ML20217C754

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Amend 43 to License SNM-696 for General Atomics, Incorporating Changes to Emergency Plan
ML20217C754
Person / Time
Site: 07000734
Issue date: 03/25/1998
From: Weber M
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20217C748 List:
References
NUDOCS 9803270157
Download: ML20217C754 (7)


Text

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NRC FORM 374 u.s. NUCLEAR REGULATORY COMMisslON l-SIATERIALS LICENSE (q!

.S 93-4381, and Title 10. Code of I g Pursuant to the Atomic Energy Act of 1954, as amended. the Energy Reorganization Act of 1974 (Public Law g federal Regulanons. Chapter I. Parts 30,31,32. 33. 34,35,36. 39,40, and 70, and in reliance on statements and representations her l by the licensee, a hcense is hereby issued authori/mg the licensee to receis e, acquire. possess, and transfer by product, source. and special nuclear j p

h material designated below; to use such matenal ror the purposeh) and at the placch) designated below; to dehser or transfer such material to i h persons authorved to recene it in accordance with the regulatmns of the apphcable Parth). This license shall be deemed to contain the conditions i

specified in Section 183 of the Atomic Energy Act of 1954. as amended, and is subject to all applicable rules, regulations, and orders of the j 9

?j Nuclear Regulatory Commission now or hereaf ter in ef fect and to any conditions spe

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General Atomics

3. License Number SNM-696,

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S Amendment 43 t

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P.O. Box 85608 IXcimbeT3171989 E

f Sl San Diego, Califomia 92186-9784

4. Expiration Date h

S70-734 l

5. Docket or w

g Reference No.

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6. liyproduct, Source, and/or
7. Chemical and/or Physical
8. Maximurn Amount that Licensee 9l h

Special Nuclear Material Form May Possess at Any One Time 12l ti Under This License D

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A.

Uranium A.

Enriched up to 19.99%

A.

200 kilograms U-235

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.3 U-235

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5l El Uranium B.

Enriched 20 to 100% U-235 B.

Less than 5000 gm*

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U-233 C.

Any C.

Less than 2000 gm

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Plutonium D.

Encapsulated and/or D.

Less than 2000 gm l

9 sealed sources total Pu'

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E.

Plutonium E.

Bred but unseparated E.

Less than 1000 gm

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,5 total Pu*

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Plutonium F.

Plated calibration F.

Less than 5 grams O

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source total Pu*

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Plutonium G.

Sulutions, precipitates G.

Less than 5 grams

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?j The sum total quantity of strategic special nuclear material possessed at any one time must be less I$"g

$jj than 5,000 grams computed by the formula:

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grams U-235 in uranium enriched to 20% or more p us 2.5 (grams U-233 + grams d

plutonium)

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Authorized place of use: The licensee's San Diego, Califomia site as specified in the aforesaid

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NRC'f0RM 374A U.S. NUCLEAR REGULATORY eoMMISSloN PAGE 2

oF 7

PAGES !!

y License Number p.

SNM-696 Amendment 43 j,

lp MATERIALS LICENSE

!Auct or Refereme Number j

g SUPPLEMENTARY SHEET 70-734 E

5 B

E W

E W

E N

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10.

This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.

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These sections are part of the license, and the licensee is subject to compliance with all listed E

g conditions in each section.

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FOR THE NUCLEAR REGULATORY COMMISSION N

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Date:

By:

Michael F. Weber B

Division of Fuel Cycle Safety H

Hj and Safeguards, NMSS El sj Washington, DC 20555 h

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$j (Provided w/ Amendment 31) fl!

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Enclosures:

1. License Condition for Leak Testing W

Sealed Plutonium Sources, did 4/93 l

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2. License Condition for Plutonium Alpha l

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3. Guidelines for Decontamination of l

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or 7

PAGES g

License Number g

g SNM-696 Amendment 43 a

g p

MATERIALS LICENSE Docket rr Reference Number g

g SUPPLEMENTARY SHEET 70-734 N

N N

SAFETY CONDITIONS N

y N

SAFETY CONDITIONS U

N N

N S-1.

