ML20236K872

Rev 18 to Application for Amend to License SNM-1097,revising Part I of License Application Currently Approved by Condition 9 of License.Fee Paid

ML20236K872
Person / Time
Site:	07001113
Issue date:	10/23/1987
From:	Winslow T GENERAL ELECTRIC CO.
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20236K874	List: ML20236K872 ML20236K879
References
28724, NUDOCS 8711100003
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{{#Wiki_filter:.- i RETURN.T6 396-55 [.///J l GENERAL () ELECTRIC /6 NUCLEAR FUEL & COMPONENTS MANUFACTURING GENERAL ELECTRIC COMPANY

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• WILMINGTON. NORTH CAROLINA 28402 AD-October 23, 1987 r

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~ Office of Nuclear Materials Safety & Safeguards g U. S. Nuclear Regulatory Commission. 4 (9 [ Washington, D. C. 20555 Attention: Uranium Fuel Section

Dear Sir:

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Reference:

NRC License SNM-1097, Docket #70-1113

Subject:

LICENSE AMENDMENT REQUEST (REVISION #18) GE Nuclear Fuel & Components Manufacturing herebyLrequests I approval of the attached revised Part I of the license. application for NRC License SNM-1097 which is currently approved by. Condition 9 of that license. to this letter describes the revisions made and Attachment 2 is the revised Part I. 6 Pursuant to 10 CFR 170.31, a GE check for $150 for processing ~ this amendment request will be forwarded under separate cover. If you have any questions regarding this matter, please contact me. Very truly yours, GE NUCLEAR ENERGY Th/ LEO $6h0 T. Preston Winslow,. Manager Licensing & Nuclear Materials Management M/C J88-l TPW:bsd 4 t 5-bV-- N ~ b --------- Attachments O N N bo2NI92 E' - - - C S .usNRc Am *t";* $ % * ?- ~ 'A. ~-~~~ Fso Cat: c:ry./D-- de----d ~ I3 019p 2 Type of Fa &nw e B-NAtss .O I Date Chock Re 'd.Li 1

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i 1 GENERAL h ELECTRIC l 1 l l Director - ONMSS October 23, 1987 j l ) ATTACHMENT 1 4 DESCRIPTION OF REVISIONS 1 Section Description General Throughout Part I, the Wilmington facility is now referred to as "GE-Wilmington". The Table of Contents and Revisions By Pages have been revised to reflect revision to Part I. 1.2 A site plan has been added. 1.4.4, Editorial changes i 1.7.1.3, 1.7.4.4, 1.7.6 q 1.8.2 Incorporated new NRC guidelines. 1.8.3.1 Editorial change 1.8.4.2. Revised to reflect current Physical Security Plan. 1.8.4.3 1.8.10 Current License Condition 12. 1.8.11 License Amendment Request - At GE-Wilmington, wastes originating in restrooms across the plant site are routed through the sanitary waste system to a treatment facility consisting of collector sewers, a lift station and an aeration plant. L1 quid effluent I from the treatment facility flows to the river. Monthly sampling of liquid influent and effluent have not indicated any detectible uranium concentrations. Digest sludge from the treatment facility 's transferred to a two acre, clay-lined, dh d " land application" area. (See Figure 1.1 in Part I.) This area is located adjacent to the final process lagoons and had been used as a sanitary treatment stabilization lagoon prior to the installation of the

p --ra J GENERAL $ ELECTRIC Director - ONMSS October 23, 1987 g - Page 2 i Section Description sanitary treatment facility. Siteoaccess to the sanitary sludge disposal lagoon is restricted by. property line fencing and separate lagoon enclosure fencing. s For treated sanitary sludges, land application'is a standard practice. '). I Gro'und water around the application area, adjacent lagoons and calcium fluoride storage areas is. j included in the quarterly monitoiing< program for i chemical. uranium, gross alpha and gross beta. (See Table 5.1.) l l Based on recent NRC information regarding concentrated uranium' levels in sewage treatment processes l, a program of monthly sampling.was initiated for the digest sludge discharged to the i lagoon. The uranium in influents to.the sanitary l sewage' treatment process is on the order of less than detectible to 0.02 ppm. However, as solid. material in the treatment process is concentrated on the order of 5,000 to 6,000 due to the constant vaporization /. effluent withdrawal / recycle of material during. processing, low levels.of uranium in the dried l treated sanitary sludge can result. (The uranium level in this sludge is well below the uranium levels j in the sludge in the adjacent final process lagoons.) I GE-Wilmington requests authorization to accumulate treated sanitary sludge containing trace-amounts of uranium in the land application area. 2.2.1.1 Editorial change 1 i u

~ l -1 1 i 1 GENER AL $ ELECTRIC Director - ONMSS ) October 23, 1987 - Page 3 i Section Description i 2.2.1.3 , Changed " radiation" to " nuclear" in applicable 3 portions:of this section to reflect organizational terminology at GE-Wilmington. 2.3.2 Reworded to more clearly state the objectives of the ~ operational Radiation Safety. Committee. 1 2.5.2 See 2.2.1.3 above 2.5.3.2, Revised to detail current.joo position titles and-2.5.3.3, qualifications. 2.5.3.4 2.7.1 Deleted reference to Job Hazard Analyses 2.7.2 See 2.2.1.3 above 2.8.1 Editorial change i 4 i 3.2.1 Deleted reference to random badge monitoring. i f Table 3.2 Revised instruments' typical ranges. Corrected typo-graphical error. ) 1 Section ) 3.2.4.1, Editorial changes 3.2.4.4 3.2.4.5.1 Changed "a combination GMR canister" to " applicable canister". Added reference to full face piece respirators. 3.2.4.6 Added action limit for lab controlled areas to table. 3.2.4.9 Editorial change

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GENERAL h ELECTRIC l 1 r c Director - ONMSS October 23, 1987; j -'Page 4 i h Section . description 5.1.1.2 Added'"weNkly" to c cruspond with commitment ip Table ~ 5.1. 5.1.5 ' Revised >to reflect organizational changes l Table 'O, h 5.1 For airborne discharges, adde,d reference to Figure l 5.2. For nitrate waste stream, revised detection limits y for canal and clarifier sludges. j / i-Section r 5.2.1.2 Corrected reference tc' air - sampling station locations. a 6.1 Editoria2 change Chapter 8 Revised to reflect current Radiological Contingency & Emergency Plan q 'a i I J /

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't +..;. s. i1 .j 4 o 1 .e ,..k' ~ i1 lf c . TABLE OF-' CONTENTS: .c ~Section: Title . Page - j M, .PART1 LI v ?LICENSELCONDITIONS: H CHAPTER1LF STANDARD'C NDITIONS &=SPECIAL'iAUTHORIZATIONSi 1 l'.1 Corporate &: Financial + Information ..I-1.1 =6 l 1.2 Location &'GeneralLDescription of Wilmington' I-1..1 ;

Plant-1.3 License Number

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.y _.. l 1.4. Possession Limits I--1. 3 l I 1.5' Material Use Locations. I-1.4 O 1.e-oerinitione 1-1. 5 - "l 1 Authorized Activities . I-1. 6 1.'7 18 Exemptions.& Special' Authorizations lI-1-91 C'HAPTER 2 GENERAL ORGANIZATION & ADMINISTRATIVE REQUIREMENTS 2.1 Policy .I-2.1-2.2 Organizational Responsibility &: Authority-- .I-2.1 I-2.6

2. 3-Safety' Review Committee' 2.4 Approval Authority for.Personne,1 Selections I-2.9 j

2.5 Personnel Education &) Experience ~ Requirements-I-2.9 1 a . jr5 n Q ~ LICENSE SNM-1097 DATE 10/23/87 Page' ) DOCKET 1113 ' REVISION

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1 .i ( TABLE OF' CONTENTS Section Title Page_ j ~ i 2.6 Training I-2.14 l 2.7 Operating Procedures - Administrative Controls I-2,14' j I-2.17 j 2.8 Audits & Inspections 2.9 Investigation & Reporting of Unusual I-2.21 occurrences i 2.10 Records I-2.21 l J 1 CHAPTER 3 RADIATION. PROTECTION 3.1 Administrative Requirements I-3.1 J 3.2 Technical Requirements' I-3.4 1 ,m CHAPTER 4 h NUCLEAR CRITICALITY SAFETY 4.1 Administrative Requirements I-4.1 4.2 Technical Requirements I-4.4 j CHAPTER S ENVIRONMENTAL PROTECTION i 5.1 Effluent Control Systems I-5.1 l 5.2 Environmental Monitoring Program I-5.14-i 'i I l \\ s"< LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 l a

Ky, ip .1 ,3( , '[ A ', ifyp 'H s t gs s ,4 9 I S / l' '/ t ) '- i.., j t' v p fj .'TABLEcOF? CONTENTS' ,4 k "S'ection' Title-Page d s 5 CHAPTERl'6 lSPECIAL PROCESS. COMMITMENTS i., .J 6.1 'UF Cylinder Movement-' '. I -- 6.1 : ] o 6.2 .UO,_-. Powder Moisture Analysis?&, Moi'sture.Limith. I-6 [1' p r u lif 6.3 Transfer.of.'UPS'& Fluoride Liquid' Wastes,from;

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a 6.4 Prevention of'.UF,-l Contact'with Hydrocarbons:

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CHAPTER <7-DECOMMISSIONING. PLAN 'I-7)1 l t 1 CHAPTER'8 EMERGENCY: PLAN. I-811 i PART.II SAFETY : DEMONSTRATION, a CHAPTER 9: 1 ; OVERVIEW OF OPERATION 9.1 Corporate Information 'II-9 1' 9.2 Corporate Financial Qualification II-9 1'- ~ 9.3 Summary of Operating Objective & Process' t II-9.1 ; y 9 .c c '} f) LICENSE SNM-1097 D AT E.- 10/23/87 . P6ge - .00CKET 70-1113 REVISION 'IB - ~~ ~f3-.

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.t zu I!h*- \\ r t r i 4 .~ STABLE OF CONTENTS Page-u: . Section~- -Title- .) s II-9'2-y 9 '. '4 ' Site Description II-9.'2a .9.5. ' Location of-Buildings.On' Site. . s LII-9 ? 2:. s 9.6 ' Location of the Plant Site w. 9.7 -License History

II-9~2' 9.8 Significant. Changes'.in CorporateLStructure

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'II-9."8L ] Changes in Procedures, Facilities'&.LEquipment LII-9i8'~ 'I 9.9 i do

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CHAPTER 10-j FACILITIES DESCRIPTION Li 10.1 Plant Layout II-10.1 .I 10.2 Utilities LII-10.6^ =1 J O 10.3 Heating,. Ventilation & Air.; Conditioning (HVAC) II-10.13? 10.4 Waste Handling II-10.26 10.5 Chemical Systems . I I 1 0.~~ 3 2 10.6 Fire Protection II-10'34 ] 1 ' (j CHAPTER'll' ORGANIZATION & PERSONNEL 11.1 Section Functions ' II-11.1, 11.2 Organization Charts II-11.3 11.3 Organizational Procedures II-11.'3 .1 i i 'h' LICENSE' .SNM-1097 DATE-10/23/87J. Page-q - 0OCKET '70-1113 REVISION 18 l __m__ m______. _. _ _ _. _ _ ~. _ _ _ _ _ _ _ _ _ __ ___ m_ u

] i i f TABLE OF' CONTENTS-m 'Section Title Page 11.4-Key Functions II-11.9 11.5 Education & Experience of Key Personnel II-11.12 11.6 Training II-11.53-CHAPTER 12 RADIATION PROTECTION PROCEDURES & EQUIPMENT i 12.1 Procedures for Radidtion Surveys II-12.1 j 12.2 Posting & Labeling II-12.2 12.3 Personnel Monitoring II-12.3 12.4 Operational Surveys II-12.6 .) 12.5 Records II-12.7 ,,A ~ Reports II-12.8 I 12.6 12.7 Instrumentation II-12.9 12.8 Protective Clothing 'II-12.15 J 12.9 Administrative Action Guidelines II-12.15 12.10 Respiratory Protection II-12.17 i CHAPTER 13 j OCCUPATIONAL RADIATION EXPOSURE 13.1 Occupational Exposure Analysis II-13.1 i 13.2 ALARA at GE-Wilmington II-13.54 I I .I l ~ i /) \\. LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 5'- l 1 f

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j; 1 -V TABLE OF-CONTENTS i 1 Section-Title Page -.j -W 13.3' Bioassay. Program-II-13.67-1 13.4 Air Sampling & Assigned' Airborne' Exposure 'II-13. 7 3 - 13.5-Surface Contamination Control Program" . II-13 ; 80 l 13.6 Shipping & Receiving Controls. II-13.85: i

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1 . CHAPTER 14 ENVIRONMENTAL SAFETY 14.1 Radiological II-14.1 14.2 'Non-Radiological II-14.1' \\ CHAPTER'15 NUCLEAR' CRITICALITY SAFETY 15.1 Administrative Practices - Area Managers- -II-15.1 l 15 2 Administrative Practices - Criticality Safety. Function II-15 '. 7 15.3 Equipment'& Facility Design Considerations' II-15.10 1 1 15.4 Methodology in Criticality Safety Analyses- 'II-15.14 15.5 Analytical Methods' II-15.19 15.6 Method Validation II-15.29 CHAPTER 16 PROCESS DESCRIPTION &. SAFETY ANALYSES-16.1 Receiving & Storing UF,- 'II-16.1-o t 16.2 UF,-to-UO Conversion - ADU Process II-16.6-2 'l rO LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION-18 ' .w_______

' 'b; n r TABLE OF CONTENTS' Section- ' Title Page' c 16.3 . UF,-to UO. Conversion.-'GECO. Process . II-- 16.18 2 16.4 UO, PowderiPre-Treatment . II-16.'28!. II,16.36

j. I 16.5 UO, Powder-Blending 16.6 Pellet Production-l

II-16.38, 16.7' Sintering II-16.~40 16.8' Pellet Grinding- '-II-16.41' ][ 16.9 Fuel Rod Loadirig:

, II-16.421 16.10 Fuel Bundl'e: Assembly II-16.44.'

16.11 Fuel Bundle Leak Test & Final Inspection; II-16.47' 4 16.12 Fuel Bundle Storage II-1,6.48 -j l 16.13 Packaging of Fuel Bundles.for Transport. . IIs16'.50' 16.14 Scrap-Recovery II-16.51-1 II-16.55 ~ l 16.15 Waste Treatment & Disposal 1 16.16 Chemical-Metallurgical Laboratory II 16.'65' j 16.17 Outside Product Can Storage II-16'.67.. .j 16.18 Process. Technology Laboratory II-16.68' l CHAPTER 17 ENVIRONMENTAL EFFECTS OF ACCIDENTS II-17,.l' ] O LICENSE' SNM-1097 DATE- -10/23/87', Page DOCKET ~70-1113 REVISION 18-l - 7"- ~ ' ._...m_i___'____.___.____.._

1 1 l j REVISIONS BY PAGE 1 fs / ( s) i s Effective Effective Effective Page Date Page Date Page -Date I-3.6 10/23/87 j TABLE OF CONTENTS I-1.21 10/23/87 I-3.7

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10/23/87 I-3.9' 2 I-3.10 3 I-3.11 4 I-3.12 CHAPTER 2 ~ I-3.13 5 "^ 6 I-3.14 I-2.1 10/23/87 7 I-3.15 i I-2.2 8 I-3.16 ' I-2.3 9 -I-3.17 l 10 I-2.4 I-3.18 I-2.5 11 I-3.19 I-2.6 12 I-3.20 I-2.7 13 L I-3.21 I-2.8 3 I-3.22 l I-2.9 I I-3.23 l PART I I-2.10 I-3.24 (- I-2.11 (>) I-3.25 I-2.12 I-3.26 CHAPTER 1 I-2.13 .I-3.27 I-2.14 I-3.28 I-2,15 I-1,1 10/23/87 i I-2.16 I-1.2 l I-2.17 I-1.3 l I-2.18 I-1.4 CHAPTER 4 I-2,19 I-1.5 I-2.20 I-1.6 I-4.1 10/23/87 I-2.21 I-1.7 I-4.2 i I-2.22 I-1.8 I-4.3 j I-2,23 I-1.9 I-4.4 I-2.24 I-1.10 l I-4.5 I-1.11 I-4.6 I-1.12 I-4.7 I-1.13 4 i CHAPTER 3-I-4.8 I-1.14 I-4.9 I-1.15 I-3.1 10/23/87 I-4.10 i I-1.16 I-4.11 I-3.2 I-1.17 I-4.12 I-3.3 I-1.18 I-4.13 I-3.4 I-1.19 I-4.14 I-3.5 I-1.20 l' r LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 l A

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q REVISIONS BY PAGE t's i \\_) l 1 Effective Effective-Effective 'l Page Date Page Date Page -Date i II-10.22 7/25/83 II-11.15 7/25/83 1 II-11.16-PART II II-10.23 l II-10.24 II-11.17 II-10.25 II-11'.18 CHAPTER 9 II-10.26 II-11.19 II-10.27 II-11.20 l II-9.1 7/25/83 II-10.28' II-11.21 II-9.2 II-10.29 II-11.22 1 II-9.3 II-10.30 II-11.23 II-9.4 II-10.31 II-11.24-II-9.5 II-10.32 II-11.25 II-9 6 II-10.33 II-11.26 II-9.7 II-10.34 II-11.27 II-9.8 II-10.35 II-11.28 ) II-10.36 II-11.29 { II-10.37 II-11.30 I CHAPTER 10 II-10.38 II-11.31 i () II-10.39 II-11.32 II-10.1 - 7/25/83 II-10.40 II-11.33-II-10.2 II-10.41 II-11.34 II-10.3 II-10.42 II-11.'35 II-11.36 ) II-10.4 II-10.5 II-11.37 l II-10.6 CHAPTER 11 II-11.38 II-10.7 II-11.39 II-10.8 II-11.1 7/25/83 II-11.40 II-10.9 II-11.2 II-11.41 II-10.10 II-11.3 'II-11.42 II-10.11 II-11.4 II-11.43 j II-10 12 II-11.5 II-11.44 j II-10.13 II-11.6 II-11.45 II-10.14 II-11.7 II-11.46 1 II-10.15 II-11.8 II-11.47 I II-10.16 II-11.9 II-11.48 ] II-10.17 II-11.10 II-11.49 II-10.18 II-11.11 II-11.50 II-10.19 II-11.12 II-11.51 II-10.20 II-11.13 II-11.52 ( II-10.21 II-11.14 II-11.53 j 1 G(~ 3 LICENSE SNM-1097 DATE '10/23/87 Page: DOCKET 70-1113 REVISICN 18 - 10'- i

x. ? REVISIONS BY PAGE: f -) LJ J Effective Effective Effective Page Date Page Date Page Date II-11.S4 '7/25/83 II-13.10 7/25/83 II-13.49 7/25/83 II--11. 5 5 II-13.11 II-13.50 II-11.56 II-13.12 II-13.51; II-13.13 II-13.52 II-13.14 II-13.53 ' CHAPTER 12 II-13.15 II-13.54 II-13.16 II-13.55 II-12.1 7/25/83 II-13.17 II-13.56 l II-12.2 II-13.18 II-13.57 II-12,3 II-13.19 II-13,58 II-12.4 II-13.20 II-13.59 II-12.5 II-13.21 II-13.60 II-12.6 II-13.22 II-13.61 II-12.7 II-13.23 II-13.62 II-12.8 II-13.24 II-13.63 II-12.9 II-13.25 II-13.64 II-12.10 II-13.26 II-13.65 3 (] II--12,11 II-13.27 II-13.66 ) I 'v II-12.12 II-13.28 II-13.67 II-12.13 II-13.29 II-13.68 l II-12.14 II-13.30 'II-13.69 l II-12.15 II-13.31 II-13.70 II-12.16 II-13.32 II-13.71 II-12.17 II-13.33 II-13.72 II-12.18 II-13.34 II-13.73 1 II-12.19 II-13.35 II-13.74 ~ II-13.36 II-13.75 'II-13.37. II-13.76 CHAPTER 13 II-13.38-II-13.77 II-13.39 II-13.78 II-13.1 7/25/83 II-13.40 II-13.79 II-13.2 II-13.41 II-13.80 II-13.3 II-13.42 II-13.81 II-13.4 II-13.43 II-13.82 i 1 II-13.5 II-13.44 II-13.83 II-13.6 II-13.45 II-13.84 II-13.7 II-13.46 II-13.85 II-13.8 II-13'.47 II-13.86 l II-13.9 II-13.48 II-13.87 l

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} i REV.TSIONS BY PAGE { fT i J i ,1 Effective Effective Effective Page 'Date Page_ Date Page Date 1 II-16.~54 9/30/83 II-16.55 II-16.56 II-16.57 II-16.58' II-16.59 II-16.60 II-16.-61 II-16.62 i II-16.63 II-16.64 II 16.65 3 II-16.66 II-16.67 II-16.68 II-16.69 II-16.70 j ij II-16.71 l s-- II-16.72 II-16. 7 3 a i i CHAPTER 17 II-17.1 7/25/83 1 1 r. '~' LICENSE SNM-1097 DATE 10/23/87' Page 00CKE'T 70-1113 REVISION 18 -< s-

CHAPTER 1 STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS j 1.1 CORPORATE & FINANCIAL INFORMATION l This licensing information document is filed by the Nuclear Fuel & Component Manufacturing facility (identified in this document as GE-Wilmington) of the General Electric Company, a New York corporat' ion with the principal place of business at Schenectady, New York. 1.2 LOCATION & GENERAL DESCRIPTION OF WILMINGTON PLANT (~)'i a nuclear fuel fabrication plant in Wilmington, North The GE Nuclear Fuel & Components Manufacturing operates Carolina. At this site, GE occupies buildings for administrative, laboratory and manufacturing activities. A sita plan is included as Figure 1.1. Fuel-manufacturing activities are conducted within the fuel manufacturing area. The full address is as follows: GE Nuclear Energy, ] Nuclear Fuel & Components Manufacturing, (name of person and mail code), P. O. Box 780, Wilmington, NC 28402. f LICENSE SNM-1097 DATE 10/23/87 Pago l OOCKET 70-1113 REVISION 18 I-1,1 1 1 _J

i '(] FIGURE 1 GE-WILMINGTON S1fE' PLAN' 'i { I i t ~ J i 3 . -j g ] i SX 6 'D / ~ j r~ ill' m W .J k- .M\\f r D, ,.q .j u.a.,71~ j-., = I y 8 orra i g Ed (g E"=. sanwennean a i. '""" \\ "=.

