ML20151S898
| ML20151S898 | |
| Person / Time | |
|---|---|
| Site: | 07000250 |
| Issue date: | 01/11/1985 |
| From: | Morgan W BOEING CO. |
| To: | Riedlinger B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20151S885 | List: |
| References | |
| 4-1635-85R-0004, 4-1635-85R-4, 70152, NUDOCS 8602100010 | |
| Download: ML20151S898 (11) | |
Text
THE BOEING COMPANY MAIL STOP 2T-04
~ ~~
seattle, Washington 98124
' ~ 'h' L,
P. O. Box 3707 C
A 4-1635-85R-0004 W
' January 11, 1985 k
N ED STATES NUCLEAR REGULATORY COMMISSION 1450 Maria Lane Walnut Creek, California 94596
{
Attention:
Beth Riedlinger j
Subject:
RENEWAL OF SPECIAL NUCLEAR MATERIAL (SNM) LICENSE SNM-255.
References:
(a) Docket Number 070-00250; Control Number 70084; Program Code 22120.
(b) Nuclear Regulatory Commission Special Nuclear Material License Expiration Notice, dated 12-03-84.
Dear Ms. Riedlinger:
The following information is submitted as required by Title 10, Code of Federal Regu-lations, Part 70, Sections 70.5, 70.21, and 70.22, for renewal of our Special Nuclear Material License Number SNM-255.
We are submitting this renewal application in duplicate per the referenced Expiration Notice.
We are requesting that the license be renewed to reflect the same quantities of SNM as approved on our existing license, including Amendment Number 7 which was issued August 15, 1984.
Along with supporting documentation is a Boeing Check (#074761) for three-hundred fifty dollars and no cents ($350), to cover prescribed License Fees listed in 10 CFR 170.31.1(K) (June 29, 1984 CFR pubfication).
The following infor-mation is provided as required in 10 CFR 70:
1.
APPLICANT:
The Boeing Company P.O. Box 3707 Seattle, Washington 98124 r3 y
" fg
' PRINCIPAL OFFICE:
Seattle, Washington s
STATE OF INCORPORATION:
Delaware PRINCIPAL 0FFICERS:
(oce Attaclunent #1)
All of the individuals listed in Attachment #1 are citizens of the United States.
There. is no control or ownership exercised over the Company by any alien, foreign corporation, or foreign government.
0602100010 051106 REG 3 LIC70 SNM-OD55 PDR 27@20M2
,7015g
NUCLEAR REGULATORY COMfilSSION January 11, 1985 Page 2 4-1635-85R-0004 2.
USES AND LOCATIONS OF SPECIAL NUC._ EAR fMTERIALS:
This section identifies the different types of SNM; describes the various activities in which these materials are used; and lists the different loca-tions where the materials may be used:
ITEM USE USE LOCATION (S) a.
FISSION FOILS Neutron Energy
- 1) Boeing operations ir. State of 239pu & 2350 Threshold Washington.
Detectors.
- 2) White Sands Fast Burst Reactor; White Sands, New tbxico.
- 3) Sandia Pulsed Reactor; Sandia Base, New Mexico.
- 4) Nevada Test Site; fiercury, NV.
b.
239Pu-Be Sigma Pile.
Boeing Radiation Effects Lab; (lo ci)
Seattle, Washington.*
SOURCE c.
239pu-Be Calibration of
- 1) Boeing Radiation Effects Lab; (2 ci)
Neutron Seattle, Washington.*
SOURCE Instruments.
- 2) Boeing Radiation Health Protec-tion Lab; Seattle, Washington, d.
239Pu Calibration of Boeing operations in State of ALPHA Alpha Washington.
SOURCES Instruments.
e.
23sPu Gamma Response Boeing operations in State of GAMMA Calibration Washington.
STANDARDS Sources.
f.
233 URANIUM Gamma Response Boeing operations in State of GAMMA Calibra tion Washington.
STANDARDS Sou rces,
g.
235 URANIUM Gamma Response Boeing operations in State of GAMMA Calibration Washington.
STANDARDS Sources.
- Radiation Health Protection Representative permanently assigned to this facility.
E NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 3 4-1635-85R-0004 3.
TERM OF LICENSE:
The license is requested for a five-year period, or for as long as current Regu-lations allow.
4.
TYPE, AMOUNT AND SPECIFICATION OF SPECIAL NUCLEAR MATERIALS:
0f Tl ITEM NAME MA M A M
CD C EALI%
gg g(gg g (uvT I
a.
FISSION 239Pu 27 25 gms Sealed Monsanto 5 mil Al + 5 mil F0ILS Source Cu electroplated on Ni + heat-treated.