Authorized use: For use in accordance with statements, representations, and conditions contained in N

N Part ll " License Specifications" dated July 24,1981, and supplements dated March 16 and N

N December 24,1982; February 4, November 14, and November 15,1983; April 10, April 12, June 28, N

N September 4, and September 7,1984; December 5,1985; May 23, September 25, and December 10, N

N 1986; December 21,1987; March 4, March 9 (2), March 22, April 26, August 22, September 8, and N

N November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; N N

March 5, March 18, June 24, and September 10,1992; January 20,1995; and in the "SVA N

N Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22, N

N 1990 (submitted by letter dated August 24,1990); June 15,1992; July 12 and August 23,1994; I

N Group 6 Laboratories unrestricted use request dated August 12,1994; March 1,1995; Group 7 N

N Laboratories unrestricted use request dated December 5,1995; Group 8B Laboratories unrestricted E

N E

use request dated August 23,1996; October 15,1996, and April 30, and Group 9 Laboratories N

N unrestricted use request dated July 17,1997.

N N

N N

S-2.

Records of all safety-related reports and analyses shall be retained as follows:

N N

N N

a.

Copies of criticality and radiation safety analyses shall be retained for at least 2 years or for 6 I

N months after a project is terminated, whichever is longer.

N N

N N

b.

Copies of all other safety-related records (e.g., plant alterations and additions, abnormal N

N occurrences associated with radioactivity releases, audits and inspections, instrument calibrations, N

N ALARA findings, training and retraining, personnel exposures, routine radiation and environmental I

N surveys) shall be retained for at least 2 years or longer if required by regulations.

N N

N N

S-3.

Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part II), if double U

N batching is not credible, the maximum safe batch size shall be no more than 75 percent of the U

N minimum critical mass independent of the degree of water moderation and reflection. However, when i

N N

the Th/U atomic ratio is 2 3.6 and the H/U s 20, the maximum safe batch size may be increased to 790 N

I g contained U-235 independent of whether double batching is credible.

N N

U N

S-4.

The Director QACD, upon recommendation of the appropriate manager within QACD, shall have N

N authority to require immediate termination of activities and/or corrective action in any situation which, in N

N their judgment, could lead to the annecessary exposure of personnel to ionizing radiation, release of N

N radioactive material, loss or damage of property, or non-compliance with the license or a regulation.

N N

N N

S-5.

The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall N

N meet at least annually to review (1) reports of audits and inspections performed since the last ALARA U

N review and (2) employee exposures and effluent release data to determine (a) if there are any upward N

N trends developing in personnel exposures for identifiable categones of workers, types of operations, or N

N effluent releases, (b) if exposures and releases might be lowered in accordance with the ALARA N

ce6 cept, and (c) if equipment for effluent and exposure control is being property used, maintained, and inspected.

y The CRSC evaluation, recommendations, and corrective actions shall be documented and the report g

shall be sent to the appropriate operations managers and the Vice President, Finance and g

Administration.

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PAGES License Number g

g SNM-696 Amendment 43 g

g 1

MATERIALS LICENSE oocket or nererence Nurnber

(

SUPPLEMENTARY SHEET 70-734 g

3 a

h SAFETY CONDITIONS

' 'd y

1 4

1 1

3 S-6.

Radiological Work Permits (RWPS) shall be issued for all unplanned or non-routine work with licensed d

1 material not covered by a WA The RWP shall be signed by Health Physics management or a senior 5

1 staff member before related work can commence. A senior staff member shall be a Health Physics d

1 Technician having a minimum of 5 years' exponence in radiation safety An evalustson of the safety 4

1 effectiveness of the permit shall be made upon completion of the work.

4 0

1 1

S-7.

Radiation safety training, appropnate to the employee's needs, shall be gu v all new employees.

4 U

I d

S-8.

Radiation safety training and indoctrination shall be conducted by the Health Physics Manager or by a a

1 similarly qualified individual. The Health Physics Manager may delegate training in that portion of the a

a course to an individual who is uniquely qualified to present it.

4 4

1 1

S-9.

Continuous air sampling shall be conducte d in any area where licensed material can become airbome.

U 4

1 1

S-10.

The location of air samplers shall be checked snnually and whenever any process or equipment 4

a changes are made to verify the representativeness of work area air sampling. In addition, the location d

1 of air samplers shall be checked at the commencement of operations in any area that has been d

1 shutdown for more 113..I 6 months to verify the representativeness of air sampling.

4 W

1 1

S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation i

1 systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.

4 4

1 1

S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached i

1

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

5 1

0 1

Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for 5 5

1 Plutonium Alpha Sources," dated April 1993.

1 4

1 S-13. Tne licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and 5 i

1 Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report whenever i

1 there is any new residential development within 1 mile around the site tnat constitutes a significant 1

change in parameters that may be affected by the release of radioactive materials into the environment, d

1 6

1

.S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and 5

1 renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition d

1 S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License i

U 1l Condition S-9 later became S-1.