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J h '1".L3.. ' LICENSE' NUMBER' .The GE-Wilmington'NRC license number islSNM-1097..I(Dobket. 70-1113). 'In ac'cordance with:the'GE-Wilmingtonitimely? renewal" i request dated 4/28/81 and subsequen,t,Lrelated. submittals, GE-Wilmington requested' license' renewal'for; a<five:.. year? period commencing;from-the timeAthat the.- Nuclear. Regulatory JCommiss' ion : completied ifinal' action.'on; that' matter. 1.4 POSSESSION LIMITS ~ The following types, quantities,i-and forms of.special; nuclear materials are' authorized: m] 1.4.1 Uranium-235,-50,000'kgs total Contained in uranium'toLa maximum,~ nominal enrichment loff UO,: :UiOi and. ~otherl solid-and-6% in the form of~UF3, 2 liquid: process intermediates _and_ products.' characteristic.. of. LEU fuel fabrication and fuelLfabrication-devel'opment activities. .( 1.4.2 Uranium-235,'350 grams total l In any form contained in uranium at any enrichment,s.for ' E use in measurements, detection,.research or development. 'i l d l; r . G LICENSE SNM-1097-DATE 10/23/87 Page .l 8 DOCKET- '70-1113 REVISION 18. 'I-1;3. J j r l,- il 1 1 1

i 1.4.3 Uranium-235, 500 kas Total {} In any form, contained in' uranium at a maximum nominal q enrichment of 15% for use in laboratory and process f technology development operations. aj 1 -l 1.4.4 Pluton 1un 1 .i 1 milligram in samples for. analytical purposes j i i 1 milligram as standards =for checking the alpha f radiation response of radiation detection instrumentation. + l 20 grams as sealed neutron sources l In nuclear fuel materials at a level of not more than j 10-5 grams of plutonium per gram of U285 l ("',) l s_ 1 1.5 MATERIAL USE LOCATIONS Uranium normally will be used at.the Wilmington site in the fuel manufacturing area only. Conversion and j fabrication of SNM is conducted within the fuel manufacturing building. 3 Small quantities (i.e., less than one safe batch of uranium in a non-dispensable form) may be temporarily moved to other buildings or site locations for special tests. l l 1 ) i i l r l $ _) ' LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.4 1 l i

/O-1.6 DEFINITIONS v' Definitions as used'in the license conditions are set forth below. 1.6.1 Area Manager - The manager designated by the GE-Wilmington facility manager,who is,, responsible for implementation of nuclear safety requirements in the area assigned. The general title _" Area Manager" does not necessarily refer to;the title of any, specific position in the GE system of organization and position nomenclature. 1.6.2 Array - means two or more-interacting accumulations of fissile material. 1.6.3 Criticality control - means the administrative and (~ technical requirements established to minimize the-(s)/ possibility of achieving inadvertentLcriticality in the environment analyzed. 1.6.4 Full Reflection - means the degree of reflection equivalent to a tight fitting shell of 12 inches or more of water. 1.6.5 Minimal Reflection - means the degree of reflection equivalent to a close-fitting shell of water, steel, aluminum, nickel or copper not greater than 1/8 inch in-thickness. 1.6.6 Minimum Critical Dimension - means the smallest dimension which constitutes a critical system for a 'l (~ i k' LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.5 'i i s m

1 -(} 'given geometry ~under conditions of full reflection and optimum moderation. o 1.6.7.- . Nominal U225 Enrichment - means the'value of enrichment 'l assigned'to a quantity of material for convenience because the precise value is not known due to process or-measurement uncertainties. 1.6.8 . Nuclear Safety - means both' criticality and: radiation-safety. ) 1.6.9 Safe' Batch - means an accumulation of.special nuclear material which is 45% of the critical' accumulation for U225 enrichments less than or equal to-6%'and133.1/3% of the critical accumulation-for U225 enrichments greater than 6%,. considering enrichment, full reflection,'and optimum water moderation for the specific material. /'_] form. \\- q 1.7 AUTHORIZED ACTIVITIES l 3 This application requests authorization-to receive, possess, use, store and ship authorized special nuclear materials pursuant to 10 CFR Parts 70, 71, 73,'74 and 75. 1.7.1 Product Processing Operations 1.7.1.1 UF. Conversion - Conversion of uranium hexafluoride to uranium oxides, r~ LICENSE SNM-1097 DATE 10/23/87 Page ~ DOCKET 70-1113 REVISION 18 .I-1.6

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- 1. 7.1. 2 5.FueltManufacturer-Fabricationxof? nuclear reacter; fuels; l

~" Q .3 containing uranium.. 3 j 1.' 7. l'. 3 : Scrap.-Recoveryi-Reprocessing.of unirradiAted. scrap- ,) .fj fromLGE-Wilmington;and fromlother' sources.with: nuclear ( )) '[l safety characteristics similar t!o GE-Wilmingtoni i*' in-process materials'. t .1. 7 ; 2 ' ~ Process--Technology' Operations 1 1 1.7.2.1 Development'.and fabrication of reactor fueh fuel; elements and fuel assemblies in small amounts or'of' a'dvanced design'. q i 1.7.2.2 Development of scrap recovery processes, z! la t 1.7.2.3 Determination of' interaction betweennfuelladditives and; j 4 fuel materials-O)- l q 1.7.2.4 Chemical analysis =and. material testing,.' including physical and chemical testing and analysis,. metallurgical-examination and radiography-offuranium-compounds, alloys and mixtures. 1.7.2.5 Instrument research and calibration,' including-development, calibration and functional'. testing of... l l nuclear instrumentation and measuring-devices. i 1.7.2.6 Other process technology' development activities'related l to, but not limited by, the above. O LICENSE SNM-1097 DAT E'. 10/23/87' Page DOCKET '70-1113 REVISION-18 I-1.7 l 1, .'\\ a

vn (v) 1.7.3 Laboratory Operations Chemical, physical or metallurgical analysis and' testing of uranium compounds and mixtures, including but not - ) limited to, preparation of laboratory standards. i 1.7.4 General Services Operations l i i 1.7.4.1 Storage of unirradiated fuel assemblies,- uranium compounds and mixtures in areas arranged specifically for maintenance of criticality and radiological safety. ] i i 1.7.4.2 Design, fabrication and testing of uranium prototype ^ processing equipment. .l l l 1.7.4.3 Maintenance and repair of uranium processing equipment i and auxiliary systems. J /~' { 't Storage and nondestructive testing of fuel rods i 1.7.4.4 l containing licensed amounts of plutonium 1.7.5 Waste Treatment and Disposal j I i 1.7.5.1 Treatment, storage and disposal and/or shipment of. j liquid and solid wastes whose discharges are regulated. 1.7.5.2 Decontamination of non-combustible contaminated wastes to reduce uranium contamination levels, and subsequent shipment of such low-level radioactive wastes to licensed burial sites for disposal. ,(') LICENSE SNM-1097 DATE 10/23/87-Page DOCKET 70-1113 REVISION 18 I-1.8 7

a '1.7.5.3- - Treatment *or.disposalfof' combustible wasteland 1scrapJ i material by' incineration pursuantitoz10..CFR 20.'302(a): and 10 CFR 20.305.- g Q

l 1.7.6 Offsite Activities-

.':h i ~ Testing, demonstration, non-destructiveimodification,. and storage of materials andidevices'containing-a unirradiated' uranium', provided^that such.materialsCand ] 1 devices ~shall be-in;GE control at'all times. l 1.8 . EXEMPTIONS & SPECIAL:AUTH RO IZATIONS-i 1.8.1 Requirements for Prior Authorization-of Activities ~by License Amendment'

1

.(] Prior authorization..by7 licensee amendment shall)beS required for the.following activities: i 1.8'.1.;1 Major changes or-additions to-existing; processes >which.. ,I may involve a.significant increase lin potential or actual environmental impact resulting.from utilizingf q such changes or' additions. L 1.8.1.2 Major process changes'.or. additions which. involve :a new' process technology for which a criticality safety-d demonstration has not been previously? submitted to the: Commission. In determining.whether'a new process l technology requires such prior ~. authorization:by.licenseL i amendment, the following factors will.be considered:' f .l L (1) type of equipment utilized,.(2) chemicalre. actions: '{ l ,y - h j . LICENSE SNM-1097-DATE 10/23/87. ' Pag'el .] DOCKET 70-1113 REVISION 18.. I-1.9' y i i. _____._______.__1____. ] 'M ~'

8 y ,I-L ? i . involvhd.' and, (3) potential: and/or actual.' environmental ] 1mpact. '1.8.1.3 Proposed' activities for which specific application'and prior-approval are required.byJCommission regulations. l'.' 8, 2 Contamination-Free Articles- ]:

'- j See?Pages I-18 through I-21, " Guidelines.for.

Decont'ami' nation of Facilities'.& Equipment Prior;to Release for Unrestricted.'Use or Termination of' Licenses i for Byproduct, Source,.'or Special' Nuclear Material," US

NRC, ugust'1987.

-1.8.3 Disposal of Contamination-Free Liquids-e Jj

1. 8. 3.' 1.

Hydrogen Fluoride Solutions-Authorization, pursuant to 10 - CFR ' 70'.42 (b) (3),.to: transfer liquid hydrofluoric' acid:to Brush.Wellman, Elmore, Ohio, through.the chemical--supplier',. Consolidated Chemical Company,. Kansas City,= Missouri, j without either company possessing alNRC-or Agreement.: State license for special nuclear material, provided' that the concentration o'f: uranium does:not exceed three parts per million by weight of the liquid.and the nominal enrichment does not exceed 6 weight percentiof: U885

1 The hydrofluoric acid is' transferred and usedrin such a.

manner that the minute quantity of uranium does not i enter into any food, beverage, cosmetic,.. drug-or.other~ l 3 ~(d') LICENSE SNM-1097 DATE 10/23/87 Page ,o 00C"ET 70-1113 REVISION 18 I-1.10; P q

(~') commodity designated for ingestion or' inhalation by, or application to, a human being such that the uranium concentration in these items vould exceed that which j naturally exists. Additionally, the acid is used.in a process which will not' release 1the low levels'of radioactivity to the atmosphere as airborne material and whose residues will'rema1n in a lagoon system, l Prior to shipment, each transfer-is sampled and' measured to assure that the concentration does-not exceed'three parts per million of. uranium. GE shall maintain records under this condition of j license including, as a minimum, the date, uranium-concentration and quantity of all hydrofluoric acid transferred. ') j i /~') 1.8.3.2 Nitrate-Bearing Liquids j \\-./ Authorization, pursuant to 10 CFR 20.302(a), to dispose of nitrate-bearing liquids, provided that the uranium ( concentration does not exceed a 30-day average of 5 parts per million by weight of the liquids;and the i nominal enrichment does not exceed 6 weight percent U885, by transport to an offsite liquid treatment system located at Federal Paper Board Corporation,'Riegelwood, 1 North Carolina, in which decomposition of the nitrates will occur and from which the denitrified liquids will j be discharged in the effluent from the system. The environmental monitoring program as described in Section 5.1.4.2 is used to control these activities. t (~, \\ 'l LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1313 REVISION 18 I-1.11

7 1 1 -!l [~') - 1.8.4 Use of Materials:at Off-Site Locations .{ u.- g 1.8.4.1 Authorization to use up to 15 grams of U885'at.other' sites within the limits;of the United States and at j temporary job sites of the licensee anywhere in the, United States where the Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material. l f The manager of the radiation. safety function-shall establish the safety criteria for material being used at i offsite locations. It is also his' responsibility.to designate the individual.who will be responsible to carry out these criteria. I 4 1.8.4.2 Authorization to store at nuclear reactor sites, uranium fully packaged as for transport in any Fissile Class I: I') authorizing delivery,of such containers to a carrier for package, in accordance with the conditions of a license 3 x-Fissile Class I transport, at locations in.the United l States providing such locations are controlled by GE ] with provision to minimize the severity of potential j accident conditions to be no greater than those in the i a design bases for the containers during transportation. 1 Provisions for compliance with applicable 10 CFR 73 requirements are described in the NRC-approved GE-Wilmington Physical Security Plan dated June 6,

1986, as currently revised in accordance with regulatory provisions.

LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.12 J w-- _ _

9 r is I t Storage at nuclear reactor sites is subject to the-f~h; us financial protection'and indemnity provision of 10 CFR. 140 and is limited to possession for purposes of delivery to'a carrier?for. transport. The requirements of 10 CFR 70.24 are waived insofar as this section applies;to the materials contained in Fissile Class I packages. l 1 1.8.4.3 Authorization to store at-nuclear rdactor sites, arrays ]j of finished reactor fuel rods and/or assemblies in any of the inner metal containers of the RA-series s' hipping. package described in package certificate USA /4986/AF,Lat j locations in the United States providing such locations are controlled by GE with provision to minimize the severity of potential accident conditions to be no greater than those in the design bases for the containers during transportation. ('% i () Arrays can be constructed without limit to the number of' t containers so stored, except that each array shall be. I stacked to a height of no more than 4 containers high f with each container separated by nominal 2. inch wooden f studs, and with the widthiand length for each' array and-f separation between arrays determined only by container -l handling requirements. Provisions for compliance with applicable 10 CFR 73 requirements are described in the-NRC-approved GE-Wilmington Physical Security Plan dated June 6, 1986, as currently revised in accordance with regulatory j provisions, j i vn LICENSE SNM-1097 DATE-10/23/87 Page ) ~' l DOCKET 70-1113 REVISION 18 I-1.13 1 4

,(. (~) Storage at nuclear reactor sites is subject-to the-financial protection and indemnity provision of 10 CFR 140 and is limited to possession for. purposes of delivery to a carrier for transport. The requirements q of 10 CFR 70,24 are waived insofar as'this.section applies'to the materials' contained in any of the inner metal containers:of the RA-series shipping package. (Reference Section.1.8.7). .j 1.8.4.4 Authorization to transfer, possess, use and store { unirradiated reactor fuel of GE manufacture at' nuclear reactor sites, for purposes of inspection,. fuel bundle ^ disassembly and assembly, including fuel rod replacement,'provided that the following conditions are met. 1.8.4.4.1 A valid NRC license has been issued to the reactor licensee, which authorizes receipt, possession and (] storage of the fuel at the reactor. site, and that E possesses the fuel only within the indemnified J.ocation. a 1.8.4.4.2 Not more than one fuel assembly and 30 unassembled fuel rods of the types described in NRC Certificatra of ~ Compliance USA /4986/AF, are possessed'by GE at any one reactor site at any one time, except when the fuel-has been packaged for transport. 1.8.4.4.3 All operations involving the fuel are conducted by or l under the direct supervision of a. member of the GE staff who shall be responsible for all work on the fuel element assembly. The person shall be' knowledgeable and I) LICENSE SN!4-1097 DATE 10/23/87 Page j DOCKET 70-1113 REVISION. 18 .. I-1.14. / a

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t '. .) \\ shall have access:to:all: applicable'.procbduresEand( license conditions.aL.the reactor { site'and'the: 3, appropriate accions that'are tobetakenDin/theeventTof' 'f s emergenci,es atotheLsite. 0 i '1.8.4.'4.4 All operations' involving the fuel 1are: conducted :in: b ' ] . locations that'have beeniseldctedIt,o' preclude: mechanical v damage.and flooding. ./- .\\ \\ 1.8'.4.4'.S Loose'rodsJare ' stored only in1RA-series inner metals. H a .s containers'- n .I in i,

1. 8. 4. 4. 6 ;/. tlel JJs ' handled in : accordance ' with: pertinent' provi'sions' F

./ J ... d.- ofJthe reactorclicense andoin accordance'withl written-1 . it S and approved GE.proceduresi The' procedures'shall define /,' ' the radiation and contamin ionsurvhsthatare'toL be performed and-the frequency of the surveys. O L. o' 1.8.V,;4.7 Written adminjs.trative. procedures-are jointly, prepared: andapprovedb[GE"andthereactoslicensee,.toprovide4 i _4 for.the nuclear and radiation safetycaf,thel operations j. M to be performed. / s i . s' 4 -) 1.8.4.4,8 Records of.the opere. tion;flucluding evaluat' ions, procedures used, audits.perbormed',Landperformance;r y. w. = reports are maintaindd;attthe'Wilmington,.Nok 5 Carolina, plant.n y r. - g 1 8.5 DisposalofIndust[ial'WasteTrbatment' Products' [ <,y ~ v e, I /f g, Notwithstanding any requirements for. state or-loca1 Q ' government agency disposal'UErNEtd,LGE $.s"atith'orized td T .h 'y 1 in 4 m . =. y jy..

_7 I

t _., p l i ) 1 ..e io m. LICENSE SNM-1097 - DATE 10/23/87J Page: H ..., s DOCKET 70-1113 . ret'ISION ~ 18 ' ' ' _I-1.15-i r i .\\ ,j. i l j{ ); l L o =___ a_w 'w I'. ,J

l i '[] dispose of industrial waste treatment' products without s._- continuing NRC controls provided that either of the two following conditions are met: 1.8.5.1 All freestanding liquid shall be removed prior to shipment. The'ur'nium concentration'in the material shipped for disposal shall not exceed 30 pCi per gram after all freestanding liquid has been removed. The. licensee shall possess authorization from appropriate state officials prior to disposing of the-waste material delineated in this. amendment. The authorization shall be ayailable for inspection at the Wilmington facility. 1 1.8.5.2 The uranium concentration in the material shipped for disposal only at the RCRA hazardous waste burial facility in Pinewood, S. C. (licensed by the State of South Carolina), shall not exceed 250 pCi per gram of f uranium activity, of which no more than 100 pCi per gram shall be soluble. The minimum burial depth shall e'at least four feet below the surface. j I i 1.8.6 Dilution Factor for Airborne Effluents l I Authorization to utilize a dilution factor to the i heasured stack discharges for the purpose of evaluating the airborne radioactivity at the closest. site boundary i l of stack discharges from the uranium processing i I 1 ,-U LICENSE SRM-1097 OATE 10/23/87 Page DOCKET 70-1113 REVISION 18 L I-1.16 ) i -l

facilities. For purposes of control, this dilution [ '} factor shall be no greater than 100. For other purposes, specific dilution factors, which consider dispersion model parameters, may be calculated and' used. 1.8.7 Monitor System Exemption i Authorization for exemption from the requirements of 10 CFR 70.24 for each area in which there is not more than: A quantity of finished reactor fuel rods equal to l l or less than 45% of a minimum critical number under l conditions in which double batching is credible, or equal to er less than 75% of a minimum critical number under conditions in which;deuble batching is (]} not credible, or The number and type of finished reactor fuel rods and/or assemblies authorized for delivery,to a j carrier for transport as a Fissile Class I shipment in the model RA-series shipping package described' f in package certificate USA /4986/AF, without limit i on the number of such stored container 6, provided l the storage locations preclude mechanical damage ] and flooding, or The quantity of uranium authorized for. delivery to a carrier for transport as a Fissile Class Y j package when fully packaged as for transport according to a valid NRC authorization for such i l i ) i U - LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.17 i e 1 I

i (') packages.without limit on the number of such ~' packages, provided storage locations preclude j mechanical damage and flooding, or Arrays of finished reactor fuel rods and/or assemblies in any of the-inner metal containers of. the RA-series shipping package, described in' j i package certificate USA /4986/AF,-under storage l conditions described in Chapter 1.8.4.3. j 1.8.8 Incinerator Operation .I Authorization, pursuant'to 10 CFR 20.302(a) and 10 CFR 1 20.305, to treat or dispose of waste and scrap material containing special nuclear ruaterial by; incineration. I 1.8.9 Posting j l'~) l i k' For those areas within the Controlled Access Area in which radioactive materials are processed, used, or-stored, where it is deemed impractical to label individual containers pursuant to 10 CFR 20.203(f), a sign stating "Every container in this area may contain radioactive material" shall be posted. 1.8.10 Uranium Recycle Enrichment Control Maximum enrichment in the Uranium Recycle-(UPMP). operation shall not exceed the minimum U825 enrichment approved by the nuclear safety function for any Uranium Recycle process. ( y. LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.18 .=

1 ( 1.8,11 Sanitary Sludge Accumulation i Authorization to accumulate treated-sanitary sludge containing trace amounts of uraniumi in-the sanitary sludge land application area pending final disposal. 1 i 1 l j q J \\ V i l ) I L fb LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.19 .s s

s. g. + .,., m m.s.._ JO RECEIVED 5%.- 1 1 q 1 AU3 211987 1 e*

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-[ GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE . 4-OR TERMINATION OF. LICENSES FOR BYPRODUCT, SOURCE, ') ,0R SPECIAL NUCLEAR MATERIAL I .i; i ~' i O U.S. Nuclear Replatory Cnsuaission Division of Industrial and. Wa g on 2055 ~ August 1037 4 h' ) i l LICENSE SNM-1097 DATE .10/23"87 Page / .o DOCKET 70-1113 REVISION 18 I-1.20' k.mm______m.__2._ _ ..u_ w._. _ _ _ _ _ _-- ,-_w --a. 2-___.u m-.-_m_m

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i l l fH The instructions in this guide, in conjunction with Table.l. specify the radionuclides and radiation exposure rate limits which should be used in ; { decontamination and survey of surfaces or premises and equipment prior to. abandonment or release for unrestricted use. : The limits in Table.1 do not' q apply to premises. equipment. or scrap containing induced radioactivity for 1 which the radiological considerations pertinent to their use may be different. il The release of such facilitf es or items,from regulatory control is considered ] i on a case-by-case basis. 1. The licensee shall make a reasonable effort to' eliminate residual' ' contamination. 3 2. Radioactivity on equipment or surfaces shall not be covered by paint. .i plating, or other covering meterial unless contamination levels, as,. determined by a survey and documented, are below the limits specified-in Table 1 prior to the application of the covering. '. A reasonable effort .1 must be made to minimize the contamination prior to use of any covering. 3. The radioactivity on the interior' surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior-y of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size.. construction, or location as to make the surface inaccessible for purposes 1 of, measurement shall be presumed to be contaminated in excess of tne limits. 1 4, Upon rcquest. the Cosmeission may authorize a Itcensee to. relinquish - possession or control of,remises, equipment, or scrap having surfaces. t contaminated with materials in excess of the limits specified. This may include, t,ut would not be limited to, special circumstances such as razing 2 ; of buildtngs, transfer of premises to another organization continuing work.- with radioactive materials. or conversion of facilities to a long'ters : l storage or standby status. Such requests must: ] a. Provide detailed, specific information desdribing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination, b. Provide a detailed health and safety analysis' which reflects that the residual amounts of materials on surf ace areas.' together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public. ,- f O ^ LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-1.21 m

, p t ] -...... e. .m .u. D 1 1 1 1 5. Prior to release of prentises for unrestricted use, the licensee shall ' i { make a comprehensive radiation survey which establishes that contamination' is within the limits specified in Table 1. A copy of the survey report-shall be filed with the Division of Industrial and Medical Nuclear Safety.' i U. S. Nuclear Regulatory Commission. Washington DC 20565. and also the 1 Administrator of the NRC Regional Office having jurisdiction. ! The report should be filed at least 30 days prior to thd planned date of abandonment' f The survey report shall 9 a. Identify the premises,

b. ' Show that reasonable effort has been made to eliminate residual-contamination, c.

