ML20217D083
| ML20217D083 | |
| Person / Time | |
|---|---|
| Issue date: | 04/17/1998 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20217D089 | List: |
| References | |
| SSD, NUDOCS 9804240194 | |
| Download: ML20217D083 (5) | |
Text
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8099-S-804-S DATE:
APil 1719983 PAGE 1 OF 3 SOURCE TYPE:
Density and Moisture Gauge Source MODEL:
PL-200 i
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MANUFACTURER / DISTRIBUTOR:
Parkwell Laboratories, Inc.
429 North High Street Croton, OH 43013 ISOTOPE:
MAXIMUM ACTIVITY:
Cobalt-60 110 millicuries (4. 07 GBq)
Cesium-137 550 millicurie (20.35 GBq) i Americium-241 2200 millicuries (81.4 GBq)
LEAK TEST FREOUENCY:
6 Months PRINCIPAL USE:
(H) General Neutron Source Applications CUSTOM SOURCE:
YES X
NO 9804240194 980417 PDR RC SSD PDR
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8099-S-804-S DATE:
APR 1719931 PAGE 2 OF 3 DEVICE TYPE:
Density and Moisture Gauge Source DESCRIPTION:
The Model PL-200 is a cylindrical, doubly encapsulated, stainless steel (Type 304) source for use in portable moisture and density gauges.
The completed source is 0.356 inches (9.04 mm) in diameter and is 1.062 inches (26.97 mm) long.
The minimum wall thickness of both the inner and outer capsules is 0.025 inch (0.64 mm).
Americium sources are constructed by consolidating AmO with a plug in an inner capsule under a 1000 pound 2
(453. 6 kg) load.
After closure of the inner capsule by inert gas fusion welding, the inner capsule is inserted into an outer capsule which is also closed by inert gas fusion welding.
Construction of the cesium and cobalt sources is identical except CsC1 or CoCl is evaporated to dryness in the inner capsule prior to consolidation and capsule closure.
LABELING:
A serial number is legibly stamped or engraved on each source.
1 DIAGRAM:
I See attachment 1.
PROTOTYPE TESTING:
The following prototype tests were performed on the Model PL-200 source:
1.
A dummy source was sectioned and etched to determine the depth of penetration of the weld.
Both inner and outer containers had greater penetration than the 0.025 inch (0. 64 mm) wall thickness.
2.
Three prototype sources were heated to 180 C (356*F) for two hours. After cooling, the sources passed the helium pressurization leak test specified in Section B2.9 of the ANSI Standard N5.10-1968.
3.
.The same three source used in the above temperature test were subjected to 300 psi (2.1 MPa) water pressure for four periods of 15 minutes each.
The sources then passes the same helium pressurization leak test.
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8099-S-804-S DATE:
APR l 7 1998' PAGE 3 OF 3 SOURCE TYPE:
Density and Moisture Gauge Source LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:
- The source shall only be used by specific licensees of NRC or Agreement States.
- The source shall be leak tested at intervals not to exceed 6 months using techniques capable of detecting 0.005 microcurie (185 Bq) of removable contamination.
Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
This registration sheet and the information contained within the references shall not be changed without the written consent of the NRC.
SAFETY ANALYSIS
SUMMARY
The PL-200 Density and Moisture Gauge source was originally approved for licensing purposes by the Atomic Energy Commission (AEC) on February 15, 1971.
This source is no longer manufactured and distributed by Parkwell Laboratories.
The company is out of business.
There is insufficient information on file for this source to have performed a complete safety evaluation.
Therefore, this registration certificate has been transferred to inactive status Without further review based on the original review and approval issued by the AEC.
l
REFERENCES:
The following supporting document for the Model PL-200 Density and Moisture Gauge source is hereby incorporated by reference and is made a part of this registry document.
- Parkwell Laboratories' letter dated December 14, 1970.
ISSUING AGENCY:
U.S.
Nuclear Regulatory Commission
REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE APR 171998' NO.
NR-8099-S-804-S DATE:
ATTACHMENT 1 ACEI" Ya1.1 Thickness ertal
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-,2r, PAGE1 NRC FORM 567 U. S. NUCLEAR RE2ULATORY COMMISSION (s.es)
REQUEST FOR A SEALED SOURCE OR i
l DEVICE EVALUATION l
INSTRUCTlONS: Send trws request AND a copy of all related letters /appleahons and drawings to: The Sealed Source Safety Sechon, ATTN: CNef, j
OWFN Meu Stop 6 H3. Change the Ucense Tracidng System milestone to 19 and assign to reviewer code 1-5.
NOTE: Retain a copy of tNs request with the applicahon and back0round files.
