ML20246F226

Amend 3 to License SNM-21,revising License Condition 24 Re Radiological Contingency Plan

ML20246F226
Person / Time
Site:	07000025
Issue date:	07/07/1989
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20246F219	List: ML20246F214 ML20246F226 ML20246F230 ML20246F234
References
NUDOCS 8907130165
Download: ML20246F226 (4)

Text

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i MATERIALS LICENSE l Pursuant to the Atomic Energy Act of1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 i Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations o l heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and tran I

source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated be I

I deliver or transfer such material to persons autherized to receive it in accordance with the regulations of the applicable Part(s). Th license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is l subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect an conditions specified below.

I I, Licensee i

I g, Rocketdyne Division SNM-21, I 3. License numbr.

8 Rockwell International Corporation Amendment No. 3 R

July 7, 1989 l 8900 DeSoto Avenue

4. Expiratica date June 30, 1989 i Canoga Park, CA 91304 l S. Docket or 70-25 l Reference No.

I 6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maximum amount that licensee I special nuclear material form may possess at any one time

,I under thislicense i

I A. Uranium enriched in A. Any enrichment or A. 5 kilograms U-235*

I U-235 isotope form except UF '

I 6 I B. Pu (principally Pu-239) 8. Any B. Maximum of 2.0 l kilograms total Pu*

I i 1. SSFL Site Hot g

Laboratory - up R

to 2.0 kilograms I Pu in irradiated and/or unirradiated E, fuel with less than y

1.0 kg Pu in process. I I

I 2. A maximum of 2 g I

I total Pu for gamma I spectroscopy and radiometric counting ,

l analysis and a y

p maximum of 0.1 g of Pu I

for chemical analysis I

used in any authorized building at the SSFL I site in accordance with NRC approved l radiation safety i criteria.

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• Enriched uranium and plutonium in combination not to exceed 5.0 formula kg calculated by

kg U-235 + (2.5)(kg Pu).

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License number 0, PAGES

! MATERIALS LICENSE SNM21. Amendment No. 3 1 SUPPLEMENTARY SHEET **'*"**"""

l 70-25

,1 July 7, 1989 l C. Pu (principally Pu-239) C. Sealed sources C. 1.0 kilograms total i (as Pu-Be sources) Pu in any authorized I

I building at the SSFL i site in accordance wt l NRC approved radiati@

, safety criteria.

! 9. Authorized use: For use in accordance with statements, representations, and a

I conditions contained in Part I of the licensee's application dated August 20, 1982, I

and supplements dated October 29 and December 17, 1982; March 2, March 7, May 29, I and June 12, 1984; September 22, 1987; December 19, 1988; and January 26, 1989.

f 10. Authorized place of use: Building 020 and other authorized buildings at the i licensee's Santa Susana Field Laboratory in Chatsworth, California, as described in i the referenced application and supplements and as specified in Conditions 8.B.2 and I 8. C. Notwithstanding the statements in Section 1.2, the Canoga Park facilities and I

R Building 055 at the SSFL site are not authorized as places of use under this license.

l 11. Notwithstanding Section 1.5(1)a, Pu shall be handled only for the purpose of i decladding, removal of bonding material, examination, and repackaging.

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12. Notwithstanding the statements in Section 1.7, the manufacture of fuel element l assemblies and related activities are not authorized by this license.

f 13. The minimum qualifications for the Criticality Safeguards Advisor and the Physicist i on the Fuels Committee shall be a B.S. degree in one of the physical sciences and a I minimum of 2 years' experience in outside-of-reactor criticality safety analyses.

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14. All personnel, prior to unsupervised work with special nuclear materials, shall l receive formal training in nuclear criticality and/or radiation safety. The i effectiveness of the training program shall be measured by written examination.

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( 15. Copies of nuclear safety analyses, criticality studies, and other reports prepared by the Criticality Safeguards Coordinator or Criticality Safeguards Advisor regarding l radiation or nuclear criticality safety shall be maintained for a period of at least g 2 yet rs or for 6 months after a project is terminated, whichever is longer.