Describe the scope of the survey and general procedures followed, ~ d. State the findings of the. survey in units'specified in the instruction. Following review of the report, the NRC will consider visiting the- ~i facilities to confim the survey.- ] O 6 4 e y l H LICENSE SNM-1097 OATE 10/23/87 - Page DOCKET-70-1113 REVISION 18 o I-1.'22 R 'l

O g n 1. -( i ee n t e t ht t i tt e ft e gt a se m a g on nn r md 2 2 m ts v erc, ; a ie e rue d ~ n c e t u a e f m m e e n rsd m c g rt 'e 6ne wf e L ~ 0 2 0 rs h1 ti r 6 0 2 m* 0 a on t i ao ^ t ci l ee E 1 m c 1 t / c / e ftb tr 4 s e 0 y b ye e a se a 0 0 s bh t yid et d t r rri e p a 0 1 p p 1 ( m n d a dps dm E a eh oe li B d / e 4 n* e hrh et E a p it c t ps on R 0 p d 0 d 0 a mw a i p he 0 0 h r f was .sc 0 0 0 0 p ed r l 1 2 2 1 l te u 'ene _se a et s eav .rr da r e-ea' r l s ehl o sc s t t sp ta f ae e tit i s a awn m s l. h e e r ,n ?, ^ d l s ~ e aa f. 't en e h i o pi ap-s rt gtt m i er y aur es b at c, l e oe l t e t pep ge a mc e ih r t a j wte .ag ~ s ef h h ti e v e ynt el b ic be. bl E s ti r i t m tt cr o dld em st F nae e u c 0 l i m tain r7 e ee S c ri f 0 l do sem n LE ~ 0 2 1/ e rg e eee nh ae r rt r ge m V f 0 L d / y h t t mt it E 1 s 0 s t yd e e e t 3 N 0 0 bn m ded l e M I p 10 1 a a v ur O m / r s n e eis s a N I d / a d t e, r b t i _' ec T A a p s t y a c r K 0 p d 0 i sc u daa t 1 R 0 d 0 s sn q luir en,_* oe no N 0 0 e t e s A I 0 0 0 ni oda t 1 T 1 3 3 1 e i 1 2, ha th 5 0 0 5 s ec m sre eg N d L C l ff n c c nu E O of a af a io I e h 0 eof mr t 0 r r ah 8 c e. A E u t 1 atu tt T C a ad e ns n A rn r n eu od F g u o a cos ce R n eo m h ams r U i h r t f ae eu O t tg r r l cs t k e e ue an E i na o o to sc v r shf .f e ~ L m rs B e ab m f u A e d ogs s, T s mr e t nt y P e o g o 2 ic hl mse E d 2 m )f a n te c s j.- C iv A c c g t r e' .f eed wi - m a e r C 2 uo v o 0sae t f 0 2 p 0 a lat a 0s p .dc C 1 m c 0 t c a 'l ani ee 0 ie e e ow t p c 1 e s O / b t b r rd as 5 / ' 0 O y re a enne ie~ 1E 0 s d ed t paeb cr e G m i/ a p o n t A e 1/ m a h e n - e l ,t d o. s R d m p p st aeel sm E p d d na d o irnu _ac V 0 d a ei l t ruio. sI u. esmh A 0 0 0 h t r s t sas 5 1 1 5 lp t p o 0 0 0 e aet let 0 0 0 0 eo ht i mrne va a rr sc gp e l poc e hy ep tj p e ca l r tl t a nb p ve f h ot a ao a iter n/ bn i n n t al u od e tsa ih l crbs ia yd mc e aea tr bn dy au v odve oor tam s s e (b t s e l 8 6. e u np n l dmmi d6 dno oe ad oh e et e 2 2 lh nd tn d v a e n e 2 1 ae id pe cc n rgrn r1 s l dt a 1 Ct an ai r ee t ein sd u ta n , e g t l yee un nc R. arn iy es ar e blhh aa au 1 .d .3 02 (eo0 ml lb ro i a pW t l n ap bo ef vp _ n m a e o 629 93 hp9. s-t p a v m oa .d ac 8r 2 - 2 2 st 3 p 2a1 r-ro re na t e ed .a m 2 - P - SU e r5v o t e t e,ya 1 t e tb l su f v n rrc _d t so o cd - y a 1. 32 id npa eu ihi r c f pel aae n oi o eny ntr Ua R .c 8 24 e 25 sooe co t m se oail b S E 5d s22 223 emicd ah td s pca. err O 3 c1 3 sx e f s nr n u t in gh o I 2d ih - ha1 eyset r i e ee a ntf o .a/s L - e nTI TR - u ai o us p mb unfi rdb C Ut a p cm)n se d e lm oeet eea 1 aeen d es rd a mb r vr U a r... N .i u07 t3. gd es ei st ul s arno aal t c s32 e21 at r rl un su owp a e 2. t ao n22 n23 ahh se ec u ao e esoo ns a - - - - 1 tt psh h u so eh h hbnr h o s rhc ha - eilit Wn Ac Ms. T Takp f0t Ua TTA TRI 8waf o a b c d f i u m _ O l k4WgN 3Q# .om$m sZYwo@N yIm gO n f Sn7Q N?wwMW y<H[oz pC H 3 ('. [

CHAPTER 2 T 4 %J GENERAL ORGANIZATIONAL & ADMINISTRATIVE REQUIREMENTS 2.1 POLICY lit is-the policy of the GE to maintain a safe work place for its employees and to'. assure operational compliance within the terms and conditions of special nuclear materials licenses and applicable'NRC regulations. The GE-Wilmington facility manager or his delegate,.has the overall responsibility for safety and compliance to this policy. In particular, GE has established the principle.of O public as low as' reasonably achievable (ALARA). xee91#9 reatetio# exo sures t ematovee eaa the se=ere1 I 2.2 ORGANIZATIONAL RESPONSIBILITY & AUTHORITY l 2.2.1 Key Positions with Safety Related Responsibilities 2.2.1.1 Area Manager The Area Manager is the designated individual in management who is responsible to ensure that all activities necessary for safe-operationsand protect 1on of the environment are conducted properly within his l designated area of the plant in which uranium materials l 1 l LICENSE SNM-1097 DATE 10/23/87 Page l OOCKET 70-1113 REVISION 18 I-2.1' 1 s l )

[ are processed, handled or stored. The' responsibility of safe operation and control of activities in the area and for the safety of the environs as influenced by the , activities conducted therein.is assigned to the Area-Manager. He shall assure approved written' operating procedures (PRODS) are used which incorporate radiation and criticality safety controls and, limits commensurate j with the particular operations involved. 2.2.1.2 Criticality Safety Function The criticality safety function-is administratively independent of production responsibilities. The j criticality safety function is the function of GE-Wilmington with designated responsibility for'providing W authoritative professional advice and counsel to Area l Managers on matters of control against accidental (] criticality. These functions include.at least the following: Establishment of.a criticality safety control l program including criteria, procedures,and

training, Analysis and approval of proposed changes in process conditions and processing equipment, j

involving criticality safety, j Measurement of the effectiveness of the criticality l control program. 'l l 1 1l I ' b l LICENSE SNM-1097 DATE 10/23/87 Page.- i DOCKET 70-1113 REVISION 18 i I-2.2 f i

i ({]) Measurement of the effectiveness of the criticality control program is determined through audit programs to assure that nuclear. safety criteria are met for the protection of employees, the public and the' environment. i 2.2.1.3 Nuclear (Radiation) Safety Function l 1 The nuclear safety function, under the direction of the ~ manager of nuclear safety, is administratively independent of production responsibilities. The I nuclear safety function provides authoritative professional advice and counsel to Area Managers on matters of radiation safety and measures the l effectiveness of the radiation safety program. The nuclear safety function has the responsibility of-establishing and maintaining the radiation safety ( )! program necessary to ensure the protection of employees l at GE.-Wilmington and the community. The manager of the l nuclear safety function shall review and approve the radiation safety program which shall include at least i the following: a Establish the radiation protection and radiation monitoring program, 1 1 Establish the radiation protection criteria, j 4 procedures and training programs to control I contamination and exposure to individuals, ] Evaluation of radiation exposures of employees and visitors and maintenance of related records, j l l 1 l (-) LICENSE SNM-1097 DATE 10/23/87 Page 00CKET 70-1113 REVISION 18 I-2.3 I j l s. __--____J

^ Emergency planning, ' ') a Evaluate the integrity and reliability of radiation detection instruments. Establishment of special conditions for the use of laboratory _ samples containing plutonium and the maintenance of appropriate records, 1 Analysis and approval of proposed changes in process conditions and processing equipment q involving radiological safety. 2.2.1.4 Radiation Protection Function l The radiation protection function is administratively ] independent of production responsibilities.and has the j f) authority to recommend the immediate shutdown of an ) ss operation believed to threaten the health and safety of employees or the public. It is the function designated f the responsibility to obtain data relative to radiation exposures of employees and visitors, and to provide operational support to department functions requiring I radiation monitoring services. Radiation protection j responsibilities shall include at least the following: i Conduct of radiation monitoring programs, Administration of radiation work permit (RWP) covering nuclear safety requirements, l l f ) LICENSE SNM'1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.4 1 l 1 J

.} L.w. .1 i.i n' 1 Measurements of a'irborne uranium. concentration,: ] h . contamination. levels and. external radiation.levelk,. C. o' ' Evaluation of the. operational integrity.and -reliability of radi'ation detection'. instruments.. 1

I l

1 .. ~ l Activitiesiare.conductedjin'accordance-with? approved'. j c written procedures. l .i ) 2;2.1'.5 Environmental Protection' Function a The environmental protection function?is.administra-tively independent of; productibn 're'sponsibilities.' fit' l is defined as:that functiion:of GE-N11mington withL designated. responsibility tol include at least the-following: l? h Identification of environment 2.re:Juirementsvof: federal, state and local regulations; governing'the department's operationi Establishment of systems and methods to> measure and document department adherence.to regulatory-environmental requirements'and. license conditions, l Evaluation and approval of new, existing or.: revised' equipment, processes and procedures involving = environmental protection, Assurance of proper' federal,and' state. permits, licenses and registrations-for non-radiological: discharges from the facilities. 4 O LdENSE SNM-1097 0 TE 10 23/87 Page. DOCKET 70-1113 REVISIEN 18 I-2.5:

,u s -e' ~ 3' + ] . o. ,y -i 1 -) k L2.'2.1'.6 Regulatory Compliance'FunctionL

)

J y The; regulatory compliance function is administratively N ~ indeperident of' production responsibilities.but Lhas the? authority'to require;the, shutdown of any' process;ori facility,when the Area. Manager,has'notEassured or "' mairitained controls for. nuclear saf,ety. 'Itfis the-function. designated'.tolest'ablish. nuclear 1 safety, criticality safety and. environmental protection programs: to ensure department compliance with federal,!stateiandE li H . local regulations'and laws: governing. operation'of1 a nuclear facility. These. department; programs,are: ' designed to ensure the. health and. safety'of employeesc and'the public as~well'Jas protection of the. environment'., tj / f The managers of.-the criticality safety,Lthe! radiation safety, the-radiation protection,.and environmental-i protection functions-.reportJto.the:manageriof' regulatory O comp 11eace ruaction-2.3 SAFETY REVIEW COMMIT'1EE l 2.3.1 Wilmington Safety Review Committee 4(WSRC): The functions of the safety review committee shall I include responsibility for..the following:- An annual ALARA review which considers'the: following: l 3 t e) n q LICENSE $NM-1097 DATE 10/23/87 Page Q DOCKET 70-1113' REVISION ~ 18- 'I-2.6; i ii

/.

j

l ] 1 4 l ) Programs and projects undertaken by the radiation i %i safety function and the operational radiation { safety committee. l 1 1 Performance including, but not limited to, trends l in airborne concentrations of radioactivity, personnel exposures and environmental monitoring I results. I o Programs for improving the effectiveness of j equipment used for effluent and exposure control. Review'of nuclear and industrial safety practices ) applied to major changes made or proposed in author.ized plant activities, Professional advice and counsel on criticality and (/ radiation safety issues, w 1 The committee shall consist of at leas't five senior I members of the GE-Wilmington technical staff, appointed by the GE-Wilmington facility manager and shall include competence in the scientific and engineering disciplines. Senior members of management shall also f I serve on the committee upon the request of the GE- / Wilmington facility manager. ] The committee is responsible to the GE-Wilmington facility manager. Its proceedings, findings and recommendations shall be reported in writing to the GE-Wilmington facility manager and to.the section level managers responsible for operations which have been .{ /"') ] . i LICENSE SNM-1037 0 ATE 10/23/87 Page J DOCKET 70-1113 REVISION 18 I-2.7 ) ) m.___-m_. ?

) reviewed by the committee. Such reports shall be retained for at least two years. The committee shall hold at least four meetings each calendar year with a maximum interval of 180 days between any two consecutive meetings. 2.3.2 Operational Radiation Safety Committee The objective of the operational Radiation Safety ) l Committee is to improve fuel manufacturing operations so i as to affect visible improvements in employee. 4 radiological exposures and potentia) health / safety hazards. i The Committee typically meets at least monthly to maintain a continual awareness of the status of () containment projects, performance measurement and trends, and the current shop operations radiation safety conditions. 1 A written report of each operational Radiation Safety j Committee meeting shall be forwarded to cognizant Area j 1 Managers and the manager of the regulatory compliance { function. The report shall be forwarded within 15 ) working days of the meeting. Records of the committee ] proceedings shall be maintained for two years. The Committee shall consist of engineering, shop operations, maintenance, radiation safety function, 1 radiation protection function and quality control management or senior contributors. _=a n - ~~ LICENSE SNN-1097 DATE 30/23/87 Pags DOCKET 70-1113 REVISION 18 i I-2.8 \\

,.y 1 t ') r a ,n i - 2,4 APPROVAL AUTHORITY'FOR PERSONNEL SELECTIONS. .1 J j l The assignment:of individuals to Area Manager 4 a criticality safety and-radiation' safety.: functional JI positions' identified inTSection 2.2 shall be approvedLbyL d 4 manage'.nent at :the 'second organizati,onalllevel above the ac! - position:to-be staffed. Assignments.:to all?othhr safety-related staff: positions 1 a shall'be:made within the normal administrative practices- ] 3' of GE-Wilmington. < X: ,,) 2.5 PERSONNELVEDUCATION &-EXPERIENCE REQUIREMENTS .o q i 4 !? - 2,5.1 Area Manager e ? The minimum qualifications'of an Area Manager:shall be a 'BS degree from :a-college' or universityL in a techn1 cal j 1 I field'and two years experience in nuclear fuel plant-operation.or a.high school diploma'with ten years experience ininuclear. fuel plant operation.' I .i Each Area Manager shal1Lbe'. knowledgeable of the' criticality control. procedures and!the. radiation safety l-program as they relate to their--area of responsibility. j 1 Each Area Manager shall have proficiency:in;the.- application of. criticality control procedures'~and'be: ] knowledgeable in the procedures applicable to the. area .] under.his management. y J 1 ll {# 1 ) LICENSE SNM-1097 DATE - 10/2'3/87 .Page ~ l DOCKET 70-1113 _ REVISION .18' l I-2.9 .1 ,1 l i.- W

-7 i 1 /N() Each Area Manager shall have' proficiency in the application.of a radiation safety program as it relates to limitations and radiological controls for the kind of ) 1 activities in his assigned radiation or radioactive l l materials area. l 2.5.2-Criticality Safety Function / Nuclear Safety Function Criticality safety function / nuclear safety function manager (s) shall hold a BS degree in science or l 1 engineering, and shall.have at least five years of _] experience in a responsible position in the nuclear-f field such as engineering, physics or chemistry, at least three years of which shall have been in an ) activity which would develop an understanding of criticality problems and five years experience 11n assignments involving radiation safety, s Y (~/) { A_ ] The criticality safety function and the nuclear safety function responsibilities are currently vested with one manager. i 2.5.2.1 Criticality Safety I The criticality safety function is generally staffed by { personnel of three different classifications (senior, junior, trainee / technician). A senior' member holds a j l BS/BA degree in science or engineering with at least two years of experience in' criticality safety work and an j additional year of experience in either criticality safety or reactor engineering / physics. A junior member holds a BS/BA degree in science or engineering with at' ,~U LICENSE $NM-1097 OATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.10 a

i' ( }) least one year of experience establishing and monitoring e criticality safety limits. The trainee / technicians U position is assigned to persons who have the potential to eventually meet the qualifications of at least a junior member. i The criticality safety function shall consist of not o less than two technically l trained personnel, one of whom must meet the qualifications of a senior member. At least one of the personnel shall be based at GE- ,1 Wilmington. The senior member has authority and responsibility to. f' conduct al? activities defined in Section 2.211.2.

j The junior member performs the activities identified in q

1 Section 2.2.1.2. Criticality analyses and approval of proposed changes require an independent review by a () senior member prior to being' implemented'.- The. trainee / technician, under the direction of a senior or junior member, assists in the activities defined in .I Section 2.2.1.2 but has no authority for approval. j q 2.5.2.2 Radiation Safety Qualifications for radiation safety' engineers or specialists assigned to the radiation' safety function shall vary depending upon position assignments and delegated responsibilities. .Such position assignments shall be made and/or approved by the manager of the L radiation safety function and his manager. t Y% '~ LICENSE SNM-1097 'DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.11 n--~-._-.------

l I I ( ) Qualifications for a senior member of the radiation safety function include a master's degree in science or engineering with no less than three years of experience in general health physics: or a bachelor's degree in-science or engineering with no less than five years of experience in general health physics or.two years of j health physics experience in a nucl, ear fuel fabrication j plant; or certification in healtb physics. 2.5.3 Radiation Protection Function 2.5.3.1 Radiation Protection Manager The qualifications'of the manager of the radiation protection function is a BS degree in a scientific field with two years of experience in assignments' involving health physics or a high school diploma and eight years ll health physics experienco. v 2.5.3.2 Radiation Protection Supervisor Qualifications of a radiation protection mc

or and two years of experience as a radiation protection monitor, or at least five years of equivalent experience in the field of radiation protection, t

2.5.3.3 Radiation Protection Monitor ) ) Qualifications of a radiation protection trainee plus_at least six months experience. Prior to being certified as a radiation protection monitor, successful completion l 'l of a GE training program is required. This training l c LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.12 .j 1 w a l

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includes both. oral'and written examinations covering

t radiological'and criticality control (proce'ures. d w 2.5;3.4..

Radiation Protection

Trainee,

• J A minimum of.a high school education with twelve months'

-monitoringKexperience'or; equivalent, experience' working} with radioactive materials; or,two. years college-. ora technical.. institute training with mathematics orfscience major and aininimum ;of zfour months monitoring ~ I I experience or equivalent experience working;with-1 radioactive' materials.. d 2.5.4 Environmental Protection Manager- .w The qualification-;of the'manageriof-the environmental. l protection. function is' ALBS degreefin; chemical or.. i i 'O environ =e#te1 en91aeerins 91ue seven veere or re1etea-experience or a'. BS degree'; in ~ a non-technical: field. plus 1 ~ y ten years of experience in chemical or environmental -{ engineering. ] 2.5.5 Regulatory Compliance Manager ,j l ] 1 t The manager of regulatory' compliance function must hold-

I l

a BS in science or engineering and have 8 years-of j management experience, of which 5 years must-have been j l in a nuclear facility. l ..q 1 V LICENSE SNM-1097 DATE 10/23/87, Page-DOCKET 70-1113 REVISION-18 l I-2i13 l

n (~') 2.6 TRAINING v. Training policy requires that employees complete formal nuclear safety training prior to unescorted access in the controlled area. The method'for evaluating the understanding of employees includes pasting an initial examination covering formal trainin,g contents. j A Such training'is performed by_ instructors. certified by-the manager of the criticality safety and radiation ) safety functions. Training program contents are' l reviewed at least every two years by the manager of the criticality safety and radiation safety functions to ensure that training program contents are current and adequate. Previously trained employees allowed unescorted access () to the controlled area are retrained every two years. The effectiveness of the training program will be measured. 1 2.7 OPERATING PROCEDURES - ADMINISTRATIVE-CONTROLS Fissile material processing is conducted in accordance with properly issued procedures or instructions. 2.7.1 Adopting & Issuing Procedures I l Area Managers shall assure preparation of wri'tten 'f nuclear safety control procedures incorporating limitations established by the criticality and radiation LICENSE SNM-1097 DATE 10/23/87 Page-DOCKET 70-1113 REVISION 18 i I-2.14 1 __o

(3 safety functions. They shall assure that these V-procedures are'made readily available to foremen, ] operators _and'other concern'ed' personnel through posting of limits, training programs and other appropriate j written notifications. I The radiation protection program is. designed to' 'l i establish and maintain a comprehensive set of written instructions for radiation health and' safety practices I so as to maintain occupational radiation exposures at levels as low as reasonable achievable. Such instructions are reviewed by the' radiation safety I function prior to issuance by appropriate managers. 3 3 Subsequent procedure review frequencies are shown below: i Reviewing & Approving R9 vier Functional O o c""e=t trea"e"cv "ee aer 3 Operational (Process When Radiation Safety i Requirement changedt & Criticality & Operator Documents) Safety Radiation Protection Annually Radiation Safety (Nuclear Safety & Criticality Instructions) Safety i Environmental Every 2 Environmental (Environmental Years 3 Protection Protection i Instructions) l 1The radiation safety and criticality safety portions 1 of these operator procedures are reviewed and updated by the radiation safety and criticality safety functions when warranted based on process related ) facility change requests. 8 Annually means a maximum interval of 13' months. 2Every 2 years means a maximum interval of~26 months. /~, U LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.15 x

,j t 1 1 n Criticality safety control and radiation protecti'on. procedures 1for workers in. uranium processing areasJare . incorporated into'the appropriateLoperating,'(maintenance-and. test procedurestin place.for t uranium 1 processing: 4-operations. 2.7;2 Changesein SafetyeRelated Procedures-Activities whichJdo not-involvetacchangefinLlicensel conditions but'which, require procedures', facilities!or.- equipment 'substantiallyLdifferent1fromithose:previously; used are. initiated only after therapplicable' conditions. ' H stated below are: met: Changes which involve ~radiationLhazards. considerations are reviewed and. evaluated, andl < s-(,) ' approved.in writing by the nuclear; safety.

function, Changes which involve-a change in'the.parametersLon which criticality safety was" established'are.

analyzed and approved.in writing by;theicriticality safety function and. documented.by-a. written criticality analysis. 2.7.3 Procedures-for New or Changed'Act1vities A request'for nuclear safety: (criticality,and radiation' safety) analysis is prepared iniwriting by,L or at} thel ~ direction of, an Area Manager for any proposed:new-activity or change in activity 1which may require a* 'i ~ (if 10/23/87 Page' LICENSE-SNM-1097 DATE DOCKET 70-1113-REVISION '18 JI-2.'16-y

.~_____, n f)- proposed change in criticality safety or radiological u-safety controls. The changed activity will not be initiated until the nuclear safety analysis demonstrating safety of the activity has been completed, a preoperational inspection has been conducted to verify that t,he installation is in accordance with the nuclear safety analysis, and-appropriate' procedures and/or instructions are in-place. j The results of these analyses are documented in nuclear 1 i safety reviews and maintained for the period of time. i they remain applicable. l 'l l 2.8 AUDITS & INSPECTIONS I^T \\,._/ Written operating procedures are based on GE-Wilmington practices, applicable regulations and license l conditions. Audits are performed to assure that plant operations are conducted in accordance with the operating procedures. 2.8.1 Criticality Safety & Radiation Safety Internal Audits Quarterly (an interval not to exceed 100 days), senior members of the criticality safety and radiation safety functions conduct formal, scheduled safety audits of-nuclear manufacturing and-support areas in accordance ] with a procedure approved by the GE-Wilmington facility manager and in accordance with written procedures which r~s \\_) LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.17 L-_______

f i 0% () have been approved by the manager ci* the radiation. f safety and criticality safety functions. Such audits are performed to determine that actual operations y conform.to to criticality and radiation. safety requirements. Audits are performed by criticality, safety and radiation f I safety personnel under the direction of the manager'of the criticality safety and radiation safety functions. / Personnel performing auditsI o not. report to,the d 4 i production organization and have no direct .j responsibility for the function and area being. audited. Violations of license conditions' identified during I quarterly audits.for criticality safety and radiation safety shall be communicated within 8 hours to the Area' ] Managar and to the neanager of the regulatory compliance V AV function. Written notifications of such violationst shall be provided to the Area Manager.and the manager of-the regulatory compliance function within 10 working j days after the audit. Corrective actions'shall be documented in' writing and approved by.the Area Manager. Weekly nuclear satety inspections of all nuclear manufacturing and support areas are conducted in-accordance with written procedures and guidance which have been reviewed and approved by the manager of the radiation safety and criticality safety functions,.by persons having at least the qualifications of a Radiation Protection Monitor as described in Section 2.5.3.3. Violations of license conditions identified during weekly inspections are communicated within 8 o ___m k) LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2.18 __-__-___=u