239Pu 10 1 gm Sealed Eberline Electro-deposited Source on Ni foil.
2350 66 120 gms Sealed Monsanto 5 mil Al electro-Source plated on Al +
heat-treated.
2350 20 1 gm Sealed Eberline Electro-deposited Source on Ni foil, b.
Pu-Be 239Pu 1
160 gms Sealed Monsanto (Sec Attachments NEUTRON Source II 6 III aub-SOURCE mLtted telth 8/20/74 Reneaut Application. )
c.
Pu-Be 239Pu 1
32 gms Sealed Monsanto (See Attachment 4 NEUTRON Source II 6 IV sub-SOURCE mitted (cLth 8/20/74 Rencaut Application. )
d.
ALPHA 239Pu 4
23 ugms Sealed Eberline Electroplated on SOURCE Source Na + heat-treated.
e.
GAMMA 23sPu 2
3.8 ngm Sealed Oak Ridge Double encapsu-SOURCE Source National lated in stain-Labora-less steel to tories meet 00T Special (ORNL)
Form requirement.
@@EDM@
701512
F NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 4 4-1635-85R-0004 4.
(contd.1
" 0I gfgu T
M MA M ACTURER MM OF SEAM 9
ITEM NAME ggyg(g3 f
f.
GAMMA 233U 2
425 mgm Sealed ORNL Double encapsu-SOURCE Source lated in stain-less steel to meet D0T Special Form requirement.
g.
GAMf1A 235U 2
1.8 gm Sealed ORNL Double encapsu-SOURCE Source lated in stain-less steel to meet 00T Special Form requirement.
5.
NOT APPLICABLE.
6.
PRINCIPAL USERS:
a.
NAME:
GEORGE A. WHITSETT EDUCATION:
Approximately 3 years in Education, Business, and Public Health Courses at college level.
(1)
U.S. Public Health Service Courses:
(a) Radiological Defense Officer.
(b) Occupational Radiation Protection.
(2) Hanford Course:
Radiation Protection.
EXPERIENCE:
(1) Hanford - 3 years as a Radiation f1onitor.
(2) Boeing - 26 years as a Specialist in Radiation Protection.
R7&&27/&M 70152
NUCLEAR REGULATORY COP 91ISSION January 11, 1985 Page 5 4-1635-85R-0004 6.
b.
NAME:
MELVIN R. KIMMEL EDUCATION:
B. A., General Business - University of Washington.
(1)
U.S. Public Health Service Courses:
(a) Basic Radiation Health.
(b) Occupational Radiation Protection.
(2) Reynolds Electric Course:
Nevada Test Site Monitoring.
EXPERIENCE:
Boeing - 3 years as a Radiation Monitor; 20 years as a Radiation Specialist for the Boeing Radiation Effects Laboratory.
c, NAME:
ANDREW R.-LOWREY EDUCATION:
M.S., Physics - University of South Carolina.
EXPERIENCE:
Boeing, since 1958.
Has handled radioisotopes most of this time.
Is in charge of the Dosimetry Program for the Boeing Radiation Effects Laboratory, d.
NAME:
DENNIS A. RUSSELL EDUCATION:
B.S., Physics - University of Washington.
EXPERIENCE:
Boeing, since 1969.
Has handled radioisotopes while at Boeing, and at the University of Washington.
He is primary custodian of the Company's Special Nuclear Materials.
NOTEt WlLLIAM E. MORGAN is The Boeing Company's Radiological Safeky 0fficer, and has served in this capacity fot 21 years.
The Users of these Sowtces wilt be wider his direction.
LE@EDM@
70152
3 c
NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 6 7.
DESCRIPTION OF EQUIPMENT AND FACILITIES:
a.
FISSION F0ILS Pennanent storage of the Fission Foils is provided by a security-approved steel safe located within the BREL Sigma Pile Room.
Once every three months each Foil exceeding 10 pCi will be checked for leakage-except when the Foils are in storage condition.
(P.tior to acuse, the Foita teitt be tested for leakage whenever they have been in stotage fot periods exceeding thtee months.)
All initial operations Ltemoving f tem storage, FoLC teak (cat ptoccdasca, picpatation fot 4ttadiation, etc.) will be conducted inside a HEPA-filtered glove box.
The exhaust air from the glove box is filtered through two HEPA filters into a three-inch flex duct where the air is ducted to a ceiling ex-haust fan.
The ducted air is refiltered prior to release to the outside environment.
This ceiling exhaust process also maintains negative pressure within the Sigma Pile Room where the Foils are stored.
