ML20034E342

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Responds to 920814 Fax Requesting Export Licensing Jurisdictional Determinations for Us Customs Export Cases 92-227-03 & 92-227-04
ML20034E342
Person / Time
Issue date: 08/27/1992
From: Hauber R
NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP)
To: Fraser G
AFFILIATION NOT ASSIGNED
Shared Package
ML20034D629 List:
References
FOIA-92-508 NUDOCS 9302250325
Download: ML20034E342 (2)
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AUG 2 71932 OIP Dir r/f OIP r/f Emport file E0Hemby JBecker RDHauber i

Hs. Glenna Fraser Operation Exodus And Outbound Enforcement United States Customs Service Headquarters Room 6215 1301 Constitution Avenue, N.W.

Washington, DC 20229

Dear Ms. Fraser:

This is in response to your August 14 fax requesting export licensing jurisdictional determinations for U.S. Customs export cases 92-227-03 and 92-227-04.

Regarding case 92-227-03, enclosed, per your request, are copies of export licenses XCOM0219, XCOM0222, XCOM0244, XCOM0274 and XCOM0289, with all amendments, which the U.S. Nuclear Regulatory Commission (NRC) issued to Hoke Incorporated in the late 1970s and early 1980s for the export of nuclear reactor components to Canada and South Korea. Dur.ing that time period, specific licenses were required for exports of all nuclear reactor components which, were under NRC export jurisdiction. However, on December 24, 1984 the NRC export regulations in 10 CFR Part 110 were amended to authorize persons to export under general license any nuclear reactor component listed in Appendix A (5) through (9) for use in any light or heavy water-moderated power or research reactor in any country listed in 10 CFR 5110.26(a).. Therefore, a specific license is no longer needed for these exports. A copy of 10 CFR 110 is enclosed for your information.

Additionally, effective June 25, 1980, the NRC transferred export licensing authority over certain r,uclear reactor plant components to the U.S. Department of Commerce (DOC). At that time DOC assumed export licensing authority over all

" balance-of-plant" nuclear reactor components. The NRC retained export licensing authority over only those nuclear power plant components which are "soecially desianed or orecared" for use in the nuclear reactor portion of a nuclear power plant. Under the international Nuclear Exporters' Committee (Zangger Committee), to which these changes were designed to conform, a " nuclear reactor basically includes the items within or attached directly to the reactor vessel, the equipment which controls the level of power in the core, and the components which normally contain or come in direct contact with'or control the primary coolant of the reactor core."' An illustrative list of the NRC licensed components is contained in Appendix A to the NRC's export regulations. The components in Appendix A (1) through (4) require specific export licenses from the NRC, and, as stated above, the components listed in (5) through (9) may be exported under the general license in 10 CFR 110, fl10.26(a), only to the countries listed therein. Otherwise, specific NRC export licenses are required.

9302250325 921119 PDR-FOIA LAWSON92-508 PDR

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Ms. Glenna Fraser 2

gg,7 Regarding Customs case No. 92-227-04, the Hoke diaphragm valves and bellows sealed valves described in the literature which you provided appear to have non-nuclear as well as possible nuclear-related uses.

These are defined as " dual-use" components and, on that basis, we have determined that the valves fall under the export jurisdiction of the DOC.

It is noted that the NRC's regulations specify that the NRC has jurisdiction over exports of specially designed or prepared manual or automated shut-off and control bellows valves made of UF6 resistant materials with a diameter of 4 cm to 1.5 m for installation in main and auxiliary systems of gaseous diffusion enrichment plants (10 CFR 140, Appendix C, paragraph 2.4).

of this size included in the literature.

However, we did not find valves The U.S. and other nuclear supplier governments are engaged in ongoing discussions within the framework of the International Atomic Energy Agency's (IAEA) Zangger Committee to clarify the international nuclear export control

" Trigger List" by identifying components which are especially designed or prepared for use in nuclear facilities.

time to time to reflect the addition of new components which the nuclearNRC expo supplier countries recommend be subject to export licensing control by supplier nations.

licensing jurisdiction are subject to change.Therefore, the components whic You may wish to call us periodically to determine whether new components have beer added to the controlled list.

jurisdictional determinations, please call Betty Wright at (301)S04-234 Sincerely, Originalsigned by Ronald D. Hauber i

(

Ronald D. Hauber, Assistant Director Exports, Security, and Safety Cooperation Office of International Programs

Enclosures:

1.