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n. w L y.; I W ? y ~- '9 N: ' y 4, m + m,y ; 'gl H f. l' 3 J f' s,j <d 1 3 [, it ,L' .ho urs ; to :the Area Manager' and the: managerJ,ofi the? ', H 1 L., Jr c Written 4notificationLofi' R radiation,protectionifunction. d isuchiviolations'are provide'd(by the manager'ofst'el N radiation protection function? to theLAreaL Manager aridL

the manager of1 regulatory. compliance ;functionr within : 10!

eM a h 'i working days.< .x + 'n 1 Records"of,the instructions and procedures, persons] [j 3 i) the auditsJor inspections,fviolations?.ofi .conductingi i .licenseLeonditions-identified"and'borrectivefactio,ns taken.shall ie maintainedLby-the' radiation safety-E e 'l function'or;theLcriticality safety function:for?a1 a '); minimum period of'2 years. l d Audit results'in the form of, corrective-action' items'are? reported to the: GE-Wilmington-f acilitys manager'andthis staff for-tracking ~until-their closure; ~ Environmental Protection Internal Audihs 2.8.2 An audit schedule of the.environmenEallprotection. E program is developed.by the environmental: protection-function on an annual basis. Auditscare conducted'in accordance with a written procedure approved by the-GE-Wilmington facility manager?to~ ensure:thatJ operational activities conform to documented. environmental. requirements. Personnel.under the directioniof the~ manager'ofRthe' environmental protection functionP perform thei environmental protection auditu. Personnel' performing; the' audits do not report:to the production o ganizationL 1 '" p Q DATE 10/23/87= ~Page ~ LICENSE SNM-1097-DOCKET 70-1113 REVISION '18 I-2i19: q !q m-m ,o 7 a a a o.. n

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.r <s.- m 1.appro,kg by the. GE-Wilmingtonif acil,ity manager. 71 9 L3 0 4 manage.@n of the' environmental. protection] function 3rjhis' / n.. .... ~. w delegade is responsible for-formalafollow-upland l closure: a of lid'entified noncon$ormances. ' AUditir'esults ;iNitNe a, .n w form of f corrective - actioMitems V 'are reported c to;enei 4 s 4 GE-W13mington fhcilitly manager ' 1 m !,iand:hisustaff:for b s o . r r 7 3 > ? . tracking u>ntil. theirr, elosure'.: .v. 1 ,..c 1 - 3 % [ n,,, e . J.. w -v. n a.e 4, 4 2. 8 ~. 3 Exter.nal' Audits, . h !, ..,i 5 J., C 3 i The:GE-Wiimi Qton; criticality safety (and1 radiation! -2 >g g safetyj pfogramsjare' audited atia freque'ncyiofieveryjtwoj jf ,(' years 9by an Appropriate function %utsidELoff theI GE 4 i

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The."auditL eamiis' composed;of4 R Wi ~ lmington organization.. t 1 inclividuals J whose Laudit fqualifidations arel approvsd %yf m s s theGE-WilmingtonfacilIty!manahe,rf j* W^*#' W 3m' < n. ] 8 p w. -)~ <c ' Audit.results are reported 1 in1writingLto the 7 ^ Y:, 1o. 'd .9 c GE-Wilmington? facility manager,ito thelArealManager,-and A4 d e r> 'l to the' manager of the-criticality safety And"radiationh 4 - ) - safety functions. The criticalit!y= safety function, I '(( /q radiation safety function and/or' Area"Mddagers,far N v' q - A d appropriate,-' take nece'ssary ; response actions *in ' 3 accordance with documented corrective. action-l 'f j commitments. T,m l .9 mg . p( g q w e l I t ( !.ICENS E ' 'SNM-1097 ' DATE '10/23/87 'Pagel L y $ 2020 ',U REVISION 118L u 4 00CKET-

70-1113' y

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3 W. ...q ? g !;+; ,j to d y' q o J .... :a 3 Audit results in the formcofjcorrective actibnlitemstare~ ] reported.to the.GE-Wilmington: facility managerfand:his, staff"for tracking.until their closure'. '2.9 INVESTIGATION ^& REPORTING OF UNUSUAL OCCURRENCES ) l 2,9.1 - Incident: Classification 4 1 j Alliunusual eventsi;which p6tentially threaten or lessen the< effectiveness.of health, safety or environmental? Of o! protection are' identified by the; Area, Manager and~ [1 reported to.the quality. assurance section. _Each. .] -incident is considered in terms of its: severity. Tables ] '2.~.1 provides _ general 'guideli'ne's' for use in classification.. j q l ( -2.9.2 Investigation of Unusual Incidents-a Each reported unusual ~ incident is.' evaluated to. determine-f the level of investigation required. These; evaluations and investigations are? conducted-in'accordance with q approved procedures.. The-depth of the investigation' H depends upon the severity of'the incident-'in' terms of' the levels of uranium released'and/or-the degree of potential for exposure of workers ~or the public. 2.10 ' RECORDS i Records appropriate to criticality and radiation safety-activities, occupational' exposure of' personnel.to-q n Q ~ ~ . LICENSE-SNM-1097.- DATE: 10/23/87' Page i 00CKET' 70-1113- ., REVISION 18. I-2.21-J i i i ___.____ __i. i _

O TABLE 2c1 "/ -s INCIDENT CLASSIFICATIONS CATEGORY CLASS I CLASS II CLASS III ONSITE Evidence of apparent Evidence of apparent o Death or disabling-PERSONNEL. exposure less than exposure less than injury as defined f INJURY OR the regulatory five times the under appropriate EXPOSURE limits but greater. regulatory limit but OSHA regulations. than or equal to the greater than.the administrative regulatory limits o Evidence of guides (internal or (interna 1 or apparent exposure external) external) ir excess of or equal to five times the regulatory limit 1 (internal or j external) { PROPERTY Damage or loss less Damage or loss ) DAMAGE than $200,000 but greater than or i greater.than or equal to $200,000 -) equal to $50,000 1 VIOLATIONS OF LICENSE OR REGULATORY n LIMITS: i) o Effluent Uranium Uranium Uranium J concentra-concentration less concentration less concentration tion than permit criteria than 10 times permit greater than or j limit for and regulatory criteria but greater equal to 10 times l liquid, or limits, but greater than or equal to permit criteria for i airborne than or equal to permit criteria for all three categories ) o In-plant administrative all three categories and in excess of airborne guide and in excess of 500 5,000 times the o Contamina-times t.n+. regulatory regulatory limit tion limit release both inside and outside of controlled j area SHIPPING & Damage to container Shipment received Breach of container RECEIVING in excess of externally in-transit offsite of container)grity (loss of inte administrative contaminated in guides with no loss excess of license or of container regulatory limits. integrity. ,r % - \\,j LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-2,22

i 1 i c n i j radiation, releases of radioactive materials to the. v environment, and other pertinent activities, are maintained in such a manner as to demonstrate compliance 4 with Commission license conditions and regulations. l Records lof criticality safety analyses are maintained in-l sufficient detail and form to permit independent review and audit of the. method of' calculation and results. Such records are retained'during.the conduct of the activity and for six months 1following-cessation of such' activities to'which they apply. (Two years minimum.) Records associated with personnel. radiation exposures j are generated and retained in such a manner as to comply j with the relevant requirements of 10 CFR 20. The following additional radiation protection records will j be maintained for at.least two. years. /S l (_/ ~ Records of safety review committee meetings, 1 Survey of equipment for release to unrestricted-

areas, i

Instrument calibration, i i Safety audits, Training'and retraining, Radiation work permits, /% V LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 .I-2'.23 i w_m____m

n .e., m l + r ih -Surface.contaminationLsurveys, ~ + 3 Concentrations of airborne ridioachiveLmaterial.in theifacility,- ' Radiological. safety analyses'~, All'recordsfassociated-withlthe environmental; protection. activicies:' described inichapter 5 are'. generated..andi [ retained'inisuch.a manner as to comply:with;the1 relevant: requirements of?10-CFR.'20:and thisllicense..- W =1 1 P 'ia 's J, .oj .\\ 10 d) d i I i -j t I

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-l /^; y 10/23/87-Page. j LICENSE-SNM-1097 DATE DOCKET: 70-1113

REVISIONi 18'

I-2.24

j p

-m (_) CHAPTER 3 RADIATION PROTECTION 3.1 ADMINISTRATIVE REQUIREMENTS-i ? 1 (RWP) Procedures. 3.1.1 Radiation Work Permit 3 Routine and repetitive maintenance work performed'in j radiation controlled areas is administered by.the use of standard procedures. Non-routine activities,- particularly those performed by non-GE employees (e.g., a contractor personnel), which general'ly are not covered by documented procedures, are administered by the RWP - system. This includes facility construction, l maintenance, and service work (e.g., equipment. relocation, floor tile replacement, ventilation duct i r"T l (,) removal, etc.). J Radiation Work Permits are issued for non-routine l i operations which are not. covered'by an operating procedure'and where the radioactivity levels are likely ] to exceed the limits specified in 10 CFR 20. The RWP specifies the necessary radiation safety controls, as appropriate, including personnel monitoring devices, protective clothing, respiratory protective equipment, special air sampling, and additional precautionary measures to be taken. ? The manager or his delegate responsible for performance of the'non routine work is responsible for obtaining the RWP from the radiation protection function and'for nV LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 i I-3.1 i L _ _ m_ __m._

I i l ' _) obtaining RWP approvals by.the-manager or a supervisors l ( of the radiation protection function, the Area Manager or his delegate and by the; requestor. He;is also _i t responsible for assuring that only personnel.who have l completed required. radiation safety training are assigned to perform work under a RWP. i A copy of the RWP listing any apecific radiation safety y i d precautions is posted in a conspicuous. location throughout the duration of the activity, and work is monitored by the radiation protection function, as required. All RWPs have expiration dates and the status of issued-RWPs is reviewed on a weekly: basis'by the radiation-j 1 protection function. /"N ] (_) Upon completion of'the work under the RWP, the ] requestor is responsible to assure that the RW'P is: l terminated and that the work area is returned to normal j I conditions. f I Responsibilities and elements of the RWP. system are i j documented in the department Practices and Procedures (P/P) system. 1 l 3.1.2 ALARA Program GE-Wilmington has established a' radiation. protection-program designed to' ensure that occupational radiation j exposures are maintained at levels as low as reasonably-i achievable. The approach consists of (1). a strong } q a <s b LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.2 ]o

r ' management commitment,L(2) development-and implementa-

tion of improved detection / measurement capabilities,1(3)l j

development of advanced exposure-related management: information systems, andc(4) provisionLin, facilities,for exposure. reduction'via implementation of well-. engineered systems.

l

3. l. 2. 1' Management Commitment.

j The GE-Wilmington' management commitmentito the ALARA concept is emphasized inJdepartmental level P/Ps;and'-is evidenced.in continued support'of long range development-programs and near-term improvement projects. ..In-addition,' implementing instructions to the: operating.and' engineering personnel stress the importance of g continuous effective exposure control. l () 1 3.1.2.2 Detection ~and Measurement Systems-j. Health physics detection and measurementLsystems, some y computer based, provi~de the. capability'to-determiner l airborne concentrations, internal. exposures, extremity. exposures, external exposures, Water concentrations and criticality detection, f 3.1.2.3 Information Systems A major program has been developed for: an1 advanced, .i l computer-based management' system to calculate, monitor and record personnel radiological exposures. Relevant; data (i.e., demographic, time-in-area, air sample-results, etc.) are entered into the system and provide l' i D 1O LICENSE $NM-1097. DATE 10/23/87 Page. DOCKET 70-1113 REVISION 18 ' I-3.3

--m-, ,o i ): managementiwithinear.real-time'informationion employee; j ] exposure. Data analysis-_ capability built intolthe system'.provides1 ~ accurate?informationDfor management (planning ofjthe' continued :employeel exposure. reductions. o / 3.'1.2.4 - Major Facility'& Equipment' Changes. 1 [ 0 Management attention is.addressedEto: identifying < o operating conditions.which' require modification for - reduced. personnel exposure. Major ; facility ' changes and: equipment process development programsLmeetJcriteriai directed.towards exposure reduction and/or 1mproved shop ~ l conditions. Project safety 3 reviews'are heldfto assure' that ALARA has been addressed in proposed. project-designs. l i l ("% l l s_/- ~ Current shop conditions are monitored;to identify;needed. q ) ) near-term upgrades in process equipment', equipmentu q accessories and operating systems which, when' U implemented, will result in; reduced; potential for occupational radiation. exposures. R 3.2 TECHNICAL' REQUIREMENTS 3.2.1 Access Control Controlled areas in the fuelcmanufacturing building are: as demonstrated in Chapter 10. Access points to [ controlled areas are established through change. rooms. l i } r-1 . U LICENSE SNM-1097 DATE 10/23/87 Page-00CKET' 70-1113' REVISION 18: I-3.41 a tr y l

i l i i () Each change-room includes a'" hot" side and.a1" cold" side, with a step-off area provided between the hot and cold sides. I The personal clothing and other worker belongings are { stored on the cold side in the change. rooms.. Clean -l protective clothing (described.in Section 3.2.4/4)fis { made available on the cold side to personnel entering a { l controlled area. Used protective clothing is stored on j the hot side and collected there for processing through i the laundry facility. Disposable protective clothing is used, where applicable, k l Entry points to' controlled areas are posted *in i l accordance with 10 CFR 20.203. Instructions controlling entry and exit from controlled areas are posted at the entry points..Special instructions regarding. reporting-(~') time in the controlled areas, personnel dosimetry j %/ ~ badges, protective clothing,' personnel surveys and j emergency evacuation, etc., may also be posted as necessary. 1 Personnel survey meters are provided in the step-off area of each change room for use by personnel leaving l the controlled areas. Posted instructions address the use of the survey meters and appropriate decontamination methods. Notification instructions regarding contamination detected during the exit survey are also included. Personnel are instructed to notify the radiation protection function before performing decontamination activities if they detect any contamination on their face, or if the prescribed /~; s LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.5

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l decontamination routinesf(Section 3;2.4.7)fdo'not:,removei Jl G,

i the contamination :on.'other parts :of their lbody. .(This? 1 f ! requirement became-effective November;10: 1984.)- .j 3 1 n n d Personnel-auttiorizedtoentercontrolledhareasiare i issued'a coded badge)which'denotesTcomp1'etioniof properg M radiation protection"traihing.. Otherfpersonnel.(must be! g escortedTby an authorized: person when1 entering"the -R controlled' areas. j 1 3.2.2 Ventilation' Require ents j ij 3.2.2.1 Inter-area' Air Flow: Design l Ventilation-: equipment is' designed to provide' air? flow-d -) from-areas ofl lesser potential. contaminate'n'to' areas;of .] o l higher potential contamination. Specific facilities and J () capabilities of ventilationisystems?are.fdetailed:1ni j Table 3.1. Direction of air flow in the work: area.is checked. monthly. y 3.2.2.2 Enclosures Containment designs for fuel. manufacturing' areas include. hoods, and other special, enclosures as applicable to contain airborne uranium and~thereby minimize personnel exposures. Other equipment in which processing operations' generate' airborne uranium'is. designed with filteredienclosures,. .i i b LICENSE SNM-1097 DATE .:10/23/87 Page DOCKET 70-1113" REVISION' 18 I-3.6' l 1

t G TABLE 3.1 -N d' SPECIFIC FACILITIES & CAPABILITIES OF VENTILATION SYSTEMS. t -j Alarms. Interlocks &' Facility-Safety Featurns Purpose Hoods Air flow during cperation Prevents spread of 1 > 80 lineal feet per minute-radioactive materials # rom j work area to immediate room j area Fire extinguishers in work Provides fire prevention ) area Effluent air filtered with Prevents release of 3 d HEPA filters radioactive materials to environs i High Velocity Air flow designated to Prevents spread of radio ' i Local Exhaust maintain an average of 200 active materials from work lineal feet per minute area to immediate room area Sintering Automatic hydrogen shutoff . Protects against hydrogen Furnaces and switch over to nitrogen explosion and resultant i with alarm signal spread of contamination as I well as physical injury to room occupants ,i UF, Temperature controller and Controls temperature to not vaporization alarm exceed 300' F, which.is 40F Chambers below the temperature at which unsafe cylinder pressure might be generated Ventilation enclosure Provides containment in event of cylinder. rupture or abnormal leakage Recirculating Air flow designed to provide Provides' cleanup of air Air Systems a minimum of eight (8) room within rooms & Exhaust air changes per hour Air Systems Air filte' red in potentially Removes essentially all contaminated zones with HEPA contaminants from room and filters or water scrubbers exhaust to environs i G- %J LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.7

/~e TABLE 3.1 { A/ (continued) Alarms, Interlocks & 1 Facility Safety Features Purpose t Recirculating Pressure drop indicator set Maintains adequate j Air Systems to alarm at > 4" H 0 A P circulation for removal of 3 & Exhaust across final filter dust and contaminants from j Air Systems the room air J (continued) Effluent air filtered with Prevents release of radio-HEPA filters active materials in environs l q l 1 1 i i <~ x j (.) 4 .1 l l l

J LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.8

I) aust ports and other devices hoods, dust-capturt J rs which maintain air coc> 4trations of radioactivity 'in work' areas-below.10 >.20 limits under normal and J foreseeable abnormal operating. conditions. Air flow through openings:in these containment devices is-measured monthly,Lat a minimum,,to assure adequate system performance as necessary for protection of' 1 4 personnel. When air _ flow through any point of.the j opening approaches'the minimum requirement of.80 LFPM, i action is instituted to correct'the problem. j Additionally, there are differential pressure indicators j i across exhaust systen. filters to assure system performance, l When a differential pressure is observed to have reached four inches of water, the effectiveness'of>the filter is j s (- - [) ~ differential pressure, the filters are changed when they I investigated. Notwithstanding the monthly-checks of l are unable to all'ow the airflow necessary for the system which they are designed to serve. 3.2.2.3 Effluent Air Duct Design 1j i Effluent air ducts and air flow velocities are designed to minimize radioactive dust accumulations. 3.2.2.4 Exhaust System Exhaust systems in potentially contaminated airborne effluents are equipped with filter media which are selected to maintain its integrity when subjected to 1 1 (Y L' LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18' I-3.9 l -_---_a-__-

i 1 l 1 . g). chemicals, sol' vents andc abnormal operations of the~ (, Theseifilters are at least 99.97% eff'icient { processes. for removal of 0.3 micron particles. All HEPA filters (both' primary and secondary) in the exhaust system are' f equipped:with'a device for measuring differential-pressure. Filter effectiveness'is investigated when the pressure-differential across the filter exceeds four. inches of water. A filter is replaced following. evidence of the inability of the filter or the exhaust system to perform its function properly. In no case will filters be operated at A P values which exceed the manufacturer's ratings for the filter. ] I Water scrubbers or other appropriate devices are provided where necessary to treat effluents before () filtration. Such scrubbers are installed so that effectiveness of filters is maintained. ] 3.2.2.5 Air Recirculation Room air may be recirculated within the uranium processing areas after being filtered. 1 3.2.3 Instrumentation 3.2.3.1 ' General Appropriate radiation detection instruments are I available to ensure adequate radiation surveillance can be accomplished. Selection-criteria of portable.and' ^ (G LICENSE SNM-1097 DATE 10/23/87 Page DOCKET '70-1113 REVISION' 18 I-3.10

m 'c _ T; 3.~ 9 e f 's .j t at, i' 1 1 .c

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J f. j_. s{ l t' laboratory) counting.egu'ipment?is L ba'sdd [oni they typesidff 'T radiations dete'etede'maihtehance. requirements;;,m .,/',M m p)

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.e. 'su m. - .. t ruggedne ss, ' int erchangeability fand ' upper < andAlower \\] . 2 .9, l limits of. detection" capabilities!. .The" radiation safety,3;g p y function. annually reviewsLthe appropriateness of$ bha M 7, . ;;,4 y+ ni . 8: n. s.. '~ types of instruments being..used for'each4 monitoring: l y o.; R function. n ,4

• 7[.3 3.2.3'.2 Equipment' Description' 4

a m .c n Table.3.2. lists examples of;the. types.and usescofi 1 available instrumentation'. 3.2.3.3 Calibration ] Monitoring. instruments utilized for radiation safety. ,l ' o purposes are calibrated.betore ihitial;usei Jafterdmajorv h maintenance,. and on'a routine:basisL,at least six.monthsc ~ following the'last calibration. Such' calibration ? consists:of (but is not~limitedito) a.performancescheck on each range. scale of'the instrument withia.radioac'tivel source of known activ$ty.' Prior to each use, operability checks,are: performed on' monitoring and laboratory countingxinstruments utilizedi R for radiation safety purposes. ] J The background and efficiency of laboratory counting- -) instruments are determined on.a daily basisgduring; periods when the equipment is in use. Efficiency is: d determined using; radioactive: sources of knownLactivity.: ? ? ,,e ~~ LICENSE SNM-1097 DATE. 10/23/87 Page j DOCKET- '70-1113' REVISION 18 I-3.11- ~ S

~ TABLE 3.2 (S_./ TYPES & USES OF AVAILABLE INSTRUMENTATION (TYPICAL) _ Type Typical Range Routine Use DOSE RATE METERS CM Low Range O 01 mR - Area Dose Rate Survey, 2000 mR Shipment Survey GM High Range 0.1 mR - Emergency Monitoring 1000 R Ion Chamber - Low Range 0.1 mR - Area Dose Rate Survey, 10 R Shipment Survey Ion Chamber - High Range 1 mR - Emergency Monitoring ) 1000 R t ALPHA SURVEY METERS 50 cpm - Direct Personnel & 2 x 105 cpm Equipment Surveys l NEUTRON METERS 0.5 mR - 5 R Special Dose. Rate Surveys LABORATORY INSTRUMENTATION ( Multichannel analyzer N/A Lab Analysis Automatic air sample counter N/A Lab Analysis i Windowless gas-flow N/A Lab Analysis f proportional counter i Fixed geometry Geiger-Mueller N/A Lab Analysis { j counter I Sodium iodide well Counter N/A Lab Analysis { Phoswich detectors N/A Lab Analysis ) Beta surface barrier N/A Lab Analysis ] detectors i t Scintillation Counter (MS-3 N/A Lab Analysis with Detector RD-14) In Vivo Lung Counter N/A Lung Deposition Measurements ,i l i l \\ / LICENSE SNM-1097 DATE 10/23/87 'Page DOCKET 70-1113 REVISION 18 I-3.12 1 l l I - - _o

7 ll - yg 7: g., q ( ,1 e ~ -o . nc A'i . g.- i -8 i t j ,.; } t 1 ; -J a t a ,Y_l.1 :< ~ s i .), ' t) : }; 8 t s. f y 7 ,o 3.2'.'3.4 !Critica'lity' Detection&' Evacuation

• Alarm System?

