ML20055F626

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Forwards Revised Pages to 900326 License Amend Request,Per .W/One Oversize Drawing
ML20055F626
Person / Time
Site: 07000371
Issue date: 07/11/1990
From: Gregg R
UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.)
To: Haughney C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NIS-90-7-9, NUDOCS 9007180210
Download: ML20055F626 (13)
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e, UN. M N.u aval' Products om:u,-,,,.8, 67 Sandy Oeser1 Fload L 203/848 1511 lelocopy 203/048 0022 TWX 710/4321243 -

IN REPLY.PLEASE REFER TO:. I NIS<90-7-9 i July 11, 1990 ~ Mr. Charlec Haughney . Fuel Cycle Safety Branch Mail'Stop WF1 6h3 ~1

Division of Fuel ~ Cycle & Medical, and i

Commercial Use' Safety U.S. Nuclear. Regulatory Commission Washington, DC 20555 'Ref.: (1)- Letter R. J. Gregg to C. Haughney, March 15, 1990 (2)- Amendment: request from R J. Gregg to C. Haughney, March 26, 1990 ((3) Letter ^G. H. Bidinger to R..Gregg, May 9, 1990 (4) Letter.R.-J.-Gregg to G. Bidinger, June 6, 1990

Dear' Sir:

In response to the letter from your staff,.(ref..(3)), we are- .i.ubmitting revised'~pages to'our requested license amendment (ref..(2)). The: enclosed provides the evaluation authorized by. -10CFR.70.22 removing the requirement for maintaining a RadiologicaliContingency! Plan as. stated:in Condition #23 to SNM-368.- The license revisions were made to better address dose potentially received at all off-site locations and other

concerns expressed in'ref. (3).
In addition to the. enclosed evaluation, our present shutdown

. schedule calls-for all' product to be out of the B-South area'by learlyd1991.. That action will add'an even greater margin of safety.toLassure that no off-site individual will--receive , greater than-.1. rem exposure as a result of an accident. c I VeryjTruly:Yours, b' (( f R. ; J. Greg Irector C Technical Services-RJG: mag'. 5 Enclosur'e ~. i: b78mg/6, 090071602io 900711 {DR ADOCK 07000371 lb A u...., Cornparty Loswouc pdc sw

p. }C x -License SNM-368I Part III Page 6-1 Date 7/09/90: ((DocketNo.70-371 Chapter 6 Rev.1-Chapter ACCIDENT hMALY8E8 6.1-Need for a Radioloaical Contincency Plan ' Potential 1 accidents were discussed and evaluated.in Section'4.3.2 of-- -Reference 1. A Radiological Contingency Plan is not required per 10 CFR 70.22.. (i) (1) (i). The analysis for this demonstration is given in Sections 6.1.1 and 6.1.2. 6.1.1 Accidental' Criticality Evaluation An accidental criticality is-assumed to have occurred in B-Blog'at a height no greater than'six-feet as determined by work and Ltorage locations. -This excursion occurs in a ygnted vessel of unsafe fissions over an a-hour geometry and produces.a total of 1 x 10 period per Ref. 3. 6.1;1.1 Nearest' Residence A.. Direct Radiation Dose The Naval-Products facility lies in a valley mostly hidden from view? from the front gate and'ths nearest residence. On-the western side Of_the plant',t a hill of land rises up to a' vertical height ofL31-feet t L above the shop floor.of B Building (the closest fuel-handling' ' building to the residence).. This' hill then gently slopes downward towards:the.gata=and the nearest residence.' The distance from-Bi Building to the: nearest corner of the roeidence is.1024 ft.-(312 m) when transversed along the ground. The analysis assumes m'1000-.ft (305 m) distance. This hill, in;effect, acts as an carthen shield, approximately 300 . feet' thick, which separatesiall fuel handling and storage from the residence' (see Figure 6.1).. A shield of this thickness will shield all~ direct radiation resulting from a potential criticality. Thus the dose from prompt-gamma and prompt neutron radiation at.the neareat1 residence is equal to zero mR. lB. Airborne Radioactiv!ty Ref.-1 41sts the airborne radioactivity intake calculated for a " residence at a distance of 425 meters from the plant. Assuming a class F stability-and a 1 m/sec. wind speed, Figure.1 from Ref. 2 can i be..used;to calculate the increase.in X/Q (concentration / release rate)- .for a decrease in distance to 305 meters from~the plant. Figure 1

reveals an approxistte increase of 1.6 times the value obtained'for the 425 meters.

The analysis uses the conservative value of 2.0 times ~that presented in Ref. 1. This is tabulated in Table 6.1.

