ML20210J706
| ML20210J706 | |
| Person / Time | |
|---|---|
| Site: | 07003025 |
| Issue date: | 06/25/1985 |
| From: | Janzow E FRONTIER TECHNOLOGY CORP. |
| To: | Adam W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20210J508 | List: |
| References | |
| 78333, NUDOCS 8604030539 | |
| Download: ML20210J706 (108) | |
Text
r-1 FRONTIER TECHNOLOGY CORPORATION 2671 Crone Itoad
- Xenia, Ohio 45385
- 1513) 4261656
- Teles 119103338287 EasyLink 62586340 June 25, 1985 Materials Licensing Section ATTN: Dr. William Adam U.S.
Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Re Control No. 78333 Your letter dated May 30, 1985 Dear Dr. Adam Your lettar dated May 30, 1985 requesting additional inform-ation concerning our license application was received by us June 5,
1985.
We urgently need a license authorizing us to manufacture and distribute sources as requested, and to conduct activities related to manufacture and distribution.
As.we stated in our February 15, 1985 cover letter to our application, our schedule calls for source production in June and early July and requested early notification if issuance of our license might be delayed beyond the end of May 1985.
The information received was that new licenses usually are issued four to six weeks after your receipt of the license request; we therefor proceeded to make commitments under the assumption that issuance of our license would occur before
- June, i.e.,
within 15 weeks after our request.
Lack of a license is causing us to miss commitments.
Each commitment missed by us as a new company very likely means 4
permanent loss of a customer.
Due to the now extreme urgency of our need for authorization to manufacture and distribute sources, and respecting the time it will take to properly respond to your questions regarding
- services, we request that our license be issued in stages with authorization to manufacture and distribute sources (and activities thereto related) being the first to issue.
As you may
- recall, this option was suggested by Mr. Bruce Mallet during our will delay our response to your questionsMay 24,lating to services to three-way telephone conversation of 1985.
We therefor re other licensees (Section 1 of your letter) until after a license authorizing source manufacturing and distribution has been issued.
Our response to your other questions is detailed below:
Item 2.a.
Section 10.5.4 has been added describing the method by which records of the results of contamination surveys will be maintained.
Item 2.b.
Section 10.7.3.D has been added describing actions to be taken when removaole contamination limits are exceeded.
Item 2.c.
v Radiation area surveys: Radiation monitoring inside the l
restricted areas is addressed by Section 10.4.2, Paragraphs A l
through C, and radiation monitoring of other areas is addressed Paragraph D.
by Section 10.4.2,ify frequency ofA new paragraph, 10.4.2.E has been added to spec formal surveys and a new, j
Section, 10.7.5, has been added to specify levels which require corrective action.
Monitoring of contamination by measurement of radiation levels at surfaces is part of the radiation monitoring (required by Paragraph 10.4.2.A) to be done before
- during, and after each work assignment involving processing of, radioactive j
may(q$(fg.lygygface monitoring of each item to be removed from t
l JUL 031985 1
l l
REGION III B604030539 e50722 REQ 3 LIC70 SNM-1957 PDR L
3
the restricted areas is required as specified by Section 10.7.3, which also specifies allowable levels and corrective actions.
Item 3.Opening of shipping containers. We have no intent of exempt-ing any package which does or might contain radioactive materials from safe opening procedures.
Paragraph 10.10.1.B is intended to apply to all radioisotope shipping containers we receive, regardless of content. For that reason, we have changed the head-ing of Paragraph 10.10.1.B from " Procedures" to " Procedures For Opening All Radioactive Materials Packages" for clarification.
We have also added a sentence to item 3 under " Opening Shipping Containers" to clarify that packages containing materials in other than special form may require precautions in addition to those required for packages containing materials in special form.
Item 4.a.
Criteria for issuance of-extremity monitors.
Paragraph 10.3.1.B was intended to cover this item.
The paragraph has been re-written to more clearly state the criteria for issuance and use of wrist badges.
Item 4.b.
Radionuclides of interest for bioassay purposes are those which were handled in unencapsulated form within the period covered by the bioassay.
Paragraph 10.3.2.G has been added to specify isotopes of interest.
Action levels are specified in Paragraph 10.7.2.A.
Item 5.
Two copies of cur
" General Instructions for Entry to Restricted-are enclosed withAreas"Ehiscovering the items specified in your Item 5, letter.
~ Items 6 and 7.
These two items imply that you intend to limit our manufac-turing and' distribution license to specific _ source models and furthermore to limit us to specific shipping container models for the shipment of our sources.
Such restrictions are not required by the regulations, nor have they bean imposed on other source manufacturers.
These restrictions would be seriously damaging to our business.
With regard to source models:
(1)
A major portion of our business is the
- design, manufacture, and-distribution of Cf-252 neutron sources for nuclear reactor start-up.
Such sources are not standard, but are designed and built to match the requirements of particular reactors or classes of reactors.
Several major U.S.
and foreign reactor manufacturers have standard designs for their reactors which designs are the reactor manufacturers property and are pro, priatory.
The recipients of start-up sources either have NRC licenses to receive californium and other radioactive materials in any form or are outside of the United States.
In neither case is an NkC or Agreement State license for the specific source model required, and thus, registration of the source model with the NRC is not required.
Whether the ' source design is a
customer's propriatory design, design which we generate, the or a result is a source design containing information propriatory to our customer.
Information most start-up source buyers consider propriatory includes neutron output, materials of construction and exterior geometry of the source.
If Frontier is required to obtain a sealed source registration from the NRC or an Agreement State for start-un while FroEtier's sources,tred esti and fore oTose Ents markelgn opmpetitors are n4 5t so reau.
Fron ier,wil Tnis is because the registratlod process invo ves costs, time de-2
lays and, importantly, the public disclosure of the customer's propriatory information.
(We are aware of the theoretical possi-bility of obtaining NRC registration of a propriatory source; we are also aware of the practical impossibility of obtaining such a
propriatory registration in a timely and inexpensive manner.)
Loss of the reactor start-up source market would likely cause Frontier to fail as a business.
(2)
A significant portion of our non-reactor source customers are either exempt from NRC and Agreement
. State licensing or have NRC licenses allowin them to receive including californium g radioactive material z52 and cobalt-60 in any form.
These customers include DOE laboratories and facilities, all foreign customers, and nuclear fuel manufacturers.
While such customers sometimes buy standard sources such as the SRL SR-Cf-100 industrial buy custom sources designed to meet specificsource,tricthey also geome and/or environmental requirements.
Again, specific source licenses are if Frontier is required to obtain not required.
Again, tom source while our competitors are not, registration on each cus Frontier will lose this market due to the
- delays, costs, and disclosures involved in registration.
(3)
Adequate mechanisms already exist to assure that those persons and organizations requiring specific licenses for californium and/or cobalt sources in fact obtain licenses prior to receiving sources.
Specifically, 10CFR 30, paragraphs 30.41 (c) and (d) require that each shipper of licensed material must prior to each
- shipment, obtain evidence in one of several specific forms showing that the intended receiver of the material has a
proper NRC or Agreement State license to receive the specific
- type, form, and quantity of licensed material being shipped.
(4)
The requirement described in (3) above effectively requires us to register and obtain
" approval for licensing purposes" for each source model we sell to persons or organizations who must obtain a specific license or license amendment to receive the source, for the only way they will receive a license for a Frontier source is for Frontier to have registered the source.
(5)
We most strongly object to any provision being placed into our license which would restrict our manufacture and distribution of sources to specific source models or to source models which have been registered with the USNRC. or with an Agreement State.
The only apparent results of such a provision would be (a) to cause the.large fraction of our customers who are authorized to receive non-registered sources to such from us, purchase sources from our competitors rather than and (b) to cause the failure of our business due to lack of such customers.
With reg) a rd to radioisotope shipping containers:
(1 The shipping containers we will use'in many cases will be designed to match a
particular source design and/or a
particular customer's cask handling or unloadina equipment.
This is especially true of shipping containers for reactor start-up sources.
Containers for this purpose generally must be designed to protect sources of unique design and to be compatible with the customer's remote unloading equipment.
Since neither source geometry nor unloading equipment specifications are known with certainty at this time, details of the shipping packages cannot be specified at this time.
In addition, several customers own their own shipping packages and require that their packages be used to ship sources they order.
We must have the flexibility to-design and fabricate special packages and to use customer-specified and/or rented packages,lations.provided that each package used meets ap)plicable NRC and DOT regu (2
Most of Frontier's shipments will be Type A qucntities 3
of radioactive materials in Special Form.
Accordingly, DOT Type A packages will be used for such shipments as authorized by 49CFR 173.415 and 10CFR 71.10 (b)(1).
The great bulk of Frontier's source shipments will be made in US DOT Specification 7A packages.
The specifications for 7A packages are sufficiently broad that special features may be incorporated into the packages while still meeting the 7A requirements as specified in 49CFR 178.35.
Frontier intends to submit its Quality Assurance Program to the USNRC and request that it be approved as satisfying the provisions of Subpart H of 10CFR 71.
Once such approval has been
- received, Frontier may make Type B shipments of radioactive mat-erials under the general licenses of 10CFR 71, Subpart C, provid-ed that each package used has been issued a license, certificate of compliance, or other approval by the NRC or is a
DOT Specification container as specified in 49CFR Parts 173 and 178.
(3)
With regard to your item 6:
Radionuclide,Pd cermet or alloy, or do odel chemical / physical form m
number:
(a)
Cf-252 as Cf/
60 as Co metal, all models.
(b)
Description of packaging:
Type A packages per 49CFR173.415 and/or Type B packages per 10CFR 71. Subpart C.
(c)
Maximum activity per type of container:
Type A:
2 curies of Cf-252 or 1 Curie of Co-60.
Type B:
10 milligrams of Cf-252.
(d)
Type and thickness of shielding.
Depends upon shipping container model.
It is ex-pected that most packages used for Cf-252 ship-la of ments will be shielded by successive polyester,yers steel, lead, and water-extended although other shielding materials may be used.
Packages used for the shipment of Co-60 will normally be shielded by steel and/or lead.
(e)
Maximum radiation level at surface of each shielded container when filled with the maximum activity permitted for that container:
200 millirem / hour unless the package is' shipped as an exclusive use shipment per 10CFR 71 paragraph 173.441, in which case the radiation level at the surface of the package will not exceed 1000 milli-rem / hour.
(4)
We most strongly object to any provision being placed into our license which would impose shipping restrictions on us beyond those specified in applicable regulations, i.e.,
which would restrict us to using packages of specific model numbers or designs.
Such a provision would make it impossible for us to meet the requirements of our customers without first obtaining an amendment to our license.
The expense and the time,d and most require to do this especia11 the uncertainty in the time, would li ely result in our customers buying their sources from our competitors who do not have such restrictions on container design.
The inclusion of such a provision in our license would in no way benefit the public or improve safety and is not required b
the regulations-it would however, most definitely damageourbusinessand benefit our competitors.
Item 8:
Instructions to customers relating to source returns.
In many cases, organizations or persons shipping sources to Frontier will be fully familiar with NRC and DOT shipping be DOT laboratories or facilities,izations or will be regulations, will It is likely that such organ or in foreign countries.
persons.will find detailed instructions from Frontier unnecessarv and/or inappropriate for them.
Such organizations or persons arb 4
likely to have their own shipping and related procedures, and their own shippino documents and labels.
Due to the requirements of 10CFR 71, all shippers of Type B quantities will be of this class.
For this reason, Frontier will~ offer shipping instruc-tions to organizations and persons likely to have need of such assistance but will not insist upon providing such instructions.
A copy of Erontier's " Instructions for Radioactive Source Shipments to Frontier Technology Corporation" is enclosed with this letter.
These instructions may be modified at any time to keep them current, to improve clarity, or to make corrections.
Additional Items:
We have reduced the number of doors through the firewall separating the unrestricted (office) area and the restricted support area from two to one to rovide better entry control area accordingly.ged the floor pfan of and have rearran the unrestricted (ofEice)
Appropriate changes have been made to Figures 9.1 and 9.2, and to Paragraphs 10.9.1 and 10.9.2.
Revised and supplemental pages to our license application reflectin the prepared,g changes and additions described above have been and are enclosed with this letter.
As stated reviously in this letter we are sufferin becauseour license tomanulactureanddistribuke financial losses sources has not been issued.
These losses are a direct result of our reliance upon NRC statements at the time of our application in February that a new license would be expected to issue four to six weeks following receipt of the application by the NRC and the fact that we were given no indication-despite repeated, phone calls to the NRC and yourself-that additional information would be required from us (or that significant delays in issuance could be expected) prior to our three-way telephone discussion with Mr.
Bruce Mallet on May 24 1985.
Even then, the extent of the additional information Eo be requested and of the delay was not made known to us.
As late as April 11 you stated in telephone conference with our Projects and Fac,ility Manager that you expected the license to issue " easily bef ore June 1" then on April 23 " Barbara" told that same Manager that you were, sending a
" letter" to us. You took no calls from us thereafter, nor did you return any of the calls we placed to in the vain hope of getting some idea of when that " letter"you might be coming to us.
That letter was not sent until May 30, and was not received until June 5.
-We feel that we are losin misinformation from and/or delays wighin the NRCcustomers and money due to We therefor request immediate issuance of a
license to manufacture and distribute sources.
If there is any reason to prevent immediate issuance of such a
license; telephone me immediately.
I will come to your offices in Glen Ellyn and if necessary, I will append or modify our application on_the spot.
llg/g Y
-f if e
Edward F. Janzpd, President Frontier Technology Corporation cc:
Mr. Bruce Mallet Mr. Bill Axelson 5
m,gr
. 1.39t FRONTIER TECHNOLOGY CORPORATION 1
- L i I.i ts71 Crone Road = Xenia.chio 463ss e estap 43s 1464
- Teles 119103338287 Easyunk 03546340 L
im b f
p GENERAL INSTRUCTIONS FOR ENTRY TO RESTRICTED AREAS V;i.
! [$.
Restricted Areas are those of the factlity where doors or j'
perimeters are posted on the outside with signs containing
')
the words " RADIATION AREA" and/or " RADIOACTIVE MATERIAL 4
[
AREA".
Restricted areas are kept locked from the outside.
Only persons authorized to use radioactive materials in section 7.1 of Frontier's Radioactive Materials License or i '
who have been trained and certified by Frontier's Radiation Safety Committee under section 8 of that License may enter a e
Restricted Area without escort.
All other persons must be j
escorted by an authorized or certified person whenever they are within a Restricted Area.
1.
PROCEDURES FOR OBTAINING PERMISSION TO USE RADIOACTIVE MATERIAL
- l Persons specifically authorized to supervise the use of-lg radioactive material, and to use radioactive material
' Lw j
- 4.
without supervision, in section 7.1 of the License have r,
gfp permission to use radioactive mat eri al.
Such persons will
' /d have keys which will allow their entry into Restricted Areas v5 at any time.
Other persons recei ve permi ssion to use 7
radioactive materials by being certified in writing by 3
Frontier's Radiation Safety Committee as approved to perf orm
.[
specific operations or classes of operations, involving
'I Y radioactive materials under section 8 of the License.
Such i
t.c persons will be given combinations or keys to locks which l
will allow their entry into Restricted Areas during such times as one or more persons authorized to supervise the use lt of radioactive materials are on site.
License section i
10.9.1 details access controls to the Restricted Areas.
2.
PROTECTIVE CLOTHING (safety equipment)
J Protective clothing will be speci fied by Heal th Physics baned on contamination and safety factors. Available protective equipment includes, but is not limited to, 166 coats, coveralls, shirts & pants, shoe covers, safety glasses, gloves, tongs, and remote handling devices.
If specific protective clothing or devices are required in an area, the area will be so posted.
i r
- 3. HANDLING OF UNENCAPSULATED RADIOACTIVE MATERIAL l.
[
All unencapsulated radioactive material handled by this
[f,(
facility is in a wire or pellet form that is not readily i
J3 dispersible. All unencapsulated Cf-252 is worked with, using manipulators, inside the shielded closed facility. Small quantities of Co-60, which will not cause significant personnel exposure, may be handled nutside the shielded facility. Health Physics approval must be obtained prior to working with any radioacti ve materi al outside of the shielded facility.
y 7
- p
..o r
a ym r
.lv j
@M ;_
d i
f lE Mm!;
Page 2 we 79; 1
?
jh,
l jg '
i j;
4.
ROUTINE SURVEYS
! Q Routine formal surveys of the restricted areas will be e
h:,,
performed by Health Physics personnel as required by the
- p license. In addition operating personnel are to survey their j if work station at the start, during, and end of each work
- g' assignment and report any abnormal levels-to, Health' Physics prior to continuing work. Additional surveys are to be u
i performed any time _an action may have caused a change in i h contamination or radiation Invels in the area.
I is t~
f,
- 5. MOVEENT OF RADIOACTIVE MATERIALS
{p Health physics approval must be obtained prior to moving any radioactive material from the restricted process area.
y i
g i
4 ;<
6'.
STORAGE All radioactive material that is not being worked with is to L.
lrp*/
be stored in the storage tubes buttt in to the shielded I
?. 4^ -
facility or in shielded containers approved by health a
i
} D physics.
Each item must have a tag or label with the isotope, amount and date as required by 10CFR20. These tage j %
may be kept on a tag board provided near the storage tubes.
~
} $
Equipment with loose contamination should be cleaned prior j
M*
to storage. Health Physics approved protective clothing must i
be used when handling contaminated equipment. Minimum A
- ?
protective clothing includes lab coats and gloveJ. If an L
p' item can not be cleaned then i t should be wrapped in l lT plastic, tagged and be stored - in the restricted process
-)!.
area.
{-
l j [
- 7. PERSON Ei. NONITORING
~ p:( _
All personnel entering the restricted process area or other i
i M6 radiation area must obtain personnel monitoring equipment I
! jy?
from Health Physics prior to entering the area. Personnel N
who routinely enter such areas mi11-be issued permanent l !!~
monitors (film badges) which are to'be kept on the board U
provided outside the door to the restricted support area j ' ; M[M j
when not in use. t#iole-body badges must be worn at all times when in the restricted areas, and at any other time when
!g radiation ewposure might occur.
Wrist badges must be worn l f in addition to the body badges whenever radioactive l
?
matorials are being handled by means other than master-slave j ig manipulators.
Health Physics personnel will collect the in monitors for processing on a regular basis.
l ly i O j hl v
B. WASTE
, ?
Waste generated is to be placed in the appropriate drum in le "
the restricted process area. The drums are labeled as
. b appropriate for the source of the waste. No liquid is to be
' h@l disposed of unless it has been neutralized and solidified in 1
, M;j:
l' - lbk -
a
't
- [
~ J.
c,A
@'A' p 3
,r p)} (..?
T: l g ;*
g
=*
, M 'i,
Page 3 JM; -
+
?, bh< 4 GkV cement. Each item or trash pull bag must be surveyed ' pr:ior e,
.b{~
to placing in the drum and the level and isotope recorded on the form provided by health physics. Health Physics pf personnel will calculate the amount of isotope present from Q{f the dose rate.
Health Physics will also designate where g
each waste drum is to be stored and the amount and type of
[!
shielding, if any, to be used.
_ y:
TL
- 9. RECORDS ON T>E USE AND DISPOSAL OF RADIOACTIVE NATERI ALS i:J Whenever the quantity of radioactive materials in a
_ [ }"
particular container er cell is changed, an isotope control
: Eduard F. Janaow, President (513) 426-1656 er (513) 376-5691
- v i,: JJ 5.