,j. 1 Yl, 9 A iAfcriticalityfalarmisystem.is'provided)that' conforms,tof g-thefrequirements-ofi10 CFRi70.24.1 j ~ , m p' 4 .e il 3 'A: predetermine,d-' alarm point;not to exceediS0Tmr/hrfabo,e3 .J v . background,is,programmedffor-leachidetector..The. u m.. evacuation: alarm ~ logic;:l1s satis' tied when'two.orlmore.- M detectors.in the sameiarea: exceed'theihlgh7AlarmJset!D . p; t s . point or'if-one detector isLin-thel-failsstatus1and! r w another in the'same'~arealexceeds.the',high al'armiset: j ~ point. / i The' evacuation al. arm system meets the guidan'ce-7 established'in. ANSI 8 '.-3--1979, " Criticality TAccident L Alarm. System". T. d il O 3.2.4 1nterne1 e externe 1 z>moeure 1 i 3.2.4.1 Ventilation and Containment 4 ,1 M ~ The, internal radiationiexposureof. workers is controlled! [ primarily by the ventilation. systems.and-the' containment;. ~ of uranium within process. equipment. 'Within work. areas j uranium liquids or powders :are L haridled by: workers in' such a manner that reduces the potential for airbornet contamination. 1 .i 4 The ventilation systems for the fuel manufacturing. f* building are designed to maintain.a conditioned air: supply and to exhaust potentially contaminated. air' 3, through appropriate filt'ering or washing devlces. Under 1 O J LICENSE SNM-1097 DATE 10/23/87. Page-d DOCKET 70-1113 REVISION 18 I-3'.~13 t. Ej v/'; r_ (J

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. y (3 normal'operatingdesignprocess(co'nditions{fpersonnel ,d ~ ~ will.noc require: respiratory. protective? equipment'. i - .7 ' TheLfollowingLdesignic' considerations are" implemented ath GE-Wilmington to.reduceiinternaldradiation',' exposure'sifori d 1 4 controlled area personneljwi6hiregard toLthe'hentilationT and' containment' systems: ..s r o a g ')'- ,k b s ,j LThe primary; barrier-ofJcontainment for.the radioactive materiallis'the process; equipment..andi is designed to'contain~potentially dangerous. y substances -during? norma 1 operatiions. ~ -] Secondary containment barrierssare used to. , c: supplement.the.. primary process barriers.: iThesel di include. hoods or other similaridevices to control 4 . airborne - contamination:if" the ' process (f ails' toi d

]

O .t> coateia cue eterie1. 3-m 3y These containment: systems:shall be' designed to: Oi dy minimize the.need for' direct.contactJof contaminate'd radioactive _ materials;by the j operator. d b The design philosophy'oflprimary and' secondary. containment systems shall..be 'to prevent: the. release of uranium contamination:to work areas;during L planned operations:and-'to minimize lit'during.' ] anticipated accident. conditions'. l The process area' atmospheric; pressure shall'be' 1 q negative relative to the outside. 1 f) 1 Q LICENSE. SNM-1097 DATE 10/23/87 Page T -3."144 l 4 DOCKET 70-1113 REVISION. J 18' I i d b. f I'

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• D

- The. exhaust equipment:is3 designed to;proVids;airi jy 2 . flow.fr'om areas of lesser. contamination potential: I ' to areas of'high'er/ contamination potentiali;to. confine and containEair_streamsTcontaining radioactive constituents 4 and to minimize ~the: - potential.accumulationfof contamination ~;within?the j 4 air. handling ductwork.. 3.4.4.2 Air Sampling s Analysls 1..?.4.2.1' Routine Air Sampling in the'Controll'ed Area: Air samples are continuously taken"fromieach processa n area Wnere. licensed' materia 1'~isLb'eing handled'in ~ dispersible form in' order to assess the. concentrations; of uranium in air. The air samplesLare collected"in' such a way that the concentrations of uranium'are . O representative of the eir:1n :which worxere ere exposed. Filters from air samplers are changed'eachLshift'during- . normal operating' periods or.at'more frequent intervals. dollowing the detection of anLevent'that may haveL released airborne uranium,obasedJupon. knowledge of the. o y q particular' circumstances. ' Consideration'is given to ] running samplers over. weekends when:no work.isJin 1 progress or to changing-part.of the= samplers each: day of: the weekend. The filters are processed through: 1 1 laboratory counting' equipment to determine the dranium' j concentration in air.for each-area. 1 1 A concentration indicated by an' air sampler which 'I exceeds 1 x 10-to pCi/cc, not directly attributable.hto,a q i -\\ ) SNM-1097 DATE: 10/23/87 Page j LICENSE DOCKET 70-1113 REVISION

18 I-3.15' l

l '.j

( I L () known cause, is investigated'to determine the probable Appropriate corrective actions are implemented cause. and documented based on the frequency-and magnitude of events causing releases of airborne uranium which noticeably perturb.the weekly average airborne concentrations typical'of the area. 1 1 t Each air sampler is equipped.with a rotameter to j indicate flow rate of air sampled. These rotameters.are calibrated or replaced at least every 18 months. j 1 4 The routine survey data and individual personnel exposure assignments are monitored by the radI1ation safety function to evaluate the effectiveness of the j i radiation controlu of personnel exposure, I J The radiation safety function annually evaluates fixed. j () filter sampling points for representativenesr of ~ personnel exposures and as!a p' art of.each radiation safety function review for all' licensed' process or ( equipment changes. j l 3.2.4.2.2 Special Air Sampling The routine radiation air sampling program is i supplemented with backup portable air sample surveys as required to evaluate operational trends or to evaluate breaches in containment. Special surveys of airborne i concentrations may be conducted for non-routine maintenance and, based on these special' surveys, additional radiation protection requirements for-the particular operation may be established. Typical of 1 i 4 ? r,U LICENSE SNM-1097 DATE 10/23/87, Page c a DOCKET 70-1113 REVISION 18 I-3.16 1 j s s

7 .theselspecial operations.arel burning,. welding',TandL> '~ 4 E cutting _ operations'which mayJresultLinLincreased' airborneLeoncentrations. ..e 13.2.4.3 -Internal-Exposure Measurements' 3.2.4.3.1. Airborne: Exposure Assignment:&' Control Indiv1 dual airborneLexposure assignments;are made based? on-airborne concentrations in'the.areasDinlwhich the i individual' worked and the' time the individual spentjini LInterna11 con'ro11 action's are providedito t c each area. prevent.an individual.from exceeding'the weekly'40fhour control measure specified in 10 CFR120. : Control' actions ~ ~ include restrictingfthe individual from working infan ~ area'containing airborneLradioactivityifor the remainder of that work week.and actions areitaken;asenecessary to. e () assure against' recurrence. 3.2.4.3.2 Bioassay Program-4, Weekly and daily routine.urineLsamplingufrequencies~are established for all individuals assignedEto7 work _in areas where. soluble (Class D)f uranium: compounds are. processed. These areas include; portions'of1the chemical-conversion and Chemet. lab areas. -Thesbioassay sampling-program is conducted to reflect the'ap'plicable guidelines outlined in. Regulatory. Guide 8.11, June'1974; ] WASH-1251, " Application of ' Bioassay for. Uranium"J,- June' 1 1974; and Draft ANSI Guide N341, " Internal' Dosimetry. j Standards for Uranium", July 1974. q l _ p). . 1 54 ' LICENSE-SNM-1097 ~DATE 10/23/87' Page ' j DOCKET 70-1113 REVISION 18 .I-3.17_ 'l c

]

.x s;s + m l-i< 7-m ,2 er> 1 -[ i p i - -n t 1 y :g 1 s ,1 -e q. ActionIlevelsiand. actions based'.on sampiingjfrequencyl ~ U a' +- are:as follows- ' Sample ~ Action-Level' iketion Daily 135 pg;U/ liter'

Investigated.,

f & back-calculate'- 1., uptake Weekly 1115 pg:U/literi fInvest.igate ~ !&'back-calculate' y uptake; y,- J The _. investigation includes. calculating Ltih'e maxiinum potential uptake basedLon--the lapseditime from the' previous stanple..If theLindividual;ma[ havel: received (an? 4 e .m . uptake of greater than s2. 5lin1111 grams.'.uraniumf the. I individual is immediately restricted from further: y exposures to-soluble' uranium. ~ Re -entry is ? authorized 2

1 when a urinalysis result.isJ<15 cpg?.' uranium per' liter.-

d

O For non-routine operations, perturbations',yor anL incident where it' is: suspect ed thatJsoluble materials ^

l 'may<have:been-ingested,;the; radiation' safety or-l ,g 1 radiation protection functionsLmay request additional 3 bioassay sampling. 3 1 3.2.4.3.3 In Vivo Lung counting ~ m 11 In vivo lung counting is provided for the timely! y y detection and assessment of individual intakes;of.. h

j radioactivity and as a method' t o verifyf thel adequacy of the air sample program'.

(a 'd A

y

,D. d] p LICENSE SNM-1097' DATE. 10/23/87. . Page. DOCKET '70-1113 REVISION- .18 LI-3.18-1 X ' 'y I > l l. L:_. _ _ _ .M :

p-y j y j Rou' tine in Vivo lungLcounting:.-frequencies arei l I j establish'ed fore 1'ndividuals : who normally1workL in f are'as J F 1 whereJnon-transportable uranium:compoundslare' processed. Individuals.'are scheduled. for. :in. vivo lung: counting based.upon'their. airborne exposure; assignments and x previous counting!results as follows: . Previous. ~In Vivo-Count Count Assigned Airborne Exposure Result': . Frequency. Annually > 1.3 MPC hours / quarter 1 52.MPC hours / quarter or > MDL' ' Monthly ' Quarterly. .{150pgU285: > :40 MPC hours / week or ASAP

• 1 520 MPC. hours / quarter.

I

• ASAP means that'the individual is' restricted.from-n,V working an area containing' airborne < radioactivity until-counted.

Appropriate actions areitaken based upon in vivo' lung: counting results to ensure =the. maximum permissible.. lung burden will'not be' exceeded. If an: individual's lung-j burden'is indicated.to be' greater thanT250:pg U885, the

}

individual is temporarily restricted-from working:in-y areas containing airborne radioactive' material. 3.2.4.4 Protective Clothing ] Protective clothing is provided.to all persons who'are required to enter radiation controlled areascwhere' personnel contamination potential' exists-as determined. .4 .l . ll l rd j; LICENSE SNM-1097

DATE, 10/23/87.'

.Page: .j i DOCKET 70-1113 REVISION .18l "I-3.19 q j ~ w g

mi) by the radiation safety function. The amount and type. s of protective clothing required for a specific areaLor l 1 operation is determined by operational experience and the contamination potential. Available clothing includes caps, hoods, laboratory coats', coveralls . safety glasses,' boots, overshoes,. shoe' covers, rubber and cloth gloves, safety shoes, and. respiratory protection equipment-The minimum clothing requirement for controlled area entry is as follows: 1 Managers, Supervisors, Inspectors and Visitors Controlled Area Workers Only Observing Operations l Shoe covers or controlled Shoe. covers 1 area work shoes I i Covera 11s Laboratcry coats n \\ k,) Head covers Head covers ~ j Rubber gloves Rubber gloves (as appropriate). Safety glasses Safety glasses The protective clothing is' removed upon exit in the 1 controlled area cliange rooms. j In a few areas such as the Chemet. Laboratory, personnel contamination is controlled by exit monitoring. The q minimum clothing requirement for entry into these areas j is a laboratory coat and safety glasses. f (x l V LICENSE. SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.20 1

m i -4L [ ? .i h._ "3.2.'.4.5 Respiratory Protectioni rogramL P ,1 The respiratory protection program:shall be conducted in" 1 ~ a 'accordance,with thelapplicable portions.of 10 CFR 20/ ~*' j m l 1 3.2,'4.-5.1 Respiratory Protection Equipment q Respiratory protection equipment.specifically-approved; j by the: National Institute for Occupational Safety and; # Health (NIOSH) is. utilized. - Two'typesLofJrespirators. are commonly available - half masks and full'. face .j ~ .q masks. -q '] Half' mask respirators equipped-with particulate Niltersi () are utilized as a precautionary measure'during, routine- !f operations which may~ generate : uranium : dusts. -Noi

• M protection factor'is taken for: half mask usage;:unles's"

...N 'l O meexe ere fitted in eccordence w1th'10.CFa:20. a Full face mask respirators, aquipped with5an applicable; canister, are utilized.as precautionary measures in routine and-for emergency actions?which may requir'e additional protection' capabilities when,there exists;a potential for release's of solubleLuranlum} gases ( LA' protection factor of SO 'is :taken for-this. type of respirator usage'. j NIOSH-approved' continuous flow' airline. supplied hoods-A and full face piece respirators, and.self-containedi, breathing devices-are also available for-certain ) operations. Respiratory protection: equipment 1ofithese( 'J r. H g q.l 1 5l.! b SNM-10971 .DATE-10/23/87.' .Page'. 'd m LICENSE DOCKET 70-1113 REVISION 18 LI-3121i o q s o I,, ,~ v m,y _____.=_m 1 _x-- _a

g.

e

...f t 4 ^- ' d;h? pf .M l n-a .i { e .1, cf'. ..o 1 9 l types.are!operatingfinfaccordance with?10: CPR~20'and-a specified protection 1 factors are utilized. gf, } 3.2.4.5 2. Employee-Qualifications p~ j 9 n Employee'anagersiannually-review andsspecify:those. <f m individuals-for:whomtrespiratory prptect' ion devices may 'd /- be required. Each de'signated employee?s medicalf' status ' ,j ) is, initially'determinedandreNewed; annually?by?.the.. 'l medical: function tordetermine..if thereJare. medical -restriction's which may prohibit-an-individual':'fhom using,, 'd <) a respiratory protectionjdev' ice. 'If thet.individusi hasl4 g l no restrictions, he isLprovidedtrespiratoryLtrainingiand ' fitting by a qualified instructor. Additionalvtrainingj 1 on the use and limitations of.self-contained breathing 1 devices'is provided to' designated respifator ussrss f3 .V An. adequate mask [fiC in determined usingLqualitativel ~ (irritant smoke) methods. Mask' fits determine'dNy. y qualitative methods are re-evaluatect annually;( mask: fits 1 determined by. quantitative methods are're-evaluat'ed biennually. Quantitative resultsLmay/be, substituted for j i qualitative. Respiratorequalificationirecords areL g maintained on s,ach individual'as a part ofithe I J i.- employee's personnel' exposure' file.- q Reports showing the status'of qualified' individuals are i routinely sent to the appropriate managers for~ review. [ a i' ) .\\ 1 j } f3 _La 1 v-4 LICENSE >SNM-1097 .L DATEJ 10/23/07 Page" q DOCKEi 7.C4113 REVISIONT 18' ?I-3.22(- ik l aj c y a )! ! 7:, ',['. y' j ).' ) .N,Y [

3.2.4.5.3 Testing and Cleaning of Equipment i a Each respirator is processed for cleaning, inspection,- and replacement of parts ab'necessary. Air purifying i cartridges and canisters are challenge atmosphere l penetration and differential pressure tested against parameters according to internal procedures. The respirator and canister assembly is challenge atmosphere tested and pressure tested prior to reuse. New respirators and canisters are similarly tested on'a j quality control basis. Self-contained breathing devices are inspected for 't i operational capability and are cleaned and re-inspected after e6ch use. I 3.2.4.6 Surface contamination Monitoring l g v Routine contamination survey monitoring is perfonned for j all uranium process and manufacturing areas including i t non-controlled areas such as hallways and lunch rooms immediately adjacent to controlled areas. The type of j monitoring includes direct and removable contamination j measurements based on the potential for contamination in these areas and operational experience. Survey frequencies are determined by the radiation safety function. The minimum survey frequencies are as follows: LICENSE SNH-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.23 a

., ' m... + 39 (. -,, ,c.. - 9..,,. j '/ } 41 d, 4., n c .j i l.) i a, i. ' .i 4 A yy &w u, u. p' ty ~.} j w p ;_ m .a,._, .].lj. - j

q

-

,,g l .g,, , f, i.f ,M s 1 r < y;~y 3 y< ' 91 . s on m n D w m + ,, i e '~ ,,s g,, .,o . ; t,. .c s. g,,; m-3g u,.7 ,. 9 p,. qq p' ' my i em

<>s,

..u* y {9 f-w 7 -] Frequency Q. ,*y O Area;

f.

, ',J;p , s p -l (y r n

Weekly,

~ ,,'x: Contro11ed' Areas- >+ f G,rsh& % j; Ik Receihing,Ltoraged{ Nipping! ~ S s EatingAheas(UsediPrimarily'by %.sWeekly'y W. u, ipontrolled Areal. Personnel? ' d

[

y j;q 3 i n 2 j '1 lMon': ply - - g Une: int, rolled? Areas - ^ m y 7 s' 1, .....a ..e surveyiresults:are~compareditoTactiopguidel,valuesbass \\/.' n specifiedlin internal,proegduresLand(appropriate' i f, *j y.e 6, p' 3' LresponsesLareitaken: 4 7 ActIonLimits. Q: j/ p \\p y ..n. A y Jpl %r / 3 N7 - -

4,., I,.4 g ' "u \\

L for Removable Surface ContAmdiation : .:t' ff dpm a/100 cmr W H ,.) Contro11'ed' Areas (Floors)' !15,000 c,, j x m -v Lab Controlled: Areas: 11,000 q i .i Uncontrolled Areas 1 220 1 J i Controlled' Area Clothing-

11,000 Persbnal' Clothing'(worn outside1 D'

Leontrolled areas) E.220+ .y Skin Non-detectible' iH Hi Innocase.shallthe_ delay'to: initiate'decontaminatic)n ( actions exceed 24Ehours. a i! l .1 Personnel contamination-surveys for externa 1Y7 ,] 3 l contamination'on clothing'and the body:arefrequiYed by' i all'. personnel whenileaving thelcontrolledl area.,T y. l ~ 'V_ r I e l. 'f' y 3s'.. _j

e

.j-y .,. e,, - f, .f): 'i ,i K~ i. s. . LICENSE -SNM-1097 , DATE 10/23/87 7 - Pagp.. 00CKET: 1113 - REVISION 18 - I-3.24 ,i a, r }- 2 ,,Ih' ( 4

f 1

1. %.()

3.2.4.7

Decontamination.

Self-monitoring is required upon. exit from the j controlled areas (see Section 3.2.1). IfLeontamination. 1 is found in excess of background levels, the individual-attempts self-decontamination at the facilities provided in.the change rooms. If decontamination attempts are not successful, decontam1 nation assistance will be I provided by.the radiation protection. function. If skin or personal clothing is still found' contaminated above background levels, the individual may not leave the area without. prior" approval of the radiation protection function. Personnel contamination 1 accompanied'by potential chemical injury is treated by the site medical i 1 department. The radiation safety function reviews the I () contamination levels with medical and makes determination for bioassay or in vivo counting to j further assess potential' internal exposures, l 3.2.4.8 Emergency Evacuation All personnel working in the fuel manufacturing i l operations are instructed to immediately evacuate the area in the event the criticality warning system alarm j is activated. Personnel are instructed to leave'their work stations and proceed as rapidly as possible along predetermined routes to the designated staging areas. l Persont.1 from controlled' areas, who may be l contaminated, are segregated'from non-contaminated personnel upon arrival at the staging area. p i LICENSE SNM-1097 '0 ATE 10/23/87 Page j DOCKET 70-1113 REVISION 18 I-3.25 j i J

) Emergency evacuation drills demonstrate that.the evacuation plan is effective. 3.2.4.9 Personnel Monitoring -- External Radiation Whole body or partial whole body exposure from external sources of radiation are. determined by individually assigned dosimeters. These personnel monitors are. scheduled for reading at least quarterly or sooner if 'there is an indication of an exposure in excess of established action guides. Action guides for external i exposures received on site are as follows: j - Action Wholebody 1 1 rem / quarter Restrict for-remainder of quarter [V3 Skin 1 6 rems / quarter Restrict for remainder of quarter Extremities 115 rems / quarter Restrict for remainder of quarter i In event of accidents or evaluation of unusual exposure 1 conditions, whole body or partial whole body exposures may be calculated by the radiation protection function on the basis of data obtained by investigation. l 1 Extremity exposures may be determined.and_ assigned on -] l the basis of engineering evaluations when TLD measurements are not practical. i l n(/ LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 i I-3.26 i

n______- i l ' t,) 3.2.4.10 Leak Testing of Plutonium _ Alpha Sources _ i The sources when not in use.shall be stored in a closed- 'j container adequately designed and' constructed to contain plutonium which might otherwise be. released during storage. At least once every three' months, the sources shall be f tested for loss of plutonium in.one of the following ways, using radiation detection instrumentation capable of detecting 0.005 pCi of alpha contamination: l By measurement of the source o'f potential' alpha contamination through surveys of the storage container and areas in which the source is used; or 3 i By wiping thoroughly the external surfaces of the s i j source mount, other than the radioactive surface of the source, with a piece of filter paper of'high wet strength and low porosite moistened with a solution which will not attack the mount and after the paper. is allowed to dry, measuri 1 the radioactivity on the paper. 1 If any survey or measurement performed as required by the preceding paragraph discloses the loss of more than 0.005 pCi of plutonium from the source, or if a source has been damaged or broken, the source shall be deemed to be losing plutonium. -The licensee shall'immediately withdraw it from use, and cause the source to be j 0 decontaminated and repaired, or disposed of in accordance with the Commission regulations. Within five ('>y l A-LICENSE SNM-1097 DATE 10/23/87

• Page j

DOCKET 1113 REVISION 18 I-3.27 { i

) (5) days after' determining that any'suurce has' lost plutoniva, a report shall'be filed with the Division'of Fuel Cycle and Material Safety, U. S..-Nuclear Regulatory Commission, Washington, D.,C.. 20555, describing the ') i source,.the test results, the extent of contamination j and the corrective action taken. A copy.of the report shall be sent to the Administrator,of the NRC Region II office. Records of test results shall be kept in units of I microcuries and maintained.for inspection by the t Commission. Notwithstanding the periodic test required above, any plutonium alpha source containing not more than 0.1 pCi of plutonium is exempted from the above requirements. OL) ) l 1 p) L LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-3.28

c: c .y ' j '.l: j: l-j. 4 I.' i'l ' ? ,i 1 =n .. /* CHAPTER 4-1* ' NUCLEAR CRITICALITY' SAFETY - 4 1 'I, Jl ) J-

Y

4. l'

. ADMINISTRATIVE REQUIREMENTS: W ' w T 4.1.1 Process / Facility Design Philosophy

c

't' I Process designs sliall in' corporate: suf fici'ent; factors of 4 -j y 1 safety.to require-at(least:two unlikely, Independent,. -andconcurrent!changestinprocessconditions!before!k: ~ ~ criticality accident 01s possible', i j The preferred methodffor"a'ssuringsnuclear. criticality. l safety in production' quantities of! fissile materialfis by the use'of safe. geometry. -However,t;other. controls" may.be used when' safe,geomet:ry isinot practical.-, For: example, batch control may be' used' in situations: I involving experimental quantd. ties'of material oflfrom 7'%- to 15% enrichment. (See. Table 4.4.): Fixed netitron absorbers.may.be -usedsas.part -of a safe j geometry'. Such use-is' preferred over;the.use.of administrative controls. i ] The use of administrative controls for nuclear-criticality safety willibe:: restricted'to those cases in-which safe geometry is?not practical.1 j 1 i ?l l {} LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18- 'I-411 .in f. 1 _

9 4.1.2 Requests for Nuclear Criticality Analyses e j The Area Manager assures that all changes, modifications or additions to the plant which have the potential to j affect criticality safety, are appropriately reviewed-and approved for criticality safety prior to implementation. If the Area Manager concludes that a proposed new activity or change in activity has the potential to affect. criticality safety, a request for a nuclear criticality analysis shall-be submitted in writing to the criticality safety function. After review of the ] request, a member of the criticality safety function having the qualifications of a senior member as described in Section 2.5.2.1, shall make the decision as to whether or not an analysis is required. s ( ) '~' If an analysis is required, the chenge shall not be placed into operation until the criticality safety analysis is complete and the concomitant nuclear l criticality safety requirements and approval for operation are received from the criticality safety i function. 4.1.3 Criticality Control Procedures Each Area Manager shall assure that criticality control procedures incorporating limitations established by the criticality safety function are developed and maintained and shall assure that foremen, operators and other / LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-4.2

f~'s concerned personnel are made aware of these procedures throuah posting, training programs or other appropriate '~ written notifications. 4.1.4 Posting of Nuclear Criticality Safety Limits Nuclear criticality safepy requirem,ents which are received from the criticality safety function for each j process system shall be available at each work station either in the form of operating procedures or as clear, 1 J visible signs or notices. Posted nuclear criticality safety requirements shall be i J defined by the criticality! safety function and may include: limits on material types and forms; allowable-quantities by weight or number; allowable enrichments; ] required spacings between units; control'11mits, when j (~') applicable, on quantities such as moderation, and j 1 (_/ density or the presence-of additives. ) 4.1.5 Labeling of Containers of Fissile Material i Containers of fissile material (not including fuel rods, { 4 shipping containers, waste boxes / drums, samples and the j like) shall be labeled such that the material type, U885 .i enrichment and gross and net weights can be clearly identified or determined. specified in theseLtables, smooth curve ~ interpolation'of, values may be.used, i .rn V-LICENSE-SNM-1097 DATE 10/23/87-Page DOCKET 70-1113 REVISION. 18 l I-4.5 y i -] 1 l l 1

l ( f. 4.2'.1.2 The safe batch values of Table 4.4.areDspecifically. licensed for use'in the Wilmington facility. 1 Criticality safety.may be based on U835 mass limits lin either of the following-ways: V 1 'If double-batching?is credible,,Ithe mass ofnanyf single' accumulation shall not1 exceed a safe'b'atch which is defined toebe 45%:of the minimum critical y1 Table 4.4 lists safe batch ' limits-'for - mass. homogeneous mixturesfof UO,z and water'asfa-function 1 of U285 enrichment 1over'the' range:of11.1% to 15.0%1 for uncontrolled ~ geometric configurations., Where engineeredLcontrols~ prevent'over batching,Ea-mass of 75% of a minimum critical-mass-shall not bel exceeded. O The. safe batch' sizes for UO,lof' specific enrichments set. forth in Table 4.4 shall be adjusted when applied to other' compounds by.the formula: i kgs UQ, x 88% = kg X x1f where f.=1% U in Compound-X-4.2.1.3 Subject to provision for adequate protection against ~ precipitation or other circumstances'which m.ay/ increase concentration, the following safe concentrations are: specifically licensed for use at.the Wilmington' -l facility. j .i l (#\\ LICENSE SNM-1097 DATE 10/23/87 -Page '~ DOCKET .70-1113 REVISION 18~ I-4.6 R ~~ l 1 11

j rX r TABLE 4.4 SAFE BATCH U MITS FOR'UO, & H,0 J (kgs UO ). 3 ~ Nominal' ' Nominal. ' U2 2 8., U2$5.. Enrich-- Enrich-UO, der *- - UO ment-UO;;.. .UO, ment i Pow ,Pe$kets5 w/o - Powder

• Pellets
• w/o-i 1.1 2629 510-4.0 '

25.7

24 7-1 4.2-23.7 J22.9 1.2 1391 341 1.3 833 246 24.4 21.9 21.4 1.4 583 193-4.6i 20.2' 20.' 0.