REQUESTER REGION / LOCATION:
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]l ll 111 IV UV C HQ R LFDCB TELEPHONE NUMBER DATE TYPE OF ACTION REQUESTED (Check as _. W ^ '
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APPUCANTS NAME SOURCE REVIEW AMENDMENT OF REGISTRATION SHEET mat CONTRtA NUMSG3(S)
DEVICE REVIEW
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LETTER /APPUCATION DATE UCENSE NUMBERm CUSTOM REVIEW ie 3 h //1/'97 W
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C CA>h"6 M V3MS FOR SSS5 UlsE ONLY REYEWER MODEL NUMBERS, pg, _ j y q
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DATE TO FEES DATE RECErVED DATE ASSIGNED I \\ ll'll 99 l/
hY TYPE OF ACTIOkt (lpar* the nuweer of each type) l COMMERCIAL DISTRIBUTION (FOREL) l USE BY A SINGLE APPUCANT (CUSTOM)
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SOURCE (9C)
DEVICE (9A)
SOURCE (90)
DEVICE (98)
NFW NEW NEW NEW p
v AMENDMENT AMENDMENT AMENDMENT AMENDMENT d NO SAFETY EVALUATION REQUIRED j UCENSING ACTION REQUIRED IF KNOWN NO NO FEES REQUIRED
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JOTHER (Spec #y) l TOTAL NUMBER OF NOTES g yg M REVIEW HOURS 1
NUMBER OF DEFICIENCY LETTERS NUMBER OF DEFICIENCY CALLS FOR SILLBfG PURPOSES ONLY RESSMON -
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NAME CHANGE ADDRESS CHANGE ADD TO BILUNG REMOVE FROM BILLING FOR FEE USE OfA.Y TYPE OF FEE FEE CATEGORY
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OECK NUMBER MATANN UPDATED AMOUNT RECENED
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4 WASHINGTON, D.C. 20666-0001
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- M 171998' DATE:
April 17,1998 NOTE TO:
Parkwell Laboratories Files (SSD-97-70)
/
THROUGH:
John W. Lubinski, Mechanical Engineer /
FROM:
Eric Compton, Engineering Aide Materials Safety Branch
/~ bA The following registration certificates have been transfer to inactive status:
FROM TO MODEL NUMBER NR-532-S-101-U NR-8099-S-801-S PL-AmBe NR 532-S-102-U NR-8099-S-802-S AM NR-532-S-103-U NR-8099-S-803-S AC l
NR-532-S-104-U NR-8099-S-804-S PL-200 NR-532-S-105-U NR-8099-S-805-S PL-104 These scurcss were originally approved for licensing purposes by the Atomic Energy Commission -(AEC) during the late 1960's and early 1970's. These sources are no longer manufactured and distributed by Parkwell La'.soratories. Parkwell Laboratories' was purchased by the General Nuclear Company around Fobruary or March 1967. The company has been out of business since at least 1980.
The background files only contained the registration certificate. I contacted Oak Ridge and had the AEC archive files sent to me. These fi!cs contained some additional information, including drawings, which I have included in the inactive registration certificates. In addition, I copied all the documents from these AEC archive files to be included with the NRC background files for these new certificates. However, there is insufficient information on file for these sources to have performed safety evaluations. Therefore, these registration certificates have been taken to inactive status without further review based on the original review and approval issued by the l
AEC. This action is necessary for administrative purposes.
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Report No. 030-05868/9300k(DRSS):Rp%;a y? 2 -
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_ License No. :34-13517-Ol%%,t+$M ' %$f ' Y" N' ',
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AssociatedLicensesNo.134-II'05-01',"SNM-1347,andSNM-909(tcrminated) 1
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g,y.. c c Facility: General Nuclear,'Inc., and.
Parkwell Laboratories, Inc.
429 North High Street Croton, Ohio %..
Inspection At:
Private residence of Mrs. Nancy Wells (a former General Nuclear and.Parkwell Laboratories facility) 429 North liigh Street Croton, OH 43013 Inspection Conducted-Jan a
,-1993 Inspector:
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Wiedeman Date Senior Health Physicist' Approved By:
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o'n A. Grobe v DRe f F c1 facilities and Decommissioning Insnection Summary
.Iniocction on January 21. 1993 (Recort No. 030-05868/93001(ORSS))
Areas inspected: This was a special closcout inspection which included a review of the licensce's former activities associated with the decontamination and remediation of their formerly used office, manufacturing, and laboratory areas located at 429 North High Street, Croton, Ohio. This inspection was in response to an NRC project.in which an evaluation of approximately 17,000 retired licenses was conducted by an NRC contractor, Oak Ridge National Laboratories (ORNL). On the basis of the information in the retired license flies, sites having a potential for significant residual contamination in their former facilities were to be investigated further. Due to the lack of documentation in the General Nuclear, Inc. and Parkwell Laboratorics, Inc.
retired license flie, the NRC contractor concluded that the former facilities used by these companies during the period of 1965-1980 could have significant amounts of residual contamination.