1 4

i 1

S-15. At the end of plant life, the licensee shall decontaminate the site and facilities, authorized as a place of 5

1 use for special nuclear material, in accordance with the general decommissioning plan submitted by N

3 your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and I

1 grounds can be released for unrestricted use. The corporate commitment that funds will be made I

I available for decommissioning the facility, provided by letter dated September 10,1986, is hereby I

mcorporated as a condition of the license.

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or 7

PAGES g I

License Number h

SNM-696 Amendment 43 N

MATERI ALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 g

g h

SAFETY CONDITIONS E

N E

N N

S-i r,.

Release of equipment, facilities, or packages to the unrestricted area or to uncontrolled areas onsite E

N shall be in accordance with the attached " Guidelines for Decontamination of Facilities and Equipment E

N!

Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special I!

N Nuclear Material," dated April 1993.

E, E

N N

S-17. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and E

N released for general use.

E N

N N

S-18. Notwithstanding the statement in Section 4.2.1.4, Part il of the license, the trip levels will be readjusted E

N after each monthly test of the criticality alarm system if the alarm point fails to activate within E

N approximately 5 seconds, more than once out of four trials.

I!

E N

N S-19. Notwithstanding the statements in Section 4.2.1.4, Part ll of the license, no material handling shall be E

N allowed in any area in which the required criticality alann system is inoperative.

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N S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and E

i N

released for general use.

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N S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee I!

N on October 3,1988.

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I!

N N

S-22. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned and

E E l N

released for general use.

E N

N S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan E

N dated October 10,1997, supplemented by letter dated November 6,1997, or as further revised by the jl!

N licensee consistent with the provisions of 10 CFR 70.32(i).

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PAGES fg Lkense Number lE, SNM-696 Amendment 43 g

p MATERIALS LICENSE pocket or nererence Number Ei g

SUPPLEMENTARY SHEET 70-734 E

i g

E N

SAFEGUARDS CONDITIONS Ei 1

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6 E

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B SAFEGUARDS CONDITIONS lE i

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n N

N SECTiON 1.0 - FACILITY ORGANIZATION lE

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Currently there are no license conditions in this section. The necessary information has been incorporated into E p

cn approved plan.

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N g

SECTION 2.0 - FACILITY OPERATION E

E N

N SG-2.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E g

E B

SG 2.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E N

lE N

SG-2,3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license, jE s

lE d

SG-2.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SECTION 3.0 - MEASUREMENTS E

E 9

N SG-3.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

{E N

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W SG-3.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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W N

SG-3.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

9 R

W SECTION 4.0 - MEASUREMENT CONTROL E

E 9

E B

SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E E

B SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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B SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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H SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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N SG.4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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B; SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

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SNM-696 Amendment 43 In g

p M ATERI ALS LICENSE thlet or Reference Number g

I g

SUPPLEMENTARY SHEET 70-734

!g E

N SAFEGUARDS CONDITIONS g

g E

N E

N lE N

SECTION 5.0 - INVENTORY E

N N

SG-5.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

lE E

N N

SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E E

N N

SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E E

N N

SECTION 6.0 - RECORDS AND REPORTS E

E N

N SG-6.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E E

N E

N SECTION 7.0 - INTERNAL CONTROL E

N lE R

SG-7.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

j N

'E j N

SECTION 8.0 - MANAGEMENT E

E N

N SG-8.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

E N

N N

SECTION 9.0 -- PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA QUANTITIES OF STRATEG E

E N

SEECIAL NUCLEAR MATERIAL E

N B

SG-9.1 The licensee shall follow the measures described in the physical protection plan entitled, " Fixed E

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N Site and Transportation Plan for the Protection of Special Nuclear Material of Moderate and Low E

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N Strategic Significance," dated May 1989, submitted by letter dated May 8,1989; and as it may be E

N further revised in accordance with the provisions of 10 CFR 70.32(e).

N N

E N

SECTION -10.0 - TEMPORARY OR ONE TIME CONDITIONS N,

8 N

SG-10.1 Deleted by Amendment 31, dated July 1995.

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N jE B

SG-10.2 Deleted by Amendment 31, dated July 1995.

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Nl SG-10.3 Deleted by Amendment 31, dated July 1995.

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