ML20155D631

Amend 12 to License SNM-696,authorizing Release for Unrestricted Use of Approx 18 Acres & Adding Date of 880822 to License Condition 9

ML20155D631
Person / Time
Site:	07000734
Issue date:	10/03/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20155D617	List: ML20155D614 ML20155D631 ML20155D637 ML20155D642 ML20155D651
References
NUDOCS 8810110323
Download: ML20155D631 (5)

Text

r =is _

Jrk- _ .

q C C Fora 374 1 5

'#"" "O" ##S i man u.s. NUCLE AR CEGULATcW COWIS$10N lg!

la; MATERIALS LICENSE Pursuant to the Atomie Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 - 438). and Title 10, I

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

l

" , heretofore made by the licensee, a license is hereby issued authonzing the licenses to receise, acquire, possess, and tran fer byproduct, y source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I dehver or transfer such material to persons authorized to receise it in accordance with the regulations of the appheable Part(s). This I l license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is I subject to all appheable rules, regulat. ions and orders of the Nuclear Regulatory Commission now or hereafter in e conditions specified below. .

I

! ucensee t

t 1. 3. Ucense number 1 Amendment No. 12 I m , :- _ _ I P. O. Box 85608 92138\,.;\*is. 4,

'E'ipkr[tIhe )

San Diego, California December J J 9 y

5. Docket or " _Y/N i

, h(/ Reference No. , , 70434 y

3

, 6. Byproduct, source, and!cr A 7, Chemical and/or physical (3 Maximum arnount thatlicensee l l special nuclear material N-s form .s hay possess at any c.c.e tirne I

6) N N ' e' '6 der this license I

l ui :q q, l l

Uraniumenricfiedin L c1 /M C g I i A. A s' describe td h:et A 985 kilograms of l U-235 isotope,% , portion o thellicensee's U-235 Il i} r

- . applicatfo(rt' referred to, p r m e 3- ,

linptem9oG.thifItcense

,, 11 P' is -

f c.

[

y B. U-233 -

B; An .i . ," BGSkilogramsof I I, '3 I

i

--]-

" , . _y i ,, i 1,, M A , ,3 U-233 .t l . > l C. Plutonium v C. ' Encapsulated and/or ' C. 3 kilograms total Pu I Sealed Sources

{ (

D. Plutonium Bred but unseparated.

D. D. 1, kilogram total Pu  !

t E. Plutonium E. Plated calibration E. 5 grams total Pu source t(

C F. Plutonium F. Solutions, precipitates F. 5 grams total Pu  !

and solids c r

I

[

1 No rr. ore than 1,000 grams of U-235 will be in the fom of UF '

6 t

j ..

4 E'

q oo3 ll 8310110323 PDN ADOCK ss;o0734 07v C p pq-ll IEWw scor= = = ----- w --,

]TwYinFi~m w:h u v u w u n w w w w w w - = = = = www-m

ym.amm_--m5A*=****^^="""**M """ -

U.S. NUCLE Aa CECULATCGY COMMISSION ,, 2 c, 5 p ' P.O41

.C i om 374 A Lic'J o nwattr ,mm )I 12 h MATERIALS LICENSE [h g hg"[d,nt, flo .__

1 SUPPLEMENTARY SHEET i 70-734  !

f OCT j 9. Authorized use:

3 1938 s l

8 11 i

! For use in accordance with statements, representations, and conditions contained in Part !! "License Specifications" dated July 24, 1981, and supplements dated

!l 3)! !

March 16, and December 24, 1982; February 4. November 14, and November 15, 1983; April 10, April 12, June 28. September 4. and September 7,1984 December 5, 1985;

p p

I 1l 1 May 23 September 25 and December 10, 1986; December 21, 1987; March 4, I j March 9. (2), March 22, April 26, August 22, and September 8,1988 j 10. Authorized Place of Use: )

)

The licensee's San Diego, California site at 10955 John Jay Hopkins Drive and 1 11220 Flintkote Avenue as specified in the aforesaid application and supplements. ;I 1 > >

11. Records of all safety-related reports ano analyses shall be r,etained as follows: j

-lf 4 Ccpies cf criticality and. radiation safety analyses shalYbe retained for at least 2 years or/for 6 months after a project is teminated, whichever is

)

,1 1

ll longer.