Other Companies involved None. Pt JiA 4. i and inue Aetivitys T^ 1 een un-2 10 millieraes mawimum. oali een um,is to be In the fore of Cf=pd gecost N g:s, er the a ley formed by heating the normet te high ra%re. 1 man;, mum radioactive coot,ent is a f unction ei the d' a ve d volume within the capsule, with an abeelute eaminun of 10 me.. A table shouing the maximus califeenium-152' loading associated with various minimum void volumes follows: 3 mg. Ci-252 Minimum void volume (om, s i 2 0.01.44 4 .g 8
- gP41l7l t
10 I 7. Leak Test Frequency: Recommended every sin months. a& S. Principal Uses General Neutron Source Applications. jo aid 9. Custy Meses No. However. sources will tee needed to A partacusar sustomer's spoeificatione, and may be put inte additional sealed or unsealed capsules. 10. Custon User None. 1 e- ,,,.,7.--*.r,-% am- '-----w---r----'" ' ' ' ' " ' ~ ' " * " ' ' " - ' ' ~ 7 h' 1 3 d - i dQ. kk( O. DESCRIPTIVE DATA a 1 1. Summary Descrintion 9 The FTC Model 10 neutron source is a singly-oncassulated californium-252 neutron source.' Californium-252 in the iore !i of Cf-Pd oermet or alloy is sealed inside a tyDe 304L sepaule by tungsten-inert-as (T16) fusion welding. The sa le is ti !I made to FTC drawi AtOO10-AA00 and is 0.217 inch ou side diameter by O.97 i in length. The Cf-252 eatoria is 'i e located in a cavity approximately 0.154 inch in diameter by O.75 inch long. The cavity nay also contain stainless steel a'ted/or copper spacers to position the active material provided that the minimue void volume requirements are maintained. Minimum seal ueld penetration is 0.030 inohes, measured along the plug-to-wall joint. The Model 10 is FTC's embodiment of the Savannah River Laberatory's Series SR-Cf-tX priegry mapsule as described in Appendlm E of Reference 1. Emoept that several dimensions of the FTC 1 Model 10 have tighter toleranoes than those of the SR-Cf-tX, { the capsules and minimum weld penetrations are identical. The FTC Model 10 also meets all dimensional and other spoo-3 i, ifications of the Model 27el-AADO califo 'f-standard primary om e Monsanto drawing A2745-Rev. 2 page 94). The FTC Model 1 meets f.ia,and Amerlean Ngtional standards 3 as published in DOT Special Form ori r 3 Institute (ApSi) classifinstion 64E&e445 by virtue of its j .j-compliance with previously-tested source designs. ) 2. Label e The F Model 10 neutron source is intended to be used i either as a sin as the inner capsule of a multigly-ensapsulated source or peulated su res. leven used as a Model 10 capsule uilt be electro-singly-encapsulated, taprinted with a unique p ial number engravada er etched, format FTC-Cf-XXX in the to identify the manuracturer, iso-tope, and uni r. The capsule will also be electro-RIAL. printed with the words CAUTIONWhen used as the inner capsule etched er s encre RADIOAdTIVE MA the outer surface of the of multi-encapsulated sourceIl be marked as specified above. outermost sealed espoule sha 3. Diagress See Page 3. 4 i of 1 Use coctsikTfMedel [neutronsourceisintendedforvarious '[ The noutron soures asalteations under envi ntal conditions wbich are not deFrimental to the Type L oapsule material. raahy activation neutronradi1ontroIbyactivation i Tyisical uses may include
- r analysis, mineral emenoration l
W analysis and nuolear fuel processscanning. For some rod O, - applications such as those requiring a source of very small i physical dimensions, the Model 10 may be used by itself. l a 2 'l i 1, I s M IQ 4 7 DIAGRAM d-f SECTIONED ISOMETRIC e ,e ph + g ~ 1 We WEL Q.QN nues. 9 tnt Tb610nl e #,4 N
- 4
( / (),. b H[,. !d l$ W i V
- l S, f.9
- 55t3909
. (( > 1 h f ! Neavtry co me N / 844Titant i E I ALSO COMT 88t er SPAC.ER5) I 'jp l I i t j Mj carwar ( n m j MAT *t. : 304 L
- i
-( sr. sre n J e ns=sesse asa ascess=< k FTC Mopst 10 51ANDAMD fffWf4>00 'AWIEC i e 9 l t If ' Q I [p le !I. 7 i 'y 4 For other amplications such as those requiring increased resistance to chemical attack or increased resistance to the Model 10 may be further encapsulated external pressure,itional capsules designed ior a particular in one or more add applicationIul life of the Model 10 source is ex ed to be The use (! that period during which the neutron output is a ate for the intended use. Tests on source designs to whio the ~9 Model 10 conforms show that the Model 10 will meet Special In addition,t Form criteria at the time of manufacture. analysis of the Model 10 capsule shows that it will mee a the Special Form heating test at the time of manufacturer and at any time within 30 years af ter manuf acturer. assuming that the capsula has not been subjected to chemical attack or physical abuse. 5. Supportine Date 1: q The FTC M6 del ron source is constructed per FTC Drawing number At 0-The capsule material is type 304 stainless stee per TM A276 or A479. All dimenstens
- r are shown on the drawing.
The capsule components are then the californium inspected and cleaned prior to assemblyI.he container wire and/or pellet (s) are slaced into navity i? along with any spaser or filler material. The cao is pressed into the container until the tip of the plue as flush with 1,he @R - then welded tungst6n-inert-s (Till) J container,imum aseeptab wele penetratio along top of th fusionwe$d1 d Man J the plug-to-tainer joint is D.0 inches. Spacer and/or 6 filler mater an is eitner stainless steel or cooper and limited in values such that the minimum void volume as specified in re A.e of this document ior the spooiiic + californiva ing loaded is maintained. The FTC Medel 1 seuree meets al1 dimensional and other specifications of the Savannah River Laborateey Berles SR-Cf-Appendis E) and at the 4 1X primer espggle ( orence 1,ium standard primary oapsule californ Monsanto 1 2765-eages 91-94) both of which have been lound to (Reference be acceptet e foe licensing. purposes by the Nuclear Regula-tory Commission and both or which have been certified as r:l Special Form by the Department of Transportation. t x i + T Oe 4 4 e i 4 y e 1 i-i h h-a M hk C. HEALTH AND SAFETY DATA 3 k 1. Safety Analysis Summary i The FTC el 10 neutron source is equivalent to hath the Savannah ver SR-Ci-tX primary oapsule and the Monsente i Model 2765-erteary mapsule. Special Form tests were performed at the savannah Ravec Laboratory shouang at the SR-Cf-tX sou and therefor also the FTC Model i
- roo, e
i meets Caseia ~ ore eriteria at time of manutasture .for details). ANSI tests were - lL Appendis A Corporation showing that tN ciereed by Monsente Resea Mensanto 5 Model 2768-soures and therefor the FTC Model 10 ' ~ source, meets the regulroments i e classification 45Ee6445 was pertermed on the FTC Model 1 n additionInea life analysis (See ApSendia 5 for details). source us ethods spectsied in the AS E Pressure Vessel Code, DIvasion 1, l $a Section Illy and enoumins an internal gas cuantity equa 1 that e;;f z ini 'Anitt desay of the californium. Thas analvels (See: nm C) ghews that for the californium quantity and,ve ve liette stated in Section A.6 of this the F; Model 10 source is able to pass the Special Fore 0 eating est at any time after sealing. 2. Manu eine and Distribution Controles a. i ity Assyrance and Controla Genere Gapsuae -:-:
- .w d s are made irom traceabiAl$
steels sere,1fied to meet Fhe drawing specification. r hardware is esamined ier dimensions, Welding is perIormed by the, and fit and iinish i is cleaned prior to use. l tungsten-inert as (TIS) method usino a proerammable welder e previously prov6n to p#ov and a weldt tration and quality for the parta$de welds of euter the e capsu e des n. Each source is iabricated to a Manufasturing Ordee (MO) 4eh sesoities the californium content Cf /N material,confAguration, other internal components If any, and sauce soraal nuater. That the void volume within the source satisfies the minimum void volume requirement ior the 5 partfeuler salifornium Roads and volume of internals is verisied hefers the MO is rol ogd for manufacture. + Assa Method. ei the eaIowing methods may he used to date ine the radi tive content or the sealed sources iver Assays. Ca ifornium is (t use of Sa eteent of Enerey}e Savannah l l eMained frem the l Rever W ratory ( ) which laborat6ty assays the y eatifornaus prior to shi t. Their assay e are te e to the Natione reau of Standards ( ) and hk to y senstst of comparing the neuteen output of l ?!- es rial toine assayed to that of a neutron tee trated by N35 by p acins each successively i a moderater containins,rs couAting tubeslouter Cf/pd l u When a soures Is made using a part t q wire er sellet er a perticular aroup of wires and/or it pellets Ior.which an SNL assay In avai1able. the radie-estive centent of the source may be taken as that r, y H \\T'l f ,s. A a e* 'WY
- w,-
X reported in the SRL assay documents. When a source is W made usino a portion of a particular wire or pellet er 4 a carticular group of wires and/or pellets for which an SRL assay is available 'the content may be determined by compatison of the neutron output of the source to the neutron output of the item or group assayed by SRL. The comparison shall be made using an appropriate neutron counter such as those described below, and appropriate corr,ections shalI be made ior difierences count rate,ison ofpositioning, and the like. (2) Compar the neutron output of the souros to that of a seuse of known neutron output. The neu outout of the known source shall be traceable to either directly or indirectly. The comparisen sha be, made either by clasine each source sucocesively into e m darator containins 6ounting tubes (similar tb the SJIL method) er counting each source successively using a +b LePerence i etu.rofie correo%Pangher type (see ision nte the andotherta.wes.rri.trawaed. s fo iA oning,i'Mst "? 'rai" "'A'2 i ei i oa i tester"s!"Co source ~ '"vrp American Na tenen 'k Sources, Classifloation$ed N 54 -19 7SSS HandbooE 1 and led Radiomotive i i N~ Sources having less Ihan 0.00E micromurie of removable I d contamination are asseptable and may be shipped to the C oustomer. 11 b. Manu cer's Recommended Maintenance, Servicing, rt and Testine trements for Uses 6 The FTC 1 10 soures requires no maintenance or servicing. Periedio leak testins (dev wipe method) and 1 visual emaninetien for mechanical, ohbmical or other i damaos is recommended. The recommeMed leak test interval is sIx months. 3. Safety lysi Aspects a. Peo esting and Evaluation 4 Maximum et en Levels. Maximum radiation levels per 'i milligram of 25 at e and 30 centimeters from the surface
- t of the soures are summarised in the table below.
The levels i reported in the table are based on dose rates for an un-
- t shielded californium-252 point source as reported by Savannah 1
River Laboratory (reference 4 pages S & 9) .e ' distance using the inverse-squ,are relation., ed. justed f or i j Distance icom seuroe, om 5 30 S. - dose ra w, .4. i O+ 2.4 m 18) / mese/hr 4.8 x 10 Neutron dose rate.,ree/hr 1.84 b Total dose rate, mese/hr 9.4 w 10 24x 10+ Total dose rate, Rom /hr 940 2 6 n ^ h .. K i li l l$ \\J
- ?
- [
k[' Result Tests: Spoena$koresiProthbyStpasof ro the Savannah River SA-Cf-tX n series aguroes were sub ted to the testa specified for Special Fore regiomotiv materials at the Sewannah River Laboratory. Fellowang emeh of the four the test a capsule was enternaLiv pressue med with te,i heti then po tested ior leakage us'ing a het um mass spectrometer k l detector having a lower detoot on limit of 1 m 10*s e ndard oubio centimeters of helium per second. No leaks weqe ound. <2 These tests and their results are resortog in Appendim of Reference 11 the pertinent information gree snet reiseense in Ascendia A of this d-:- i 10 seu showing ) Trnt at with a is reproduoea l BR-Cf g and FTC Mede ei et N th FIC M The b 45aY the S 1X sour and therefer the F Model 10 seuroes meet all Speak ,9ere eriteria, l !s Prototy stins in edance with American l National Sta ed 13 85.10-1 " Sealed Radteactive periermed,by Monsanta Research Clas iteet Sourcesdion is, tend reported in Asterense 23 en Corpora dummy I 7M,AAOO seuroes that the Model l 4 2 y iti_. a the requirements ior 1 etassifioation 6__i riptions ei the test pr tem used and f the its are meesented in A in se the PT Q seures Is in all ways agu valent to the Model 2 65-FTC 1 10 neutron source also meets the re- .i qui ier elassif Anation 6M64445.
- t, t t.
fety Ana sisa The tal F and ANSI tests described above show iy that the 10 neutron seuroe as manufactured is ing senditions of nereal use transport capable of withs and sien fteant atuse in the ieres of,high toep-eraturedion.aooidents,igh esternal pressures, vibrationd mpact and ir, h i y' presente in detail in penetra A life analysis,FTc Model to seuroe usine ? A ndia C, was pertermed the me spogified in the Pressure Vessel Code Division if 1, Scotten III. The analysis shows that the Model,10 will '} pass the Special Form heating test at any time after sealing. E The analysis assumes infinite decay of tue salifornium and j thereby assumes maximum gas quantity within the capsule,. 1T\\; k 8 o 't d n i e 9if I .A .i ~ -M ~' t j.i -
- x n
!j NEFERENCES: U.S.Ab Capsule Assembly Design and Test and Shi pin Energy Commission, South Caroline, 1. Cf Sou .j Information Savannah River OperationsOjiiosf2. Post Office Sox A, Aiken, 29801, May 15, 19 ip E.F. "R The r Manufactur and Janrowh istles"adioactive Souroes,Amor can Myolear E'.. 2. QC Charao p
- - ' M at the et gf Nuclear fechnolog,y E;nhliilt, October 23-1,19at, Seij ne, y in China.
- t; P
3. DePangher J. and Nishels " Precision Lone Counter for L L.,ity"0M Nns Sattelle-Northwest if Measuring, Fast Neutron Flu,m ~ Laboratory, SNWL M, UC-37-6, June 1 N Cf Sources", U. I 4. AtonioEnergyCommisNon,dHandlingSavannah River Operations Off ce, " Guide for Fabricati an Aiken, SoutW Carolina, January 1971, SRO-153. d< !4 ,[ .I id P 3 l * ] $,y P i i i 9 3t I 1 t I 4 i .s m . '. ) : !d Ik 4 -b. l. t 3 ,l' 10 ~8. g. t4 s: $ gi t y,b 5 M. 4 t k ?- u DC I t D g g I-- N* 3 o ec 18 i $. 8 12 I g \\ \\ 4 } t $, lf7 W / // M %. o' l E i j == 1 Pa i I 1 i 1 -u-u g2 \\ r w yd $! t N-d.- ac 5 k n j {It !. c, / t.Q q 3 L 5 k ^s 1., . 1, a i3* ?,i Ys 5 II s s t a v s k k $35. sr r h li k'k Ty (} a, N \\ 8 s 8 ,i s 3 l.,3 a t (
- 4. -'
- i. l s
,r. t h il1g k e agt il . I o 5 % s i
- I c
t II h k in ik k ggg I't %e 3 ;312ij1 2. 4 i I a-I t K f d ' a.,g I. l 'i l ' $ ' pi T 3 g 1 - g% ~ x o t.t s g g ge, $gl St$411 ~~ a 4 tg 1 " 4 I / 3$ 1 ~, - ~ ' R, 7 wc-7 APPENDIX A {] l Special Form Tests, Model to Neutron source. - {[ (with up to 10 mg of Cf-252) j 4 i s j I _; ? k li 1. References i ? ? l / a. Assendia E. Primary Cassule. 5R-11 Series. U. 5. Ateels Energy Cesatssion. Savaanah Alver Operattens Office. I 5 P. O. Ses A. Aiken. 5.C. ,f d } /renfilse%t.km.elgCorporationsourcecontainer.Brawing b. ? Alte48 AA00.
- i a
t I 2. Special Fate Tests ^ f. l Test for special fers materials were performed by the U.S. l Atomic EnePgy Ceamissten. Savannah Ather Operattens Office. P. O. Son A. Alten. South Carolina en the Series 3R-Cf-1X - 3 Primary Capsels. Tests were performed en capsules made of ,l both 304L stateless steel and aircaley-2 constructed to i-figure t.) of reference a. The differences between this !f drawing and FTC drewtag AledM-AA00 are as follows: ,!t 1i { a. fYC drawing speelfles only 304L stainless steel; l b. rTC drawleg allows for marking of hettom of capsule up to 0.003' deep. Note that because tolerance is tighter l l on FTC drawing, the statsum betten thickness of the two j capsules are t%e same; c. There are ne specified tolerance on the SR-Cf-1X capsule for the tapered plus height and the inner diameter of the capsule while F7C dramlas AJee88-AA00 speelfles e tolerasse of 0.085* and 0.001*.. respectively. i = y Otherwise the capsules are identical. The following tests were performed on the SR.Cf-IX-primary capsule: ff 4 Qf a. Free Drop - A free drop through a distance of 30 feet i j onto a flat essentially unylciding horizontal surfase. j' striking the surface in such a positon as to suffer maximus damage. b. Percussion - Impact of the flat circular and of a 1.inah h f diameter steel rod weighing 3 pounds. dropped threegh a j 'j distance of 40 inches. The capsule or material shall be placed on.a sheet of lead, of hardness number 3.5 to 0 4.5 en the Vickers scale, and not more than 1 fach thick, supported by a smooth essentially unyleidtag surface.
- (
4 f Heatles - in air to a temperature of 1475*F (800*C) and c. f remaining at the temperature for a period of 10 minutes. d. Issergien. Immersten for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in water at room tea. ) perature. The water shall be at pH 6-pH 8. with a mast-mun seeductivity of 10 mocromhos per centimeter. + After each of tha fevr tests the test capsule was externally pressurised with 300 pst helium and helium leak tested. At a lower detettlen limit of I x 10~6 standard cubic centi. meters of helles per second no leaks uere detected. Therefore (ht, 3R-Cf.1X-primary capsule, and because of its similar construction FTC Nodel do, AA00, passed the special d form tests. 1l l .g l b P' i. C. t 4 7h dk N APptHDIX 6 A815I Tests. Model ? 76b-A Aug ( M o NS M4TO) [ 'y,h n If F f), ' [), ' 1( 1. References
- f;
?\\ f a.
- Classification of Sealed Radioactive sources by Walted
)Ti a i States of America standards Institute Inc. as approved bl q8 g' 22 Apr11.1968. y{,0 b. Mensante Asseprch Corporation source contaleer. Orawings t A2765 4A40. b. a{ 2. ANSI (USASIl Test Results The duesy peerse was constructed as shown in drawf ag A2748.AA00 Rev. 2. Tbg phystsal differences between this drawing and drawing A2785.AA89. Rev.'s are tighter tolerances en the Inner diameter and the bettee thickness. The tighter tolerance en the bettee of the espsele allows for identificalien marklags l. en the bettes serfose per note 3 so that the minimus thieksess of the balles is within the specifications of drawing A2785-AA80 Rev.-2. { All ANSI tests referred to in this appendia except the vibratica test were dose et fitasente Research Corporation. The vibratise text was performed by Sewser.Morner Testing Laboratories. Inc. of Dayten. $his. 'u t. L h II e 1 l a' 1 v
- .a l9 a.
Temperature Test 6 j p .* y j ,z R 3 fi Model No. A2765-AA00 dummy source was tested to temperatu 6 as specified in Section 8.2.1 thru 8.2.3 and evaluated by leak f test methods 82.6 and 82.9. After the dummy source passed 82.9. ?.. [ the test was re-run at at 300 psi with a pressurization time of i f D.. 30 minutes. -g;. .Ih.- ') Results
- c 1.V Model A2765-AA00 was tested and passed this test.
