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 Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations i

heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and tran l

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

deliver or transfer such material to persons autherized to receive it in accordance with the regulations of the applicable Part(s). Th I

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.

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Licensee i

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Rocketdyne Division

3. License numbr.

SNM-21, I

Rockwell International Corporation Amendment No. 3 8

R July 7, 1989 l

8900 DeSoto Avenue June 30, 1989 i

Canoga Park, CA 91304

4. Expiratica date l

S. Docket or 70-25 l

Reference No.

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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

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B.

Pu (principally Pu-239) 8.

Any B.

Maximum of 2.0 l

kilograms total Pu*

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1.

SSFL Site Hot Laboratory - up g

R to 2.0 kilograms I

Pu in irradiated and/or unirradiated E,

fuel with less than y

1.0 kg Pu in process.

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I 2.

A maximum of 2 g I

I total Pu for gamma I

spectroscopy and l

radiometric counting analysis and a y

maximum of 0.1 g of Pu p

for chemical analysis I

used in any authorized I

building at the SSFL I

site in accordance l

with NRC approved 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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PAGES

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License number 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

building at the SSFL I

i site in accordance wt l

NRC approved radiati@

safety criteria.

9.

Authorized use:

For use in accordance with statements, representations, and conditions contained in Part I of the licensee's application dated August 20, 1982, a

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.

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10. Authorized place of use:

Building 020 and other authorized buildings at the licensee's Santa Susana Field Laboratory in Chatsworth, California, as described in i

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

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

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11. Notwithstanding Section 1.5(1)a, Pu shall be handled only for the purpose of 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.

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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 I

criticality accident is possible.

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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.

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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

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documented.

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E l.P 84 PAGE OF PAGES Lic;nse number MATERIALS LICENSE men No. 3 l

SUPPLEMENTARY SHEET

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I July 7, 1989 l

19. The licensee shall comply with the following regarding in plant airborne sampling and monitoring:

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Notwithstanding the statement in Section 3.2.4.2(1) of the application, the breathing i

a.

I zone air, in work areas where the dispersible form of radioactive material is I

handled, shall be sampled for airborne radioactive material during the normal 8

operations.

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b.

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

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at these locations are representative of the air being breathed by workers.

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addition, prior to the commencement of operation in an area that has been shutdown I

for more than 6 months, the location of air samplers shall be chec.ked to verify the representativeness of the air sampling.

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

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E a.

Employees working in the area where there is unencapsulated Pu shall submit urine l

samples at least quarterly for routine plutonium analysis.

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b.

If an employee has been exposed to greater than 40 MPC-hours of plutonium in any consecutive 7-day period, or if urinalysis shows >0.2 dpm of Pu per day, then fecal i

I analysis shall be performed to evaluate exposure.~ If fecal analysis indicates a I

significant exposure to plutonium, then in-vivo lung courting shall also be performede N

l If in-vivo lung counting indicates an individual has a MPLB, the employee shall be c.

immediately removed from further exposure.

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i d.

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

program.

l 21.

The licensee shall comply with the following regarding the surface contamination:

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

a.

personal clothing, and shoes for radiation contamination.

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b.

The licensee shall not allow an individual whose skin, personal clothing, or shoes g

are found contaminated above background levels to exit a restricted area without

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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 l

accordance with Annex A, " License Condition for Leak Testing Sealed Plutonium j

y Sources," dated November 1979.

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

onsite shall be in accordance with Annex B, " Guidelines for Decontamination of 4

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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N2C Fu,m 3MA U.S. NUCLEAQ r.EcuLATO3Y COMMISSloN l

• • 883 pact 4 or 4

pacts License number I

Sht-21, Amendment No. 3 I

MATERIALS LICENSE l

SUPPLEMENTARY SHEET pocket or Reference number 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

change in his Radiological Contingency Plan that would decrease the response I

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

Chief, Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear I

Safety, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555.

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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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FOR THE NUCLEAR REGULATORY COMMISSION l

l Original Signed By

[i Date:

July 7, 1989 By:

Leland C. Rouse g

Division of Industrial and q

Medical Nuclear Safety j

g Washington, DC 20555

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