Results: The NRC inspector did not identify any radiation icvols above natural background wl' thin the facilitics or surrounding environment.
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upan this inspection and a revicW of previous Atomic Energy Commission (AEC)
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inspection reports, it is concluded that the facility was successfully decontaminated to levels below the NRC release critoria.
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Persons Contacted j :l@, p f a ;,4' *,
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c+:0 Nancy Wells, Resident and owner'of property'
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- Steven Ott, Esq., Attorney for Nancy Wells
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- Contacted by telephone on January 21, 1993..
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(if AEC Licenses No. SNM-1347, SNM-909, 34-11105-01, and 34-13517-01 were issued to General Nuclear, Inc. and Parkwell Laboratories, Inc.,
respectively, for development, manufacturing, and distribution of sealed Ue sources in their former manufacturing facility at 429 North High Strcot, b
Croton, Ohio, during the period 1965-1979. On October 17, 1968, License G'
Ho. 34-11105-01 was amended to include irradiation of gem stones with
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The work was conducted in an 800 ft' single story Butler building at the r,-.
High Street address. The former facility consisted of a business P
office, machine shop, assembly and test areas, shower, restroom, and (p,;
small utility room.
License No. 34-ll105-01.was issued on June 24, 1965, and was terminated on February 3,11970.' In two letters to the d
Commission dated February 24, 1967, and March 1, 1967, the licensee S
informed the Commission that all assets and materials possessed by
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Parkwell Laboratories have been assigned to General Nuclear, Inc. (see Attachment A).
In another letter to the Commission dated Occember 10, 1969, the licensee stated that'all radioactive materials were transferred to their Texas License No. 4-734 and the only material that remelr.ed was contaminated hoods and glove boxes which was possessed pG,'
under License No. 34-13517-01-(sce Attachment B). Subsequent telephone ey conversations were made between NRC Region III staff and Mr. Charles ik Wells (now deceased) in the early 1980's prior to the termination of
@M License No. 34-13517-01, in which Mr. Wells indicated that these
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contaminated items were buried in'two burials in accordance with 10 'CFR 20.304 sometime in early 1980. These burials consisted of less p
than 20.0 microcuries of americium-241 as contaminated equipment, metal, and concrete (see Attachment C). During this inspection, Mrs. Nancy
[E Wells (wife of the deceased), informed the inspector that she was not 4
aware of any burials of radioactive material on the property. Assuming N,
that the contaminated items were actually buried, the NRC staff r
performed a hypothetical dose assessment and pathway analysis using the 1
computer modeling program RESRAD hypothetical assessment was based (upon the following assumptions:
version 4.34).
The conclusion to this ly r
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Buried material consisted of 20 microcuries of americium-241 in
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the form of contaminated equipment, metal, and concrete; v.,;
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9 Total volume of waste was' contained 'in.two 55-gallon drums
.,y amounting to 15 ft((7.5. cubic feet /55-gallon drum); and
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All waste was buried at 'a' minimum"of.isix f eet.
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s The NRC staff concluded that if this' hypothetical' burial'actually
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1]r occurred, the long-term effect to members 'of the public and h-environmental would be negligible. Thereforer if the burial of this' 1,pn quantity of. radioactive material;actuallyl occurred it would not pose a j
hazard.
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l Pi-t(fy The address changes and transfer of radioactive' materials to the above-referenced licenses were subsequently made the expired license files did not show'.any docume;ntation of a closecuthowever, a
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f, Mrs Wells was positive:that a. finaljsurvey was conducted; survey.
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however, she was not able to locate any documentation that would indicate that a radiologic' survey was conductec at the High Street
,t address prior to the termination of the licenses. ' A review of the Region Ill files show that on August 6-9,.1979,- an_ inspection and close-out survey was conducted (Report No J79-02). The inspection report issued on October 23,~1979, shows that at the time of this inspection, there was no residual contamination, except for waste waiting 'o be shipped to an authorized recipient (see Attachment D).
Information regarding past activities and locations of the former equipment was provided to the NRC inspector,by Mrs. Nancy Wells, u
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l1 During the license file review by ORNL, the conclusion that extensive contamination may be present at the formerly used facility was based upon the fact that the licensee worked with hazardous loose material and n.
the files did not indicate that the AEC/NRC conducted a final survey of E
the facilities prior to the license termination. However, as stated above, the NRC conducted a close-out survey of the facility on August 6-(
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Facility Status W!Ajf ',yg,jg The current resident of 429 High Street, Croton,-Ohio, is Mrs. Nancy Wells and she has. lived in the faellity since the early 1980's with her J
now deceased husband, who was the former owner of Parkwell Laboratories, u
Inc.