!}' 4 . b Classification 0 l L e O b (lf
- f Monsanto Model Musber A2765-AA00 meet the criteria for Temperaturg; (,.
f ![ Test 6.htch consists of holding the dummy source at -57' and 'N h 1010*C for one hour each and then returning to ambient conditions h, 't[ in the test chamber; thermal shocking from '1010*C to 15'C in g . ate,. .y i j 4 x(k. ' 4 1 ? O s. 6 =- .c- .:y ; t i p h kh; - b. External pressure Test 6 'y ' a. c s 'd [:. Hodel No. A2765-AA00 dummy source was tested to external pressure lg-class 6 as specified in Section 0.3.1 thru 8.3.2. Evaluationwasj' Ij by visual inspection and as specified in Section 82.9. s ,i ii i i j j J~, (j Results i *- Model A2765-AA90 was tested and passed this tost. 3 k p,. j- 'i t. Classification i, $i-yI A \\,c Honsanto Model Number A2765-AA00 meet the criteria for Enternal j,i Pressure Test 6 which consists of exposjng the dummy source to f/p a vacuum (3 4 psia) for 15 minutes, repeated four time and a pressure of a 25.000 psia for 15 minutes repeated four times. l f l I e i g: 1.i k '* s. ' I, h h g .e; k } t l i t2 h-t h l} j ni $f y h y }f c, Impact Test 4 W PJ j m., v' u 9 4;f Model No. AIF65-AA00 dummy source was tet.ted to impact class 4 lfi( g, m as specified in Section 8.4.1 thru fl.4.3 and evaluated by leak , SY; ' f[if y, test methods B2.6 and 82.9. Af ter the dummy source passed 82.9,l[ I the test was re-run at a pressure of 300 psi with the time '[ increased to 30 minutes. [ ] i;'I* c
- 6 v..-
Results y @!l .[hb i Two sources were submitted to thjs test. Both dummy sources l' 7.'d I; tu g-H rA were distorted, but the hermetic seal renajned intact. zi. d ID 1 f4 ik il; j '? . M Classificatten - W~ d 0 .l i ,t y-Monsanto Model Number A2765-AA00 meet the criteria for Impact ,{ e to ') f~ Test 4 which consists of a 20 pound weight dropped 5 feet onto s' h the source. .tl ?'nf 9 E i 3 h g { y ) iF i 1 t A
- 7.._
h= ..a u 4,. y i I h b v d-- Vibration Test 4 1. 14.. , This test was performed by Bowser-Morner Testing Laboratories, 'laj i l 5 p,Inc,ofDayton, Ohio. This outside testing is covered by Boswer- ' ijpi IT Morner Report No. 20464. Bowser-Morner reported no dummy source Pi .i failure. 'j i L. y hlResults 4 + j. Two sources were testoy and both passed. j;>, 1, '2 [ h Classification (;;. 5 fu' f i. . Monsanto Model Number 4M45-AA00 meets the criteria for Vibration rr Test 4 which consists of vibration for 90 minutes, 25 - 100 cycles / .' T n.i,
- m:
sec, at 0.06 in. amplitude, peak-to-peak and 100 to 2,000 cycles /
- J O
sec at 30 G. - g 1 g .1=. kt g oa ,t Y i 9 e khiy [ f, e 9 -7 I ( h.. R Rn e. Puncture Test 5 g $? h jiModelNo.A2765-AA00dummysourcewastestedandevaluatedbyleak I test methods 82.4 and 82.9. The pin was dropped onto the source from 10 feet. To compensate for the difference in height (ANSI f L [ Puncture Test 5 requires 15 feet), the weight'of the pin was r a p. increased to 1 1/2 times the weight of the source. The energy h absorbed oy droping the source onto the pin from 15 feet is q (15 ft)(W) where W is the weight of the source in pounds. The ( i fb energy absorbed by dropping a pin of weight 1 1/2 W ten feet is 9] (1 1/2W)(10 ft) = 15 ft W. An additional 6% of the weight was y b added to the pin to offset the small drop resistance offered by j the guide tube. The actual weight was made from a 1/8" drill 1 lf blank with a 1/16 radius ground in the nose. The weight has a ) I [ rockwell hardness of 58 on the C scale. The pin was dropped through a guide tube. Both sources were tested with the impact of the ) _ j puncture pin stricking the side and on the welded end. ] l
- d; Results j
d Each of two duasy sources tested received a slight indentation in l D the welded and and on the sides of the sources. All dummy sources ~ submitted passed this test. ? b e [ Classification Monsanto Model queber A2765-AA00 meets the criteria for Puncture Test 5 which consists of dropping the source 15 ft. onto a 1/8 ] inch diameter pin. { l 9 di ji h) h e ff] { f APPENDIX C y Life Analysis, fic @dgl go Neutron Source pf i (with up to 10 mg of Cf-252); 1: c! - 1.0 References ~ \\? a. Rules for Construction of Nuclear Power Plant Cessements. j j Section !!!. Division 1 Subsection ND Class 3 Comtesents. ? 6 ASME Soiler and Pressure Vessel Code. 1974 Edition. The American Seclety of Mechanical Engineers. New York. 1974. l1 1 b. Steels far Nuclear Aeslication Section 3. United States 2 Sted) Corporaties. Pittsburgh, Pennsylvania. 1g67. kN Q: frorttittMAshyCorporationsourcecontainer. Drawing I c. AI00d&AA90 d. W. D. Burch. J. E. Sigelow. and L. J. King. Transurantes Processina Plant Sealannual Report of Production. Status. and Plans for Ferted Endine Dec3 &er 31, 1971. ORNL-4767 Oak Ridge settenal Laboratory. Oak Ridge. Tennessee. May. 1972. p e. Personal Commentsstion. D. E. Troutner of the University of Nissouri. Celsebla. Misseurl, to C. C. Robinson of Monsente Research Corporatten. Dayton Ohio. March 20, 1973. f. Chart of the Nuc11ees." Tenth Ldition~ Aevised to December 1968, prepared by N. E. lloiden and F. W. Walker,
- u. S. Atomic geergy Coasission. Knolls Atomic Power Labore-tory. In Radielegical. Health flandbook. Revised Editten.
U. S. Departecat of Nealth..Edrcation, and Welfare. Public Health Service. sockville. Maryla,nd. January. 1970, pp. 69-85. )u i Y. b f, g.
- 8. Srinivaspa. E. C. Alexander. Jr.. O. K. Manuel, and 2
/ D. E. Trouteer. " Xenon and Krypton from the Spontaneous k 7 Fission of Californium-252."',Pjjysical Review. 179. March 29,1 1969. pp. 1166-1169. h. H. W. Schmitt. W. E. Kiker, and C. W. Williams. " Precision i Heasurements of Correlated Energies and Velocities of i I 2 52Cf Fission Fragments." huical lleview. 137. February 25,[ 1965, pp. 8837-8847. [? tij i.
- Primary Capsule. SR.Cf-1X Series." as],Gf Source and Shisolan Cassula Assembly Design _gnd Test Intersatten, s
'l Appendia E. it. 5. Atomic Energy Consission. Savannah River Operaticas Office. Aiken. South Carolina. October 1973. \\' ~ , i q 2.0 Analysis i It is the policy of f*vn.'n. T.J.. Ly Corporation to perfera v source analyses on s "werst case basis"; that is, to assume that, tolerances en saterial propertiet..-dimension. isotope loading, etc. will assunulste so as to result la minimum capsule 7 strength and saatava stress. With respect to capsule dimenstees, this policy results in the following: A. Capsule dimenstens to be used in stress calculations are ,4, those based on tolerance limits which product the thinnest f wall and the thinnest heads. 6. Capsule dimenstens to be used in calculating internal pressure build-ups due to isotope decay are these based os tolerante limits which product the smallest internal volese, Additional geeservative and worst case assumptions are used in the analysis. and are noted therein. The capsula stresses are ~ t ] C T -f 3 S t. ' {. ?, s 4 I t> calculated using the methods specified in the ASt1E Pressure h Vessel Code. Division I, Section 111. fven under the cumula- ? th(j } tive conservation of the ASME Pressure Vessel Code and the numerousworst-caseassumptions,thecapsuleisshowntobeable'jy' to pass the Special Form Heating Test at any time. j 'i t - 1.
- s..
y pi 'k- 'h'fW .l [ I p v; y,. , jf 1@ij a
- 1
' ')
- i.
if z j': ex a n, p-w ?
- e I
t Y y
- s ft iA 1
l t I e l, .?.l 9 J / , i.!. t ,c s i% ; L p 2.1 Cassule dimensions .'; ;l 3 f 'l 2.1.1 Dimensions per drawjn,g. numi'er Atosto-AA00. Rev. O. 3 L'
- b 3.
3 0.0.. 218/.217s d I.D. = .154 2 .001 i 0.L. =.950/.970s r f .155 .005 t = Thickness of he?d = h g t = Thickness of bottom =,.075/.072 f i b y; ..t -h } ' !;?- rg f#^ 2.1.2 Olsenstaas to be used for stress calculattens unu if 'f (0 0.) (0.0.) - (tol) = .217 i = '{ l (i.p.), = (l.p.) + (tol) = __ .155 (t,), Wall thickness = 1/2[(0.0), - (I.O.),) = = 1/ 2[,, .217 .172 _) = 0.0225 l (t Is
Head thict. ness e [(t h - tol)
h 4
(Q, setten thickness twi, - sotto marklass -
[.072 002) =
.070 2 1.3 Diaensfees to be used for internal pressure calculattoms (1.8.), = (l.D.) - (tal) *..
. J,5 3 (l.'L.), = [(0.L.) - (101)] - (th + (101)] - (tb + (tel y.
.970__..__
.160-
.075 e
.=
e
.735 i
1 l
t l
,0 f
e
/
,.s j*'
. }'.;
s-
'sj a.
Internal Volume a j(1.0.)pl.L.)p=
.j.
..ji 4[f
{(j53)2(.735.)=
.013 in8-
.013__in x 16.39 cm /in3 =
.213 seS$
}4 3
8
=
w i
d 6
'e j
[s 2 l
ca.
i LT *-
o
- 3 4.?
g b
. p.
4
?
.' ?L ci
.; 1 I
j
- Q V
t 9
i s
3
- N g
.p,
{f f, l
't l.
A
?
if 4
4-
- j J
4
~
f
\\\\
e V
Y a.
7 4
[
s y,
fil tj 4
6 k
J
r,
- g n.g
[ I
[.
3.0 Stress Analysis
.k a
Here,themesimumpermissibleinternalpressurefortheprimary{f]
capsule is determined by methods of analysis given in Rules for Ib P
Construction of Nuclear Power plant _C egu ents. Sectfen III.
[
Division 1. Subsection NO. Class 3 Components. A5ME Boiler and j
Pressure Vessel Code. 1974 Edition (Ref. 4) for the heat test ten.perature of 1475'F and assuming infinite decay of the a
callfornium.252.
g
. ;(
h
- Now, l'
at assembly, the plug (F7C drawing Aloe'#-A400) is pressed into the Cf.352 primary capsule body and sealed in place by y
i fusion welding.
The resulting closure is assened to be at least j
.as strong as the unwalded, screwed-in end cap coeffgeratise f
depleted by fig. 50 3325-1 sketch (q) of the ASNE Code (Ref. a. )
- p. 47).
Accordingly, the allowable internal pressure, P ' I' b
g N
psia, as lietted by stress in the end plug (head stress), is taken to be reisted to the thickness of the ping, t, in feches, in the menner specified by the Code for fig. ND-3325-1 sketch (g);
namely (Ref 4,
- p. 48), t. D/CP /5 where D is the major dia-H meter of the tapered plug (inches). C is a dimensionless facter dependent spea_ such considerations as the method of attachment of p--
the head and the shell dimensions, and 5 is the seminus allewable stress value (psi) obtained from the applicable table of stress S
values in the Code.
Solving for P,.
y t
- OfGF l5 y
y ta = 38(CP /5) y Py = (ta/C08)5 y
'. J p
g s
g --
h'
[7 Here, per the Code discussion regarding sketch (ql. C = 0.75-
- j
,g.
l[
(Ref. a
- p. 49).
Also, going with worst-case values (Appendix.
f if
?
gW C. Section 2.1.2). t = 0.150" and D = 0.172".
Then, for the I
E welded end.
.L 7
3 s
j; 2
2
= (t /CD }$
a -}
j.
P g w
[(0.75)(0.172")2335 0
= ((0.150"):
- f
,;@(
I
(
r
= 1.01 5 g
? te
- p 4.?
s 2 7;, $
g For the non-welded and, the same model may be employed upon replacing 0 with d. where d is the inside diameter.of the capsule 4 jf j [
~
g$,,
M it s.
(inches).
Here, t = 0.070" and d n 0.1f5" (Appendia C. Section 7, 'j h QJ f
2.1.2).
Thus.
t
- % : })
vt.
uc 4 k
P
=(t/Cd2)5 1@ ]
H u
n
'i 1 N i :l
[
= ((0.070"): #
[(0.75)(0.155")2335
= 0.273 5 Returningtothewe}dedand.thereistobeacknowledgedforthe head stress analysis here employed the requirement that, as stated in the Code discussion regarding sketch (q). design of the weld joint against failure in shear must be based on a factor O
l of safety of at leest 4 (Ref
- s. p. 49).
For the seal weld joining the plug to the capsule body, the area in shear is j
A3 =
Dt,. where D is again the major diameter of the tapered l
l plug (inches) and t, is the weld penetration (inches).
Acting lj over the area AF = (s/4)D8.is.a force given by F = P A, where j
SF j
p is the head-stress-limited internal pressure (psta).
The l
3 resulting shear stress is $5 = F/A3 = P A /A3=P3. x l
S7 (w/4)0 /wDt,= P D/4t,.
f 2
5 1
3 if
(
[
=
I
[
.r
- t Introducing the safety factor of 4 the shear stress developed M
is the maximum allowable (l
[
is limited to $$ ' II/4)35, where 55
.h(s value of the shear stress.' Thus.
m L
}
(1/4)S
- P D/41, S
S h,
j a
t or 3* = P D/t,
[
5 g
1
{
Taking the spsimum allowable shear stress to be half the naufose.
(1/2)5. se that (1/2)5 e p
allowabis stress value in tension. 55
=
Soleing for P '
)
'}
5
+
1 P
m (1/4)58,/9 l
s 3
- i. I t
l
- St,/20 J
1 5
1
- ($,/tals 4
~
Specified for the ss11forniva capsule closure weld (Fft drawing Al#### AA00) is a alaisum weld penet ration of 0.030".
As before, j
De D.172".
Evaluating.
[
i rj P5 * (4,/2D)$
- (0.830' e [(2)(0.172")))5 i
= 0 9872 8 f
i.,.l
.I Also to be considered are the maximum permissible internal pressure values obtainable from the Code for stress limitations withir. the primary capsule shell.
From paragraph #10 3324.3 e
(Ref, a, pp. 39.and 40) for the cylindrical shell in question.
the internal pressures ilmited by circumferential and longitu.
j(
l dinal stresses are, respectively.
l
)
1
j.
A.
i
(
- set, j3
-}j PC " R + 0.6t r 4
4
= [Et e (R + 0.6t I33 r
r N)i and
.y ISEt I t r
P t = R - 0.4t, l
4
= [agt, e (R - 0.4t I35 n, l r
.j whereEisajolatefficiencyfactorhavinglathisinstancetheh value of E = 1 stase -- the only weJd being that sealing the
[
plug to the body -- there are no joints in the capsule cylladel. N can shall partien proper and the head (plug) is aise seamless k)
(see paragraph NS-3324.2. Ref. a, p. 39) t is the c'nfaus
['
r required shell thisksess which is here simply equivalent to the.
wall thicknots et the welded end of the capsule where it is the thinnest (lashes). A is half the major diameter of the tapered ping (f aches), and 5 is the maximum allowable stress value (psi) as befort.
Agata go. lng with worst-case values (Appendia C. Section 2.1.2 and FTC drawing Alses*AASS) t, = 0.02250" and R = 0.084".
Then, with R + 0.6t a 4.0840' + [(0.6)(0.0225")) = 0.0995" and R < 0.4t,a r
0.0860". [(0.4)(0.0225')) = 0.0770".
l.
PC
- EfIr * (R + 0.6t III r
- (((1)(s.0225-)) < 0.0sss is 1
- e.ats s l
_b nj
v.
vn, s
kk;I4
) Ij~and Pg = [2Et e (R - 0.4t I35 r
r y
k
= ([(2)(1)(0.0225")] : 0.0770"15 i./
B
= 0.584 5 II
[x A cor::parison of the five pressure relations (P 1.01 S.
=
gw
['
P
= 0.272 S, Pg = 0.0872 S. PC = 0.226 5, and Pt = 0.584 S)
H y
n C
), '
shows that the critical expression is the one derived from the k
shear stress analysis; namely. P3 = 0.0872 S.
To calculate P,
3 it is only necessary to arrive at the figure to be used for 5.
?
4
).
@$ The capsule temperature during the Special Form Heating Test is
[1475'F.
Here, then, 5, the maximum allowable stress value (in tF.
.4 (:
C tension) for 304L stainless steel for metal temperatures not exceeding 1500*F is taken to be the 0.7% offset yleid strength at 1500*F. down-graded by 20%.
The 0.2'i of f set yield strength
(
of type 304L stainless steel at 1500*F is 9.400 psi (Ref. b,
- p. 45),
g g
y;' Accordingly, the maximum internal pressure permitted in the cap-i f
sule during the ten minute Heating Test is:
(
/l P=
0.0872 5
.r.
P=
0.0872 x (9.400 x 0.80) i P = __ 655.7 psig 670.4 psia j
=
t 1
~
(y p?ja
- r
(,
p.
I_
1 z
't I
1 4.0 Physics Relations jjitj 2 J
$U Employed in the analysis is the MRCEP-Cf2 program developed for P[
[f an IBM 370 computer, using the " Continuous System Modeling Program !!!," a digital analog simulator program.
i
{
6 j
The basic differential equations incorporated in the computer i
program are as follows:
For seCf 45, dNas..g,,y,,(g) 2 dt mq t
where Nes(t) is the Cf.24g atom popujation as a function of time, g
- [f(
and As, is the total disintegration constant for Cf-24g.
g g
I For esCfaso,dNas=-As[ Nee (t) di
~
g y
y I
where the rest of the notation jn this and subsequent equations j
is to be interpreted in Ilke manner to the preceding.
h for geCf 2s}, T.
3,{g,3(t)
Ms K
2 dNs2 For geCf sa, Y. -As Ne7(t)
.v se r
For ssCf 53, 788=-AsfMg3(t) 80 l
2
- 884 s e C f '* ", T = -As Neu(t)
For There are, moreover, equations for the nurlfdes which undergo spontaneous fission, 9
e i
O'..
Dt-
s
$F tj dNas.3l(Nas(t) dt whereA!sistheCf-249partialdit.integrationconstantfor
[jj spontaneous fission.
{
i v
dN!!=A!!Neo(t) f N
dt f
i
.).
dN!!=A!!Nat(t)
A-34 dt g
M N
dil!(*1l(Nat(t)
I i
dt
}
Next are the alpha decay equations, related to helium gas pro-
).
~
L duction, there being one alpha (leading to a helium atom) released per disintegration.
a:
{
dNsj, gsgyesggg dt where1)istheCf-249partialdisintegrationconstantfor 8
.;4 alpha decay.
Ae M.. =nlNeo(t)
F e
dt i
1 dHui.1,1Naitt) dt l
{ej= lejNs:(t) dt dN$.g,ggg(g) 6 dt l
9 r
[:.
i 1 '.
1.
< > e.5
- f-4 a
l a
dit l
! 53 64 =As!Ns4(t) i k T
l 1 j? '
3 l.:<
Besides helium, fission gas is generated.
The quantity of h~
fission gas produced is obtained by summing up all fissions E
occurrino spontaneously and multiplying the result by 0.18 gas i
atoms per fission.
(How this factor is arrived at is described j
in the next section.)
t k.
h 1
.i I
j i'
i y
(.
4 s
j; %
4-
.;f
=
,,e a
l, e
f 4.
L h'
f' 6
O a
9
A
-r ~
- 5
/*I A
5.0
- Dgg, Q'i Q-
{g Appearing in the differential equations listed in Section 4.0
- y '
are various disintegration constants -- partial, as well as p'
h
/;
total.
Basically A. (0.693)
(tf,).Q)r,e,heret
(
w is the half-g 11fe.
Thus. AT = (0.693) :
lic the superscript T for
~
total really refers to an effective value insofar as the half-ny.
e t
life is concerned, as given by e
1 1
1 0
/"h f Y
i 4
4 k
[
5 where t( is the partial half-life for a decay an.1 1 is the partial half-life for spontaneous fission.
Similarly. A' =
b i
k (0.693)e(t()andASF. (0.693)
(t().
3 It follows that AT, t
SF xa, 3 5
i w
Now, reproduced ja Table 1 is a portion of Table A-1 from the
/
Dak Ridge National Laboratory Transuranium Processime Plant Semiannual Resort of Production. Staty,s,,_a_,nd Plans for Period Ending December 31, 1971 (Ref. d).
To make use of the data tabu-Icted therein to obtain the disintegration constants sought requires deriving a number of expressians by algebraic manipula-
[
tion.
1 T
To employ the branching ratto a/SF in determining A. for example, l
noting that (e/5F) = (A*/13I),
L U
xT. x= +,$F c,5r4>
l
. x =, (L.Fa* )(a*)
S e
y
~
, 1-I 4.
I I
= 18+
~
-(A*)
ig-(h)_
,y I:
i
- ;.y s
1 a A
'g 4 if o
I~g57).
~
1, O!
g.
1 -
((
, 0.693 j,
1-
((
t{
(gp)
{
Then, as a sample calculation, using Table 1, for the Cf-249
~
[
total disintegration constant, l
j-T, _
0.593 1
(j,
I (352 yrs.)(3.156 x 10 yr.)
~
1.992 x los}
3 7 IIC-v,
~l
= 6.238 x 10~31 sec"3 2
The other disintegration constants are arrived at in like, manner,
_r if not by means of the one algebraic relationship already derived,
- (
then either by the basic defining equations or by the following
[
additional derived expressions.
T a
1 3
3 1* +
i.
Id!
t r
1 n
3 u
1 1
1+
j (f)
T l
SF,
A 3
(g) + 1 0
-~
~
{
Table 1
[4.
s
_1
,fM:
s.