1.5 404-158 4.8' 19.1-18.8 1.6' 293.3 135 ~ 18.1. 18.11 1.7 ' 225. 0,- l116 5.0-1.8 183.0-102 -5.5 15.4" 15.4= 1.9 '150.6 90.5 6.0 113.8 : .13.8 '7.0-8.3~ ~8.3 2.0. 127.5 81.6. 8.0 L '6.9 -16.9 2.1. 109.2 73.1 .9.0-5.9 ~5.9. 2.2 96.8-66.4 2.3 84.3 61.0 10'

5. li

5.1:

O 2. 4~ -74.7 56.1

11,

' 4. 4 - . 4.'4 ' 1 2.5 68.9 52.1 .12 '3.91 3.9 j-2.6 60.5 48.8 13 3.5-13. 5 2.7 56.6 45.4 14 3.3 3.3 ) 2.8 52.2 42.9 15 '3.0' 3.0 'l 2.9 47.6 40.1-d

f 3.0 44.5 38.1 NOTE:.For enrichments'not;specified 1

3.2 38.9 34.1 in.this table,' smooth curve j 3.4 34.6 31.0 interpolation of safe! batch- ') 3.6 31.1 28.5 values-may be used. 3.8-28.3 26.4 L 2 Homogeneous mixtures 2 Heterogeneous mixtures-i Q LICENSE-SNM-1097 DATE 10/23/87 Page - I DOCKET 70-1113 REVISION 18 .I-4.*/; i k

7 .q

1 I

]

A concentration of less than one-half'of the {}_ minimum critical'. i A system in which the ' hydrogen tcr U8 3 5 -atomic! ratio: isEnot less than.5200. ,o .j 4.2.2 Nuclear' Criticality Safety Methodology l J j 4.2.2.1 Nuclear criticality. analyses shall utilize. experimental ] data or analytical methods _which have been bench marked.> l l by comparison with experimental data. An analytical. j . method shall be considered bench marked when the following are. established: (a) the type of systems which can be modeled, (b) the range of parameters which may be treated, and (3)'the bias, if any,,which exists' in the results produced by.the method. 4.2.2.2 Each nuclear criticality analysis shall be verified by {} an independent and qualified member of-the criticality 1 safety function having the qualifications of a senior member as defined in Section 2.5.2.1 of this j application. 4.2.2.3 When analytical methods are used ininuclear' criticality analyses to determine system. neutron' multiplication. i factors, it is required'that at the 99 percent' confidence level the neutron multiplication factor for- .) normal operations be no greaterfthan 0.90 and the. neutron multiplication factor for all conditions required to be critically. safe.by the double-contingency j policy be no greater than 01.97. ,] 1 1 LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-4.8

m a.

a t g.

These restrictions shall'be applied astfollows:- j a.+ 3o - bias 1 90 for. normal cond'1'tions ) K { 1 K + 30 - bias 1 97 forlfallure of!a single' contingency a. \\= ~ Where K = e average e ecWefmu,Mplicadon factor a' ' calculated'forathe'desirediapplicat16ni ] (.- .c' .i .o -= The statistica1'or! convergence uncertainties 1, ] .in'thelcalculationfof K,iand< a .) F Bias = : The bias of' the Tealculational t echnique j i O ' defined-as the calculatediresult minus-lthe-experimental result.. 4.2.2.4-Criticality safety analyses shall take the,following1 into consideration: l Normal conditions - The most reactiveJvalues not.- excluded by referenceable controls'br system-l parameter shall be. assumed for the,following' j variables: l Moderation. Reflection Heterogeneity of fuel, absorbers,. moderators and. structures i L h LICENSE SNM-1097 DATE 10/23/87 Page: DOCKET-70-1113 REVISION 18

.I-4.9-1

)

i Possible buildup of fissile material in f~^)- s inaccessible or unplanned locations '~' i Interaction between individual pieces of equipment Interspersed moderation between individual pieces of equipment Absorption characteristics of materials of construction l l Enrichment ] Accident conditions - In accident condition calculations, the controls cited in normal condition j I calculations are assumed'to fail in accord with the /~ requirements of Section 4.1.1 and the reactivity of \\~)% the system is reeva,luated. 4.2.2.5 Calculational methods used in nuclear criticality safety ) analyses shall include GEKENO and GEMER Monte Carlo Codes, k calculations using the reactivity formula, eff and the solid angle technique of array evaluations. Newly developed codes or techniques may also be used 4 l when they have been validated and bench marked in accord i with GE internal procedures and with the applicable ANSI standards. l I () \\- LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 l I-4.10 a . - ~.

.y.

i;

-(' / 4 ~ ' 4 ~. 2. 3 - Control Phi 1osophy 4.2.3.1-A. criticality safety control'must be capable'of~ preventing a' critical-accident < independent of'the. operation.or fallure of any.other control.- e '4'.2,3.2 A' single: criticality safety control,may_be composed..of-limits. applied to two or more system parameters. Controls on geometry, mas's',. moderation,' concentration, enrichment ~and: density may.-be'used;in such combinations. For example,-thel volume of a system may beLused in combination withLa concentration control to. establish mass as.a control.for the' system. 4.2.4 Nuclear Criticality-Safety Design" Considerations for Geometry Control s l 4. 2. 4 ~.1 The use of-geometry control in criticality. safety, Q except as specifically licensed in Section 4.2.li shall-comply with the requirements of Sections!4.1.1, 4.2.2.3. and 4.2.2.4. Thst is, a control (s)_must' exist:on'- another parameter (s}'such that fallure of the geometry control to the most reactive credible value will not violate the multiplication limit for'.acci' dent conditions L specified in Section 4.2.2.3. ateEial'and 4.2.4.2 Equipment used to process or store fissile designed on the basis of neutron multiplication is; considered to-be safe geometry if,'under' normal' conditions, the fully _ reflected' effective multiplication satisfies the normal condition specifications of.4.2.2.3' l l I LICENSE SNM-1097 DATE -10/23/87 Page DOCKET 70-1113 REVISION 18 I-4'.11 x. aa___.2.2____ -__i2--__m__A__32._ m

l.- y H ) and if, when accident conditions are' credible,'.it'also, 4 satisfies the accident. condition. specifications of-Section 4.2.2.3.. . henever'criticalityJcontrol is directly dependention l 4.2.4.3-W the integrity of a structure.used to retain.the geometric form offa fissile mater 141 accumulation or the'- spacing within a storage array, theistructurefshallibe q designed'with an. adequate'stren'gth factor to assure j ~ { against. failure under foreseeable loads:or accident conditions ~. Materials of' construction shall be fire. j resistant. The degree to which~any corrosive. environment might affect nuclear safety shall be considered and-corrosion-resistant materials'or,coatingst applied as necessary. .1 4.2.4.4' The use of fixed neutron absorber ~systemsla's geometric () controls shall require that: i l, 1) The neutron absorber is one of the following: a) Elemental cadmium b) Elemental boron alloyed with steel. c) Solid, stable boron compounds sneh as boron carbide fixed in a matrix such as aluminum or. l J polyester resin. j I 2) The neutron absorber and any hydrogenous' material' used to thermalize neutrons are sealed in.a stainless steel or other suitable container which may be an integral part of the process equipment. l . p, ' O LICENSE SNM-1097 DATE 10/23/87 Page., DOCKET 1113 REVISION 18 I-4.12 r- 't

(~) 3) The neutron absorber system-(i.e., absorber, moderator, container) is installed as,a permanent part of the process equipment such that it cannot be readily removed. 4) Prior to using a fixed neutron absorber system for-criticality control, an inspec, tion shall be performed using written. procedures developed and approved by management, to verify the presence of' the neutron absorbers and to verify that the system installation is in'accordance with design-and nuclear criticality safety requirements. Inspection records shall be documented and maintained for the life of the system'. 5) The void volume of the neutron absorber ~ system is-negligibly small to prevent internal q (~~l rearrangement. \\~/ 6) The effectiveness of the neutron absorber system is demonstrated utilizing validated calculational methods. ) 7) The integrity of the fixed neutron absorber system must be maintained against any credible fire hazard. 8) The integrity of the. fixed neutron absorber system j must be verified on a periodic schedule compatible with the rates of corrosion and deterioration i credible to the process system. l l 4 (f~') l LICENSE SNM-1097 DATE 10/23/87 Page j f DOCKET 70-1113 REVISION 18 I-4.11 ad 2

i 'l

)

t 9) If.the absorber.isiremoved,:theEsystem'shall:be locked out.in~accordance with safety' lock and-tag a procedures (e'.g., circuit switch locked, circuit breaker remove'd, feed ~ lines' removed)-'or operated l under controls authorized ~ 1n writing by tlieD . criticality' safety. function ~which ensure, as a minimum, that the' requirements:of Section!4.l'.1 are- ) i .] met. 10) The ' fixed ' neutron; absorber system must-be. designed to-withstand all: credible industrial)' accidents and' natural events. 1a 4.2.4.5 Whenever criticality control is directly dependent'on' the integrity of physical barriers or neutron absorbers,- thestructureshall-bedes[gned:toassureagainstlloss of integrity through foreseeable. accident conditional such as fire', impact, melting, corrosion.or. leakage of: materials. 1 j] 4.2.4.6 Where control of the spacing : and/or. heiglit lof: movable-units is used to provide criticality safety, th'e geometry of the system'is administratively controlled by' d one or.more of the'following techniques: ] 1 The geometry of.the system _is defined.by engineered. devices that determine the location of.the' movable units. 1 q LICENSE SNM-1097 DATE 10/23/87 Page I-4.14 DOCKET 70-1113_ REVISION 18 l .----._-AN_'___ ja

-{ J The geometry of the system is defined by procedure (~3 RJ 1 through the use of visually identified storage areas. The geometry of the system is defined by engineered devices that limit the height of fissile material, f 1 The geometry of the system is defined by procedure-1 through the use of maximum height restrictions. Where this type of control is used, movable units must P be safe geometry and must contain less than a minimum j critical mass based on the form of the fissile' material (i.e., powder, pellets or rods). l l l 4.2.5 Nuclear Criticality Safety Considerations for Administrative Control of Mass 1 l n() l 4.2.5.1 Where control of mass is used to provide criticality safety, the mass of uranium (or U225 or U228) is' l administratively controlled based on measurement by one or more of the following techniques: l The mass of uranium (or U225 or U22*) is determined as the product of the volume and the uranium (or U225 or U228) concentration as measured by j qualified counting methods. The mass of uranium (or U225 or Unse) is determined i by qualified counting methods. I l l \\ ) \\"' LICENSE SNM-1097 OATE 10/23/87 Page l DOCKET 70-1113 REVISION 18 I-4.15

The total mass or change in-mass of a system is- /~N V measured assuming the most reactive credible composition. 4.2.5.2 The use of mass control in criticality safety except as 1 specifically licensed in Section 4.2.1, shall comply with the requirements.of. Sections 4, 1.1, 4.2.2.3 and 4.2.2.4. That is, a control (s)-must exist on another parameter (s) such that failure of the. mass control to the most reactive credible value will not violate the-multiplication limit for accident conditions specified-in Section 4.2.2.3. i 4.2.6 Nuclear Criticality Safety Considerations for Administrative Control of Moderation 4.2.6.1 Criticality safety of vessels, structures or processes (" } may be based on control of moderation provided'that the following conditions are satisfied: I Sources of moderation internal and external ~to the. I process shall be identified and controls established for each source which are consistent with the requirements of Section 4.1.1. ) j l Support equipment associated with the control or l processing of moderating materials shall be designed so that they are either geometrically safe or designed to prevent backflow of fissile i I i I / s LICENSE SNM-1097 DAT.E 10/23/87 Page DOCKET 70-1113 REVISION 18 I-4.16 ---wa i r-a m

(~) materials and/or flooding of the fissile materials. 4.2.6.2 Where control of moderat1on is used to provide criticality safety, the degree of moderation is limited by one or more of the following techniques: l Moderation is removed by an engineered system and i the resulting material is' inspected and sampled to ensure proper functioning of the equipment. I Moderation is added procedurally and controlled by I limiting the mass and/or volume of the moderator and fissile material. Moderation of the mixture is determined by analysis or engineered methods prior to using moderation as 1 ('J a criticality control. 'i 4.2.6.3 The control of moderation for purposes of criticality. safety must comply with the requirements of Sections l ^ 4.1.1, 4.2.2.3 and 4.2.2.4. That is, a control (s) must exist on another parameter (s) such.that failure of the i 1 moderation control to the most reactive credible value will not violate the multiplication limit for accident 1 i conditions specified in Section 4.2.2.3. J l 1 r-:! v LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18, l I-4.17

i T 4.2.7 Criticality Safety Requirements for Use of Concentration j (~J \\ Control l 1 4.2.7.1 Where control of uranium concentration-is used to provide criticality safety, the concentration is controlled by one or more of the following techniques: ] o:The solubility.is controlled to prevent precipitation and the material is either agitated or. recirculated at a rate sufficient to prevent J settling into an unsafe concentration. -{ i a The uranium concentration is limited by on-line ) l measurement of concentration (or density if the l worst credible composition is assumed). If the limit is reached, automatic controls must prevent j ) continued increase, j ("h The uranium concentration in a precipitate is I measured and limited assuming the worst credible 1 a composition. ] 4.2.7.2 A full density mixture is used in determinations of uranium concentration (i.e., the effect of voids or inert materials mixed with the accumulation is not i included). 4.2.7.3 The control of concentration for purposes of criticality safety, except as specifically licensed in Section 4.2.1, shall comply with the requirements of Sections 4.1.1, 4.2.2.3 and 4.2.2.4. That is, a~ control (s) must l l (V'a LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 10 I-4.18 t_-_____

), l, ', ' E l ,l ,1 j.

.j 7 q

t ,s ^ . exist;on anothe'r parameter (s) such that failure of thb? J concentration.fcontrol to'.the/most reactive; credible ' vaiue will not' violate the multiplication'n. limit for ,j) accident..conditionsEspecified in Section'4.2.2.3. l 4.2.8 Criticality Safety Requ1'remerits for Us'e Lof ~ Density - Control I q .4.2.8.1 .Where control of.' uranium density is used';to; provide ~- 1 1 criticalityLsafety, the uranium densityL-is administratively controlled by onefor more of the j 'i 'following: techniques: 3 d Fuel displacing media is maintained /within!the': d geometry by useiof mechanical' attachments or'by use-of'a size / shape that:cannot exit:from theLgeometry i during'use. Where this methodioffcriticality~ contrcl is used, it is necessary'to assume.the j worst credible. distribution of mediaswithin'the. 1 geometry. The uranium density is controlled by use of-homogenized mixtures with measured:uraniumi density. Where materials having different uranium densities are. j mixed, the maximum density. measured is assumed .] throughout the system. l r R 'l 4 i L7 CENSE $NM-1097 DATE .10/23/87 Paga-DOCKET 70-1113 REVISI'ON - 18 I-4.'19 3 R o m

o ('J 4,2.8.2 The' control of density for purposes of criticality x.- safety must comply with the requirements of Sections j 4.1.1, 4.2.2.3 and 4.2.2.4. That is, a control (s) must exist on another parameter (s).such that failure of the . density control to the most reactive credible value will not violate the multiplication limit for accident conditions specified in Section 4.2,.2.3. 4.2.9 Criticality Safety Requirements for Use of Enrichment Control 4.2.9.1 In the controls of Sections 4.2.4 through 4.2.8,.a maximum area enrichment is implicit in the analysis. l l However, for some situations in a limited portion of an area, it is desirable to control enrichment to a lower value. Where control of enrichment to a value lower ('] than the maximum area value is used to provide u-criticality safety, the U235 enrichment is administrative 1y controlled based on measurement by standard assay techniques prior to enrichment being used as a criticality control. Where materials having different enrichment values are mixed, the maximum enrichment measured is assumed throughout the system. 4.2.9.2 The control of enrichment for purposes of criticality safety to a value lower than the maximum area value must comply with the requirements of Sections 4.1.1, 4.2.2.3-and 4.2.2.4. That is, a control (s) must' exist on another parameter (s) such that failure of the enrichment control to the maximum area value will not violate the ( ) LICENSE SNM-1097 OATE 10/23/87 Page DOCKET 70-1113 REVISION 18' .I-4.20 i

l, 0 t' Um .c. i, O ' multiplication' limit ' for. accident ' conditions specified ; - J V' in Section 4.2.2'.3. 4.2.10' criticality Treatment of Interaction between'Subcriticall "i Units 1 p g .o l., 4.2.10.1-Equipment and facilities,may be coilsidered to bec 4i nuclearly isolatedjif,theyfare separated by=either,of. -c the following: A one foot slab'of' water.orIby theidistance..which 'is. equivalent in' isolation. ability to a~one footi slab of water. q. u; s The-larger of 12 feet;orLthe greatest distance q -across an orthographic project 1on;of.theLlargest of:- q the fissile accumulations on a plane perpendicular - / l Q to the line joining.their centers.' 4.2.10.2 The criticality effects of-the exchange of neutrons. l between individual subcritical units'which are not

i j

isolated may be treated by eith'er of'the'~following' t techniques: 1 1 Techniques which produce a calculated multiplication' factor of the entire' system l(e.g., Monte Carlo).may be used. When this~1s done, the-l analysis must comply with the requirements of-Sections 4.1.1, 4.2.2.3 and 4.2.2.4. l s, a f} l LICENSE SNM-1097 DATE 10/23/87 Pag'e l DOCKET 70-1113 REVISION 18 .I-4.21 4 _.---._---,._--__----x_

,.4 1 / Techniques which do rpt produce a calculated- /~ ; multiplication, factor for the entire system but instead compare, the sysEem t;o, accepted criteria (e.g., Solid Angle technique)' may be used. When. j this is done. the ar$blysis must comply with the 1 requirements of Sections 4.1.1 and 4.2.2.4. ~ g 1 4.2.11 Requirements for EngiEeered Controls 7 Engineered controls detect an undesired situation and implement corrective action without requiring human l intervention. Engineered controls must be: t Sufficiently dependable and sc used that the probability of failure is minimized. 2 1 C i, Capable of performing'the criticality safety ('; purpose for which they arefspecified. %.) Maintained e.nd/or calibrated on a schedule suitable for the specific device and the specific applicati,on. Verified as being properly installed prior to first t a use with fissile materl31. Modified only with documented,(prior approval of the criticality safety function. d i / 1 O LICENSE SNM-1097 DATE 10/23/87 r!Page 00CKET' 70-1113 REVISION ,18 1 I-4.22 c- ,x ( .l

Y.', 1 v{l 1 -r. li e g Support'ed by procedures: and/or: devices: whicht '( provide' continued control'_if' operation is.to-be' allewed'to: continue;after'a' control has failed'. So designed that when sampling is part of:'la control, the' sampling is performedfat.fa frequendy A consistent.with' the; rate of: variat5.onL'of thel . parameter and with the implementation of4.' control'l action; , a M o - 4.2.12-Requirements'for Procedural Controls .g q-A procedural controlirequires human interventi'on in- ' detecting an.undesiredL' condition. and/or' implementing + corrective action. Procedural controls-must.be: j Sufficiently.. dependable and so used that,the O pro'eb111tv r re11ure'i= 1at=1 zee-Capable of performing the' criticality. safety + purpose for~which they are specified. 3 i . Implemented by-formal written procedures. Shown *,o be complied with by' formal written a records.- Modifiedonly with documented, prior approval'of the criticality safety. function. X Q)'- LICENSE SNM-1097 DATE 10/23/87 Paget 00CKET 70-1113 REVISION-l18 I-4.23'

.o i j2 o ! '\\g ll , f l Alff N} ^ ' 's Q ? W u y g / ,p: ,p,s a . Supported 1 bg 'pr0ce'dures nd/orfdevibes"'IEhi hh [i r /,e a provide. continued control'ifroperationiits/m :beX 7/d ..a tos 7 allowed to: continue?after alcontrolihas Ma11a b J.; 4 h yy1 4 q .u n . / ;,

s..

,1 ?) I. 'S6 designed that when:samp14ng isipart.of a; j control,'the'samdlihg$1s'pehformed at. a'frequencyk.I h ~ -consistentiwith /the. rate 'ofIvariation 'df f the . u ~

• j parameterandiwith<the71gple' mentation-ofIcontrSil

($$ f -( h. M fH . action. ? j' ,f. .f....