Export Licenses XCOM0219, XCOM0222, XCDM0244, XCOM0274 and XCOM0289, with all amendments 2.

10 CFR 110 (8/30/91) l IG:cust oms 2. b1w)___

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84 NAME TABLE 84 DATE 10/22/92 DESCRIPTION Aff's Codes of Office of Nuclear Reactor Regulation (post 4/28/B0)

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-143 BAS Program Management. Policy Development & Analysis Staff (Post 870411) 234 BASMI Management Information Program Assessment Group (890702-910824)

--- --- a 144 - BASPM Planning. Program & Management Support Branch (Post 870411) 264---YBASPS Inspection & Licensing Policy Branch-(Post 920712) 145-=QBASPT Policy Development & Technical Support Branch (870411-920711) 198=..yBASRH Inspection & Licensing Program Branch (B80913-920711) 146 BASRI Inspection. Licensing & Research Integration Branch (870411-880912) 254 BO Associate Director for Advanced Reactors & License Renewal (Post 910918) 266---)BOSSK License Renewal & Environmental Review Project Directorate (Post 921004) 255=-980SSL License Renewal Project Directorate (920517-921003) 256 BOSSP

. Standardization Project Directorate (Post 920517) 257 BOSSR Advanced Heactors Project Directorate (Post 920517) 147 BP Associate Director for Projects (Post 870411) 259=--)BPO Division of Operating Reactor Support (Post 921004) 260

)BPOE Events Assessment Branch 2 61 ---yB POG Generic Communications Branch 263

!BPON Non-Power Reactor & Decommissioning Project Directorate 2 6 2 ---)B PO T Technical Specifications Branch 148 BPP Division of Reactor Projects'- I/II (Post 870411) 149 BPP1 Assistant Director for Region I Reactors 151 BPP11 Project Directorate I-1

'150 BPP12 Project Directorate 1-2 152 BPP13 Project Directorate 1-3 153 BPP14 Project Directorate 1-4 154 BPP2 Assistant Director for Region II Reactors 155-BPP21 Project Directorate 11-1 156 BPP22 Project Directorate II-2 157-BPP23 Project Directorate 11 235 DPP2T

' Project Directorate 11-4 (formerly TVA Project Directorate) (post 900603) 240 BPQ Division of Reactor Projects - III.IV.V (Post 901216) 259-==>BPQMN Non-Power Reactors. Decommissioning & Environmental Proj. Dir.(920517-921003) 241 BPOO Assistant Director for Region III Reactors'(Post 901216) 242 BPQO1 Project Directorate 111-1 243 BPOO2 Project Directorate III-2 244 BPQO3 Project Directorate III-3 Reactors (Post 901216) 245 BPQP Assistant Director for Region IV/V 251 BPOP1

' Project Directorate IV-1 252 BPQP2 Project Directorate IV-2 253 BPQP5 Project Directorate V 246' BPR Division of Advanced Reactors & Special Projects (901216-920516)

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-247

.BPRQL License Renewal Project Directorate (901216-920516) 248

BPRQN Non-Power Reactors. Decommissioning & Environmental Proj. Dir. (901216-920516) 1209 BPRQP Standardization Project Directorate (901216-920516)-

250 BPRQR Advanced Reactors Project Directorate (901216-920516) 158 BPS Division of Reactor Projects - III,IV.V & Special Projects (870411-901215) 224 BPS 0 Assistent Director for Region III Reactors (891001-901215) 235 BP501 Project Directorate III-1 226 BPSO2' Project Directorate III-2

'327 BPSO3 Project Directorate III-3 220 BPSP Assistant Director for Region IV/V Reactors (891001-901215) 236 BPSP1 Project-Directorate IV-1 (900603-901215) 237 BPSP2

' Project. Directorate'IV-2 (900603-901215) 229 BPSP4 Project Directorate IV (891001-900602).

230 BPSPS Project Directorate V 231-SPSQ'

. Assistant Director for Special Projects (891001-901215) 239

- 232-

. BPSQL' License Renewal Project Directorate-(900603-901215)

BPSQN Non-Power Reactors. Decommissioning & Environmental Proj. Dir.(891001-901215) 238 BPSOP Standardization Project Directorate (900603-901215) 233.

BPSQS Standardization & Life Extension Project Directorate (891001-900602) 159.