Californium Half-Life Data *
- jjf, v-tf f Partial lla1f-Lif e i;
Total Half-Life for'e Decayj _
Branchine Raties i't
- w a y n/5F=(1.992*0.040)afles Cf-249 352 26 y Cf-250 13.08 so.09 y a/5F = 1260 *40
,r i ;Ii Cf-251 900 150 y yj ki i
t t-Cf-252 2.646 30.004 y s/5F = 31.3 20.2
,i [
{
s/8 = (3.1 t0.4) x 1978!
l
,' Cf-253 17.81210.082 d I
s/SF = (3.10 #0.16) a Ig's Cf-254 60.5 s0.2 d
- Quoted f rom Table A-l. lief. d 1
)
j i
l l
l e
l
k.'e I
y' N
p 4
The disintegration constants, obtained as described, are recorded
(
p G
in Table 2.
9p The 4]
1 Listed in Table 3 are the neutrons per fission (v) factors.
source of the data is again the Oak Ridge National Laboratory jl report (Ref. d).
p*
f(i
.h The fission-related factor pertains to gas generation.
Signift.
- ji 3
]
cant insofar as Cf-252 spontaneous fission gas buildup (Ref, e)'
I l
are the isotope products, together with percent yields, listed
.in Table 4.
Now, the som of the yields given in Table 4 is 15% (rounding up).
Adding 205 for conservatism (the overall f
uncertainty is more likely to be s 105. Ref. e), the factor a
sought is then 0.15 + (0.20)(0.16) = 0.18 gas atoms / fission, I
Although strictly applicable only to Cf-252 spontaneous fission.
[
j.
it is reasonable (Ref, e) to generalize this result to embrace I*
l the other californiva isotopes.
a j
p Lastly, required as general input are the initial values for the I
l number of atoms of each californium isotopic species present.
Recalling that the design analysis is predicated upon 10000 pg l
g (10 mg) of Cf-252 (maximum quantity) and referring to Table 4
}
l I
for the pertinent isotopic mass, the initial number of Cf-252 atoms. N a', is [(10000 x 10~6 g)(6.0225 x 1023 atoms / mole))
a j
(252.08 g/ mole) = 2.383 x 101S atoms.
To obtain the values for the other cattfornium isotopes, it is first necessary to arrive l
the total number of (undifferentiated) californium atoms.
at
/
According to the Savannah River Laboratory typical analysis for cerset (Ref.1), the californium is 82.5 atom 5 Cf-252.
Pd-Cf,03 Thus, there are here (2.389 x 10lS Cf.252 atoms) e (0.825 Cf-252/
i Cf) = 2.896 x I0le Cf atoms.
Using this number, together with the referenced typical abundance figures, the remaining values l
are calculated by straightforward multipilcation; for example, 1
atoms.
forCf-249.N,l=(0.04)(2.896x1038 atoms)=1.138x107 In practice, this entire calculational, sequenco for determining i
l J
i Y
7
---q L
vtl
'. ' * %e l
1 1
T NYI
-Tabic ?
l
'; d-M hl Disintegration Constants for Californium (sec~l).
- 3.,..
. wg5g ii.
Partial Disintges, j
i.
Total Disintegration Partial Disintegration tion Constant for i
Constant
_Constan1 forln Decay
$sontaneous Fission,
6 Cf-249 6.238 x 10'13(1, )
6.238 x 10ll(A ng) 3.132x10'38(n!!)
fCf-250 1.680 x 10(As )
1.679 >. 10 9(4 ")
1.332x10ta(g((}
3
- s+
ICf-251 2.440 x 1018( As!)
2.440x10ll(AaY) 7
}Cf-252 8.299x10(As!)
8.042x10S(AE) 2.569x10se(gl[)
t Cf-253 4.503x107(a 1.392 x 10(4:5) s 3 lCf-254 1.326 x 10~7(As ) 4.098 x 10'88(AsR) 1.322 x 10 7( Al() I a e 47 I s
- /
l l O f
r, .2 l 4' Table 3 4.. j y { (i.. 1;.. Neutrons per fission factors l I f i t, 4f , r. p ,f v (n/ fi s s i onj,* tj '7 s: Cf-249 3.44(va9) ,k Y 6 Cf-250 3.56(voo) [ t
- y.,
cf-252 3.796(una) ~ Q-a } Cf-254 3.90(vs s. ) - ;^. t
- ?
4 i
- Taken from Table A-1, Ref. d.
omitting associated notes and uncertainty values 4 -) v. s e k l
(# . - ; z, rA I ,A:' s. 1. ih the initial stos populations is performed by computer. Data i and findings are summarized in Table 6. ?$ t i.t li ', ,f[ ) j 4 a: \\} l
- +
" Y ;- 4 th a: i li ;. i hii 4 t n 1 !)f, + TN >2- _I{1 T$? !^. i' 1 3 J,. e t 6
- 1 f, -
f h
y y,, q %i 3 T'; 4
- t. q.
} Tabic 4 4' s; 't Isotopic Mass * '. ~ i c, - ,a j 'I !sotopic Mass l, .i I' 4 i. g ,l Cf-249 249.0747 4-g.. S- ~ Cf-250 250.0764 I h Cf-251 251.08 y r; Cf-252 252.08 %'na u 1 bli -2 H. 253 ' ~ Y, Cf-254
- 254, f)
S
- Taken from Ref. f l
t, 4 3 I L
rf y,. . t ',' 1able b ~ i t,3 j Hass Vields from the Spontaneous fission of Cf-252 j. t r .f -f Percent Yleid lp t r ' f. - Kr-83 0.051* ), A i' ,F ~ 0.085* e Kr-84 t i Kr-85 0.109= = Er-86 0.156* h Xe-13} l./3** 1 i Xe-132 2.57** 1,;.- Xe-139 4.45** i ~ Xe-136 4.953** 1-127 0.171*** 1-129 0.557*** -j
- Taken from Table II, Ref. g, the l' ail No. 245 data I
(considered by the authors the more reliable for the fission yiel'ds of krypton), omitting associated notes 1 and uncertainty values
- Taken from Table II, Ref. g.
the l'oll No. 237 data (selected as having the greater magnitudes and hence being the more conservative of the two sets of xenon yields), emitting uncertainty values
- Token from Table 11. Ref h
h
't. .k h,. Tabic 6 .j. M 1 ir.itial Californium Atom Populations .l r J, c c. i}- d k! n! Yi ,? o 4, Aton 5* lL(.3, tons ) ip p k i e i $9 Cf-249 4 1.15H x 10l8(Nas) .11 y.. j g l Cf-250 11 3.186 x 10 "(Neo) l;; 8
- (
Cf-251 2 8 192 x 10 >(Neg) l ?? 0 h ;f. Cf-252 82.5 2.399x108'(No!) i -a t ') iL }3 ;i g ) Cf-253 0.5 1.448 x 10 87(Na ) i i 4 L 6 d}i. Cf-254 <0.025** 7.240 x 103 5(Nn) )$ l
- Quoted from the listing entitled " Typical Analysis -
Cf", Ref i 9
- Taken here for this analysis to be 0.025 p.
it S I% %? k 9 I e e i . ]
I 5. o, f6.0 Void Volume Calculation tr ? [5 From the program previously described in Section 4.0 the number ,E of gas atoms due to californiuna gas prnduction (decay helium { plus fission gas) as a function of time (in years) is found. 1 Table 7 lists the number of gas atoms per 10 mg of Cf-252. At 5 the end of 100 years, the percent of Cf-252 remaining of the 1 ( ) original number is found by the universal decay law to be I N/N exp(.ht) = exp(-(In 2 x t : T )) = g g exp(-) n 2 x 100 yrs. 2.646 yrs. ) = 4.2 x 10 12 4.2 x 10~80 't y = a d k where number of atoms of Cf-252 at time t j N = f N, fnitial number of Cf-252 atoms present = decay constant from Cf-252 =1 n ? : T 1 = g half-life of Cf-252 = 2.646 years T = g time, years t = l Thus, the percent of atoms remaining of Cf-252 after 100 years of decay is negligible. Other isotopes of californium, parti-cularly Cf-249 and Cf-251 continue to be present due to their long half-lives. However, they are a minor cons tituent of the total californium initially present (see Table 6). / l From the number of gas atoms generated, and the maximum internal pressure permitted in the capsule during the ten minute heating test (calculated in Section 3.0) the amount of void volume required for a glyan amount of californium is calculated. Two terms comprise the pressure. The first is that due to l l l s l l J
ftt. : r L I, s j, - fc-g y s californium gas production (decay helium plus fission gas). I j Denoted by N is the equation to follow, the total number of i f/ californium-generated gas atoms corresponitings to 100 years is 4y read from Table 7. I. mg i N 1-p As to the second term, there is initially a pressure inside,the l FA d californium capsule of I atm at 71*r (295"K). 3" -dB The total pressure inside the capsule is, then, t ?
- w h
(N)(0.0821,*, $ )(84. % )(Ta) pl (6.0225 x 1088 atoss/ mole)(V, cm )(1 x 10'8 a/cm8), E 3 i + (14.7 psi)(2 'K I 4 M where p is the maximum internal pressure permitted in the ) J capsule during the ten minute heating test; ,Ih N is the number of gas atoms !enerated; 3 To is the heating test temperatue in 'K; and v, is the veid volume in cm). 4 0 g From tnis expression, the void vola =e is (N)(0.0s21)(14.U S ) Y il v " [P-((14.7)(T,) < (295))](6.0225 x 10: 3)(1 x 107) t , (2.00 x 10~28J.N_Tg_ [p .0438 To] l Since To = 1475'F = 1075'K {i s I P = 670.4 psia (lection 3.0]. and T' 8 = 2.7 x 10 8/10 mg Cf-252 then N V = 0.0941/10 mg Cf-252 y 1 ~ -.. _,
r
- ..v -
Jy I
- j. i t
[4 s t p1 r i' ^ Table 7 t ,yi j Gas Ateas as a functon of Time for 10 mg Cf-252 i
- 5. --
t, l 65 - (Time (years) cas Atoms E d' f,, j h 0 0 4 5 1.8 x 1085 y f f' 25 2.6 x lolS I g
- 1-1 l
50 2.6 x 10
- t 75 2.7 x 101S
'. s ,t.
- 104, 2.7 x lot *
, c.'. a M y, -; I .;. p. J. - 4 4
- t:
2 e t e '. O t / r f d1 I l N L I
r,,'i - Viz. t m. i l;? Table 8 lists the required void volme for.i given number of i micrograms of Cf-252. Note that the minimum internal volume 3 from Section 2.1.3 ts 0.213 cm.
- t
,i 0 ?. +: i g ($ F 0 ?: .i t s r-f . y i k-mbl f. lo x .1 ' s. Iy c 9 o
F -ji 1 o 'oo c!: , !(.... IP!! L' u 's e Required Void Volume f or A Giver. Aimunt Of Cf-252 q t Cf.252 fi.ini Hjnimum yo H. Volume [cm3] e
- i-2 0.0188 F
L 4 0.03/4 6 0.0665 '( 8 0.0/53 Ph 10 0.0941 e t; i h* .i g p r ? i ?
7 I %n - Ql[ i SEALED SOURCES CONTAINING BY-PRODUCT MATERIAL FTC Model 100 Neutron Source A.
SUMMARY
DATA 1. Date of Submission: June 17, 1985 -l, j 2. Sealed Source Type Standard neutron source. 3. Model: Frontier Technology Corporation, Model 100. 4. Applicant: Frontier Technology Corporation P.O. Box 486' 1641 Burnett Drive j Xenia, Ohio 45385 Frontier Technolo C (FTC) is both the manufacturerandkkeororation distributor of this source model. Person to be contacted for further informations Edward F. Janzow, President-(513) 426-1656 or (513) 376-5691 l 5. Other Companies Involved: None. 6. Isotope and Maximum Activity: Californium-252,is to be10 milligrams maximum. The californium in.the form of Cf-Pd cermet j or the alloy-formed by heating the cermet to high temperature. The maximum radioactive content is a function of the k# void volume within the inner capsule,the maximum with an absolute maximum'of 10 mg.. A table showing californium-252 loading associated with various minimum void volumes follows: og. Cf-252 Minimum Void Volume (cm ) 1 2 0.0188 l 4 0.0376 I 6 0.0565 8 0.0753 10 0.0941 7. Laak Test Frequency: Recommended every six months. I; 8. Principal User General Neutron Source Applications. 9. Custom Sources No. However sources will be loaded to particular customer's specifications, and ma sealed or unsealed capsules.y be put Into additional 10. Custom User None. -i 1 i i 4 I l1 l 1 r
f1 A I f B. DESCRIPTIVE DATA
=== ____ 1. Summary Descriptions The FTC Model 100 neutron source is a doubly-encapsulated californium-252 neutron source. Californium-252 in the form 4 of Cf-Pd cermet or alloy is sealed inside an FTC Model 10 capsule (described in detail in Reference 5) by tungsten-fusion welding,dthen the completed and inert-gas (TIG) is seale inside an FTC Model 100 tested Model 10 source outer capsule. The Model 100 capsule is made of type 304L stainless steel to FTC drawing A10100-AADO and is 0.370 inch outside diameter by 1.28 inches in length. A 10-32 threaded the capsulel 10 j stud is machined into the unwelded and of i bringing the overall length to 1.48 inches. The Mode l source containim the Cf-252 is located in a cavity approxi-mately 0.235 ind in diameter by 1.020 inches long. The cavity may also contain stainless steel and/or' copper spacers to limit movements of the Model 10 capsule. Minimum seal I weld penetration is 0.D50 inches,FTC's embodiment ofmeasured along'the plug-joint. The Model 100 is the to-wall Savannah River Laboratory's S7-Cf-100 series industrial sources as described in Appendix B of Reference 1. Except 1 for minor differences which will not affect capsule integrity, the FTC Model 100 capsule and the SR-Cf-100 capsule are the same. Minimum weld pnetration also is the same for both models. The FTC Model 100 also meets a11' dimensional and other specifications'of the Monsanto Model 2765 californium standard source (Monsanto drawing A2765-AA01, Rev. 3 and-A2764-PA02, Rev. 3 as published in Ref. 2 pages 97,and 98). 6 The FTC Model 100 m,eets DOT Special Form cr,iteria and American National Standards Institute (ANSI) classification 68E66445 by virtue of its compliance with previously-tested source des 2gns. 2. Labeling: The FTC Model 100 neutron source capsule will be electro-etched, format FTE or imprinted with a unique serial engraved number I in the Cf-XXX to identify the manufacturer, iso-i tope, and unique number. The capsule will also be electro-etched enoraved or imprinted with the words CAUTION RADIOAUTIW MATERI AL. If used as the second capsule of the outer surf ace of the a multi-encapsulated source,ll be marked by electroetching, outermost sealed capsule sha engraving, or imprinting with a unique number (which may be a customer-specified number and format), a marking identifyino the isotope contained as being californium and the words CAUTION RADIOACTIVE MATERIAL or DANGER RADIOdCTIVE MATERIAL. 4 3. Diagram See Page 3. ( 2 )
F i l -: DIAGRAM RFCTIONED ISOMETRIC DlNEN51045 F08t RifI QuiER cat 5dLt*, I c.D. AT wf L O e. 325 i o.D. 3.310/.31l
- 1. D. 8.239/.23 5
- TIG M L D, ml N. LENGTH W/0 57uD *l ZB PENiTilflII'P L EN6TH W. ShlD a 1.*p e O.OSO i
- l. L.
- l.0 2 i:
INNER CAPsutC; I
- 40. 5.287/. 2sp 1
i s.D. '.859 2.sel y C.L. '.9 Po/.9td g 0 L' ' 'b %- TKa wlLO, MIN. l j PEN. 0.030 s, MAT'L' 304L is. )'! i :' s k k ,$ / N s y; \\cAvlTY roA Q s Cf hl MAT'L { (Mh1 / Woo i {) CON il)l N m s .l SI'inctus) Y ) l .s t -10 24 UNF -Ib IllR1 ADI D i FTC Mon t 100 5TANOARD NEuIROH SOURCE 3 l ! .i l 1 l l
' l :- a t e 4. Conditions of Normal Uses The FTC Model 100 neutron source is intended for various neutron source applications under environmental conditions which are not detrimental to the Type 304L capsule material. Typical uses may include neutronradiograkbyIbyactivation activation q analysis, mineral exploration, process con ro analysis and nuclear fuel rod scanning. For special appli-o cations such as those requiring increased resistance to chemical attack or increased resistance to external pressure, the Model 100 may be f urther encapsulated in one or more additional capsules designed f or a particular application. The useful life of tne Model 100 source is expected to be that period during which the neutron output is adequate for 4 1 the intended use. Tests on source desions to which the } Model 100 conf orms show that the Model ' YOO will meet Special Form criteria at the time of manufacture.- In addition, analysis of the Model 100 capsule shows that it will meet the Special Form heatina test at the time of manufacture and at any time within M years after manufacture,l' assuming that the capsule has not been subjected to-chemica attack
- j or mechanical damage.
l S. Supporting Detail The FTC Model 100 neutron source is constructed per FTC Drawings numbers A10100-AAOO and A10100-PA01. The capsule material is type 304 stainless steel ' per-ASTM A276 or A479. All dimensions are shown on the drawings. The capsule i components are ine m ted and cleaned prior to assembly, then the completed and Meted Model-10' source is placed ir.to the container cavity along with any spacer or faller material. The cap is pressed into the container until-the top of the plug is flush with the too of the container, then welded by tungsten-inect gas (TIG) lusion wolding. Minimum acceptable a weld penetration along the plug terialto-container joint is 0.050 inches. Spacer and/or filler ma is either stainless steel or coppr. ' i The FTC Ndel 100 source is essentially identical to the Savannah River Laboratory SR-Cf-100 series industrial source (Reference 1 Appendix ~B) and to the Monsanto Model 2765 californium standard source (Reference 2, pages 95-98), both of which have been f ound to be acceptable for licensing purposes by the Nuclear Regulatory' Commission and both of. which have been certified as Special Form by the' Department of Transportation. ' ;j ! ~ l' t l i t t 4 'i l., I 'f 1 I
r1 '. 1: 1 5-i i i 2 Je. C. - y, HEALTH _ AND SAFETY DATA 1 4' 1. Safety Analysis Summary: The FTC Model 100 neutron source is equivalent to both the Savannah River SR-Cf-100 series industrial source and '1 the Monsanto Model 2765 standard neutron source. Special s Form tests were performed at the Savannah River Laboratory ] show1 that the SR-Cf-100 source,l Form criteria at time and therefor also the FTC el 100 sourceAppendix meets Specia 1 of manufacture (See A for details). In addition, the inner capsule of tne Model 100 (that is, the FTC Model 10 source) has been shown (Reference 5) to meet Special Form criteria even without the protection of an outer capsule. q-Savannah River Laboratory also performed a crush test and a hydrostatic compression test on SR-Cf-100 capsules. The crush test consisted of placing the source between two stainless steel anvils and applyig a load of 10 tons to the anvils. The test sources were'llattened but did not leak. i The hydrostatic com ression test consisted of subjecting I. test capsules-to 25 000 psi of external helium pressure. The test oapsules These tests are described-in detailid not measureably; deform, Appendix B and did not leak. in i Reference 1 and'in Appendix A of this document.. ANSI tests i: were performed by Monsanto Research Corporation showing that the Monsanto Model 2765-AAOO source, and therefor the FTC 3 Model 10 source, ference 5 meets the requirements for classification j 68E66445 (See Re for details). Since the FTC Model 1 10 source is the inner capsule of the Model 100 the Model 100 also meets the requirements for ANSI classilication 68E66445. In addition life' analyses were erformed on the FTC Model 10 source and, on the FTC Model 1 M outer capsule i using methods specifiedein the ASME Pressure Vessel Code, 1-Division I, Section III to thaE and assuming ~an internal gas quantity equal produced by infinite decay of the californium. The analyEes show that for the californium quantity and ' void volume limits stated in Section A.6 of i this document, the FTC Model 10 and'FTC Model 100 are each 1 indepndently able to pass the Spcial Form Heating Test at any time after sealing. The analyses on the-Model 10 and 1 Model 100 are presented in detail in Appendix C of Reference 5 and in Appendix B of this document, respectively. i' 2. Manuf acturig and Distribution Controls: a. Quality Assurance and Control j General. Capsule com p nents are made from traceable 4 steels certified to meet the drawing specification..All hardware is examined for dimensions, fit}ormed by the and finish, and I is cleaned prior'to use. Welding is per tungsten-inert-gas '(TIG) method using a programmable welder and a welding process'previously proven to provide welds of the proper penetration and quality for each particular capsule desion. 'Each source is fabricated to a Manufacturing d ich s m ifies the californium content,f Order (MO) Cf/Pd material configuration, other internal components a
- any, i
5 s
- \\
i i 1'
f^j ti ) and source serial number. That the void volume within the source satisfies the minimum void volume requirement for the particular californium loading and volume-of internals is verified before the MO is released for manufacture. .i Assay Method. Any of the following methods may be used to determine the radioactive content of the sealed sources (1) Use of Savannah River Assays. Californium is obtained from the De m etment of Energy's Savannah River Laboratory (S E) which laboratory assays the californium prior to shipment. Their assay methods are traceable to the National Bureau of Standards (NBS) and generally consist of comparing the neutron output of the material being assayed to that of a neutron source calibrated by NBS by placing each successively into a moderator containing BFJ counting tubes. a When a source ~is made using a particular Cf/Pd .,y' wire or pilot or a particular group of ' wires and/or pellets for which an SRL assay is available, the radio-active content of the source may be taken as that f reported in the SRL assay documents. When a source is made usam a' portion of a particular wire or pellet or a particular group of wires and/or pellets for which an a i l SRL assay is available, the content may be determined by comparison of the neutron output of the source to the neutron output of the item or group assayed by SRL. The comparison shall'be made using an appropriate neutron counter, such as those described below, and appropriate corrections shall be made for differences s in count rate, positioning.:and the like. i (2) Comparison of the neutron output of the source to 1o. that of a scuoe of known neutron output. The neutron outWt of the known source shall be traceable to NBS either directly or indirectly. -The comparison shall be made either by placing eachtsource successively into a moderator containina counting tubes (similar to the SRL method) or by counting each source successively using a i precision long counter of the DePangher type. (see Reference 3). Suitable corrections for count rate, and other factors will be applied. source psitioning,ldig, each source will i-Lesk Test. After we be leak tested usig the Dry Wipe Test pr caragraph A 2.1.2 of i American National Standard N 542-1977 Sealed Radioactive - NBS Handbook 126. Sources, Classification"Ehan 0.005 microcurie of Sources having less removable contamination are acceptable and may be shipped to the customer. I b.. Manufacturer's Recommended Maintenance, Servicing, l and Testina Ru uirements for Uses The FTC M el 100 source requires no maintenance or servicing. Periodic leak testim (dry wipe method) and visual examination for mechanical, chemical or other damage is recommended. The recommended leak test interval
- f is six months.