)-) ,; ,

)

3 j

j i . 1

b. Copies of all other safety-telated records (e.g., plant alterations and

[h additions, abnonnal occurrences associated with radioactivity releases, audits and inspections. instrument calibrations. ALARA findings, training

(/ and retraining, personnel exposures, routine radiation and environmental b 1 surveys) shall be retained for attleast 2 years or longer if required by ,8 i

j regulations.

.l

)

}it 12. Notwithstanding)the statements in Section 5.4.0 in the License SpecificationVolume b l

shall be no more than 75 percent of the minimum critical mass independent of the ,b degree of water moderation and reflection. However, when the Th/V atomic ratto 4 >

1 is 3.6 and the H/V 20, the maximum safe batch size may be increased to 790 ) }

}1 contained U-235 independent of whether double batching is credible. [

1 l

k 4' 13. The Director QACD, u)on recommendation of the appropriate manager within I i

i 1

4, QACD, shall have aut1ority to require imediate tennination of activities k l

and/or corrective action in any situation which, in their judgment, could 8 '

$j lead to the unnecessary exposure of personnel to ionizing radiation. l t release of radioactive material, loss or damage of property, or ,

i i non-compliance with the license or a regulation. > '

4 .

t 4

14. The Criticality and Radiation Safety Comittee (CRSC), functioning as an ALARA i j Comittee, shall meet at least ant.ually to review (1) reports of audits and [

4 inspections perfortned si. ice the last ALARA review and (2) employee exposures and g i effluent release data to detennine (a) if there are any umard trends developing in i i personnel exposures for identitiable categories of workers, types of operations, or 6 j

4. effluent releases, (b) if exposures and releases mignt be lowered in accordance with i i L the ALARA concept, ano (c) if equipment for effluent and exposure control is being 8 l

j properly used, maintained, and inspected.

[  !

4 . '

I )

4. >

h Td.TM&fdALT Td&1TiTdd.TdKT;T;T&TXTXLT TMMZL1fATXA%i.1T.T.TX.nTALTA

a yms m m m mmm mmm m m arm'R ' * ..'w* ' ' ' ' ' ' ' * ' ' ' ' ' ' ' ' ' ' '

' ^ ^ m ^ ^ ^ ^ ^ ^ ^F NAC Form '374Q U.S. NUCLE AR QRCULATORY COMMISSION [ nog 3 o, 5 f

l ts s4  ! Licen,e number 3ces.llN I

q SNM-696, Amendment flo.12 il y

q MATERIALS LICENSE SUPPLEM ENTARY SHEt!I ooctet or aeterence number /

( 7W 734 h

\

j OCT 3 18E8 i i 14 l The CRSC evaluation, recomendations, and corrective actions shall be y documented and the report shall be sent to the appropriate operations I managers and the Vice President, Finance and Administratjon. i a l f 15. Radiological Work Pemits (RWPS) shall be issued for all unplanned or l

t j g non-routine work with licensed material not covered by a WA. The RWP shall be signed by Health Physics management or a senior staff member before related I

l g work can comence. A senior staff member shall be a Health Physics Technician I havf' a minimum of 5 years' experience in radiation safety., An eva wation of k the Fety effectiveness of the pennit shall.be made upon completion of the work.

I j ,. ..adiation safety training,_ app.ropriate to the em lby'e s needs, shall be given to all new employees..

j ) Q;' ,p 17.RadiationsafetytrainikandindoctrinationshallbecondultedbytheIbith 4 Physics Manager or by'a similarly qualified indMdual. Jhe Health Physics .