BPSR Assistant Director for ReDion III &-Region V. Reactors (870411-890930) 116d BPSR1 Project Directorate III-1 161 BPSR2 Project Directorate III-2 162-BPSR3

, Project Directorate III-3 163 BPSR5 Project Directorate V 164 BPSS Assistant Director for' Region IV Reactors & Special Projects (870411-890930) 165 BPSS4

. Project Directorate IV 166 BPSSC TMI-2 Cleanup Project Directorate (870411-880201) 167 BPSSI Integrated Safety Assessment Project Directorate (870411-871127) 214 BPSSL

' Standardization & Life-Extension Project Directorate (890730-890930) 213 BPSSN Non-Power Reactors. Decommissioning &-Environmental Proj. Dir.(890730-890930) 168 BPSSS

. Standardization & Non-Power Reactor Project Directorate (870411-890729) 200 BS Associate Director for Special Projects (890101-900602) 202 BSP Comanche Peak Project Division (890101-900602) 211 DSPI Assistant. Director for Inspection. Programs 209

- BSPP Assistant Director for Projects, 210 BSPT Assistant Director for Technical Programs 201 BST.

TVA Projects Division (890101-900602) 205 BSTI Assistant Director-for Inspection Programs 203.

DSTP Assistant Director for Projects ~

204 DSTTE

. Assistant Director for Technical. Programs.-

. 206 BSTTP

-Plant Systems Branch

- 207 BSTTR Reactor Operations Branch'

. 208-BSTTT Engineering Branch. Inspection & Technical. Assessment (Post 870411) 169 BT Associate Director:for 17 0---> B T A Division:of Operational Events Assessment (870411-921003)

'171---y BT A E A Events Assessment Branch 172~~~? BT AGC -.

Generic Communications. Branch 173--~?BTATS Technical Specifications Branch 215---) BT C -

Division of Engineering Technology (890827-921003)-

2174--?BTCE Mechanical Engineering Branch 216-- -pB T C M..

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NUCBER ITEM DESCRIPTION 219 --78T0 Division of Systems Technology (890827-921003) 2 20 --T BTDE Electrical Systems Branch

- 2 21---7 B TDI Instrumentation & Control Systems Branch 22 2---) BTD P Plant Systems Branch 223---PBTOR Reactor Systems Branch 174 BTE Division of Engineering & Systems Technology (870411-890826) 175 BTEE Assistant Director for Engineering (870411-890826) 212 BTEEB Materials & Chemical Engineering Branch (890703-890826) 179 BTEEC Chemical Engineering Branch (870411-890702) 177 BTEEE Nechanical Engineering Branch (870411-890826) 176 BTEEM Materials Engineering Branch (870411-890702) 178 BTEES.

Structural & Geosciences Branch (870411-890826) 180 BTES Assistant Director for Systems (870411-890826) 182 BTESE Electrical Systems Branch (870411-890826) 181 BTESI Instrumentation & Control Systems Branch-(870411-890826) 183

.BTESP Plant Systems Branch (870418-890826) 184 BTESR Reactor Systems Branch (870411-890826) 18 5- =-) B T I S Division of Reactor Inspection & Safeguards (870411-921003) 188=-->BTISI Special Inspection Branch 18 7-* -> B T I S S

-Reactor Safeguards Branch 186---)BTISV Vendor Inspection Branch 18 9---? B T P E Division of Radiation Protection & Emergency Preparedness (870411-921003) 19 0---7 B T P E E Emergency Preparedness Eranch 19 2---? B T P E P Radiation. Protection Branch 191-.)BTPER Risk Application Branch 193

->BTPQ Division of Licensee Performance & Quality Evaluation (870411-921003)-

19 5 - -> B T P OH.

Human Factors Assessment Branch 199=--)BTPQN Performance & Quality Evaluation Branch (890101-921003) 19 7---> B T PQO Operator Licensing Branch 194 BTPQP Performanco Evaluation Branch (870411-881231) 196 BTPQQ Quality Assurance Branch (870411-881231) 276---)STR Division of Reactor Controls & Human Factors'(Post 921004) 278 -->BTRH Human Factors Assessment Branch 277--a>BTRI Instrumentation & Controls Branch 279--->BTRO Operator Licensing Branch 2 65 ---P B T S Division of Systems Safety & Analysis (Post 921004) 2 7 0 ---4 8 T 5 0 Probabilistic Safety Assessment Branch 267---4BTSP Plant Systems Branch