-} l l 6 1 I
Fi! } ['. i' q 3. Safety Analysis Report: a. Prototype Testing-and Evaluations Maximum Radiation Levels. Maxtmum radiation levels per milligram of Cf-252 at 5 and 30 centimeters from the surface .t' of the source are summarized in the table below. The levels reported in the table are based on dose' rates for an un-i shielded californium-252 point source as pages 8 8'9) ported by Savannah re J River Laboratory (reference 4' adjusted for
- j '
distance using the inverse-square relation., Distance from source, cm 5 30 x 1 0 +f 1 Neutron dose rate, mrem /hr 8.8 x 10 + 2.4 Gamma dose cate, mrem /hr ~ 6.4 x ~10 1.8 x 10 Total dose cate, mrem /hr 9.4 x 10 2.6 x 10 8 ]. Total dose rate, Rem /hr 940 26 q Results of Prototype Tests: Spcial Forms Prototypes of the Savannah River SR-Cf-tX J - and SR-Cf-100 series sources were subjected to the tests specified for Spcial Form radioactive materials at the i Savannah River Laboratory. ~Following each of the four tests, the test capsule was externally' pressurized with 300 psi i helium, then tested for' leakage using a helium mass spectro g i meter leak detector having a lower detection limit of 1 x 10~ l standard cubic centimeters of helium per second. No-leaks 1 were found. These' tests'on the SR-Cf-1X and their results eted in A Reference 1 arecefytotheFkbendixEofModel'10 in Appendix A and are shown i .i: to app of Reference 5. The tests on the SR-Cf-100 and their results are reported I in Appendix A of this document. The tests show that the FTC Model 100 source meets all Special Form criteria at time of manufacture. ANSI: Prototype testi in accordance with American National Standard (USASI) g 2.10-1968,by Monsanto Research " Sealed Radioactive SourcesEion, Classification", performed Corpora Da ton Ohio 1 (and reported in Reference 2) on "= dummy Monsanto Nodel 2765 AADO sources showed that the Model !=' - 2765-AAOO meets the requirements for ANSI classification 68E66445. Descriptions of the test procedures used and of the results are presented +in Appendix B of Reference 5. j,i Because the FTC Ndel 10 source'is the inner capsule of the FTC Model 100, and'is in all ways equivalent to the Model 2765-AADO,the requirements for ANSI classi'ication 68E66445. the FTC Model 10 and Model 100 neutron sources also meet Other tests: The Savannah River Laboratory conducted a ten-ton crush test and a 25,000 psi external pressure test on prototype SR-Cf-100 sources. The test sources were flattened during the crush test which consisted of placiq the source between two steel anvils and applying a load or ,l' 10 tons, but did not leak after the test. No visible de-j formation resulted from subjecting test sources to 25,000 i 7 i n l.
1 I-l t psi of external hydrostatic pressure, nor did the test capsules leak following the test. These tests are described in Appendix B of Reference 1 and in Appendix A of this document. Because of the similarity of the FTC Model 100 source to the SR-Cf-100 sources tested, the FTC Model 100 will also pass these tests, b. Safety Analysis: The prototype tests described above show that the FTC Model 100 neutron source as manufactured is capable of withstanding conditions of normal use transport accidents, l and signifloant abuse in the forms of,high temperature high external pressures, vibration, impact and penetraElon. I Lite analyses were performed on the FTC Model to and Model 100 sources usina methods specified in the ASME Pressure Vessel Code Division.1 Section III. I that the Model 10 and Ehe Model 100 will eachThe analyses show 4 andependently i-pass the Special Fore heating test at any time after. sealing. ? The analyses assume infinite decay of the californium, and thereby assumes maximum gas quantity:within the capsule. i The life analyses on the Model 10 and the Model.1 N are pre-sented in detail in Appendix C of Reference S and Appendix B of this document, respectively. li 4 t I l l 8 e 1
Pii j i-
REFERENCES:
" as1 U.S.A$ ping Capsule Assembly Design and Test 1. Cf Source and Shi omic Fner y Commission, South Carolina, Savannah River Information" PostOfficebox-A, Operations OlficeY2.
- Aiken, 29801, May 15, 19 j
ii ! 2. Janzow Their Manufacture and E.F., " Radioactive Sources,American Nuclear Society d CharacEeristics" presented at the Nuclear Technolog,y Exhibit, October 23-31, 1981, Beijing, China. DePangher, J. and Nichols L.L., " Precision Log Counter f or 3. Measuring Fast Neutron Flu,x Density"1466. Battelle-Northwest S Laboratory, BNWL-60, UC-37-4, June UI i 4. " Guide for Fabricating and Handling Cf Sources" U.S.
- i Atomic Energy Commission, Savannah River Operations, Office, jl t Aiken, South Carolina, January 1971 ',' SRO-153.
5. " Sealed Sources Containing By-Product Material, FTC Model 10 Frontier Technology Corporation, Xenia Neutron Source",to the U.S. Ohio, submitted Nuclear Regulatory Commissio,n in June, 1985. t-y- J, e i f l 9 I~ i t
} . ~. ~- 73--- (ff.,,m N4 NO.MtW U MAT L ~DE SC R I P.l ~ l3 N REVISIONS DE fG QA. AGS De SEE Sgt?.W CON T AIN E R cy ms. ccsc:::sPTION DATE APPROV AL 02 8 SEE SELew PLU6 4 80 97#
- ,075
. L.15 5
- 072
.002 MAX.fMAm. /.002 M. CHAM. s - // /-///////////-/n - ~
- I72
.2t 854 D8 A.
- plA' ff.Ql0 R.
,/ { .) f / o ////////////////iss/1 /' l I 1 7 -TAPERED Ptu6 To STICK UP..OO5 / / o, /7;c7g 3 - AMTC HING TAPER AT A55EMBLY FINfER f.Ti6dT J6' lNCLUDE'D AN6LE NOTES
- D
- t. BR E A n ALL roRNER5.o50.020. UNLZ55 OTHEtevtSE SPECIF8ED.
- 2. P#tE55 PLUG FLUSH WITH C ONT A#N E R TO P, TIG-WE L D.
minimum O.030 W ELD PEN ETR ATION (MEAsuRfD ALO N G, J O f NY ),
- 3. ELECTRoETCH, EWERAVE, OR tmPRINT ]DENTsFIC ATroN MARRING NO MORE THAN.002 DEEP oN SumFAC ES $N DIC ATEQ
~ DIMENSIONS ARE IN XINCHES !1 MILLIMETERS UNLESS OTHERWISE SPECIFIED FRONTIER TECHNOLOGY CORPORATION 'o'ca ^" cts DECIM ALS FR ACTIONS EJ,p 6-MS oA )xxI.cos E XE N i A, 0010, U.S. A. ANcLES .xxxx BASIC
- 30 MFG g h
- g. 33.rp s
ALL SURFACES Y STANDARD NEUTRON soutcE M510- A AOO ~5 MATERIAL 3O+ L J S. PER_ MODEL lo ASTM A276 OR A479, ~ DRAWN M 6*lM$ g o o g, [#'a 321k[o 3A_X.-~ sic NAvu Rc' oAvt Acr. 5A 10 J ** m :1 OF l Mf10Pe 6LW4 Paspel LU. De tenOD
to cm tu nu.ntu u mnsL UL 3 Ch t t* 1 3:fM REVISIONS DE fFy GA l MS Cl i SEE SELOW C O N T AIN CIR cm. casc::lPTION DATc A PPRO V C L 02 i SEE SELew PLU6 4 = 1.48 0 o .200 = 1,23 o r R U. K ~ ~ l.2OO = = ~l 8 9 t- + e u-F g f g, '~ 6 a LWV/////M///////h ~ E 77 Ok a T o% [ o p r-w / w // w m e/# r m-8 1*A%. + + l NOT E 3 10-32 uur - I A Suf F ( ?QLt.5M NOTES *
- 1. S R FA K ALL CORNERS.010.020 UNLES$ OTHERWs3E S PE CIFIE O.
- 2. TIE WELD, MrNamvM o.oSo WELD PE NE T R AT e o N.
- 3. EL E C TRO ETCH, E NG R A VE, OR IMPRINT 10ENTIFIC ATION MARMING No MORE THAN.005 OEEP oN SURFACE IN DIC ATEO.
R E F. S R-Cf-100 SERIES DIMENSIONS ARE IN KINCHES O MILLIMETERS UNLESS OTHERWISE SPECirlED FRONTIER TECHNOLOGY CORPORATION TOLERANCES DECIM ALS FR ACTIONS .xx = - XEN I A, OH IO,. U.S. A. o .xxx oos ANGLE.S a MFG g %s 4/3g .xxxx aAsic 30 ALL SURFACES 3F STANDARD NEUTiitDiv 500RCE DE ncy. o.a.no(00-P AO I MATE %IAL 3O+ L S. S. PER MODE L I00 CAPSULE NO O gjf 6 f3 85 ASTM A E7(, on A 479. onawN I..... SCALE 2X WT. c,ge sAlosoo .cy. 3 SHEET i OF s.on avu n c oarc una==m we w
, ) REVICIOND DE MFG QA MS SYM. DESCMaPTION DATE A PPRO V A L k I.46 128 .050 MIN. PENETR ATION ^~ W/ ////////////M / h 'm uxu __h .I M s w. .ss-c w ~4 ~ 378 a .sto + - - uxs s. ax ur. mx mm 4 '/////////K47///MJ h y ~ \\\\ (e .030 MIN. Pi NETR ATION \\ '. ORIM ARY C APSul E PER DvV6. AlOo10- A AOO - ID-32 'JNF lA \\ (McDEL to) \\ \\- - IDENTIFIC ATION MARKfNG ~5ECONDARY CAP 5utE PER DwG. Aloloo-PAO! l I i DIMENSIONS ARE IN X INCHES ' MILLIMETERS UNLESS C THERWISE SPECIFIED FRONTIER TECHNOLO6Y CORPORATION 'o'taa"cos DECIM A LS FR ACTIONS q 2 XENI A, OHIO U.S. A. .XXX-ANGLES e XXXX BASIC MFG g ALL SURFACES / . STANDARD NEUTRON SOURCE ~ MSbO-MOO "E M ATERI AL _ _ _ _ _ _ MODEL 100 ASS EMBLY Nf d'II SCALE 2X W T *,"c*. {SMI87o~h ~ SHEET g .OF l sioN ATun E oAsc .. van ew. euw co. n ia.o.
f.y r { .9.-
- s
~ .:us r: ij i~ ~
- I '
APPENDIX A
- i _
Special Form and Other Tests, Model 100 Neutron Source f-
- l 1.
References
- x a.
Appendix B, Primary Caps _ule, SR-1X Series, U. S. Atomic Energy Commission, Savannah River Operations Office, f P. O. Box A, Aiken, S.C. l):.j; b. Frontier Technology Corporation source container, Drawings A10100-AA00 and A10100-PA01. ! (- 1; L 2. Special Form Tests Ib. Test for special form materials were performed by the U.S. Atomic Energy Commission, Savannah River Operations Office, j! ' P. O. Box A. Aiken, South Carolina on the Series SR-Cf-100 is Industrial Source. Tests were performed or. capsules made of i t 304L stainless steel, constructed to figure SK-184-PM of f: reference a. The differences between this drawing and FTC drawing A10100-PA01 are as follows: ). The FTC drawing specifies only 304L stainless steel. a. li ' [! i; b. The outside length of the capsule per the FTC drawing is 1.280+0.005 inches whereas the SRL drawing specifies 1.280"/1.282". The length of the weld relief per the FTC drawing i c. i inches whereas the SRL drawing specifies is 0.050+0.005 1: I 0.050"/0.051". 'O
- li
[i; q; d. The outside diameter of the weld relief per the FTC .l, ; drawing is 0.325+0.005 inches whereas the SRL drawing ]l specifies 0.324"/0.325". 1; O b e. The inside diameter of the capsule is 0.2340"/0.2350" per the FTC drawing versus 0.2340"/0.2348" per'the SRL. t? f. The FTC drawing specifies a '0.050-inch deep by 0.141-inch diaraeter weld relief in ' the end plug (to provide improved welding control) whereas the SRL drawing specifies a solid plug. 9 The plug-to-body press fit is 0.0005"/0.0008" per the j FTC drawing versus 0.0003"/0.0006" per the SRL drawing. . ! l- +- lh h. The FTC drawing provides a 0.030-inch long tool relief at the base of the 10-32 stud whereas the SRL drawing I' does not. li lE i. The FTC drawing places a limit of 0.005 inches on the ( depth of the identifica tion marking, whereas - the SRL drawing does not specify depth, ti-y j' Otherwise the capsules are identical. It should be noted lI that the bulk of the differences between the two capsules lf are those relating to welding control, i.e., to geometry If in the region of the closure weld. Since-both capsules have the same weld specifica tion, tungsten-inert-gas (TIG) fusion welding with a minimum penetration of 0.050 II inches, the minor difference in the weld joint region are not relavant to capsule integrity. !L i c I:' l 'l
rq ip-4 l 3. The following tes ts were perf ormed on SR-Cf-100 prototype sources; n a. Free Drop - A free drop through a distance of 30 feet j onto a flat essentially unyielding horizontal surface, striking the surface in such a position as to suffer maximum damage. b. Percussion - Impact of the fla t circular end of a 1-inch diameter steel rod weighing 3 pounds, dropped through a distance of 40 inches. The capsule or material shall be placed on a sheet of lead, of hardness number 3.5 to 4.5 on the Vickers scale, and not more than 1 inch thick, supported by a smooth essentially unyielding surface. c. Heating - in air to a temperature of 14750F (800 C) and remaining at the temperature for a period of 10 minutes. d. Immersion - Immersion for 24 hours in wa ter a t room tem-pe ra tu re. The wa ter shall be a t ph 6-ph 8, wi th a max-imum conductivity of 10 mocrombos per centimeter. After each of the four tests the tes t capsule was externally l pressurized with 300 psi helium and helium leak tested. At 10-8 s tandard cubic _ centi-a lower detection limit of I x meters of helium per second no leaks were detected. Therefore the model SR-Cf-100 indus trial source, and because of its similar construction the FTC model 100, passed the special form tes ts. l i
F7 ' th-j. 4. Other Tes ts. Other tests as described below were performed at the Savannah River Labora tory on SR-Cf-100 prototypes. Because of the similari ty of the FTC Model 100 to the SR-Cf-100, the tests are valid for the Model 100. a. Crush Tes t i Prototype sources were placed between stainless steel anvils loaded with a total af 10 tons, removed and pressurized with helium at 300 psi for 30 minutes, i-then tested for leaks with a helium leak detector. j At a lower detection limit of 1x 10;8 s tandard I cubic centimeters of helium per second, no leaks were detected. A photograph of a prototype source af ter tes t is shown in Figure B-1 of reference a. b. Hydrostatic Compression Test The hydros tatic pressure a t 10 miles depth in a bore i hole is about 25,000 psi. Tes t capsules were subjected i to 25,000 psi helium pressure without measurable deforma-tion, and then tes ted for leaks with a helium leak detec-tor whose lower detection limit is 1x 10-8 standard cubic centimeters of helium per second. No leaks were detected. c. Burs t Tes t of Circumferential Veld Hydros ta tic burs t tests on the circumferential closure { weld in the outer capsule revealed that the average burs t i strength of the circumferential weld is 52,000 psi for stainless steel.
6: ,.e. t il 1 The above tes ts are repeated in Appendix B of reference a. .y. i.e + 4 i ' f. ? 6 5 4- .! ~ l.' f f k" lI j, p' 4 I i ki' 4. ) s L:
m, t g e I A 4~ a f e APPENDIX B h jk. I i ,4 5 8 f g$ t ' k $ (' t: C e5' -t ? n 0 4, i -
- l. 'i t
e v: 6. t h
- k. r.
I i J wi.v---
Jl P" ( y,- ,,1. i APPENDIX S W e Life Analysis, FTC Model 100 Neutron Source (with up to 10 mg of Cf-252) 4 ?y_ 1. References i a. Rules for Cons truction of Nuclear Power Plant Components, ll Section III_, Division _l, Subsection ND, Class 3 Components, ASME__ Boiler _and Pressure Vessel Code _1974' Edition, The-1 American Society of Mechanical Engineers, New York, 1974. i* b. Steels for Nuclear App 11ca tion, Section 3, United States S teel Corpora tion, Pi ttsburgh, Pennsylvania,196 7 c. Frontier Technology Corporation source container, Drawings A10010-AA00 A10100-AA00, and A10100-PA01. j L I d. " Sealed Sources Containing By-Product Material, FTC Model 10 Neutron Source", Frontier Technology Corpora tion, Xenja, Ohio, submi tted to the U.S. Nuclear Regula tory Commission in June 1985. 5; 2. A n a ly s_i_s, b It is the policy of Frontier Technology Corporation to perform source analyses on a " worst case basis"; that is, to 9 <' t assume that tolerances on material properties, dimension, isotope loading, etc. will accumula te so as to result in } minimum capsule s trength and maxinium s tress. With respect to capsule dimensions, this policy results in the following: 1. t 9
a :. ~y c., ii j! a. Capsule dimensions to be used in s tress calculations are li those based on tolerance limits which produce the thinnest wall and the thinnes t heads. ,j i ,;{; b. Capsule dimensions to be used in calculating internal ic pressure build-ups due to isotope decay are those based on-tolerance limits which produce the smallest internal volume. l Additional conservative and wors t-case assumptions are used in the analysis, and are noted therein. The capsule stresses are calculated using the methods specified in the ASME Pressure Vessel Code, Division I, Section III. Even under the -cumulative conservation of the ASME Pressure Vessel Code [ and the numerous wors t-case assumptions, the capsule is y shown to be able to pass the. Special Form Heating Test at
- [-
any time. i 2.1 Capsule dimensions l5 2.1.1 D i me n s_i o n s p e_r_ d ra w i n.g n umb e r A 10100 - P A01, Re v. 0 i= k. O.D. .370/.371 = iE I.D. =.234/.235 [ 0.L. 1.280+.005 (excluding threaded s tud) = isjp th Thickness o f head =.180t.005 =
- f tb
Thickness of bottom
.0 80 t.010 1: ] ;, 2.1.2 Dimensions to be u?,ed for s tress calculations i' (0.0. )3 = (0.0.) - (tol) =.325* -.005 =.320 l (I.D.)s = (I.D.) + (tol) =.235 b:
- 0utside diameter a t weld relief.
