also warranted. However, since the maximum authorized possessed quantity of SNM at King Avenue and West Jefferson combined will now be well below the applicable i

limits specified in 10 CFR 70.24, such exemption is no longer needed for i

either of your two sites. Consequently, we are deleting Condition 18 i

altogether. Additionally, since Battelle has decided not to construct and J

operate the Volume Reduction and Demonstration Facility, Condition 26 is also no longer necessary, and it too is being deleted.

j With regards to the small piece of spent fuel, we have determined that authorizing its receipt and use for characterization measurements is permissible and warranted and will not adversely affect the public health and safety or the environment. -Accordingly, we are issuing a new License Condition 24,-for this activity and it reads as follows:

24.

Notwithstanding the possession limits stated in Conditions. 6, 7, and 8, the licensee is authorized to possess and use, at its King Avenue site, g

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2 up to 50 milligrams of SNM contained in irradiated spent fuel, provided i

such use is limited to the activities defined in the enclosure to the licensee's letter dated September 7,1993, (from Gregory Fess to NRC's Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards).

It should also be noted that previous Conditions 9 and 10 have been switched with respect to numbering sequence, so as to be consistent with our revised SNM licensing format. That is, previous Condition 9 is now Condition 10, and previous Condition 10 is now 9.

We have also deleted item "b" from previous l

Condition 9 (i.e., new Condition 10), redesignated item "c" as "b" and added i

the three clarifying statements (as new items "c", "d" and "e") as you i

requested. Condition 10 reads as follows:

10.

Authorized use:

a.

For use in accordance with statements, representations and conditions contained in the following portions of the licensee's i

application for renewal (BCL Document 1081) submitted by letter dated October 23, 1981, except as may be modified by the conditions of this license:

1.

Pages vi through x1, Introduction 2.

Part 1, License Conditions 3.

Appendix A, Radiological Safety Ccmmittee Charter i

b.

Conduct controlled field studies using up to a maximum of 3 curies of carbon-14 labelled compounds at the licensee's West Jefferson, Ohio site.

The effective pages of these portions of the application shall be those identified in Annex A that is attached to this license.

i c.

The principal use for items A and B under Conditions 6, 7, and 8 are i

as residual contamination in the Hot Cells of the West Jefferson Facility Building JN-1.

d.

The principal uses for item H under Conditions 6, 7, and 8 are use as residual contamination at BMI's King Avenue and West Jefferson facilities, and as sealed source shielding.

e.

Items E and f under Conditions 6, 7, and 8 have been transferred to the license from DOE inventory to be used for calibration.

In addition, to reflect our Division's February 8,1993, reorganization, License Conditions 11,12,13, and 15 (previously 19) have been revised as follows:

11.

Sealed byproduct material sources shall be subject to the leak testing and actions specified in the attached procedure titled " License Condition for Leak Testing Sealed Byproduct Material Sources," dated April 1993.

Sealed plutonium sources shall be subject to the leak testing and actions specified in the attached procedure titled " License

3 Condition for-Leak Testing Sealed Plutonium Sources," dated April 1993.

3 12.

Notwithstanding Table III and Table IV presented in Part I, Sections-3.4 a

and 3.5, for the release of materials, equipment and facilities for H

unrestricted use the -licensee shall adhere to the provisions of the attached " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use of Termination of Licenses for Byproduct Source, or.Special Nuclear Material," dated April 1993.

13.

Item 10 above incorporates Appendix A (Radiological Safety Committee Charter) of the licensee's renewal application (BCL-1081) as a condition 4

of the license to clarify and define more fully administrative procedures for review, approval and audit of activities covered by the license, as described in Section 1.3 and Section 2.0 of Part I.

The licensee may make-revision to the provisions of Appendix A, based upon written evaluation of the changes, without NRC approval if it is determined that such changes will not decrease the effectiveness of the Committee in carrying out its functions. Revisions to the Charter and supporting evaluations shall be submitted to the Director, Division of Fuel Cycle Safety and Safeguards, NRC, with a copy to the Administrator, Region III Office, NRC, within 60 days following such changes.

15.

The licensee shall provide three copies each year of its annual environmental report to the Director, Division of Fuel Cycle Safety and Safeguards, NRC, and a copy to the Administrator, Region III Office, NRC.

j Enclosed are copies of the revised License SNM-7 and the Safety Evaluation Report which contains the Categorical Exclusion. Should you have any questions regarding these matters, please contact Mr. Donald Joy of my staff on (301) 504-2352.

Sincerely, Oriainal rJaned by ChWs W. Emeich hRobertC.Pierson, Chief Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMS3

Enclosures:

1. License SNM-7

2. Safety Evaluation Report DISTRIBUTION:(Control Nos: 1105, 1205)

Docket 70-08 PDR NRC File Center Region III NMSS r/f FCSS r/f FCLB r/f FCLSI r/f l

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