-268

!BTSR Reactor Systems Branch 2 6 9 ---> B T S S Containment Systems & Severe Accident Branch 280---4BTT Division of Reactor Inspection & Licensee Performance (Post 921004) 283 IBTTP Performance & Quality Evaluation Branch 282---90TT5 Special. Inspection Branch 281--d>BTTV Vendor Inspection-Branch 284---) BTU-Division of Radiation Safety & Safeguards (Post 921004)-

285---)BTUP Emergency. Preparedness Branch 286--J4BTUR Radiation Protection Branch 2 8 7---) B T U S Safeguards Branch 271---)BTV Division of Engineering (Post 921004) 2 7 4 ---9 B TV L Civil Engineering & Geosciences Branch 272---)BTVM Materials & Chemical Engineering Branch 2 73 --ay B TVN Mechanical Engineering Branch e

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HUMBER ITEM DESCRIPTION

~275---)BTVP Electrical Engineering Branch 1 '

C Office of Nuclear Reactor Regulation. Director (851125-870411) 2

-CDORA Operating Reactors Assessment Staff (851125-870411) 3 COPA Planning & Program Analysis Staff (851125-870411) 4

.CHf Division of Human Factors Technology (851125-870411) 5 CHTHF Human Factors Issues Branch 6

CHTMT Maintenance & Training Branch 7

CHTOL Operator Licensing Branch 8

'CHTTS Technical Specifications Coordination Branch 9

CPA Division of Pressurized Water Reactor Licensing - A (851125-870411) 10 CPA1 PWR Project Directorate i 11 CPA2 PWR Project Directorate 2 12 CPA3 PWR Project Directorate 3 13 CPA4 PWR Project Directorate 4 14 CPAS PWR Project Directorate 5 15 CPAT Assistant Director for Technical Support (PWR-A) 16 CPATE Engineering Branch (PWR-A) 17 CPATF Facility Operations Branch (PWR-A) 1B CPATI Electrical. Instrumentation & Control Systems Branch (PWR-A)

Ig CPATP Plant Systems Branch (PWR-A) 20 CPATR Reactor Systems Branch (PWR-A) 21' CPB' Division of Pressurized Water Reactor Licensing - B (851125-870411) 22 CPB6 PWR Project Directorate 6 23 CPD7 PWR Project Directorate 7 24 CPB0 PWR Project Directorate 8 25 CPBCP TMI-2 Cleanup Project Directorate 26 CPBIS Integrated Safety Assessment Project Directorate 27 CPBSS Standardization & Special Project Directorate 28 CPBT Assistant Director for Technical Support (PWR-B) 29 CPBTE Engineering Branch (PWR-B) 30 CPBTF Facility Operations Branch (PWR-B) 31 CPOTI Plant Electrical. Instrumentation & Control Systems Branch (PWR*B) 32-CPOTR Reactor Systems Branch (PWR-0) 33 CR Division of Boiling Water Reactor (BWR) Licensing (851125-870411) 34 CR1

.BWR Project Directorate 1 35 CR2 BWR' Project Directorate 2 36 CR3 BWR Project Directorate 3 3 7. -

CR4 BWR Project Directorate 4 38 CRT Assistant Director for Technical Support (BWR) 39 CRTE-Engineering Branch (BWR) 40 CRTF Facility Operations Branch- (BWR) 41 CRTI Electrical. Instrumentation & Control Systems Branch (BWR) 42 CRTP Plant Systems Branch (BWR) 43 CRTR

_ Reactor Systems Branch (BWR) 44

.CS Division of Safety Review & Oversight (851125-870411) 45 CSEI Engineering Issues Branch 46

'CSRI Regulatory Improvement Dranch 47

.CSRRA Risk & Reliability Assessment Branch 48

'CSRSI Reactor Safety Issues Branch 49 CSSPE Safety Program Evaluation Branch 50

.D Office of Nuclear. Reactor Regulation (800428-851124) 51 DCRB Clinch RiveriBreeder Reactor Program Office a

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' NUMBER ITEM

. DESCRIPTION' 52-DEP Emergency-Preparedness Program Office (after 801119 see I&E) 53'

.DEPD Emergency Preparedness Development Branch (after 801119 see I&E) 54-DEPE Emergency' Preparedness Licensing Branch'(after-801119 see I&E) 55'

DPA Planning & Program Analysis Staff (800428-851124)

~ 56; DPAM Management Analysis Branch 57 DPAR Planning & Resource Analysis Branch 58 DPAT

. Technical Support Branch _

Sg.

DTMI.

TMI Program Office 60 E

Division..of' Engineering (800428-851124) 61 EC

- 62

, ECGS.