'f l a. m.
C,- ja
- <.g t
(tg)3 = Wall thickness = ',((0.D.)3 - (I.D.)3) = 1 \\(.320 -.23E, = 0.0425 (th }s = Head thickness a t bo ttom-of weld relief, minimum {' (.180 -.005)'- (.050 +.005) = = 0.120 (tb)s = Bottom thickness = 0.070 4-3. Stress Analysis Here, the maximum permissible internal pressure for the- ,7 primary capsule is determined by methods of analysis given in Rules for Cons truction of Nuclear Power Plant Components, Section_ III, Division 1., Subsection ND, Class 3 Components _, 1974 Ed' tf on (Ref. a) ASME' Boiler and Pressure Vessel' Code, ~ I for the heat tes t temperature of 14750F and assuming I infinite decay of the californium-252. Now, a t assembly, the plug (FTC drawing A10100-PA01) is pressed into the Cf-252 primary capsule body and sealed i in place by fusion welding. The resulting closure is assumed to be at leas t as s trong as the unwelded, screwed-in end cap configuration depicted by fig. ND-3325-1 l-sketch (q) of the ASME Code (Ref. a, p. 47). Accordingly, the allowable internal pressure, PH, in psia, as limited by s tress in the end plug (head s tress), is taken to be rela ted to the thickness of-the plug, t, in inches, -in the manner specified by the Code for Fig. ND-3325-1 sketch (q); namely (Ref. a, p. 48), t = 0 CP /S, where g
- ^
D is the major diameter of the plug (inches), C is a' dimension-less f actor dependent upon such considera tions as the method of a ttachment of the head and the shell dimensions, and S is the maximum allowable table of s tress values in the Code. ) i-
YT,. ~.v TV. h:m
- ). ~
Solving for P ' g; H T1: t = 0 CP I g, H a, 2 .D (CP /S) 2 t H 'ki 2 2 l[ '( t / CD ) S P = g [j j Here, per the' Code discussion regarding sketch (q), C = 0.75
- i(
(Re f. a
- p. 49).
Also, going wi th wors t-case values (A9pendix
- t Ih' B, Section 2.1.2), t = 0.120" and D = 0.235".
Then, for the d! >welded end, j: 1 h 2 2 j P,= (t /CD )s H y an (0.120")2 (0.75)(0.235")2 3 j ;' = k d[ = 0.348 5 _ i:. k- .lj .For the non-welded end, the same model may be employed upon .n-JM' replacing D with d, where d is the inside diameter of'the fj !- capsule (inches). Here, t = 0.070" and'd = 0.235" (Appendix B, ar7 j f" Section 2.1.2).
- Thus,
.i : ' I; P 2 H
- (t /Cd2)S n
I (0.070")2 (0.75)(0.235")2 3 = i' 31 = 0.118 S hi j am !N Returning to the welded end, there is to~be acknowledged for the ll head stress analysis here employed the requirement tha t, as =, stated in the Code discussion regarding sketch (q), design of 4 the weld joint agains t f ailure in shear.mus t be based on a factor ds, - of safety of at leas t 4 (Ref. a, p. 49). For the seal weld-f joining the plug to the capsule body, the area in shear is a k
- f
p_ As = Otw, where D is again the major diameter of the tapered plug (inches) and t is the weld penetration (inches ). Acting w 2 over the area Ap = (w/4)D is a force given by F = P A, where 3p P is the head-stress-limited internal pressure (psia). The 3resulting shear s tress is S3 = F/Ag = PsAp/As = PSx 2 w = P D/4t. (#/4)D /yDt S w Introducing the safety factor of 4, the shear stress developed is the maximum allowable is limited to S3 = ( 1/ 4 ) SSa, where SSa value of the shear stress.
- Thus, (1/4)SSa = P D/4t S
w or S, = P D/t, 3 3 Taking the maximum allowable shear s tress to be half the maximum Sa = (1/2)S, so that (1/2)S = allowable stress value in tension, S P 0/tw. Solving for PS, 3 P3= (1/2)S t /D w = Stw/2D (t /20)S = w Specified for the californium capsule c.losure weld (FTC drawing 10100-AA00) is a minimum weld penetration of 0.050". As before, D = 0.235". Evaluating, P3 = (t /2D)S w = {0.050" + [( 2 ) (0. 235")J { S = 0.1064 5
[ f-Also to be considered are the maximum permissible internal pressure values obtainable from the Code for stress limitations within the capsule shell. From paragraph NO-3324.3 (Ref. a, pp. 39 and 40) for the cylindrical shell in question, the internal pressures limited by circumferential and longitu-dinal stresses are, respectively. set r ] PC
- R + 0.6t r
[Etr + (R + 0.6tr)l3 = and 2 set r Pt = R - 0.4t p [2E tr i (R - 0.4tp)lS = where E is a joint efficiency factor having in this instance the j. value of E = 1 since -- the only weld being that sealing the plug to the body -- there are no joints in the capsule cylindri-cal shell portion proper and the head (plug) is also seamless (see paragraph ND-3324.2, Ref. a, p. 39) tr is the minimum required shell thickness which is here simply equivalent to the wall thickness at the welded end of the capsule where it is the thinnest (inches), R is half the major diameter of the plug (inches), and S is the maximum allowable stress value (psi) .i as before. Again going with worst-case values (Appendix B, Section 2.1.2 and FTC drawing A10100-PA01) t = 0.0425" and R = 0.1175".
- Then, r
wi th R + 0.6tr = 0.1175" +. [(0.6)(0.0425")) = 0.14 30" a nd R - I 0.4tr = 0.1175" . ((0.4)(0.0425")] = 0.1005", 4
g w,. 9 4 $i, PC = [Etr * (R + 0.6tr))S = {[(1)(0.0425")] i 0.1430" S -i ; = 0.297 S 1 j and PL = [2Et 1 (R - 0.4 t }3 S r r ={ [(2)(1)(0.0425")] i 0.1005"lS = 0.846 S A comparison of the five pressure relations (PHw = 0.348 S, 0.118 S, PS = 0.1064 S, PC = 0.297 s, and PL = 0.846 S) j; PH = n shows that the critical expression is the one derived from the shear s tress analys ts; namely, PS = 0.1064'S. To calculate PS, ) it is only necessary to arrive at the figure to be used for S. ?!. i~
- i The capsule temperature during the Special Form Heating Test is
'I ' 1475 F. Here, then 5, the maximum allowable stress value (in 0 tension) for 304L stainless stell for metal temperatures not 0 i' exceeding 1500 F is taken to be the 0.2% of fset yield strength l. at 1500 F, down-graded by 20%. The 0.2% of fset yield s trength 0 0 of type 304L stainless steel at 1500 F is 9,400 psi (Ref. b,
- p. 45).
Accordingly, the maximum internal pressure permitted in the cap-sule during the ten minute Heating Test is: P = 0.10 6 4 S P = 0.1064 x (9,400 x 0.80) 4 i
- d..
f P= 800.1 psig .). p= 814.8 psia 1 4 s t l f: I j. p i. 1 I i. k' i j l'
W> 'ji .y a 4. Discussion and Conclusion d' It has.been shown in the previous sections of this Appendix d; that the FTC Model 100 outer capsule will survive the ( Special Form Heating Test provided that the gas pressure inside the ::apsule does not exceed 800.1 psig '(814.8 psia) at the heating test temperature. The inner capsule of the FTC Model 100 is the FTC Model 10 source. A detailed jl analysis of the build-up of helium and fission gases [! arising from infinite californium decay has been performed 1 ll~ for the FTC Model 10 source and is presented in Appendix C of reference d (" Sealed Sources Containing By-Product .j. Material, FTC Model 10 Neutron Source," Frontier Technology Corporation, Xenia, Chio, submitted to the U.S. Nuclear j Regulatory Commission in June, 1985). That analysis ji showed the following: 0: a. For the californium loadings and corresponding minimum void volumes specified in Section A.6 of this document, the maximum pressure within the Model 10 l capsule at infinite decay and at 1475 F, is 670.4 psia, 0 and i b. Under those conditions the Model 10 capsule by itself will pass the Heating Test. ll= The pressure within the Model 100 outer capsule can be no j qj greater than that within the inner (Model 10) capsule. i in the event that the inner capsule does not leak, the IL pressure in the outer capsule during the Heating Test is that due to air inside the capsule, heated to 14750F, ~ 0 i.e., (14.7 psia) x (14750F.+ 4600F)/(70 F + 4600F) = 53.7 psia. If the inner capsule leaks, the outer capsule '4. I
?O.g. ![~ may be subjected to pressure approaching that inside the inner capsule, i.e., to a maximum of 670.4 psia.
- Thus, the maximum internal pressure, at infinite decay and at the Heating Test temperature is.670.4 psia, well 'below the allowable internal ~ pressure a t 14750F, 814.8 psia.
Thus, the FTC Model 100 capsule will pass the Special Form Heating Test at any time af ter manuf acture, provided only
- ~
that the capsule has not been damaged prior to the test. t n 4 6 4 i j: }'
- {
j
y Jr-le i i kV INSTRUCTIONS FOR RADIOACTIVE SOURCE SHIPMENTS TO FRONTIER TECHNOLOGY CORPORATION l p 1. SCOPE: J These instructions apply only to certain Type A shipments originatina within the jurisdiction of the United States. 3 Specifically, these instructions apply only to the following isotopes and quantities shipped by common carriers i' Cf-252 in normal form: 0.009 curies, maximum Cf-252 in special forms 2 curies,1 maximum Co-60 in normal or special form: curie, maximum i (the Type A limit for Co-60 is 7 curies,itations) the 1 curie limit arises f rom Frontier's license -lim i i 2. SHIPPER'S RESPONSIBILITY / LIABILITY: .Under NRC and DOT regulations the SHIPPER of licensed radio-active material is the party respon,sible and liable for compliance i with all applicable regulations and for all other matters related to the shipment. This responsibility / liability cannot be trans-ferred to or assumed by any other party. The principal NRC and i ' DOT regulations relating to shipments of radioactive materials are 10CFR71 and 10CFR30.41 and 49CFR Parts 171 through 178 respectively. These instrucElons are intended to assist the Ship-per in understanding and complying with the pertinent regulations, but are not to be considered a substitute for the Shipper's reading and understanding of these regulations. In supplying these instructions, Frontier Technology Corporation assumes no responsibility or liability for any shipment of radioactive materials made by others. 3. PREPARATORY ACTIONS: (a) Obtain written verification from the oroanization to whom the radioactive material is to be sent (i.e. - f rom Frontier) that the organization has an NRC or Agroement State license which i. authorizes the receipt of the type
- form, and quantity of M
radioactive material to be sent. This verification is to be obtained prior to EACH shipment of radioactive materials and should be retained in the shipper's records for the shipment. Frontier has a standard form which is used for this purpose. Ref. 10CFR30.41. (b) If the radioactive material is to be shipped as Special Form (i.e. Cf-252 sources above 0.009 curies), the shipper must obtain prio.r to shipment and maintain of file for at least one year following shipent,,a supporting safety analysis or document-ation containing the results of the testing performed on the source to demonstrate that it meets the special form requirements. Ref. 49CFR173.476 and USNRC IE Information Notice No. 82-47 l-(Nov.30 1982). (c3 Obtain neccessary documents on-the shipping container to be used. The appropriate shipping container specification for shipments covered be these instructions is DOT Specifications 7A (49CFR173.394 (a)(1) and 178.350). DOT regulations. require that each. shipper of a Specification 7A package obtain prior to shipment-and retain on file for at least one year after shipment documentation attesting to the results of the Specification 7d performance tests performed on the package (49CFR173.395(9)(1)). i The shipper must obtain the necessary documentation, usually from the original supplier manufacturer, or user of the package. Documentation on packa,ges manufactured or supplied by Frontier is available on request. CAUTION: If a shipper modifies a 7A container in any way, he must perform and document a supplemental evaluation demonstrating that the modified packace would still meet all 7A requirements. Ref. USNHC IE Infnemation Notice No. 82-47 (Nov. 30 1982). CAUTION: A source which meets Special Form requiremen,ts when manufactured may not meet these requirements l 1 l
I .' ~ j
- (
I ? i at a later time due to the build-up of decay gases within the capsule,ipper to mechanical or chemical damage,.or to other causes. The sh must obtain documentation (usually from the manufacturer of the source) showing that the source 'has an expected Special Form life adequate to cover the time period between manufacture and expected date of shipment and in addition usually_must generate documentation that the so,urce has not been exposed to conditions which would shorten its Special Form lifedamage (i.e.,to the source capsule) Cf physical to conditions which would cause or chemical Most 252 sources manufactured by Frontier and sold as Special Form sources have an exoected Speolal Form life in excess of 30 years provided that they have not been subjected to mechanical or. chemical damage. Documentation on specitic sources manufactured by Frontier is available on request. (d) Inspect the Lackage to be used for signs of damage or degra'dation. If an inspection check list has been supplied with the
- package, inspect each item on the list.
As a
- minimum, inspect fort Mechanical damage.
Dents, punctures, holes. Any apparent damage to sealing mechanisms. Gaskets. Gaskets must be complete and in good condition. Deterioration. Look for rust damage such as thin spots and holes. If shielding material is accessible, check for cracks and other visible damage. Completeness. All parts and components sp9cified by applicable drawings and/or the 7A performanance test documentation must be present. NOTE: If the package is found to be damaged, deteriorated, or incomplete, it MUST NOT BE USED, unless a supplemental safety analysis is performed and documented which demonstrates that the container in its "as-is" condition will meet all 7A requirements. Call Frontier Technology Corporation for advice and assistance. (e) If the source is to be shipped as Special Form material, inspect the sources (1) For physical or chemical damage. (2) For leakage. Use the dry wipe test per Standard N54garagraph A2.1.2 of American National Scaled c Radioactive Sources, Classification (ANSI, Standard N542-1977, NBS Handbook 126) or other applicable leak test method. Com the " Radiation Source Test Certificate"plete Leak attached. If removable contamination is found,on the source surface in excess of 0.005 microcurie, the source must be considered to be leaking. NOTE: If the source has observable physical or chemical damage, or if it is found to be requiremenEs,it leaking MUST NOT be considered as meeting Special Form and cannot be shipped as Special Form material. Call Frontier Technology Corporatier. or advice and assistance. 4. PREPARE THE SOURCE AND CONTAINER FOR SHIPMENT: (a) Place the source (s) into the shipping
- package, following packaging directions if available and the requirements for the 7A performance tests.
i (b) Close the container and apply a security seal which must be broken or destroyed to reopen the container. (c) Survey the outer surface of the container for removable contamination. Acceptability criteria for removable contamination on the surface of th is (per 49CFR173.443: a maximum 10'y container of: Alphas microcuries per s centimeter ( 2. 2 d pm per square centimeter)quare Beta / gamma 10-8 microcuries per square centimeter (22 dpm per square centimeter) Both measurements are to be averaged over 300 square centimeters 2
f. NOTE:y part of of an the container surface. If the removable contamination exceeds the. maximum allowable amounts given
- above, the container must be
,g ~ decontaminated prior to shipment. "(f-(d) Perform radiation surveys at the surface of the jp container and at 1 meter from the surface of the container. c NOTE: Surveys must include all surfaces of the container, 'th including the bottom. Lift the container off the ground in order JM to survey radiation levels emanating from its' bottom surface. d For Co-60 shipments only gamma radiation need be measured. For - F Cf-252 shipments, both gamma and neutron radiation must.be P measured and the results summed. Maximum acceptable total rad-i~ iation levels et the container surface and at one meter from the - F surface are 200 mrem /hr and 10 mrem /hr, respectively. These are L maximum-levels at any accessible part of the container
- surface, l
Ref.. 49CFR173.441. Complete the " Radioactive Source Shipment i+ Survey Record" per instructions in Section 5 hereof. NOTE: If total radiation levels at the container surface or at }- one meter from the surface exceed the allowable maximum levels SHIPMENT MUST NOT BE MADE. Call Frontier Technology Corporatio,n for advice and assistance. 5. PREPARE SHIPPING DOCUMENTS: (a) Shippino Document (Highway Shipment): f.,C DOT regulations (49CFR172.203(d)) require a " shipping paper" con-M taining at least the first eight items below for each trans
- 1. 1/
licensee' port i of radiomotive material away from the confines of a s l facility. The remainder of the fourteen items below are not !L p specifically required by regulation, but have been found to be ! si 4 useful. .f (1 ) DOT Shippin For Cf-252~g Names l - [i _ 1n Special enter: t 1 7 " Radioactive material Form,ial i spec form
- n. o. s. "
?.. For Cf-252 or Co-60 shipped as norma,l form, enters - 4 b de " Radioactive material, n.o.s." J n NOTE: For quantities of Co-60 covered by these instructions (1 s. 9
- curie, maximum), it is simpler to ship as normal form even if it
'LI,, is in special form source because shipment as normal form avoids t U the need for special form documentation on the source. 6:[ (2) Identification Numbers For Special Form shipment enter: "UN2974" For normal form shipment,, enter: "UN2982" F 5: (3) Name of Radionuclide: )- Enter " Californium-252" or " Cobalt-60" as J< - appropriate. (4) Physical and Chemical Form: f' For Cf-252 shipments, enter " Solid, Cia 0 /Pd cermet or alloy" 3 For Co-60 shipmentscobalt metal" enter: i " Solid, ( NOTE: The above listed forms are the only forms Frontier will accept. ( (5) Activity (in curies): l5 4 Enter the total activity of the material to be
- (
shipped, in units of curies, k (6) Category of Label Applied to Package. ' ? O The category of radioactive label to be applied to '=#: LF the package is a function of the radiation dose F E !! ! rate from the package (49CFR172.403). Enter Q " Radioactive White 1" if the total dose rate at h1 each point on the container's surface is 0.5 i-l F-millirem /hr or less. Enter " Radioactive Yellow II" if the total dose 1 rate at each point on the package surface is more than 0.5 but not more than 50 millicem/hr, AND the 3 s i h,
O- ~ li i t' L - V .I total dose rate at one meter from each. point on ! i the package surface is 1.0 millirem /hr or less. L Enter " Radioactive Yellow III" if the total 4 b surface dose rate at each point is more than 50 but not more than 200 milltrem/hr OR the t'otal dose i rate at one meter from each point on the surface l is more than 1.0 but not more than 10.0 millirem /hr. NOTE: If the. surface dose rate exceeds 200 millirem /hr or the STOP. These millirem /hr,hipment. dose rate at one meter exceeds 10.0 ,r for s Call dose rates exceed the maximum values allowed i 6 i k Frontier Technology Corporation for advice or assistance. I (7) Transport Index: I The transport Index is the dimensionless number created by taking the maximum total dose rate at [i one meter from each point on the package surface 't in units of millire/ hour, rounding up to the next [ highest tenth of a millirem / hour, then deleting i. the units. (49CFR173.403 (bb)). Example: If the-
- i maximum total dose rate one meter from the package I.
surface is measured as 7.02 millirem / hour the l-Transport Index is 7.1. For "Whiite I" shipment, 1 the Transport Index is zero, t (8) Shipper's Certifications A shipper's certif ication in the exact words printed on the form is required by 49CFR172.204. 1 Per the regulation, the certification must be legibly signed b(he shipper or hisofficerb, partner,and may a principal, or employee of agen t }- be signed manually, by typewriter, or by other mechanical means. (9) Shippino Containers
- {>
under these instructions.ype A for shipments made Types -Qill always be a T b.t! Nodel and Serial No.: Enter model of container, t including name of manufacturer, and container I serial number. l [' (10) Name and Address of Shipper: self-explanatory. j (11) Name and Address of Consignee:
- l -
Normally: Frontier Technology Corporation b 1641 Burnett Drive Xenia, Ohio 45385 (12) In Case of Emergency, call Shippers Enter telephone number locluding area code to be l-called in case of emergency. If a particular i person or title is to receive the emergency calls, F enter also name and/or title, i. (13) Date of Shipments self-explanatory. (14 ) Other: The regulations permit other information to be included on the shipping paper, so log as it does not conflict with the above information. Typically, what might be entered here are source model and serial numbers, reference or file numbers, . ! O etc. l ' e l-6 (b) Shipping Document (Air Shipment-Cargo-Only-Aircraft): F (1) If a shipment is to be made by air this document I is substituted for the document detailed in (a) 7 above. The forms and instructions are identical + i except for item (8) which contains a shippers l i j { certification as prescribed by 49CFR204 for air . l 6 shipments of radioactive materials by cargo-only E aircraft. li b (2) Two copies of the Document must be presented to {f the aircraft operator. l {: 4 . Y i A: o
I1 i 1 t i 4 I-(c) Radioactive Source Leak Test Certificate: k. (1) Indicate method used for surveying source for F removable surface contamination, i (2) Source description: F Enter manufacturer, model number, and serial number. (3) Isotope and Content: Enter Cf-252 or Co-60 as appropriate, and total activity in curies. (4) Test for r Enter type of activity to which measurin beta / gamma,g r instrument is sensitive, i.e.,
- gamma, alpha etc.