"h H

,7 I, 4.' "ic 4'.'2.13- , Crit'eria for Fire. Protection:in Areas Containigft Fiss'11e'. y u-'c ? Material q l c 4.2.13.1 Fire prote'ction : shalli.be. provided]for,Eequipment,. 4 1 o processes, and facilities'containing; fissile,,lmat'erial: J and shall be.s' ele'cted :on-thelbasis? 'ofoininimum impact on; j area nuclear criticalityTsafety, o) d a; MgGj. 4,2.13.2 The1use,of; water for! fire protection;inimodogationi control areasi shall. beiminimized Landl contrrA&~ ed[ Q , 4: ' .a 9 ): ' ' j. -l 4.2.13.3 Fire prot'ection instructions: coveEinge thimanufacturing f acility are.' issued which commdn32ab rpcessary or : permissiblemethodsortechniquesjdo>be sed.- a.a i 4.2.14 Incineration of' Nuclear. Waste. o ..f 4 u >The incinerator is authorized'to operate with'an l ..a estimated uranium enrichment of not,less than 2.75% in U2S5 for batch control. Waste boxes-with assigned' '1 t a ll' ;. . ) j' i ,t } l

,s J

J> i 86 s ?(f' 9 U v -) LICENSE .SNM-1097 .DATE

10/23/87, Page q

DOCKET 70-1113 REVISION' 18 o I-4.2'4-N ,J

j-H i

w L /[U)./ !L

q: f $a / ' d;f m >f i 4 " : -: y u x f ('T ,*, N k i i i 5 n ) 'f / _ l y _, 3 _'t ,h k d ' I j 4 y; i f. f l, 'l. ( : ,,j 1 - [ dj; fl enrichmentsigreater:>thsnU2h5% n(U855Teitn be } the ': boxes,are generated -'frok process Lareas. whei incinerated;with properidemonstrationLofcsafety 1 ~ '

1. m fthe' j

c: e< g m.. .I'.., ' maximum nominal enrichmentihandled'isHnotimore thanL j i 1 s i s o, ..e

J N / 0%.

INo waste:boxesigeneratedlfrom?a: process!which,:

1. o m. n. ..... 1, "1 9- 'foperatesLwith'Ja maximumienrichment" greater than.:- 4 i 0%<,- m 1.. '=9 o m ~' inominal; willfbe incinerate'd!unless',b.riysicali measurements : l A-; l.i 's - 1. o L, ~..

of the ?U2 2 s. coritente areimade Jor'theThighe.st enrichment 1' j

1.m - A j J./ > in the box is-l assigned-to the-.batchL. l J m.g . i!! .q l 6 a l ', I' ,1 \\ (: {., .l l e'q_ s j g;}

u s

>.]q g t 7l 1 ij a 1 e .m-H'q v

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p. @.

L i 3' .u p m. .y,

r CHAPTER 5 /} ~ ENVIRONMENTAL PROTECTION .I Radiological releases from the Wilmington site can occur via three j effluent pathways: airborne, liquid or solid. The control-systems for each of these pathways'are addressed in the following

sections, j

5.1 EFFLUENT CONTROL SYSTEMS 5.1.1 Airborne Effluents i The exhaust systems from uranium processing areas in the fuel manufacturing building are designed to maintain a (O negative pressure in those areas relative to the'outside ~N environment. This assures that air leakage is inward into the uranium processing areas. The negative pressure differential is maintained by regulating the ) volume of fresh air added to the uranium processing areas All exhaust systems from the uranium processing areas are discharged through high efficiency particulate air (HEPA) filter assemblies. Each exhaust system contains one final stage of HEPA filtration preceded by other air j cleaning devices specifically suited to the process steps served by the exhaust systems. Some of these -i LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-5.1 - - _ = _ _ _ _ i

%yj f-. j" ,4 a + w;! yp. g u n s., : 0 t .f 'l,, t 3 s a 1 grW 3.-l / q.- t I ,70.....,.s other, air cleaning devices;includeiprefilterC '. primary; h V ~ g

HEPA filters, Land wetiscrubbers.

p ,y w (. lc .Each'of the exhaust' system stacks,;from. process / area's< generally:usedifor*processingiuranium compounds?in. solid, 7, s f orm ; (1. e,, ' pelletJpressing ;> pellet;.' sintering,1 pellet J j h. grinding',1 rod. loading;-' scrap' sorting, and and decontamination)Lare, serviced %p an air' clean'ing. j j ~ . system asishownLin Figure 65.1. 7s h . Thelexhaust systems from. areas.'such as chemical ] r.1 R processing'(i.e., Vaporization; conversion, " defluorination, and uranium scrap; recovery).'are!servicedd i by an' air. cleaning--system?as shown1in Figur'e-5..2. 'j 1. '.5.1.1.1 Source Point Sampling'of Airborne Effluentsi d 1 4 Each' exhaust stack from-the. uran 1umiprocessing areagist sampled continuously-at a point"priorfto' discharge and .L l ~ m after the final HEPA filter in theJsystem'. The stack-3l L air sampler continuously pulls a:Laample of-air;from.the' air stream in:the'stackethroughfa' filter. The> filter on-each sampler is..-change'd and evaluated"for: gross alpha.- activity. (See Table ~5.1.): -The'measurementLof-gross alpha activity from each stack ~sampleLis utilized'to 1 determine uranium concentration in the1 discharge.and 2 total uranium activity discharged'from theLstack. l .l 1l 1 - i W

e,g

, u ' _ s:

rc

,1 u .l 1 II ';., t 4 (. h ' p

1. f t

i s s g y, rl* y A.g ,.] m 3 y' - e

s 3

0

-s d

F ;:. .FIGUREf5.2I 7: T" TYPICAL' EXHAUST. AIR-TCLEANING -' SYSTEM, - 'FORiWET CHEMICALiPROCESSING. AREAS: j) y ji_ ~ a-in -l i r s a. i 3 '.J -A: r ,1 3 To

• Atmosphere q

To Atmosphere-1 jj il

q..f 1-t 4.,

i Sample - , Sample::'- 1 Point 'Pointt ] 1 r Blowers. l Blowers a 4;f HEPA' HEPA i Filter' Filter i l Wet' Scrubber 'i H l 4 1 J 1 Primary Legs .i

• l

'1 ' ' \\'. ,1 i r- ~$M' DATE 10/23/87-Page j LICENSE SNM-1097. DOCKET 70-1113 REVISION 18-u I-5.'4

1

-1 e 'A i k ,j ,.j .t-

n y ~ d. t ( 5 [ 15.1.172) IAction LevelL for Airborne Effluents. o j -Data from jhe air; sampling ~. measurements:arejanalyzed:forJ ] ' comparison with the concentrations established as'ans g internal.' action' guide.,The occurrence of?anL1ndividual. 'stacN value exceeding the internaliaction< guide' 1 'initiatesJreview" action. i R Personnel responsible-for operating the exhaust-system: -1 are notified if any' weekly. stack,res'ul'tiexceeds-3ix) 10 - 2 2.' pCi/cc. -In.theLevent'.one-of theseivalues exceeds H l'x1l10-22'pci/cc.:nuclearjsafety andLenvironment$1: protection peNsonnel are'also.notifledg.;An:3- ~ investigation-ma'y beiundertaken,fdepending.on'.the-r. 1 severity:of.the-event,=-in accordance-with' administrative j routines described in Section'2.9. A 5.1.1.3 ' Reporting' Method l Uranium. activity. releases:.in:the-airborne effluents are: summarized in a weekly stack; program report. This report includes pertine'nt.information;forse'ach stack.and! for the total site. Year-to-date summaries and data'for the current week are included'in,thefreports

1 In the event an action guide.is exceeded,.'addf.tional q

notification as described in Secticn 5.1.1.2/is . initiated. ] d l l .1 i ) ^ a .j 1 1 O' H . LICENSE-SNM-1097 DATE l10/23/87 Page. j 1 00CKET '70-1113 REVISION-18 ' .I-5'.5. l r k ^ m

F' -i 1 (') The activity release data are also accumulated and. ~' reported on'a semi-annual basis to'the Nuclear Regulatory' Commission. ) i 5.1.1.4 Lower-Limits of Detection, Calibration and' Standardization of Measurements- ) l A solid state scintillation detector is currently usedL to determine the activity on the stack: sample filters. The system is calibrated for gross alpha using'a standard traceable:to the National Bureau'.of Standards. { This system provides.a lower limit of detection of activity at the site boundary within the requirements of Appendix B of 10 CFR 20. Background and efficiency checks.are performed each operating shift. The minimum detection limit'for airborne effluent concentrations is 1 x 10-12 pC1/cc'at.the stack ~which /"_N \\/ equates to approximately 1 x 10-14 pCi/cc at the site boundary using a dilution factor of 100. This lower limit of' detection is lower than the limit identified q in Regulatory Guide 4 16, March 1978, and'is 1 10% of the value 3 x 10-12 pC1/cc, from Table l[I of Appendix B to 10 CFR 20. 5.1.2 Liquid Effluents The liquid waste streams containing uranium from the j fuel manufacturing operations are segregated as nitrate waste, fluoride waste and rad waste. This separatioti 1 () s LICENSE SNH-1097. DATE 10/23/87 Page '~ DOCKET 70-1113 REVISION 18 I-5.6 i t________._____

'q {]) makes it.possible to utilize. final individual treatment, prc. esses most compatible with'the specific streams. -j l Each of these separated' streams is processed through a i quarantine tank system before it is released from the l fuel manufacturing operation. The quarantine tank contro'l system assures that internql guidelines for uranium concentrations are met before the liquids are ] released from the building to the final treatment 'I processes. k 1 5.1.2.1 Source Point Sampling of. Liquid Effluents All process' waste liquids are collected,, treated and' (with the exception of nitrate wastes). discharged to the l Northeast Cape Fear River. I I'/ The treated process wastes (with the exception of j s nitrate wastes) are sampled and discharged at the i outfalls of the two final process lagoons. The lagoon . discharges are sampled on a composite basis-j t proportionate to the discharge flow. The sampling l device extracts a fixed aliquot for'each unit of discharge. Normally., this provides one aliquot added to the composite every two.cn three minutes since the total _ volume discharged is about one-half million gallons per day. The volume measurement used to activate the' sampler and-generate the total flow signal is based upon an impulse generated by the water level in a stilling well in the (y \\' 'l LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-5.7

l w l n '.' y ,ij .\\ . weir.boxJabove a 90-degreetvee notch. weir. ;The, volume ] p '( flow is recorded / and an: integrated'value is-generated 1 a x. a by.the recording instrument. ,d 1 Theicomposite; samples.are, collected daily.(except: weekends and holidays)fand.. chemically analyzed?forL uranium' concentration. -A weekly co,mposite'of1theida3.ly~ samples is. analyzed'for gross alpha:and' gross beta ' j ~ activity.1.-

• i d

5.1.2.2' .' Discharge Volume & Destination-1 j The daily discharge:of treated process' wasts waterfto-j the, Northeast Cape Fear River'is approximately'500,L000. j gallons.- - 5.1.2.3 Action Levels for Liquid Effluents. .1 O The' action' levels for the discharge of1 treated process i wastes from the final process. lagoons areospecified:in l chemical uranium-concentration-(1.e., two parts per. q (ppm) daily ~ average ' for ; the. month. and' 5 l ppm. any million 4 l one day) and.in activity-concentration (1'.e, >3--x'10-5 i pCi/ml on a weekly composite sample). For. reference,- two' ppm at a typical enrichment-wouldiequate;to-approximately 10% of the 10.CFR 20 value of 3 x 10 l pC1/ml annual average forErelease to an unrestricted l l area. i .1 Y f T, ' b '10/23/87 'Page j LICENSE-SNM-1097 DATE - 00CKET 70-1113 REVISION-18i 1-5. 8. q 4 __m____ m

m s. x -{r '. i - i i< i 5.1.2,4 Reporting:'Methodi

Uranium cliemical-). analyses. are available - daily' (except -

4

weekendstand holidays) viaLtheLgeneration'of a' laboratory chemical analysis report on the dischargeE d

sample; data. These-data:are summarized on a monthly ]

]

-hasis. Daily'and monthly. values are reviewed.against? the: internal' action guides'. l The;NRC Regional. Administrator is notified within?10.' days of any violation of the.f acility's: NPDES; permit. uj l j The activity release data.aie' reported on.a semiannual l basis'to the Nuclear Regulatory Commission.. I q 5.1.2.5 Analysis, Lower Limits of' Detection',' Calibration-:and; j Standardization of Measurements. /~T -l

v u

5.1.2.5.1 Chemical Analysis of-Uranium' ') 1J'i .The lower limit of detection.for-chemical! uranium, d analysis-on environmental. samples 'is approximately j. 0.02 parts per million. ] l j The test method is calibrated!using-standard solutions l i made from National Bureau of-Standards'950b U 0,.or' 3 equivalent. The method is verified.with.each group of j samples run by use of a-verification standard. j l L ci a .,e Q' 't LT.C EN.'i E SNM-1097' DATE-10/23/87 'Pege DOCKET '70-1113 REVISION: 18 'I-5.9: .)4

g p w s, y o 'l '.'.,l.' ,l i. s f 1 1 e 7 ,l a Ul b 5.1. 2. 5.2 Activity Analysis for: Liquid Environmerital Samples 4 ' Gross alphal:and grossjbeta arc { currently [ determined by; standardized laboratory? counting.techri1 ques'. "Lowar;, u liinits of detect' ion ' (forj samples 'with11ow absorption)f - <t a 1 w zG L. ..2 .q 1's typicallp 3-x ::10 *

• L pCi/Stl' forrgross salpha1. and?. -

+.. 5 x.10-*'pCi/m1'for gross:-beta.. Th,e.. alpha' calibration : is' accomplished'usingastandard::.calibratedb'y.;tb!' 'NationalEBureau of: Standards. Y ] + s

1. , t,

J f 'l 5.1.3 Solid-Wastes. o 4 vi n- \\ t Solid.. wastes generatedLin the fuel manufacturing 1 l operation are packaged >insboxes. These boxes ar'e'. [' o s

assigned to controlled access

queuing! areas.where-3they eq

await' processing through n a. decontainindtiod:. facility '

l <The.decontaminationToperation provider a number of? jj x . s s iQ. f unct. ions including ' reco.very. of1 uranium fo'r; recycle;, l separation of wastes into combustible andLnoncombustible: 1 categories, as well as'deccntaminationtoftmaterial for. / reuse where. feasible, d After' separation.in'the decontamination facility,..the 3 combustible wastes are. designated'forLburning in an j! incinerator designed for; processing' uranium: contaminated 1 '

wastes, Wastes which cannot.be incinerated'or reus'ed are shipped to a' licensed recipient for disposal.

n b y '. 5 i f} LICENSE-SNN-1097 . DATE. 10/23/87 Page j Y .51101 h '00CKET L70-1113. . REVISION'

18'

.I .W 'o . j _ z m I $ i.

l -] (j 5.1.3.1 Source Point Monitoring of Solid Wastes j s-Each box is assayed for uranium content to assure that' it meets storage, shipment and burial requirements. 5.1.3.2 Lower Limits of Detection, Calibration, and Standardization of Measurements i The assay of solid waste boxes for uranium is done by a. nondestructive method which employs passive and/or active scanning. The lower limit of' detection is-approximately 1' gram U235 per box. Calibration and standardization conform to the measurement control f requirements defined in the GE-Wilmington Fundamental l Nuclear Material Control Plan. i 1 5.1.3.3 Action Level O ' Boxes which exceed a U235 content, established'by I criticality safety analysis and/or burial site f requirement are returned to the decontamination facility j for reduction of U225 content.

(

l 5.1.3.4 Reporting Method q The activity data on each shipment is summarized on the shipping papers. i l l L i l l l /~T 'O LICENSE SNM-1097 DATE 10/23/87 Page l DOCKET 70-1113 REVISION 18 I-5.11 ~~ l i L

l 1 (') 5.1.4 Contamination Free Liquid t-4 l Two liquid-streams (hydrofluoric acid and ammonium nitrate solutions) generated as a result pf the l conversion operation'are transferred to unlicensed-recipients and are not regarded as radioactive waste because of their low' activity level,. 1 1 1 The annual average activity level of shipments of j hydrofluoric acid and ammonium nitrate liquids is no more than that listed in Table II, Appendix B to 10 CFR. 20, 3 x 10-5 pC1/ml. I l 5.1.4.1 Hydrofluoric Acid In the dry process for converting UF, to UO,, a product' stream of hydrogen flucride dissolved'in-water is (~'4 generated. This acid contains less than 3 parts per s_/ 1 million of uranium by weight of the liquid. J d This product is transferred to persons whose uses of the material are such that incorporation of uranium from the liquid is not likely to occur in any food, beverage, cosmetic, drug or other commodity designed for ingestion or inhalation by, or application to, a human being such that the uranium concentration in such items would exceed that which naturally exists. The acid is collected in a bulk storage tank to await shipment. Material containing 3 or more parts per million uranium is not released for shipment. The total (~ LICENSE SNM-1097 DATE IV23/87 Page DOCKET 70-1113 REVISION 18 I-5.12

~ Jc T y 3a Ji. 1 4- ,e y -volumelproduced willfvaryc. based:on:manufactu ing; a requireatents. .q .] >q 5.1.4.2 Treated Nitrate Wastes- '1 Q J -Tha nitrate' bearing liquid is produced-'as a'.iresult1of: treating! metal finishing solutions.(from'onsitei "operationsx and nitrate fwas'tes front theDuranium! processing operations.- This solution'is temporarily 1 stored in the nitrate lagoons. Thisinitrate' solution.is.' utilized-as part of the' nutrient system forithe' biological waste treatment? facility l owned by Federal Paper-Board ~CompanyLandi o l. located in Columbus County, North. Carolina.. The solution is' transferred tojthefbiologica1Lwaste 'j l treatiment fa.cility. by7 tank truck. j . O ~ 5.1.4.2.1' Source Point Sampling A grab sample is collected from eachishipment andj analyzed for uranium concentrationib'efore' release from-the site. A composite of:the grab samples takenlin one day is also collected for subsequent? uranium 1 analysis and a weekly composite samp1~e from !the shipments. is analyzed for gross alpha activity. [- 5.1.4.2.2 Action Level for Nitrate Wastes-p l The action levels'for the'tran'sfersof treated nitrate wastes to-Federal Paper Board Company are as:follows:- d i l 1 ai V 7 4' . LICENSE SNM-1097-DATE. 10/23/87 Pags l: DOCKET 70-1113 . REVISION-18' I-5.13 q u i l o 1 ____d

i n V one Truck sample > 25 ppm U - investigate cause > 50 ppm U stop shipment Composite of trucks - Daily > 3 ppm U - 30 Day average > '3 ppm U The lower limit of detection (LLD) utilized for uranium concentration in the one truck sample taken before a truck is released,-is 10, ppm. The LLD for uranium concentration in the daily composite sample is 0.02 l j ppm. i l The lower limit of detection for the gross alpha j l analysis is 5 pCi/l (5 x 10-' pCi/ml). ( ) 5.1.5 Effluent Control Responsibilities Effluent Responsible Function O Stream Effluent Control Monitoring V i 1 Airborne & Applicable Area Regulatory Solid Effluents Manager Compliance Liquid Effluents j l o Final Process Plant Engineering Regulatory Lagoons & Maintenance Compliance i o Nitrate Wastes Fuel Production Regulatory' Compliance l o Hydrofluoric Fuel Production Regulatory Acid Compliance i 5.2 ENVIRONMENTAL MONITORING PROGRAM The environmental monitoring program incorporates the 1 i point of release measurements described in Section 5.1 l l l () LICENSE SNM-1097 DATE 10/23/87 Page ~ DOCKET 70-1113 REVISION 18 I-5.14 l 1 ~

s p x 9 s 'as'wellbas the.dat'aigenerated from the: programs ~ described in'this section... 3 .i :. .The monitoring program,is: summarized'in: Table-5.1 where

j the

current programicomponents=are listed.

Theisite i l

environmental monitoring" program is' dynamic, and changes v

are made ineit'a'sJdictated by changes.in! operations! and/orJthe emergence ofinew-found information. .q l l l. In.the eventithat'a sample;specified'in':Tablel5.1'cannot n be taken'in any; single' monitoring; system,1the manager of. 'the environmental protection: function will'documentithe. j l incident,. including an. assessment of. the :.. significance 'of.- the event, and the cause of. the deviationjfrom' plan, ands d 1 ' determine what corrective'actioniis needed. t 5,2.1 Compliance with'40-CFR 190 0 5.2.1.1' ' Air Monitoring 1 ] 1 If the radioactivity in plant gaseous:etfluent' exceeds. 1,'250 pC1'per calendar quarter, atreport shall?be prepared and submitted.to'the Commission:withinf30fdays: j which identifies the_cause-of exceeding?thellimitiandf. the corrective actions'to beituken to? reduce relea'se-rates. If the. parameters 'important --to - tih'el dose a i assessment change, a report sh'allLbe sdbmittedLwithin 30 . days which describes the changes in parameters and. includes an. estimate of the resultant change in dose. f: commitment. t 1 - LICENSE SNM-1097. ,0 ATE-10/23/87.. Page j DOCKET 70-1113 REVISIONi.