To avoid overabrasiveness to the Foil protective coatings during leak testing operations, the following practices have been adopted when periodically leak testing the Foils for possible radiological contamination:
(1) An alcohol wipe is taken of the Foil storage containers' interior sur-faces.
All surfaces which are adjacent to each Foil are wiped during this process.
The wipe is then dried prior to analysis on our labor-atory counting systems.
Along with the wiping process, all inner surfaces of the containers are directly surveyed with a portable Alpha Counter.
(2) A direct Alpha measurement is then taken on both sides of each indivi-dual Fission Foil.
Since these Foils are aluminum protective coated, any Alpha radiation detected would indicate radiological contamination and require investigative action.
Immediate " wipe" leak tests would be taken, and any Foil leaking more than 0.001 pCi would be pulled from service.
Leak test results are recorded on a leak test card essigted to each individual Foil.
The Foils will be used to calibrate detectors and measure fission product ganma spectra.
There are no planned activities involving insertion of these Foils in any nuclear reactor.
When taken out of the Seattle area, the Foils will always be in the control and possession of a Boeing Licensee.
They will be shipped in accordance with Nuclear Regulatory Conmission and Department of Transportation regula-tions.
590DMA?232 70152
NUCLEAR REGULATORY C0tNISSION January 11, 1985 Page 7 4-1635-85R-0004 7.
b.
10 CURIE Pu-Be NEUTRON SOURCE The 10 Curie Pu-Be Neutron Source is primarily used and stored in the Sigma Pile assembly which is kept in the 15-10 Building Sigma Pile Room (ace Attachment III aubmitted teith 8/20/74 Rencreat Application).
The Neutron Source was placed in the Sigma Pile assembly in 1963, and has only been re-moved to conduct nondestructive tests on Pu-Be Neutron Sources at the request of the Department of Energy.
Leak Tests are performed every six months by wiping appropriate accessible surfaces of the Neutron Source access port.
The wipes are immediately checked with a portable Alpha Meter, and then analyzed on our laboratory counting equipment.
Results are recorded on a Sealed Source Leak Test Card assigned only to this individual Source.
The primary lid and access port to the Sigma Pile are secured with locks.
The keys are in the possession of the facility's Supervisor and the resident Health Physicist.
The Dose Rate from the Sigma Pile is less than 1.0 mrem /hr at one foot from any exterior surface of the Pile, c.
2 CURIE Pu-Be NEUTRON SOURCE The 2 Curie Pu-Be Neutron Source used for instrument calibration is used and stored in the approved storage container (ace Attachment IV oubmitted telth 8/20/74 Rencleal Application).
The Operator remains a minimum of 25-inches from the Source when it is exposed out of the storage container.
The Dose Rate at this distance is approximately 12.0 mrem /hr.
Af ter calibration, the Source is returned to the storage container and locked.
The key is available only to members of the Radiation Health Protection staff.
The Source is leak tested every six months, per NRC requirements.
When the Source is in its storage container, the Dose Rate is less than 1.0 mrem /hr at one foot from any exterior surface of the container, which is normally kept in the secured BREL Sigma Pile Room, d.
ALPHA CALIBRATION SOURCES The Alpha Calibration Sources will be stored in the Radiation Health Protec-tion Laboratory, and used to calibrate our Alpha Meters.
The Laboratory is a controlled area, and has free access only to Radiation Health Protec-tion personnel.
When the Sources are used in other controlled areas in the Company, they will be under the control of a Licensee.
$[f0ll$$kY 70152
NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 8 4-1635-85R-0004 7.
e.
GAMMA CALIBRATION SOURCES These Sources are presently semipermanently stored in the Nuclear Laboratory at the Developmental Center, Building 9-101.
No planned activities in-volving these Sources are known at this time.
If a program develops that requires the use of these Sources, they will be leak tested per Condition 13 of our existing license, and all operations will be conducted within the basic protection / material control / requirements listed in the Operating Procedure-Agreement submitted when we applied for Amendment #6 of our exist-ing license.
NOTE:
We a.tc.tequesting that Cenditions 13. A and 13.6 of cut existing license be inco%potated as tetitten into out teneteed license, concetning att cut Special Nucleat Itatetial sources, f.