-For C}-252, test should be sensitive to alpha and b to beta / gamma. For Co-60, test should be sensitive to at least t aamma. i' (5) Removable Surface Contamination (Microcuries): Enter amount of contamination found of each type tested for in microcuries. (6) Signed-by:, Signature of person certifying test. Printed names Printed or typed name of above person. Titles title of above person 1 Of: Name of organization which above person represents. (7) Dates date test performed. p J (d) Radioactive Source Shipment Survey Record: (1) Dates date surveys performed (2) Data A.1 Type of source: Cf-252 or Co-60 A.2 Quantity of sources: number of sources in e' container i A.3 Type of radiation emitted: F For Cf-252, enter neutron plus gamma. t For Co-60, enter gamma. A.4 Source identification: Enter manufacturer's } <,.
- name, source model number, and source serial s'
number for each source in the container. B.1 Type: All packages for shipments covered by these instructions are Type A. B.2 Model No.: Enter model number of shipping ccntainer, including name of manufacturer. P B.3 Serial No.: Enter serial number of shipping ' O_. container, n. B.4 Approx. weight (pounds): enter approximate v weight of container in condition to be shipped. C.1 Container Survey-contamination, microcuries/ sq. cm.. Enter removable contamination levels for alpha and beta / gamma contamination l: found in the survey per para 4 (c) shipments, graph (- above. For Co-60 enter Not Applicable for alpha contamination. o C.2 Container Survey-radiation, mrem /hr. Enter the surface and one-meter dose rates found in the survey made per paragraph 4(d) above. l-If Co-60 shipment, enter Not Applicable for ~ neutron dose rates. tr y Enter description of survey instruments used, rpr including manufacturer, model number, and kJ serial number. P r. D. Name and Address of Shipper: self-explanatory. 4 pt E. Name and Title of person generating forms: self-explenatory.
- =
- 5 i
hon 13 ' e 4 I. 1 i
, g. t ys; .gg4 "VS1 N l' MN-(e) Additional Shipping Documents: M eG Additional shipping documents may b*e generated and used F Wf provided that they do not conflict with th,e-above 4%vg documents. c 3, s~w li o.- LABEL THE SHIPPING CONTAINER dl ' catm ory of " Radioactive " label in accordance with (a) Each package must be labeled with the appropriate 493R172.403. The proper category of label is deter-i 1 e,7 1 mined as described in paragraph 5(a)(6) above.- Two i suoh labels must be affixed, one on each of two i - opposite sides-of the package. Proper labels are I _/ available f ecm Frontier Technology Corporation upon 1 r e q u'> s t. H (b) Mart the following information on each of the f_ '" Radioactive" labels, in spaces provided on the labels, p by legible priating using a durable, weather-resistant 4' means. Contents: Californium-252 or Cobalt-60, tents in curie as appeopriate. Number of Curies: Tota
- radioactive con r
units. Transportation Index: Enter the dimensionless number r to " Radioactive Yellowdetermined'as in paragraph 5(a)(7)" and " Radioactive p .m above. i- - t labels. I: (c) Label the container with the name and address of the i. shipper and the name and address of the consignee,labe! 2 appropriately marked as to which in which. The }. may be in the form of a, label affixed to the container or stenciling on' the container surf ace (49CFR172.306 (e )). - ? (d) If the gross weight of the shipping container is in ?+< excess of 110 pounds.~ stencil or otherwise durably N. mark the gross wei ht container (49CFR173.31blainlyonthe'outsideof the lut-(a)). (D. ' (e) All shipping containers used for shipments covered by ? F4-these instructions are " Type A" packages and must tHe so Jd marked. Verify that the words " Type A" are p1minly and 7 durably marked on the outside of. the container in letters at least one-half inch high (49CFR172.310(b)). If such' marking is not present, first verify that the particular shipping container you have in fact qualifies as a USDOT TYPE A package,ide surface of then after verifi- . cation, mark " TYPE A" on the outs the container by stenciling,t be atpainting, or other durable at in method. The letters mus least one-half-inch high. f 4+ i (f) If the shipment is to be made b air affiw a proper Js " CARGO-AIRCRAFT-ONLY" label (49bFR40E(b)). The oroper R2 label is described in 49CFR172.448 and may be obtained (( from Frontier Technology Corporatio,n upon request. E ;; 7. ADDITIONAL INFORMATION F M (a) Disposition of Shipping Papers 6 (1 ) Place one copy of each shipping document in a plastic pouch-and tape it to the container surface, y' (2) The ori and two copies of the " Shipping Documentginal 1 are to be given to the carrier transport-b ing the package. i 4 [h", (3) One copy of each shipping document should be i j-retained in your file for the shipment. (b) Vehicle Placarding F }.- x ^' For " Radioactive-Yellow III" shipments, the transport vehicle must be placardud on the front rear and each side with a " Radioactive" placard per d9CFR1Y2.504. 1 j; ' The placards must be provided to common motor carriers i l $a 1 i f y. if_ 4
~ , s:-c. EP D c, }l1 1 0" by the shipper at the time the package is picked up. Appropriate placards are available from Frontier Technology Corporation upon request. I. 7
. {- RADIOACTIVE SOURCES LEAK TEST CERTIFICATE Currently, State and Federally issued radioactive mat'erials licenses define a sealed radiation source as leaking if removable contamination is found on the source in excess of 0.005 microcuries. This is to certify that the following listed sources have been tested for removable surface contamination. with the level of removable contamination observed on the source surface being as listed below. Method of Test Standard N542;per paragraph A2.1.2. Dry wipe test of American National CJ Sealed Radioactive Sources Classification (ANSI Standard N 542 -1977, NBS Handbook 1E6). CJ Other (describe): Source description: Isotope and Content: Test for Removable Surface Contamination (microcuries): From the recorded results there is no indication of leak in the source. Signed'by: Printed Name
Title:
Of: Dates 1
f.. ~ - Vi P $t[ [' RADIOACTIVE SOURCE SHIPMENT SURVEY RECORD et Dates-----------~~- .-y 9 1. Type of Source: 2. Quantity of Sources: F 3. Type of radiation emitted: 4. Source Identifications B: Shipping Package Data: 1. Type: A 2. Model No.: 3. Serial No.: 4. Approw. weight (pounds): C. Radiological Controls Container Survey ta/Gammacontamination, microcuries/sq.em. 1. Outer Surface Se 2. Container Survey - radiation, meem/hr l> " Surface 1 meter from surface L Gamma-Gamma-U Neutron-Neutron-l= Total-Total-e s }J; (*= transport index when rounded to next higher tereth) 49CFR173.389(i) Survey Instruments Used Gamma: Neutrons D. Name and Address of Shipper E. Name and Title of Person Generating Forms 1 L-
,'t. 3 SHIPPING DOCUMENT Ij. (Air Shipment Cargo-Only Aircraft) L[ 1. DOT Shipping Names t [ 2. Identification Numbeer h 3. Name of Radionuclic8e 4. Physical and Chemical Forms 5. Activity (in curies): 6. Category of Label Applied to Package is 7. Transport Index 8. Shipper's Certification For Carco-Only Aircrafts i, I hereby certifv that~the conf,ents of this consinneent are fully and accurat.el anci are classified,y described above by proper shipping name packed, marked and labeled and in preeer e -p condition for carriage by air according Eo appliemble ei national governmental reculations. 11 This shipment is within the 11 imitations prescribed for ? cargo-only aircraft. L i-Signatures ___________,,,,,__..., T y p e d N a m e s _ _.,_,,_ _ _,,_ _ _,,_,,_ _ _,, Titles ___________________..___ U-Su 9.pplementary informations b Shipping Containere Types A Models p}
- 10. Name and Address f,,BMI..,__ __ Serial Numbers._,...
o pper: O
- 11. Name er.d Address of Consignees s
p-
- 12. In case of emeroency, call Shipper.
tr
- 13. Date of Shipmenf.s U'
- 14. Others s
-3.' -1 }- t )s i
) , : A, p.c L' f,, i n
- 1. r, j O t
' ve SHIPPING DOCUMENT + l;- (Highway Shipment) b 1. ~ DOT Shipping Names .t ? 2. Identification Number ,. t: lt j-: 3. Naes of Radionuo11de > r g 4. Physical and Chemical Forms E-p' 5. Activity (in curies): f 6. Category of Label Applied to Packages ,'[ 7. Transport Index: 4; i 8. Shipper's Certifications This is to certify that the above-named materials are O. properly classifibd, described packaned marked and 4 .. H labeled, and are in proper cond,ition for, transportation ! h accordine to the applicable regulations of.the Department j u of Transportation. $, il e S i gna t u re s ___________,,___.,___,,____ Typed Names.,_,,___,,___.,___,, _ ___ Titles _____..,_ t O 9.pplementary Information: Su ik Shipping Containers . ii, Types A Models Name and Address ET.BRI__pe.,____.,Seria l number s,__,,____,__,,___ j,' { 10. p rs
- is:
iP ' it. Name and Address of Consignee ^ '
- 12. In Case of Emergeney, call Shippert s
t: } ". 5 P i ).
- 13. Date of Shipments 3
i
- 14. Other i <.
I b oND. u bp" 4. il I f f f I ); 1, , - +
-M i ~l, %;M v
- p. p f.
- o..
l !., 2. NameandMaili[echnologyCorporation Addessa of Licensee: !?T Frontier )E 2671 Crone Road O' Xenia, Ohio 45385 [7 Telephones (513) 426-1656 This is an interie address. The facility at which the radioactive eaterials will be used or possessed is under j construction at a site on Burnett Drive -in Xeniab April Ohio. When the new facility is completed (expected to 1985) all operations will be moved to the Burnett Drive iacility. The address of the iacility will be I^~ l P.O. gew 486 Frontier Technology Corporation 1641 surnett Drive I ! . l Telephones (513)376-5691 Xenia, Ohio 45385 t + ' Y r,. pr = s 4 s a 4 / 2 i .}~ J
p iu ~ ' e ,;k s. \\I(A[h{ ' ((;g-1 n m a
- g. a
,.9 ,o.; g A-l n{.N' CW L OE 2 a .2.
- n s
5 ,- m,. ... g'
- g 5, :
g g (f t i ' [- s' ) w w w
- 1 7
(, hlb Ek ] N g p = i up n . p.q -l' Y, i i I I I s F
- f..
t M g, I N, h(, E a s + i. g l 1 j; l' F X u t l 1 f, [ k,_; Y i, 4 j ;? ') [.4 _ C ' fi jj, I er 'a M E 4 } d Y Or i i .I 4 i. + g, y y r ,x I. 2 w 4 y E i W*8 m W g, ,I La y w a i l a.. a, w-C g* I U*k i o f l' 2E I st f i
- 4 2
a c a 4 v. E g j g;34 .e,4 u = , ) fe J-i 4 g-n 20 y ~
~ seassarfes* I l l l j f i / I M Cour4ETF / I l d Freesvns 3 i l l
- *** 7 D s.E. s s
.a . l NEALTN PHYSICS PELLET UNE euM t TY y
- f.a thee, man-se)
COMTMot / e I l ] / l 1 l e l l l s i v r / .X wat AM g=: l '/ ( w me emees Y p s l f PLeest 4 t r v d e i meces. Tsuna / / N TAL STUD PART. W/%%W- ),, e at:,a** / /' f v' & a* }nsa (TFR pet. wAus) (W 853 / r l ~ p (new e ) s ',twee 888" l v , % asent s e-e l f r
- h s es.
wm i $ O l onesa g l 0 SaOP l Casmose t - Rf374eC7tt Paperss Amen f l' Asen h ,t I d rm E~~~~~ kg i U se a l 37R FiHEvvast (C8aC k N*3 ~ \\ "88E8 Ce88r. saact i e stocr w/ zowottTE lanut-8 to l 6LocE MLL ro umpHStes or a, waeras.o.,,a or 1 r .'A F S T R E T F D SUPreRT AREA .I =", l i
- I i
o o i asset susWya'amwan j* L*s'*f v".au8" "*- 13. n.- = = i C FIG U R E ~9.l;5~J~8L DCFL~00W~ PEA N7~R E ST RI CTED ARE A 5_.. ~ ~ -.
. m y.;gg.9 Ly~,, '3< Scad,a f[al' '5 ~ ,[ ' -g 7. s H ll irseem mmas. e ; L. at* r u n-u nne ~ s e ne. H wenn noen / / / / j HE A LTH PHYSICS P E LLET !.rNE o ppy. t T'( l f a r e (%8e, aan-red.eedM) toNTftot non.steensr / { $ / / fvees. m east / r 8 h op14e4s A#fA M l g j , y ; d n r. v / < ---A d = - v - (METAL j s.., ~ T ..g p v 3 g"$ Y,,,,ns) k fj STUD PART. W/Vf D.W-l I W-o' Hs4H (TyP mt, watt 3) / LLs5f p Set # 2 ctasepgarsevme,mest[ Ain somets as."@ l r \\ , agg Pmocess ameA j ( ,e s'Tuca s v s gemese M*Nas. utPA (~ t \\ stMTecBL Shnest 'etL w,qegg oacarsR eNLIT L., f E ~ gggga W 446 .O SilOP stowen f s CaenN a r /*, ADTRicTn Nrss Anza W ananPaasJ L ' **
- O e
n l DNf4Tf A 4 F#MAWST re entsee, V11 > 111:111111111,1-1-1111111,1171,s,1,1v g 3yn FsREwatt. 8"C8MC. I""* "57 " enearras / sie=== a w M Block W/ ZONOUTE setsut. 6 LOCK FILL TO UNDHSIDS ,,y $g'e[*** ,, g, g . ~ _ RESTRICT FD SUPPORT AKEAT~' ~i f,'*g*,,yj ) -g =" -a$ l NOTE: AR f a W Psefst? LOCATWNS s ans aren.ne m ovr. l awm.s W yconswan "5 L*s*U YsN.'s?"" '"' E i3 s 3 72* 8 " r _. FIG URE T2-~' EQUI PME NT T.. ~ ._TZZ~Z ~~' ~-~~
- s. w
-~. ~ _.. acw...... ~ _ _... -.. _. s ... < -.. -... _.2,._... ...m.. L m. a... _._4 d
r i p 3 = / nc 'I ^ No formal calibration is required. Test for response with a check source. t 10.2.3. Calibration Procedures for Instruments Calibrated for U Others A. The eeneral reauirements in paragraph 10.2.1 will be met. B. Detailed procedures for each instrument type wi h! be prepared in writi prior to the first calibratnen of that instrument by C. Manufacturer's ins ruotions.for calibration and adjust-ment of each make and model of instrument will be obtained and available on the licensee's site prior to the first calibration of that make and model of instrument.- The manufacturer's instructions will be adhered to. D. A certifinate of instrument calibration shall be supplied to each customer for whom an instrument is calibrated for each instrument calibrated. The certificate shall. contain at least the following information 1. Identification of customer by: Name Address Person to be contacted 2. Identifination of the instrument by: Manufmoturer 1 number Serial number 3. Calibration data such ass Instrument r each scale, eadines versus exposure rates for in units appropriate for each scale. 4. Specifin comments on calibration or calibration data if appropriate. 5. Identlficatlon of calibration sources by i Nuclide En unSuteratesatspecifieddistances (or other I eneropriate to the source and use), includ- ! 9-ing callbration accuraov. 6. Identification of individual perfarming the calibration. 7. Date of calibration. l 10.3. Personnel Monitoring 10.3.1. Film i A. Film sensitive to both neutron and aamma radiation will supplied by the licensee to All pa rreonne 6 entering a radiation area, and the licensee sha:,1 reguare that such personnel wear the i11e badge at timee durine which they are in the radiation area. al;, t B. Wrist flim badges will be provided for all persons who ^ are authorizes to handle radioactive mater;,als and who are empested to handle radiomotive materia.,e be means other than mester-slave manipulators. Wrist badges will be required to be worn Dv a;,1 esons whenever they handle radiometive mateila;,s means other than master-slave manipulators. The wris badge will be worn 2 3 in addition to th bod badge. s C. Areas requirine s will be posted. When not in us6,f4 m be O. f im b eos will be stored with a oon-E trol bades in a low background area. i E. Film badg6s will be exchanged and read at least once per month. 's M 33 %l : n b-Ny 'l
1; n " U. h li N E} f t F. Film Badges will tje supplied and read by: R. S. Landauer,h/ ps, J and Co. Division f Tec Inc. 6: s - Glenwood iones ark ?+ Glenwood 111nois 604 5 An alternate v,endor may be used provided the vendor is en-t credited under the National Voluntary Laborstory Aooredit-ation Progree for compliance with criteria estaelished in Title 15 Part 7a Code of Federal Regulations for providin specific, Personnel Radiation Dosimetry Processing Services,g fa 10.3.2. Bioassay- ~ A. Licensee shall establish maintain and administer a bioassay procram for pers,onnel who handle, i process i restricted process area. ctive materials within, orthe are exposed to radioa B. Provision shall be maintained for the oo11ection of bio-assay samples such as urineIl consist of 24-hour urine feces or sputum. l Routine bioassay samples sha C. i voids, and shall normally be collected off-site ur in an area known to be free of radioactive contamination, I During the period of collection the individeal shall be restricted fcom working in areas or under conditions in which further expgsure may occur. >z D. Routine urine le iresquencya Once per six with unsealed radioactive materials,s for employees who work routinely and once per veer for persons who frequently enter the restricted peboess area but who do not actually perform operations with unsealed radiomotive materials. E. Special bioassay procedures shall'be employed to eval-s uate possible deposition from known or suspected acci-dental exposures. Nose wipes focal and/or lu counting shall be seriormed io,r such, exposures.ng F. Bioassay services wl11 he supp!!ution, lied by Controls for Environmental Po Inc. 1925 Rosina P.O. Box 5351 Santa Fe. New Mexico 47502 6. Radionuolides of interest in bioassay samples are those 3 used in unencapsulated form within the period oovered by the bioassey normally Cf-252 and/or co-60. The licensee may select a,nd use an alternate vender for bioassav services. If an alternate vendor is used the licensee will notify the NRC in writing within 30 days of,such use. 10.4. Radiation evey Program 10.4.1. General trements j Licensee shal conduct er otherwise provide for radiation monitorine in a menner sufficient for compliance with the 10.4.2.quiremeMts of all applicable regulatory agencies. re Radiation Operating, Monitoring A. personnel shall conduct work area radiation surveys prior to, durino,ts involving processing of and after completion of individual work assignm6n s radteactive materials. B. Personnel shall not undertake work ass neents in any area with radiation levels exceeding i aree/hr of pene-trati radiation to the whole body without approval of the A ation Safety Officer or Associate RSO or assis- ) tant (i C. In add tion to operating personnet surveillance of radiation levels during processing of radioactive mat-5' r; orials, tthe intion Safety Officer, Associate RSO or assistan shall at their discretion conduct ..M EM 34 i I l J 4 . e
U ~ 9 4,-~ .c3 r zu M. ]5 "~ r i Jr b periodio spot radiation surveys of process L insure license conditions. compliance with established areas to procedures and/cr i D. The Radiation Safety Officer, or Associate RSO or assistant RSO shall for any reason and wim license conditions, appropriate for insuring saf e operations and comp conduct independent formal radiation surveys of any process or area under licensee's control. The purpose of in and around the facility,be to determine and record the radiationthis typ s shall levels and to d levels in new or unusual operations,etermine radiation been a chage of materials. nr when there has E. A formal stricted areas and along the outside perimeter of theradiation survey is restricted radioactive materials are handledareas once per week durig periods in which during periods when no radioactive, materials are being aM once per month handled. Records of these surveys will be maintained until such time as the NRC authorizes their dispsal. Records may be in written form or in the form of computer disks or tape. 10.5. Contamination Survey Program 10.5.1. General Requirements Licensee shall conduct or otherwise provide for contamination monitoring in a manner suffiolent for comp iance with the requirements of all applicable g' regu atory agencies. 10.5.2. Routine Smear Surveys A. Smear surveys on bench tops, handling and storage quip-ment, iloors, and the like are taken as needed during the performance of tasks. B. A formal survey is to be made once each ceriods in whie radioactive materials are h.endled.during week When no radioactive materials are beim survey will be made at least once per month. handled, a C. If a survey is made of all the inside of the closed remote box, restricted areas including that no removab e cEntamination in Sxcess ofwhich survey shows 9 x 104 4.5 x 100Ci/tuCi/1DO om*20 d p/tDO om om ( > O1 (t M dpm/1DO cm )pha and/or beta-gamma is
- present, then no additional wipe surveys will be required until some action is taken or some event occurs which could cause contamination.