18

'I-5 '.15 ? Mi 1 1 - -. _ -. ~ _

o p p .p C C L C C pa l 1 c 0 0 po 0 0 p p sp p p no t( i 0 r a a a-S p p t - a - a 1 a an e 1 s 1 s xs t 1 s1 s 2' t s s s 2i s s 2 J o l xoxo 0 0 e xo xo

5. r

0. l r

r D r r 1 g 1g 0g 0a 3 gS g 0 0 s s h o l = 9 mt r ar pn g /i po 1 s1 ar m .l tC e 'e '2 se iptp g >r u l m l e / e m n a o l l v 1 / i* en r ,f m a _ e C l l* io e y / v. L p C - bi v ae 1 p 00mt a. dg C e n 8 91 aa 1 a v o 8 n 1 r hC er i xet rt ne 8 s-i i. R gnen8 ov sm M t 0 A c 1 a 0 F5aeto-a 0a ep rcrm0 a 1 - cp C 4. e n a R A 1 ~ 1 py s c e G xs O s x 03vou2 - pl xs e u2 p R 0o 4> acq1 x i a n s p P 1 r 3 5a 3r o 0 G 3> 3~ > g >a 0o'. o >d > g N ~ N L I R O T a a-I r a a N e ha ha h sy ha m O t pt pt p cl t pt u t t M e l e l e l ih n l e i n n m ab at a pt e AB c e e

1. L a

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e

~ v~. el el l l el e eo gvgv .v l l nene ede e ilil l ev v s s ge e .t d ytal - L rsrn l sr o1o2 i1ed n f ,f . a vn o ,d ,a2 U UdUd e i .U' U U t a a UtU c aoao i s A pl pl asay a - a m m pk pk popa p p p '- p c c pppd p p p p . 5' 5 5-5 5u0u m 2r5r 3o30 $ t>t .>c>3 s a .a' c~- a a, a a-a r a - ha ha ha ha ha ,h a ha ha ha e t t t pt tpt ptt pt ptt pt t pt pt pt a b't e , n n l e nl e l en l e l en l e nl e l e l m e' e AB eab abe ab abe ab e a b. ab a t t t t t t r n n ss nss ssn ss ssn ss nss ss ss a o o ss oss sso ss sso ss oss ss ss P c c oo coo ooc oo ooc oo coo oo oo rr rr rr rr rr rr - rr rr rr U .U GG UGg 'G gU Gg G g U' Gg Ugg Gg Gg - oy c y y y'- y-y' y y n k y 1 c u l l l l l' l' l l r r tn r r r r r r r e' e ce t y e e' e e e' e eu y l t t t t t t t t a' r-r r r r 1 q h l k r r r a' a a-a l e c i e a a a or a a e u u u u u u u-u CF E D W "l. Q Q Q Q ~Q Q Q' s' f-e f l y o ol e pa py eamd e T tua t idse .i s e si n ys e l ovko l okl b b~ b b b b p b pi c kpcp b b' m a mdur emum a a a a-a a a a a r onro eora r r r r r-r~ r r S G Citf Wcts G G' G G G~ G G G' e r u. M

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1. f P

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( L no i 1 m 1 m 1 m l m t 1 / p 1 / p 1 / p 1 / p m p p p / i p / 1 p / i c / 1 t C p 2 C p 2 C p 2 1 C p e 1 C 1 C 1 C C p 2 e p 0 p 0 p 0 p 0 0 0 0 0 D 0 5 2 0 5 2 0 5 2 0 5 2 0 1 a S a S a S a-S l s s s s s s s s e s s s s s s s s v o o o o o o o o e r r r r r r r r L g g g g g g g g n o i 1 1 1 1 1 1 1 1 t / / / / / / / / m 1 1 c 1 1 a 1 1 A 1 1 m C C p C C p C C p C C p p p p p p p p p p p e e 5 0 5 0 5 0 n n 5 0 1 1 1 1 5 1 5 1 5 1 1 o o 0 O 0 N. N r a a a a e h a h a h a h a t p t t p t t p t t p t t e l e n l e n l e n l e n e m a b e a b e a b e a b e d a t t t t i r s s n s s n s s n s s n r a s s o s s o s s o s s o o P o o c o o c o o c o o c u r r r r r r r r G G U G G U G G U G G U l F r ). ow y l l e n y y a i e l tn y y r y r r y ce l l e l e e / eu h h t h t t e l q t t r t r r c l e n n a n a a i or o o u o u u w CF M M Q M Q Q I epy T. l e p b b b b b b b m a a a a a a a a r r r r r r r S G G G G G G G eru. 7 7 7 7 4 3 gr iG FR 5 5 5 5 5 5 s s1 t s l1 n R l t E l l l e n T s4 e l e, ig 3 i A l1 w e w8 bn o W l s w nmi P D ed s e s, oAl

1. f ps o

N wn e i s e5 itWmn A 5 e U a i r e ir, E eaSao 3 l O y r e i E p R l1 e ss r e3 R gt Si Le m G p1 S l e s y A l ae& t Bg a p Fl s ,l i rg ra TP S9. T Ae L1 n o oeEit Aa S u W Cw Z P#o S FVNAS e, G i

l sO rRcu ym*

e o 3 - m5m gO o3m r 0 t

g's 8Z n

ao ooQQ i[U .c

g ,, n;m XP o 1 [ y: 9[ e b 1 1 i' 3., i D sin theievent'that.t e.ca cu ated)doseIto any memberiof5 ih l l' z %f the public in..any consecutive )12-montihiperiod. is aboutc to ' exceed.the limits:specified in-40 CFR':.190.10,

immediate steps.shall.be~taken;to! reduce'emi'ss' ions-soxasi to comply with :40 CFR '190.'10. LAs'provided in'40LCFR

.19 0.11, c a petition'may[be;submittedLtofthe1NRC/for a

variance from the requirementsSof 4,0;CFR 190.10.- If al petition for-a. variance'is anticipate'd,. the requestiwilll 3

be submitted.at'least 90" days. prior.to' exceeding:.the- ~ 'limitsjspecified in140.CFR-190.10. ? These reports"or petitions will be; submitted to the-o Director, Office of Nuclear Material. Safety & Safeguards, with'a copyItoLthe Region-II~ Administrator. 5.2.1.2 Sampling &' Measurement t Air samplingLstations are. installed andioperated in-the: prevailing wind directions,'i.e.,'JSE,;S,JSW andLNEL 'as shown in Figure.5.3..AirJsamples-are' collected ] 'I continuously and, in' addition.to analysis for; gross. alpha, thesamples..ateach' location:are.compositbdand 1 analyzed on a monthly basis:foriuranium isotopes with an.. i analytical. sensitivity of' atileas t ;10- * * : pC1/ml. l If the results'of the sampling; program indicate'a" quarterly airborne uranium.'concentrationJof greater'than' '3.45 x 10-25 pC1/ml, within.30 days.after receiving the analytical results an air sampling programiwill be-II instituted at the site boundary'in the d1rectionsof the~~ q nearest resident to determine the particleisize! q -i i l l LICENSE

SNM-1097

.DATE 10/23/87 Page DOCKET 70-1113 REVISION 18- -I-5.19L I I i, . l .I:; o i j. t ij -j' .'V ai

'i -i FIGURE'5.'3, _g AMBIENT AIR SAMPLING: LOCATIONS '] 1 l LEGEND.- l 1. Final-Process Lagoon.Outfalls ~ j) 2' -Sanitar Wastewater Treatment. Facilit.Out fall-4 al Process Lagoon-Outfall PROPERTY-LINE . Ditch' i 5 Drainage Ditch Above Dam l 1 6 Drainage Ditch Below Dam i

1. Ambient' Air.Samplirig Site

') 1 -FIN AL O-3; d LAGOONS [ eaocess [ - SANITA RY WA ST E W ATER 1 -@d' ~ G'g l TR E AT MENT.' I FACILITY Q - WASTE f. TREATMENT g FACILITY. Q NE) ~ t .AEBG O c geg g \\c u a , ox O O FMo \\ FCo \\ SE) \\6 SW S' .x .a j 1000 o ooo tooo s PROPERTY LINE SCALE IN FEET LICENSE SNM-1097 DATE 10/23/87 PageL ~ DOCKET 70-1113 REVISION 18 I-5.20 1 i m-

m '1: 9 i ^ .? 9: ( t distribution'of radioactive. material;with'a cascade-yJ ~. ] ' l in pactor?of L multiple : stages covering 'nonrespirable ' and q i f; 'f respirable particle-size ranges; The barticle: size-1 , :1 distribution analysis'may be: performed lon a: semiannual M y ' d! ' / ibasis. H ~J Samples taken at the-station'in,th'e' southern' location W] shall beicomposited quarterly and analyzed for' uranium csolubility?if the quarterly. average airborneLuranium ] concentration exceeds!3.45 x 10-15:pci./ml,. - The' , :{ Jsolubility' analysis shall follow the' methodology land" q procedures established.by Bettelle Pacific Northwest'. 4 Laboratories (" Solubility Classification of Airborne. Products'from Uranium Oreg and)TallingsiPiles",'; a i D. R. Kalkwarf, BNWL,. November 1978; and Second. ~ Quarterly Report on Solubility' Classification.of: l r Airborne ~ Products'from LWR-Fuel Plants",~D.xR.' Kalkwarf, BNWL, October 15', 1979) or an,equivslent method acceptable to the NRC. If aLlaboratorY ather thant BNWL lj 1 is used for the analysis, a. split sample:willsbe ] provided to the NRC'So that the'NRC:can perform a: - g verification. analysis. g I J 5.2.2 Soil-& Vegetation Sampligg, l 1 5.2.2.1 Soil Sam _plj.ng 1 Program Objective:. Determine if there.is ascertainable' .i ) l deposition from stack discharges sc ( \\- \\ i if i I ^ h, ^h4 O.n-LICENSE .SNM-1097 DATE' 10/23/87 ' Page d .' DOCKET 70-1113 . REVISION. '18- . L ' ' I~ S. 21-l 1 a. 'l e

Y ,t I Li s 1 () Soil samples a'ceLcollectedfand. analyzed fot uranium concentration to monitor for long-term build 11p of uranium concentrations attributable to plant operations. 1 The locations of these stations are concentrated along-the predominant wind directions.. Figure 5;4.deta11s the sample locati,'ns, i d The samples are collected on a quarterly basis-and analyzed for uranium concentration. The results are recorded and evaluated against an internal action guide-of 0.7 parts per million. { l 5.2.2.2 Drainage Ditch Soil _ Sampling Program Objective: Obtain environmental monitoring information regarding the uranium concentration of the soil in the drainage ditch (') v Process liquids which meet the NPDES discharge _ limits-j are released from the final process lagoons. These ] liquids migrate to the N. E. Cape Fear River via a series.of drainage ditches. Soil grab samples are collected from three locations-within the ditches twice per year. Samples are withdrawn in accordance'with information in Figure 5.3 and Table 5.1. Samples are generally taken during the periods of November through December and January through April of each year. The samples are analyzed for uranium concentration and the information is retained as a part of the* environmental monitoring program records. i j s LICENSE SNM-1097 DAi - 10/23/87 Page DOCKET 70-1113 REVISION 18 I-5.22

l' I,. l.. s i FIGURE 5.47 ENVIRONMENTAL SOIL SAMPLING LOCATIONS (TYPICAL) \\ I n / i e. /~d er 1 \\

1 oy

?%M" 1 A y 3 1 @s 'f- .een.n ELECfase 's g-i / 1 a { y acao.= 1 u 4 M p H a g p f![ 1 5 ~ 4 3000 0 Roco l,.'I. @> t M,irr~~40m sco v 4', '.3 i.', O ,b, f c (j ' l LICENSE SNM-1097 OATE '10/23/87: Page DOCKET 70-1113 REVISION Id I-5.23' -1

i 1. I) 5.2.2.3 Vegetation ~ Sampling %J Program Objective: Obtain environmental monitoring l information relative.to the effect.of measured fluoride emissions j 1 Twice.a year, grab samples of the forage vegetation j within thirty feet of the NE and SW ambient air sampling stations (Figure 5.3), are'cbtained'and analyzed.for

fluoride, i

This information is retained as a part of the j environmental monitoring progran records. 1 { 5.2.3 Surface Water Sampling l 5.2.3.1 Northeast Cape Fear River Sampling { ( Program Objective: Confirm source point and provide measure of effluent control effectiveness The Northeast Cape Fear River is the receiving' stream ] l for treated liquid waste waters discharged from the l facility. The river is. routinely sampled to establish l chemical uranium concentrations in'the river upstream and downstream from the site. The sampling location, type of sample taken at each location and frequency of sampling are detailed in L Figure 5.5. 1 1 1' e k_) ~i LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18 I-5.24 _- a

,p ;Y

.lt 7 _'i, .,Q,, { 4 !.s ! -n ,,;.: c l -n!- .l h,. - /S j /- w FIGURE 5 '. I5 l r:1 TYPICAL UPSTREAM / DOWNSTREAM SAMPLING: LOCATIONS-i ho 1 i 4, I h. w + .r,: e!, .i' M ( p/ ' 4Q~- (\\ ~ ..,i' 4 4 p r<. g % [% s ,d, A s p- . f. 4 3 a ~., l / //, cENERAL,. O. ECT RIC /,, ); L-R Y/b ll. e. - jf ))

4...

L'~ e 4 b. 1 / s [% s;, +'. l'P~ -w:. t. [?ntemMWir "i w eer; t.- 1 4 Sample Location Type-Frequency

1. 1 - Upstream Public Boat Dock Grab Weekly
2. 2 - Downstream Seaboard Coastline Grab.

Weekly Railroad Bridge ...a.smam m e LICENSE SNM-1097 DATE l10/$3/87 .Page 1' DOCKET 70-1113 REVISION' 18 -I-5.25 w m i ! 'h, i

l 4 ('] 'The data from the-monitoring 1 program are evaluated against an internal action'1evel. The uranium- ) '~~ ' concentrations are typically'less'than 0.02 parts'per f million. The action leve,L utilized in this program is. i three successive' values greater than 0.2 parts per million. .The upstream and downstream.results are' reported monthly "to the' State of North Carolina. 5.2.3.2 Treated Nitrate Waste Shipments Sampliqq 4 Program Objective: Confirm source point data l One segment of the monitoring program is designed to address shipments of nitrate solutions to Federal Paper Board Company.Inc., Riegelwood, N. C., for use in their (]) waste treatment system. 1 Samples'of water and sediment are collected from selected locations in the Federal Paper Board waste treatment. system (see Figure 5.6. for locations) as wel' ~ -l as locations in the Cape Fear River that :are upstream and downstream from the outfall of the Federal Paper j waste treatment system. These samples-are analyzed for gross alpha and gross beta activity and uranium as detailed in Table'5.1. These.results are compared .i against the action guides also listed in Table 5.1. p, LICENSE SNM-1097 DATE 10/23/87 Page DOCKET 70-1113 REVISION 18. I-5.26 _n_-----

Q)g,, >'/ ;% [{j;

p}}

.(.. Q-0 y y. ,3 ~ z i,', W .~ 'C: id L)\\ i ' .h f>Nfsk , G; e,c - . /,, La.. l" 4 x .\\ q.( f il FIGUREC5-'.6

/3

. p/ SAMPLING LO'CATIOiis' FOR'- x9 , FEDERAL' PAPER 00ARD; COMPANY, RIEGELWOOD,? NC' t. i. i.p. f a _.(_ q + x 4.; 1 t n, 'd g t.l[;! ,g.' _-, '. 'il' .[Ustream 1 GE-Wilm. ~ P s Nitratel .. [f Y ~ u Solution "f) lfl e: m [fg w [ --Canal

Cape

Northy; f]

Feh Clarifier New. Papermill -+ .t Effluent. V ':Vi .' Bay ? Basin ? fI ~ River ,e V e V-.

j '

'J jf'f .f. I ?

J.1; af;

' f Downstream

1 Jlf

} 1 'f- ^l 1 Sampling Points: ? i.auid e Si tdge V. i;; i .M) s LICENSE SNN-1097 DATE 10/23/87-Page

)

.q DOCKET .70-1113 ' REVISION-18' I-5.27-i t .'i j it

$hk;j 4, t O ,1 't m 3, ',q + 4 y yo o, "s i ,q (b { 1 t t t ' QQ L -] f 5 274- . Groundwater.- 5 i '~ t ' f. (.( )1 5.2.4.1 Principal Aquifer Sampling M I t !d., Program' 'Obj ective : AssuEe qua'l'ity 'of plant': supplyg 'l,$ J' -i water'innd obtain: environmental monitoring ~1nformation. m The? process and. potable.waterifor the' site 1sisupplied' from wells'which: draw.from;:the principle? aquifer..cA' 4 r grab. sample 71s. collected monthly.'from' supply 4 wells 9,olli. and.14. The sample is analyzed-;for gross alphaland: beta!: a radiation.,These results are' compared;against action? .guideslistedlin' Table 15.1a$1dthelrecordsNare + maintained as a'partTof the environmentalLmonitoring; program. l 5.2.4.2 Water Table Aquifer WelliSamplingL q N M l Program Objective: Provide ~early. warning of.-. containment'. failure 1 Additional series of wells lhave bAen placed[in'the' water-table (shallow). aquifer immediately; adjacent to potential-sources of. contamination-such as lagoons and ' sludge storage areas. t i It should-be.noted that.a' number of other wells-exist on I site. These wells ~are not' utilized in :the environmental. monitoring. program-butLare.available for spe'cialLstudies: 'i as needed. lq .Cd LICENaE SNM-1097 OATE' 10/23/87 .Page DOCKET 70-1113 REVISION' 18 . I-5.28 ____[_ ._.____I

U.y J.;

) s 4 '. 1 g,i a; m. ,wa3 ,+ ') N j 'p ' '4, l ,o' M ' j 1

• r

,g, y i. - Reference Table L5'.1? for.' details. of1 the L program. an'd 4 i Figure l5.7 for location"ofsthe"wellsidetailed"in the T.] table. bi .i + y The data:from the program;are compared...to:the actions d a T L guides' listed in Table 5.1 ~ l In the event a' well'. ;is; foundidryfwhen initially-visited u for sampling.'during the'specifiedLperiod',jat least one; h o return visit will<be made.'beforenthe'end'of the samplinga 5; cperi'od'for.;the purpose of.. obtaining ausample. l .i l -In the event a quarterly-sampling-frequencyJwell' remains; dry for. two consecutive % sampling 'periodd :or a. monthly-l w 'H sampling-frequency,well remains drylforlthree 1 consecutive;sampilng. periods, an investigation will be f initiated.within 14: working-days;after"th'e'endeof:the? Q period to. define a corrective action program whichuwill result in the renewal of sampling'on'the<specified ] frequency. Corrective action programs 'must include consideration'.of natural phenomena : characteristic :of thel site and shall. not result in changes'which decrease 1the' effectiveness -j of the monitoring program. 'Should new wellsibe required, they must-hear the principle. identity ofL the original well (i.e., PL1) but additional l characters?may. be added to the ;end of the ; designator tio show a change - (i. e., PL1A). LICENSE. SNM-1097 DATE I10/23/87-Page DOCKET 70-1113 REVISION 1 c18 'I-5.29. L q ' y

.z yl ,r i i i 1 [D-FIGUR_E ' 5. "7 - %.} ' WELL L'OCATIONS (TYPICAL) .I 'ET en sesoo. s i.aa j Mr,p,r,,N e,,, l q ~' 3 j. N, \\(, ... _ ~...... ,, s ,L pg m x. . L9.n 's \\ , s g pw 'q . Ne ^ S,,._%w...~. n - q ~ s

=.,

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1 'NN LEGEND s.h erven %l-me e 't".".*.%*1'!*.", *."* """""""* . r a '". M*.M".",*/OJ'"" '.".,,.. N wu. e '"'tiftat 7 "'."?."*"* ****""*** - - : - ; ;;;'** n y,;tn'A;;tt n,*,l,,m w se / ,==-.- -N ,, a g.a,;.,; n g...u....

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...m..... g r a . J tt '.t"i,"'. W.0 ".it O *:.. ',cu i,,,. ' p V' LICENSE SNM-1097 OATE 10/23/87-Page 00CKE1 70-1113 REVISION 18 i I-5.30 h -______m.m____-.m-u ..____m_

f ( I' ' j g.. m,% ) Records of' investigations,. co'rrective action programsi- ~' and program changes'will~be maintal'nedLasma.part of.'the-V'

environmental monitoring l program:information..

} t;,;.u i By-Product:H9drofluoric Acid Sampling. <5.2.5 ,i Program Objective:'-Assure:that" shipments meet' action guides -M drofluoric? acid produced.by/the drV/co'nversion: process U is available for(sale..This material-is' analyzed:for

uranium content:before shipment;for.=comparlson=aga' inst'-

the action guide as'detaile'dfin.TableI5.1.

l l O 1 l l . J ..r-V .DATE: .10/23/87. .Page: .i l.ICENSE. SNM-1097 4 DOCKET 70-1113. ' REVISION 18 I-5'.31 4 i i t .) 1a -j

g. m y y.g. y j E y ,ge qf ct.. 1 7 t j l l CHAPTER'6L -SPECIAL PROCESS COMMITMENTS" ><...o r i +, +}'- 3-8 6.1 .UF, CYLINDER' MOVEMENT 3; g;~ UF, cylinders,;once removed;from.the' protectively overpack,-shall have valve covern?in place while-th'e.1 cylinders are'being; moved. 7 ,l UF, cylinders'in'which the.-UF,.[is.' liquified, shallinot' a be handled loutside tiie; vaporization ' process: area. This; jl p ~ e requirement.does not apply'to UF,:heellcylinders which" contain-only that material. residual;in'the cylinder: j following complete: vaporization '(generally A~45 kg; 1 1 j UF ). L .i !) 6.2 00, POWDER MOISTURE' ANALYSIS: & MOISTURE: LIMIT 3 Cr3.ticality safety' analyses"are based on'a 50,000 ppmL water-equivalent limit which;is maintained?through- -1 ] process controls. j

J Use of lower limits will be based ~on:a specific'.

criticality analysis and. measurement of the moderator-

content, iq

6 3 TRANSFER OF UPS & FLUORIDE LIQUIII WASTES - FROM ' SAFE TOM UJJSAFE GEOMETRIES -

Prior to transfer from'a safe..to an unsafe' geometry vessel, all UPS and. fluoride liquid waste-will be f

J ()

LICENSE SNM-1097 -DATE 10/23/87 Page; DOCKET 1113' REVISION .18 ?I-6.1<

---

_1_.--.--._

3: c. 4 .v a i.'l l ['. ]. ,j 1 ,a y 6 1 ~ s

demonstrated by measurement'to meet the. criticality

j controls limits for the unsafe geometry. vessel. r-6.4' PREVENTION OF UF; CONTACT-WITH HYDROCARBONS'

6. 4. lL UF, Processing and Maintenance

]

)

D .) ;. d Controls 1to prevent: hydrocarbons fromTcoming;;inEcontact with UF6 processing! activities are identified in^ ) h facility ~ procedures. : Personnel involved with'the, maintenance and h'andling'of UF. cylinders,andithe'UF,; processing systems'are appropriately treined. 'd 6.4.2 Transporting-UF,! Cylinders ] ) 1 UF, cylinders shipped.from GE-Wilmingtonl:willThe-sealed-t j prior to shipment. - Where GE-Wilmington.:has ' direct ~. control'over suppliers of cylinders,. cylinder service, q or filling, the supplier'will be' required ~to. assure-hydrocarbons are not introduced and~ protect'this assurance.with a' seal prior to shipment. Other veridors and suppliers will be advised to do the.same. ~ 6.4.3 Compliance with ANSI Compliance will be maintained;with.the UF, cylinder sealing directions given in current publication?of; ANSI .j N14.1, the American National.-Standard =for packaging of [ UF. for transport. i A G . 10/23/87 Page: j LICENSE SNM-1097 DATE DOCKET 70-1113 REVISION' <18 I-6;2

] g'N 6.4.4 Commitment' of compliance y a x.s Full compliance with the commitments in.Section 6.4 will be achieved by 1987 year-end, i I I 1 l l l t i i 1 i l r ~. Q} \\ l l, + LICENS*;i SNM-1097 DATE 10/23/87 Page C0CKET 70-1113 REVISION 18 I-6.3 _.__-.______m_-_.--

!1 l' '1 i I/. 1 AJ;_ i-CHAPTER 7 DECOMMISSIONING PLAN' )' .J l At.the end'of plant.' life,.GE-Wilmington;sh'all decont'aminate the= . facilities andTsite in accor' dance with the Closure.&- -Decommissioning Plan'submittsd~on' July-21,.1981;.~ approved:by the' NRC on December: 11,[1981; and cas.. rev'ised -. d n' aEcordance with '- regulat'ory provisions. The' financial' commitment,- which GE' submitted :on May L14, 1979, tok assure that fun'ds will be available for decommissioning,'shall'- 3 remain in effect. -4 t a t { l . } 1 d d LICENSE' SNM-1097 DATE

10/23/87.

Page DOCKET-70-1113l -REVISION 18~

I-7.1-q

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L -) ( ,i ' f 4 CHAPTER'8- [ EMERGENCY PLAN .+ L GE-Wilmington shall' maintain a' capability'forihandling, emergencies: 1 1 L i 'in accordance with the. Radiological Contingency &' Emergency Pla'n, ~ submitted to the NRC on Augus't 27,fl981,. and as revised on August q 25, 1986, in accordanceiwith regulatory provisions. j .GE will make no changes to the Plan which wo'ld' decrease'its u effectiveness'without' prior' approval of the' Commission... 1 .{ Changes, which do~not decrease.the effectiveness of:the Plan,'..will' be reported within six months' of the. change to the: Chief., Uranium.- 1 i 3 Fuel Licensing Branch, Division.of Fuel < Cycle & Material Safety,- I Washington, D. C., 20555. 'O 8 The requirements of the' Plan shall be implemented through approved .] J written procedures maintained by the-li~censee. i 'I 1 l l .4 O LICENSE SNM-1097 'DATE 10/23/87 Page-DOCKET 70-1113 REVISION-18 ~I-B.1 i l.. _ - -}}