O vaa. 6-1

1 JfA N. L ) ,7 s s -License SNN-368 Part II Page 6-2 Datet7/09/99 ' l {~ j Docket No. 70-371 Chapter 6 Rev.1 C. gIgund-shine / Cloud-shing 1 -COf. 2, page 12 states, H... ground-shine and cloud-shine will be j oonsiderably smaller than the inhalation dose except for a few L radionuclides (Eenon,. Krypton, Na-24, Ma-56, Tc-99a, and Ru-105). l

Therefore, it can be assumed that any dose from ground-shine or

~' .cinud-shine will not exceed that for inhalation. D. Intake of 2 milliarans of soluble Uranium L Rof. - 2, page 11 states, "...a person on the plume centerline is aosumed to inhale at most about one one-millionth of-the material t -_roleased. This is at a distance of 100 meters, i l. Therefore, for an individual to receive an intake of 2 mg of soluble uranium, 2 kg.of soluble uranium must be released into the Lcteosphere. _UNC Naval Products has very few areas where soluble uranium is present and the total accumulation is well under 2 kg. UNC does not' process any UF. Thus, the intake of 2 mg of soluble 6 uranium is not possible at the nearest residence. 6.1.1.2 site Boundaries i Figure 6.2 and Figure 4.3 show the UNC site.and the area topography. O Ao can' be seen in these figures, the facility is shielded by land in -all directions with the exception of WsW. 6.1.1.2.1 knalysis for site Boundaries other than usW u The nearest site boundary from a process or fuel storage area is 430 ft. (131 meters) north of Annex III. Although a criticality accident oimilaktto that proposed in Ref. 3 is not possible in this area, this + 41 stance will be used to demonstrate that a release would not exceed 1 rer exposure to an individual at any site boundary. The Trading Cove is over a hundred feet below a hill which lies b3 tween the' cove and the plant. This would shield all direct rcolation emitted from the criticality. Therefore, only inhalation dose coupled with possible sky-shine would be present. Assuming a' Class F stability and a 1 m/sec. Wind speed, Figure i from Ref. 2 can b3 used to calculate the increase in X/Q (concentration / release rate) for a decrease in distance to 131 meters from the plant. Figure 1 I 1*cveals an' approximate increase of 4 5 times the value obtained for the 425= noters. Table 6.1 presents the dose estimates for this ^

distance, sky-shine is assumed to be equal to this inhalation dose co discussed in section 6.1.1.1.C.

Since the distance to the nearest site boundary is greater than the i 100' asters discussed in section 6.1.1.1.D, that analysis may be used for all site boundaries. Therefore, an intake of 2 ag. of soluble uranium.is not-possible at any off site location. 3 Page 6-2 L,

.. - -.-.-.- -.__.- -..-.~_- - t l l I -License SNM-368 Part II Page 6-3 Date87/09/90 ) Dooket No. 70-371 Chapter.6 Rev.1 6.1.1.2.2 namivais for usw site.. Boundary The distance to the nearest site boundary to the W4W of the plant is greater than 1975 ft. (328 m) at all points. Therefore, this i distance will be used for the analysis. The WSW is the only direction from the plant which is closer than the 425 meter distance analysed in Ref. 1 kM which has a direct line of 4 cight to the site boundary. It is assumed ti.ct the critioality ecours in the Chen lab. This is conservative because an accident of this type would be more credible ir. the Rad Waste basement which would add both distance and additional shielding to the calculations. f If a criticality was to occur in this location, several different chielding materials would attenuate both the direct neutron and gamma i radiation. The. radiation would have to pass through at least two ' concrete walls since no fuel is handled near the west wall (see i Figures 6.4, 6.5, & 6.6). Therefore, the. radiation must pass through o minimum of 6H of concrete, 5.6H of shestrock (gypsum) walls, at least 858 of insulation, and 0.2H gtggl (the g(ggi inglgdgg the getgl calls of a Building which lies in the path). Actually, additional l Chielding material is also present but will not be considered. Ref. 4 gives the total dose reduction for 7.9H of concrete. Ref. 5 (page 317) shows that the gypsua can be compared to the concrete in terms of shielding by comparing the densities of the two materialsg Table 6.2 reveals that the gypsum has a minimum density of 50 f/fg and the concrete cinder block has a maximum density of 115 #/ft (115/50 m 2.3). Therefore, the 5.6H of gypsum can be considered i Cquel to or greater than the additional 1.9H of concrete used in Ref. i 4 (5.6/1.9 s.2.9). The shielded dose / unshielded dose given in Ref. 4 l is 0.29 +/ 0.03. The analysis for inhalation and cloud-shine discussed in Section 6.1.1.1 also applies. The data and calculations cre presented in Table 6.1. 6.1.2 Radiation Release in a Fire Although a fire is a more likely accident to occur at UNC Naval Products, there would be no measurable radiological effect to the Cavironment. As stated in Section 6.1.1.1.D, UNC does not process L UF. Reference 2 (page 44) states that H,,,((ggg hgyg hgd ligtig 6 consequences wit regard to either personnel exposure or ground contamination." Deveral safeguards are in place at UNC to help prevent-or minimise the effects of a fire. These are discussed in Ref. 1. Therefore, it is concluded that, due to the nature of the insoluble fuel processed at UNC, a fire would not result in any off-site exposures exceeding i ren. Page 6-3 O-r---r ,-,-,--,.--n_,_,_._