10.5.3. Special Smear Surveys A. Smears are to be taken any time uncontrolled contamina-i:, tion is suspected. W B. Materials and equipment to be moved irom the restricted it, process area are to be smese surveyed prior [eN
- removal, to their and if found to be over be limits for removal must be decontaminated to acceptable levels J i
prior to, r val 10.5.4. Records of evey Results:
- i A.
Permanent records are retained on file of the results of all formal periodio surve m. The records shall contain !t the date of survey ocat ons surveyed the type and centimeters f ound at each location, amount of contamina,t on in picoCu person perf ormig the survey. and the name of the 1 written form or in the form of These records may be in information on computer disks or tape, and will be maintained until such time D 35 1 3 l,( _ - - _ - _ _ - - - - - - - - - - - ' - - - - - - ~ - - ~ ~ ^ ^ ~
- 3. 4 p
p b, t I as the NRC authorizes their disposal. B. Routine and special surveys taken during the performance of tasks are ior the iniormation of persons performing the tasks and are generally not recorded, except for leak test smears on sealed sources which are handled as described in Section 10.8. 10.6. Air Sampling Program 10.6.t. Purpose The purpose of the air sampling prooram is to measure ,1 'i the amount of radioactive material In the air if any, in the working area of the restricted process, area and in the air eMhausted from the restricted process [ area. x 10.6.2. Sampling Methods. A. Samples not requiring constant monitoring are obtained by drawing air icom the region beina sampled through a suitable filter paper in a holder. The rate at whion air is drawn throuch the f11ter paper is esasured by an accurate flow meEer, and is adjusted to a particular flow rate with valves. The known flow rate multiplied i ..a nu 0;l rc .( f c 4
- p k'
?~ 'h-1 ]:
- l t
+k 1
- b f
it 35A l 1 v l lI fu
P I'4 !I # 1 I1x 1 g; i s l ' &g r materials at levels above the stated action levels. i Mandatory resampling for such persons shall be perform- . ;a~ ed if routine urinalysis indicates possible additional intake. p C. Licensee wi!! obtain expert bioassay consultation and i US assistance for cases of known or suspected significant f f. deposition. D. Licensee will obtain lung or whole body counting for personnel for cases of Rnown or suspected significant deposition. 0 10.7.3. Contamination Levels b A. Restricted Process Area a Licensee shall limit removable contamination in the h restricted process area, excluding the inside of the h closed N to box 10-*udi/tOOom8 to D 2. (500 dpm/100oe ) alpha s n 1 x 104 uCi/100ces (2200 dpm/100ces) beta-gamma ? B. Restricted Support Areas ? Licensee shall limit removable contamination in the L restricted pport areaI tos 9x 10* uCi/100cm 120 dom /tOOce") (100 dps/tOOomi1phabeta-gamma 4.5 x 10-8 uCi/100cm* ) i ~ C. Material and Equipment Release Limits Licensee shall sonitor materials and equipment for radioactivity prior to release or removal from the a controlled areas. . y Equipment and materials may be removed f rom the re-l tt stricted process area without need for further p' monitoriria or control provided radioactivity levels do not exceeds Alphas 9.0xtO'*'uCi/100cm)(20dpm/tDOom*), removable 9.0 x 10' uci/100cm OOcm8 find at surf ace o i t; g Beta-gammes 4.6 x 10-5 8 uCi/t (100dpe/100cm ), ~ removeable @1, 0.02 ar/he direct, fixed at surface. v. ! j;if Equipment and materials not meeting the above requirements for iiMed contamination may be et wed ieon the restrioted e process area provided that cr.pn such item is durably labeled )- with a label stating the levels of fi.ed end removable contamination on it. Each such item eil'. be recorded in a contaminated items los with a description of the item s t h' suitable to identify It levels of removable and iixed and their Iocations on the item,dlingI il W contamination and the date i( of removat irom the process area. Control, han su rypy-ing and disposal of such items and of sm arly conEaminated obtained fcom other, licensees these Specifications., is described in tion 12 of D. Actions To Taken When Removable Contamination Limits f, Are Exceeded s W In the event that removable sontamination levels are D found which exceed the limits stated in Parag ph 10. 4 7.3, one of the persons authorized in Pareera 7.1 te ! w use or supervise others in the use of radi6ao ive ma 5 erials shall be immediately informed of the situ.d.aun. That person will perform or direct the following actions: ' [c i (1) Determine whether protective items (such as res-2 pirators coveralls etc.) are needed in the . R( periorman. 01 oves,ce of the iollowing, actions. i (2) Determine and eliminated the cause of the contam-i,? - ination if possible. i PerIorm decontamination as necessary to comply with (3) 38 r I,[m l's
k. {lI + t i the appro riate limits. Alternately itemsmaySepackagedasradioactivewasEe. contaminated Normally, the above actions will be performed immediately after the discovery of the above-limit contamination. If this is not possible due to personnel availability or other reasons, the contaminated area will be secured and posted until decontamination to ecceptable levels is completed. In no event will normal work actf.vities be conducted in an area having removable contamination levels in excess of the limits. 10.7.4. Radioantivity Levels in Air A. Licensee in no case intends or expects to exceed the limits for restricted areas or for release to unrestricted areas as specified in 10CFR 20, Appendix S Table I, Column 1 and Table 11. Column 1, res m tively.. B. All air sample litters are counted three times as follows: 1st counts immediately after colleatiis 1.5 x 10*'OnuCi/ml alpha Action level which includes natural radioactivity up do about 1.4 x 10 -'* uCi /m 1 a l pha. ,W . ': t 2 ~ d s f-L 3 [s j.
- 3-V A 35A a
, - - _ -. -, - - - - - - -. - - - - - - - - - - -. -,. - - - ~ - - - -w-.-- ,e,-
y[v t 1 i . f{'. wy
- up
' I !DA AwiQ 2nd counts next work day after collection Action level is 1/2 applicab Maximum ffr i Permissible Concentration ( ) for one . ; !(T . day or 1/4 applicable MPC for two i !1 where the applicable MPC successive daysE52 or Co-60 for the type of !' I - i is that ior Cf- {'L= sample being measured. ( > t I. 3rd counts one week following day of collection Action level is as ior second count. I f h4 C. If a sample emoeeds the action level an investigation is . ' j. made to determine the cause and corrective steps arp {. ; taken immediately. i D. The concentration on the third count is used for air S e sample records as the actual concentration above .I )- natural background. ,+ E. Individual exposures to airborne concentration of radioactive materials are determined in accordance with ) the requirements of 10CFR 20.103. Reports of ex re above the limits of tOCFR 20.103 are made in 4 with tOCFR 20.405. Management is immediate y made !l aware of any such exposure and required report. F. Permanent records are retained on f11e for all daily air samoles. These records will be retained until suon ties . } as the NRC authorizes their disposal. b 10.7.5 RadiationLove1bable Mawimum a radiation levels outside the i V A. restricted areas including levels at the outside surfaces of 1 areas are those levels t i I the walls of restricted I' specified by 10 Paree ph 20.tO5(b), If the allowable levels outside the restf ted areas are found to be ew J
- 1 the cause of the above-a owable radiation levet shall i
ElT determined and actions taken to reduce the radiation evel h to an allowable level Temporary restricted areas as des-criber in Paragraph 0.1.3,may be used, if necessary, while correct se actions are beang taken.
- i B.
Within the restricted areas, those areas in which personnel are working will normally have radiation levels much less than 100eree/hr. Personnel are required to monitor I areas in which they work prior to, during, and af ter each work assig nt anB to ehtain a royal from the R50, or assistant R before working in any area Associate in which the do,se rate emoeeds 1 mrom/hr (Paragraph 10.4.2). Radiation levels and posure times to personnel are limited each ind is controlled as spesi-such thagaragraph gi al*s esposure j fied in .1 10.8. Sealed Source 1.eak Testing h 10.8.1. Each sealed source containing byproduct or special nucleac material shall be tested for leakaos and/or contaalnation at int.wevals not,to sweegd siw months excepf, that each source de- 's I signed for the purpose of emitting alpha particles shall be tested at intervals not to swooed three months. A. Eanh sealed source acquired irom another person and containang licensed material shall be tested for contamination and/or ,sekage prior to use. B. Notwithstanding the periodic leak test required by this condition, any licensed sealed source is eweept from such 1 leak tests when the source contains 100 microcuries or less of beta and/or gamma emittine material or 10 microcuries or less of alpha emitting material. i j, l l,# 39 i i l ts 7 Nb !i i .. p
r{- 1 i C. Except f or alpha sources, the m'rioc;c leak test requir-ed by TO.4.1.A does not apply to sealed sources that are stored on site and not being us9d. The sources ewoopted from this test shall be tested for leakage prior to any use er transfer to another person unless they have been leak tested within six months prior to the date of use or transfer. 10.8.2. Each sealed source fabricated by the licensee shall be inspected and tested for construction defects leakage and con-tamination prior to use or transfer as a seaIed source., If @e inspection or test reveals any construction defoots or
- 0. M microcurie or greater of contamination the source shall not be used or transferred as a sealed source u,ntil it has been repaired, decontaminated, reinspected and retested.
10.8.3. The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is p reanent semi-p emanently mounted or stored on which one might or em contamination to accumulate. Records of leak test results 1 be kept in units of microcuries and maintained for inspection by the commission. 39A i
r ) i l t I I, l 1 t b 10.8.4. The test shall consist of wipi the sealed source $ter entire surface area wit $ a piece of dry er i essentially its fi paper or cher suitable wiping medium or if the source is in a ~ device, of wiping appropriate surfaces, of the device, then count-im the wipim medium in a suitable radiation counter. Tongs er other remote-flandling devices shall be used when taking the wipe t portable survey instruments.g counts ofFinal counts will be mW Preliminary or screenin the w&M W be when feasible. made usi in an al a-beta-gamma gas proportional counter, with the part of detector.g material which contacted the source or holder facing the the wipin 10.8.5. Instrument descriptions and calibration procedures are described elsewhere in these Specifications. The calculation i used to convert the instrument reading into units of activity is shown below: Activity in microcuries = 0
- E/F E = instrument correction factor,per minute, D = instrument readig in counts CPM where DPM/ CPM i
F = 2.22 x 10 DPM/ microcurie 10.8.4. Wiping of the source or holder may be performed by any i of licensee s personnel who are authorized to use radioactive i materials. Counting of the wip and converting the instrument 1 reading into units of activity will be performed by mesons listed previously as persons who will count air sample Illters. 1 10.8.7. If the test required by Section 10.8.1 or 10.8.2 of this i section reveals the presence of 0.005 microcurie or more of removeable contamination, the licensee shall immediately withdraw 4 i the sealed source-from use and shall cause it to be decontaminated and repaired or to be disposed of in accordense with Commission rg ulations. If the source has been transf errW j f rom our licensed f acility and placed in service and subsequently f ound to be leaking, and investication will be made to establim 4 the circumstances and a report dall be filed within 30 days of Region III Office of Inspection and the test with the Direc % rkooosevelt Roa,d, Glen E11vn,t results, Illiness l Enforcement, USNRC 7M 60137. The report,shall describe equipment used, Les and corrective action taken. 10.9. Posting and Control 10.9.1. Access to Restricted Areas 4 Normal entry into the restricted support area is through j the door through me firewall separatig the administrative I (unrestricted) and restricted areas. The door will have two leek releases one of which may be electrieal. Persons a,uthorized to use radioactive materials without super-vision or to supervise others in the use of radioactive materials (paragraph 7.1) will have keys. Keys to one of the two look releases will be restricted only te swoh persons. This release wt11 he locked eneopt when one of the persons listed in paragraph 7.1 is on site or den all radioactive materials within me res-tricted support area are securely looked in properly shielded containers to which only persens listed in paragraph 7.1 have keys. Other persons au m orized to enter the restricted support area without constant supervision will be issued keys (or the release,icted supportis kept looked at combination) for the second lock which all times. Other doors into the restr area are lockable from the outside;h 7.ys to these doors are limited to the ke persons listed in paragrap 1. Thus, unauthorized persons mannot i enter the restricted supprt area at any time without escort. Persons authorized to enkr the area without constant supervision have access to the area when all radioactive materials are in 40 i i ~- -.- m.
t c;
- g e;
1 h,*-! 'T j ts l { l ~l' i Cl [i. y;F; T pN [I looked and shielded containers or when a person authorized to use UJ@? 'and supervise the use of radioactive materials is on site. Persons PJ y. authorized to use radioactive materials without supervision or to DE supervise the use of radioactive materials have access 'to the u area at all times. For safety reasons all doors leading out of Ut (( the area may be opened from inside the, area without keys. bi~ A similar look system is employed on the outer door of the j s-change room. One look will be kept locked except when at least 1 is; one person listed in caragraph 7.1 is on sites keys to this look Rr are restricted to such persons. The second release is kept lock-hE' ed at all times. Meys (or the combination) to the second release -d are restricted to persons authorized to enter the restricted
- )!
process area without supervision. The door between the process area and the outside of the building is also kept locked keys i are restricted to those persons listed in paragraph 7.1.3 All doors may be opened from inside the process area without a key. See also paragraph 9.3.1. All doors into the restricted areas are equipped so that they look automatically when closed. g, b 10.9.2. postiNe i' ;l - The outs of the door leading into the resteActed support area from the administrative area and the outside [ of each exterior door leading into the resEricted support area, will be continuously posted with " Caution Radiation Area" signs. ki The outer door of the change room is continuously posted t OU with " Caution Radiation Area" and " Caution Radioactive Material" 96+ signs and with a sign specifying the minimus protective clothi U 6 9 requirements for entry. All caution siens will contain e m 'W [ radiation symbol as defined by paragrap6 20.203 of tOCFR Additional postings shall be made inside and outside the <t + h.'s-restricted areas as specifled by tOCFR 20.203, when conditions A m b@[i exist which require such posting. r 5,3 v-W 10.10. Receipt and Shipment of Radioactive Materials ( r< M 10.10.1. Receipt of Packages Containing Radioactive Materials S Ur A. Requirements F4 Packages containing radioactive material are normally ? delivered to the licensee's site during normal working hours. A sion will be posted outside the building listing persons te ca1I and their telephone numbers to cover a car-n !<t rier arriving at the site te deliver a package containing .? radioactive materials during other than normal working hours. e t-In the event that a package containing areater than Type A <aA quantities of radioactive material (as defined by paragraph l s 20.205, tOCFR 20) is to be picked up by the licensee at a e i carrier *s terminal,l ofarrangements shall be made to receive s' ~y I ji notice of the arriva the packaee at the time of its ar- -l' _O ival and the package shall be pleked up from the termintl 1:- expeIfitiously upon notification from the carrier of its ~r arrival. r. Upon receipt of a package containing radioactive
- material, 1/? !
the external surfaces of the package shall be monitored for radioactive contamination by wipe f.esting except that pack-h' ages sentaining no mere than exempt quantities of p,' radioactive materials as specifled in paragraph 20.205 of tOCFR 20 paokages containing only radioactive material in <i g special form and packages containing only cadioactive material p in other than liquid iora and not exceeding the Type A + 1" quantity limit are excluded from the external contamination dw monitoring requirement. If removeable radioactive contamin-7 a py N$ h ] w D %hi ~ <N 4 .,W - - - - - - - ~ ~ - - -. -
r Y 7 "i 1 '1[ atiun in excess of 0.01 microcuries per 100 square centimeters of package surface is found on the external surfaces,f the Nuclear Regulatory Commission as spedified in both the final deliverino carrier and the Region Oftice o Appendix D of 10CFR 20 shall 4 be immediately notified. Upon receipt of a package containino quantities of radio-active material in excess of Type A quantitics (other than those transported by exclusive use vehicle), the radiation levels external to the pack g e shall be monitored. Both gamma and neutron radiation shall be measured at the surface of the container and at three feet from the container sur-face. If the total radiation level at the surf ace is found to be greater than 200 millirem per hour, -or if the the total radiation level at these feet from the surface is found to be greater than 10 millirem per hour, Region III both the final deliveri g carrier and the Director of the Office of the NHC Shall be immediately notified. The monitoring actions required above shall both be performed as soon as practicable after receipt, but no later than three hours after the packaoe is received on site if raceived durim normal working Sours, or eighteen hours if received outside of noreal working hours. Required notifications shall be made to the final delivering carrier b telephone or telegra$ephnne and by telegraph RegionalOfficeof h and to the appropriate the NRC by te
- mailgram, or facsimile.
I B. Procedures For Opening All Radioactive Haterials Packages 1[ External Surveys 1. Empty containers - make a direct external survey for gamma and neutron radiation. Survey for remov-able contamination with a smear test. If the ex-ternal radiation survey indicates the presence of radioactive material, treat the container as " loaded". 2. Loaded containers - make the surveys as in 1.
- above, then for small containers move the container inside for opening.
Large containers are openad outside. Opening shipping containers 1. Empty containers perform wipe test and radiation surveys at each stage of opening the container to verif y that the container is empty and free of contamination. 2. Loaded containers - Special form shipment Perform wipe tests and radiation surveys at each stage of opening the container. Avoid unneeded I exposure. Remove the radioactive contents, using l methods that minimize erposure to the remote-handling f acility and perform a, vipe test on the special f orm capsule. Wipe tost the inside of the shipping package and decontaminate if needed. 3. Loaded containers - Other than special form Consult the RSO. Associate RSO l bef ore opning these packages., or assistant R50 The minimum re-t quirement is as in 2 above, but additional pre-l I cautions may be required. I C. Action Levels Stop and re prt to the RSO Associate RSO assistant RSO if contaminaEion is found aE or any stage of opening a container, or if unewpected radiation levels are observed. 42 N
F - y s '. b1 s r) ; 1 y
- } ;
L 1. I t e 4 } Bh
- q;f n
D. Records Record called for data in the incoming shipment log. 10.10.2. Shipment of Radioactive Materials Shipments of radioactive materials from the l icense's shall be made under 10CFR 71,15arakraphs 71.5 71.7, 71.10 71 71.14 71.16 and/or 71. 11 shipmenEs from the IIcens.12, 71.13, ee are made In D.O.T. Specification Containers or in packages for which license,by the Nuclear RegulatoryCompliance or other approval has been Certificate of a by Commission. The licensee issued will have a Quality Assurance Prgram which will be submitted to ar.a approved by the Nuclear Regulatory Commission as satisifying the requirements of Subpart H of 10 CFR 71 and complyino with the documentation and notification requirements of paragrap6 71.12 of 10CFR 71, prior to making his first shipment of a Type B quantity of radioactive materials. For these conditions oY shipment, a special license under 10CFR 71 is not necessary. All sources containing radioactive material shall prior to removal from the licensee's facilities have a label aEtached to the source or source holder, which shall identify the radioactive contents and contain the words " Caution Radioactive Material" or I " Danger Radioactive Materia 1'. Methods of marking labels on source surfaces include but are not limited to engraving, chemical etching, electroetching, vibratool marking,
- stamping, and embossing.
Labels attached to sources or source holders include but are not limited to metal taas attached by means of a wire, cable, Source holders uman which thela bls attached by means of or chain. and metal foil adhenive. la%el may be marked or to which the label may be attached include but are not limited to devices in which the source will remain during use and metal containers in which one or more sources are located durina ship-ment (i.e. crimp-sealed metal cans, DOT Specification 2R inner containers, screw-top metal vials). 10.11. Records and Reports The licensee shall create and maintain records and shall make reports as required by tOCFR 20, paragraphs 20.401 through 20.409. 10.12. ilespirators The licensee does not have a respirator progeam which hos been approved by the NRC, and therefor cannot take credit for the use of tespirator equipment when calculating personnel enposure.
- However, the licensee will make respirators available and will require their use durig jobs which have a potential of exposing an individual to airborne radioactive material or other l
industrial airborne hazard. The RSO or Associate RSO shall designate jobs which require the use of respirators. Instruction will be given by the licensee to those employees required to use respirators. The instruction will cover at least the followinge inspection of the respirator to assure proper operation, adjusting respirator fit for proper air
- seal, testing of
( respirator a nd fit prior to each
- use, and maintainence and I
storage of respirators. 1 t 43 l 1 l ^ }[ .}}