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16. Process designs shall incorporate sufficient factors of safety to require at least I

two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible. ,

l h 17. Notwithstanding the use of alternative methods of calculation specified in q

Section 4.2.1 of Part I of the license application, only methods of analysis for i calculating nuclear criticality safety parameters, satisfact0rily demonstrated to the Commission and approved by it, shall be used in the evaluation of nuclear criticality l safety.

l 18. The licensee shall check the director of air flow in the hot cell facility each I month. When adverse air flows are detected, corrective action shall be taken and

( documented.

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• Lic;nse number PAGE OF E PAGES

! MATERIALS LICENSE ,

men No. 3 l SUPPLEMENTARY SHEET *"*

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July 7, 1989 l 19. The licensee shall comply with the following regarding in plant airborne sampling y and monitoring:

1 i a.

I Notwithstanding the statement in Section 3.2.4.2(1) of the application, the breathing I zone air, in work areas where the dispersible form of radioactive material is 8 handled, shall be sampled for airborne radioactive material during the normal operations.

I i b.

I The fixed air samplers shall be checked annually and whenever any process or equipmes I changes are made to verify that the airborne concentration of radioactivity collecte@

I at these locations are representative of the air being breathed by workers. In I addition, prior to the commencement of operation in an area that has been shutdown for more than 6 months, the location of air samplers shall be chec.ked to verify the

, representativeness of the air sampling.

I i 20. The licensee's bicassay program for Pu shall comply with the following:

I E a.

Employees working in the area where there is unencapsulated Pu shall submit urine l samples at least quarterly for routine plutonium analysis.

I i b.

i If an employee has been exposed to greater than 40 MPC-hours of plutonium in any I consecutive 7-day period, or if urinalysis shows >0.2 dpm of Pu per day, then fecal I analysis shall be performed to evaluate exposure.~ If fecal analysis indicates a N significant exposure to plutonium, then in-vivo lung courting shall also be performede l c.

If in-vivo lung counting indicates an individual has a MPLB, the employee shall be i immediately removed from further exposure.

I i d.

The dose commitment from Am shall also be considered in the above Pu bioassay program.

l l 21. The licensee shall comply with the following regarding the surface contamination:

E e a.

Prior to exiting a restricted area, all individuals must monitor hands, head, I

personal clothing, and shoes for radiation contamination.

lg b.

The licensee shall not allow an individual whose skin, personal clothing, or shoes are found contaminated above background levels to exit a restricted area without

( prior approval of the Radiation and Nuclear Safety Unit.

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22. The licensee shall conduct leak testing of the encapsulated plutonium in j

l accordance with Annex A, " License Condition for Leak Testing Sealed Plutonium Sources," dated November 1979.

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l 23. Release of equipment and packages from the plant site or to unrestricted areas I

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onsite shall be in accordance with Annex B, " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of l Licenses for Byproduct, Source, or Mecial Nuclear Material," dated August 1987.

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• • 883 pact 4 or 4 pacts l License number I

Sht-21, Amendment No. 3 I MATERIALS LICENSE l

pocket or Reference number SUPPLEMENTARY SHEET I 70-25 I

July 7, 1989 l 24. The licensee shall maintain and execute the response measures of his i Radiological Contingency Plan dated July 25, 1988 (submitted by letter l dated July 26, 1988) and revision dated May 19, 1989, (submitted by letter I dated May 24, 1989. The licensee shall also maintain implementing pro-I cedures for his Radiological Contingency Plan. The licensee shall make no I

I change in his Radiological Contingency Plan that would decrease the response effectiveness of the Plan without prior Commissian approval. The licensee

may make changes to the Radiological Contingency Plan without prior Commission i approval if the changes do not decrease the response effectiveness of the l Plan. Each change shall be submitted within 6 months of the change to the I

I Chief, Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear Safety, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555.

I l 25. At the end of plant life, the licensee shall decontaminate the facility and site in l accordance with the general decommissioning plan submitted in the enclosures to lettet i dated March 15, 1978, so that these facilities and grounds can be released for I unrestricted use. The financial plan, to assure that funds will be available for l decommissioning, submitted by letter dated October 26, 1978, is hereby incorporated y as a condition of the license.

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I tt y / . k, t FOR THE NUCLEAR REGULATORY COMMISSION l D (j @.v '

l Original Signed By Date: July 7, 1989 By: Leland C. Rouse

[i g Division of Industrial and q

Medical Nuclear Safety j g

Washington, DC 20555 (

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