Liosase SNN-368 Part II Page 6-4 Date 7/09/90 (]yDecketNo.70-371 Chapter 6 Rev.1 6.1.3 Conservatism included in the analvais several conservative assumptions were used in this analysis. These include the following: 1) Filtern and other installed or4troit sore not oredited with any removal of released gases. 2) The criticality accident is asse ed to ooour in the Chen Lab which is closest-to the residence and the Wsw direction. 3) The worst case scenario of a Pasquill Clar,s F wind stability and a 1 m/seo. wind speed were assumed. 4) No response is assumed by the individual for 8 hours where in actuality, it could be assumed that the individual would be made aware of the accident and appropriate action would be taken. 5) No' wind shifts are assumed. 6) The source torn assumes a pulsating criticality with a total of 48 bursts over an 8 hour period. This is highly conservative. m 7) The wind is assumed to have a westerly flow which is not as EU prevalent as an easterly flow. (see Ref. 1 Table A.5.) 6.1.1.7 conclusion The maximum dose to a member of the public offsite due to a release of radioactive materials will not exceed 1 rea effective dose equivalent or an intake of a milligrams of soluble uranium. References (1)NUREG-1112, Environmental Assessment for Renewal of SNN-368, Jan. 1985. (2)NUREG-1140, A Regulatory Analysis on Emergency Preparedness for Fuel Cycle and other Radioactive Material-Licenses. (3) Regulatory Guide 3.34, Assumptions used for Evaluating the Potential Radiological Consequences of Accidental Nuclear . Criticality in a Uranium Fuel Fabrication Plant. (4)UCRL-53369, Nuclear Criticality Safety Experiments, Calculations and Analyses-1958 to 1982.," Neutron and Gamma Attenuation Characteristics of Various shields During Nuclear criticality Accidents" By R.E. swaja, R.T. Greene (ORNL). (5) Comber, Herman. Introduction To Health Physics, Pergamon Press 1t83. Page 6-4

l' si License SNN-36s Part II Page 6-5 Date 7/09/90 . ( } Docket No. 70-371 Chapter 6 Rev.1 Table 6.1 Maximum 50-year dose commitment an individual from a postulated criticality mooident pose (mR) Ennosure Tvoe Total Body Thyroid RRRA Lungs 435 meters Airborne 37 72 36 35 (Ref. 1 Table 4.10) 305_Rt.t3In - Nearest Residence Airborne 74 144 72 70 Prompt Gamma 0 0 0 0 Prompt Neutron 0 0 0 0 Oround/ Cloud-shine (max) _f.4 1.41 ._H .l.9. Total (man) les Ass 144 140 131 meters - Nearest site Boundary Airborne 166.5 324 162 157.5 Prompt Gamma 0 0 0 0 Prompt Neutron 0 0 0 0 eround/ Cloud-shine (max) 166.5 RA 151 All.d Total (max) 333 648 324 315 32s meters-~~WSW site Boundary Airborne

  • 74 144 72 70 Prompt samma 204.s 204.s 204.s 204.s Prompt Neutron 37s.2 37s.2 378.2 37s.2 Ground / cloud-shine (max) 74 144

_12__ 70 Total (max) 731 871 727 723

  • Values for 305 meters were used.

Calculations for 32s meters (Der Ref. 3) D w2.1E-20 N d-2,-3.44 (d a.32s km) g D s75-20 N 4-2,-5.2d 1 (N n 1 x 10 ' fissions) a D z600 mR D =1182 mR Total Direct Dose a 1822mR 9 n shielding Pactor x0.29 + 0.3 =0.32 (per Ref. 4.) Total shielded Dose z 5s3 mR O Page 6-5

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