Manager may delegatutrainingJr. that portion of the course't(an individual who j

l j

JI is uniquely qualifief to presentQt. ff; '

l

\

r

.\ \ m / () l l

18. Continuous can become airborne, air

.(/

sampl ling shall be'conductard

/,

j s area where licensed material J

s ,j.  ; i a 19. The location of air samplers s shall'be checked annually and whenever any process I or equipment changes are made to verify the ,representativeness; of work area air  %

sampling. In addition, the location!of air samplers shall be checked at the ['

coernencement of operations in any area that has' been shutdown for more than

? 6 months to verify the represandtiveness of air sampling.  !

A .

j i

20. The laboratories in which plutonium in a dispersib1'e form.may be used shall have I y exhaust ventilation systems separate from other building exhausts and shall provide I g dual HEPA filtering of the effluent air. ,

l 21. Notwithstanding the statements made in Section 4.1.5 of the ravised application dated November 1983, the licensee shall conduct leak testing of sealed plutonium '

sources and alpha sources in accordance with Annex A. "License Condition for Leak

! Testing Sealed Hutonium St urces," dated November 1979, and Annex B "License l j Condition for Plutonium Alpha Sources " respectively.

i {

i

} 22. The licensee shall prepare and submit to the Chief, Fuel Cycle Safety Branch, j

! Division of Industrial and Medical Nuclear Safety NMSS, U. S. Nuclear Regulatory l l Commission, Washington, DC 20555, a report whenever there is any new residential l I

development within one mile around the site that constitutes a significant change  ;

in parameters that may be affected by the release of radioactive materials into

! the environment. j i

4 4 , n> !

4 i>

4 q ik J

4 >

q. .>

bairw wvw w ., w w w w w w w w w w w w w w w w w w w w w w w w w w " w w w w w w wCwv+ +~w wvw wvw wI

,*-.... .-- _ U.S.--

- - n - - ------- n NUCLE AR REGULATORY COMMISSION

-.--s g WRc'Fo m 3H A pm 4 op 5 paoes A Licen,e number )>

j s{

S 6, en ent No. 12 l M ATERIALS LICENSE g g, ,n b,,

SUPPLEMENTARY SHEET 70-734 h 8

00T 3 1988 j  !

l l>

23. The licensee shall implement, maintain and execute the response measures of his y I

i Radiological Contingency Plan submitted te the Comission on May 25, 1984, and f supplemented on August 22, 1984 The licensee shall also maintain implementing procedures for his Radiological Contingency Plan as necessary to implement the !j Plan. The Plan shall be fully implemented by February 12, 1985. This ),  ;

I Radiological Contingency Plan and associated implementing procedures supersede p l

, the emergency planning requirements of 10 CFR 70.22(1) as they refer to onsite il planning and notification procedures. The licenree shall make no change in his >

Radiological Contingency Plan that would decrease the response effe tiveness of the Plan without prior Commission approval as evidenced by a license amendment. l ly The licensee may make changes to his Radiological Contingency Plan without prior l Comission approval if the changes do not decrease' the response effectiveness of I the Plan. The . licensee shall maintain records of chang'ess that are nade to the I Plan without prior approval for a period of 2 years from the date of the change 8 and shall furnish the Chief Fuel Cycle Safety Branch, Division of Industrial and Medical Nuclear Safety, NMSS, U. S. Nuclear Regulatory'Connission.

j lp Washington, DC 20555;?and the appropriate NRC Regional Office /specified in Appendix 0 of 10 CFR/ P art 20, a report containing a. description of each change l1p within 6 months after the change,is made. ,

'c. O @

l

24. At the end of plant life, the licensee shsll decontaminate the site and facilities, authorized as a place of use for special nuclear material, in accordance with the j

I p

general decomissioning plan submitted by your letter dated July' 25, 1986, and its p supplement dated October 15, 1986.. so that;these facilities and grounds can be l released for unrestricted use. The corporate comitment that funds will be made available for decomissioning the facility, provided by letter dated September 10 1986, is hereby incorporated as a condition of the license..

f@j l )

2S. Notwithstanding the statements made in Section 4.3.5 of the revised application l1>

% dated November 1983, the release of the facilities and equipment for unrestricted *h, l/ use from the plant site or to unrestricted areas onsite shall be in accordance I i, with the enclosed Annex C "Guidelines for Decontamination of Facilities and I l

l l

Equipment. Prior to Release for Unrestricted Use or Termination of Licenses for By-product, Source or Special Nuclear Material", dated July 1982.