Assistant Director for Comp.'& Structures Engineering (800428-830131)

Geosciences Branch 63 ECHG Hydrologic & Geotechnical. Engineering Branch 64 ECME Mechanical Engineering Branch-65 ECSE Structural Engineering' Branch _

66

- EE Assistant Director for Environmental Technology (800428-830131) 67-EEEN Environmental Engineering Branch

- 68_

EESA.

$1 ting Analysis Branch

^

69.'

EEUF

Antitrust

&' Economic Analysis Branch (Utility Finance)

' 70 EM

. Assistant Director for Matis & Qual Engineering (800428-830131)

- 71

EMCH,

' Chemical Engineering Branch-72-EMEQ Equipmect Qualification Branch 73 EMMA Materials Engineering Dranch 74 EMQA Quality Assurance Branch 75 ES Assistant Director for Comp. & Structures Engineering (830201-851124) 76'

-'ESEQ Equipment Qualification Branch;

. 77 ESGS EGeosciences Branch-78

' ESME.

Mechanical Engineering Branch 79 80

' ESSE Structural.& Geotechnical" Engineering Branch ET

. Assistant. Director for Matts. Chem.

81

- ETCE Chemical Engineering Branch-

. & Environ Technology (830201-851124) 82 ETEH Environmental & Hydrologic Engineering Branch uB 3 ETME-'

Materials-Engineering Branch 94 ETSA

-Site Analysis Branch 85

' H Division of Human Factors' Safety'(800428-851124) 86' HFED Human-Factors Engineering'. Branch-87-HLQB Licensee Qualifications. Branch-88 HOLB Operator Licensing Branch 89

. HPTR Procedures & Systems Review Branch 90 1

Division.of Systems Integration (800428-811004) 91 IP

" Assistant Director.for Plant Systems-92' IPAS Auxiliary Systems Branch j

9 3.-

IPCS Containment Systems P.*anch 94.

IPIC Instrumentation & Control SystemscBranch

-95

. IPPS Power Systems Branch 96.

IR-Assistant Directornfor Radiation Protection 97 IRAE.

' Accident Evaluation Branchc.

198l

- IRET-Effluent Treatment Systems Branch t

99

- IRRA,

. Radiological Assessment Oranch 100 IS;..

' Assistant Director for-Core &' Containment. Systems 101-

- ISCP

. Core Performance: Branch-y

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c 102.

. ISRS.

' Reactor. Systems Branch'

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.104_

~J Division of-Systems' Integration (811005-851124) 105 JC Assistant Director for Core &' Plant Systems

'106-JCAS

' Auxiliary Systems Branch

-107 J C C P --

Core Performance Branch

108

'JCPS-

. Assistant Director for Reactor $afety Power Systems Branch 109-

'JR 110 JRCS Containment Systems Branch 111 JRIC Instrumentation & Control Systems-. Branch 112 JRRS Reactor Systems Branch' 113

'JS

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J$AE.

Assistant Director for Radiation Protection Accident Evaluation Branch 115'

-JSET Meteorology &-Effluent Treatment Branch

-116.

JSRA' Radiological Assessment-Branch

'117

-L-Division of Licensing (800428-851124) 118-

-LL

-Assistant Director for Licensing 119 LLBt Licensing. Branch 1 120 LLB2 Licensing. Branch 2

.121 LLB3 Licensing Branch 3 122-LLB4:

Licensing Branch 4 123' LLSS Standardization &'Special Projects Branch

'124.

LO Assistant Director-for Operating Reactors 125-LOR 1

-Operating Repctors Branch.1

.126

-LOR 2 Operating Reactors Branch 2

-127 LOR 3.

Operating Reactors Branch 3

'28 LOR 4 Operating Reactors Branch 4

.29 LS Assistant Director.for Safety Assessment

'130-L505' Operating Reactors Branch 5-131.

LSRA-

, Operating Reactors Assessment-Branch 132' LSSE

. Division of' Safety Technology'(800428-851124)

Systematic Evaluation Program Branch 133 T

134 TG.

Assistant Director for-Generic Projects 135 TGGI

' Generic Issues Branch

~

136 TGLG

' Licensing Guidance Branch 137 TGRS Research & Standards' Coordination Branch-

-138

. T T-Assistant Director'.for Technology Review

' 139

'TTOE Operating Experience Evaluation Branch 140 TTRR.

Reliability.& Risk Assessment Branch 1101

.TTSE:

Safety Program Evsluation Branch s

I L

L.

.L

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