RADIATION PROTECTION INSTRUMENTATION AVAILABLE The following Radiation Protection Instruments are available for use in con-nection with these Special Nuclear Materials:
MAKE AND If00EL RA01AT10M DETECTED RANGE Beta and Gama 0 - 70,000 c/m 1p.
r be Eberline E-510 Beta and Gamma 0 - 250,000 c/m Victoreen 740 Alpha, Beta and Gamma 0 - 10,000 mR/hr Eberline PNC-1 Fast and Thermal Neutrons 0 - $00,000 events / min Canberra Laboratory Scintillation Counting Alpha, Beta and Gamma 0 - 600,000 c/m Spectrometer System Eberline PAC-4G Alpha 0 - 500,000 c/m Eberline PAC-15 Alpha 0 - 2 x 106 c/m Tracerlab NP-1 Thermal to 15 MeV Neutrons 0 - 2,000 mrem /hr Eberline AIM-3 Alpha and Beta Air 0 - 1,000 c/m Air Monitor Particulates Eberline R0-1 Beta and Gamma 0 - 500,000 mR/hr Z:90DM/AyQ' U 70152
4 NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 9 4-1635-85R-0004 7.
f.
(contd.)
MAKE AND M00EL RADIATION DETECTED RANGE Technical Associates TBM-3 Alpha / Beta / Gamma 0 - 50,000 c/m Eberline PRS-1 Alpha / Beta / Gamma / Neutron 10 - 999,999 c/m Victorcen 471 Beta and Gamma 0 - 300 mR/hr Victoreen V-440 Beta and Gama 0 - 0.1 R/hr Eberline R0-2 Beta and Gama 0 - 5.0 R/hr Victoreen 592 Gamma 0 - 1.0 R/hr Johnston Lab Triton III Tritium Gas 0 - 106 uCi/m3 g.
CALIBRATION PROCEDURES Calibration of radiation protection dose rate instrumentation is accomplished Quarterly, or af ter replacement of any electronic component, in accordance with the instrument manufacturer's instructions.
Contamination measuring instruments are calibrated Semiannually.
Daily, upon use, all instruments are response-checked to assure proper operation.
A permanent record of cali-bration results is maintained for each instrument.
h.
PERSONNEL DOSIMETRY DEVICES AND l'QUIPMENT AVAILABLE FOR PERSONNEL WORKING WITH OR AROUND 3PECIAL NUCLEAR ftATERIALS TVP f
MANUFACTURER SEN ITIVITY gy TRU EMT 9
y Landauer Film Badge Beta / Gamma /X-Ray / Fast Thermal Neutron Monthly Dosimeter Corp Model 884 Ou'IY~
Beta /Gama/ Fast, Thermal Neutron of America Dosimeter upon use 9
Landsverk Gam / Thermal Neutron e
up ue T
r
^5 Harshaw Beta /Gama/Neu tron
, de 0O q
Dosimeter Corp liodel 002 OdIIY ~
Low-energy Gamma /X-Ray of America Dosimeter upon use Landauer FingerRing Beta /Gama Monthly MW2W722M 70152 1
NUCLEAR REGULATORY COMMISSION January 11, 1985 Page 10 4-1635-85R-0004 8.
PROTECTION PROCEDURES FOR PERSONNEL / PROPERTY / ENVIRONMENT a.
Final Disposition of Material Any Special Nuclear flaterial that can no longer be utilized by The Boeing Company will be disposed of by one of the following methods:
(1) Return to appropriate manufacturer.
(2) Turn material over to a licensed disposal agency.
(3) Turn material over to another licensee authorized to possess the ma terial.
(4) Turn material over to an authorized agency of the United States Government or its appointed designee, b.
Protection Procedures The following Applicatien-supportive documentation is included in our appli-cation package.
Occupational Safety & Health (OSH) Standard 8-201* clearly reflects the Company's "ALARA" commitment.
(1) Boeing Occupational Health & Safety (OSH) Standard 8-201*, " CONTROL OF RADIOLOGICAL HAZARDS".
(2) Boeing Operating Procedure 4-1600-202/846-005, " HEALTH PROTECTION -
RADIATION EFFECTS LABORATORY".
(3) Boeing Security Operating Procedure-Agreement, written 1-11-82 and finally approved 6-1-82, " PHYSICAL PROTECTION OF SPECIAL NUCLEAR MATERIAL OF LOW STRATEGIC SIGNIFICANCE".
Sincerely.
WILLIAft E. PpR 4
Chief, Radiation Health Protection Telephone:
(206)655-0500
- 05H 8-201 supersedes IRCD 76 (which was submitted with proviaus application).
GAW/WEM:gw AuacItmeitt,s (5):
"1 - LLst of Of ficets of Tlte Boeing Ccmpant).
M2 - Opetatiotg P.toceduac 4-1600-202/846-006 (Item 8.b.(2)).
93 - Occupaticaat Safety & Heault Standatd 8-201 litem 8.b (1)).
M4 - Secutitt) Opetating Ptocedute-Agtcement fltem 8.b. (3)).
"S - CIteck *074761, dated Occembet !?,1984, fot $350.
E62?D M M S 70152
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