( >

F

26. The licensee is hereby exempted from the provisions of 10 CFR 70.24 during the f 1

mooification of the SV-A criticality alarm system insofar as this section applies A to materials held in the SV-A building under this license subject to the following

I The criticality alarm system shall be in service in all areas where the Yh

a. )

(y{ quantity of special nuclear material (SNM) does not meet the exemption criteria in Section 4.2.1.4 of the specification volume with the exception of the SNM

)>

, storage vaults in the SV-A cuilding, j (g b. There shall be no movement of any special nuclear material (SNM) into, out of, or within the SV-A building SNM storage vaults while the criticality alarm >

system is not in service. >

l l

)h

)

Lj )

pm.........-===========--=============================m3 l U.S. NUCLE AR REGULATORY COMMISSION l NRC Io m 314 A paar 5 or 5 PAGES i g am ucen,e number J

b -6 6, en ent flo.12 l MATERIALS LICENSE g p ,,, e.

SUPPL.EMENTARY SHEET 70-734 l

q OCT 3 1938 fl lt 1 1

4 lI l 4 27. Notwithstanding the statement in Section 4.2.1.4, Part II of the license, the il  !

I trip levels will be readjusted after each monthly test of the criticality alarm ,

I 8

system if the alam point fails to activate within approximately 5 seconds, more than once out of four trials.

fl l

!p

'M

28. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no lI material handling shall be allowed in any area in which the required criticality il alarm system is inoperative, j

29. The licensee may reduce the radiation safety; nuclear criticality safety, and l environmental surveillance requirements within thefHTGR fuel fabrication and I storage areas in the SV-A Building, TRIGA fuel manufacturing building, and in I the GA Hot Cell possessingsfissile and/or other radioactive material, during a I period of reduced activities as specified in the application dated April 23, 1985, I subject to the following modifications:

L 4 j

a. Naciesdnd contamination control; mea ures/specified in the license shall The survey frekused whenever work is performed'on or with) I l

. / J/ i, i handles radioactive material ') l q ji j

y , ,

b. Any work perforsned on equipment which handled radioactive materials shall be authorized by}and performed undet a radiation work pemit.d ~

p 1 i -

- r3 <

r9ventilation ducts'and: enclosures which are not completely s l>

c. All openings of sealed shall be maintained with a minimum airflow of 25 LFM; The licensee i@t shall detennine, on at least a semiannual' basis, that this' minimum airflow is maintained. '

j 4 , ,.

' Ip p ~

i a d. If air sample results. indicate an increase in airborne contamination to ll>>

't 10 percent or more of the appropriate MPC, survey frequencies shall be

'4, increased to the levels specified for Type II labclatories.

j j,>

e. The Manager, Nuclear Safety, or his designee shall perform a criticality l>

inspection, at least annually, of all areas specified. '>

l 30. The licensee is hereby authorized to possess 16 TRIGA fuel elements at the Universi i of Missouri for purpose of packaging the elements for delivery to a carrier as i specified in the amendment application dated September 8,1988. '

I ,g l>

[ -

FOR THE NUCLEAR REGULATORY COMMISSION hf f! W s By: Leland C. Rouse lDate: Division of Industrial and I

Medical Nuclear Safety l >>

l Washington, DC 20555 j,

'k t

l .>

u ___

m.,y7, m, ,y -

gy

. _- .