Mr. Wells passed away in November 1988.' The inspector determined k
from review of the drawings.and specifications found in the terminated
{h license file that extensive remodeling has:taken place in the facility during the past 13 years. -
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Independent Measurements
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The inspector conducted radiologic surveys in and around the areas where manufacturing and testing of radioactive sources were conducted.
J The inspector did not identify any radiation icvels above natural 4.,
background.
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The' inspectoi.!touridl thel iteta'nd a'djaceritTproperty' and conducted
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with a Model'44-9 panc)ake' probe,1 RC' Tag No.1037301ind
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which was calibrated y
- on August 18,.1992.V Background measurements taken in the middle of town
- (Croton,' Ohio)'with theiludium Hode133 showed 50 counts per minute
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'sourc)e showed.1',600 cpm'andfail'pClsesluin-137 check ~
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11,000, cpm.GRando' ' measurements (ofl the floors [ walls, and ceilings m
7 where former: licensed: activities weretconducted showed no radiation p:
levels above natura1' background.'lf Smeari ests for removable t
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- contamination did notl:show. any,1cor r aljha,? beta, or gamma. radiation.
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.b' The NRC inspector a. ymetzwith'Mrs.h, Wells and w2,:a x.
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summarized the findings of the inspection.V Thelinspectorl informed.Hrsn Wells Ethat the independent 6
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radiologic survey, indicated,that'thelformer. building facilities occupied 4}, @ -
by General Nuclear,tInc.Tand;Parkwell Laboratories, Inc. did not show
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any radiation levelsf above' natural background. Hrs. Wells was also informed that the levels?of! radiation were below the release criteria M[Q described in the NRC document',7 Guidelines for Decontamination of ic Facilities and Equipment Prior 2to Release' for Unrestricted Use or eMi Termination of' Licenses' for Byproduct,SSource[or Special Nuclear m3 Material," dated _ August,1987; -
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Dear Sir:
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In reference to thol o:of;Parksolli Laboratories, Inc.,
Inchp?vojwish to adopt the. statement,
,g' representations andl. procedures,!in Parkwell's application q,gt dated May 17,(1965' signed!by charles E.Mwells'of Parkwell
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Af Laboratorics,(Inc.,iandbl'so[tho f,[?.A Ch a r l o s E. ;; Woll s ;9P'r cM(a d t $d *, i'chr u;. s t a t em tions of. thoJtelegram ary*16,$1965'. signed by gN ddEt!,$ParNell[@ Laboratories. t
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sibilityjof;'Licenso by Gcncral Nuclear,yInc2W Iflyou'do' siro [further-information3.4-11105-l' (
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3 James,H., Kniasek,@irector,',Diviaion' of Yuel Yacilities 4 & 6ahd Materials':Safet j'i?;W{hN & M & & h]$y}$@$fl% %Q1&% Wl. ?;,NM laspec tion,'?lE%
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.,,b. AR B.]Davi.s TChief / Fual'Facilityf and Materials Safety
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- lg PARNELL' LABORATORIES,5 IEC.7 LICENS E No.
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M.CLOSE-OUT SURVIT'(
211-73) h 3 5104-134 7,
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A close-out survey was,conductediat',thelicensse's" facilities on Augus t 6 r
through 9, 1979.
evaluation of vipas and '. review foff records ;confirued, that m11 5 hl
(
'1
. previously, possessed by the' }1idensee',[exchyt'.vasta, has been disposed.l*
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of in an authorized==v=r,and that there was no^ evidence of residual';
cont==ination in sic'essie f.11mitsiin Proc'edure : No h 83895B E Attachment "1 Table 1..
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-9
@h-The licensee ' stated Jin:a phonet contset; on:
15,0.1979,.. that all',
{k[i.h,. t.
Oc tober,
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site operated by, Nuclekrigineeridg[Cofdine.Dnd'Ehat copies'.of the '
radioactiva vaste' voulds be ' shipped to.tha5Richland','WashinEton, ! burial
_ N.
sh.ipping papera vould;bajailedstoithe NuclearjRegulatory Cormission.
fW!
dh Based on the above 'and.on the' guidancat of! Procedure: 83890B and 83895B RIII has no objection' to Muthorizing7r' ele 1Anof: theilicensee's facilitica r! py y
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!!DORANDUM TOR:.?L.lB.lHigginboth..
1f amp;.Chie f,j Radiological Sa fety Branch, IE pi
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SUBJECT:
R S D ' ', / l. !
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[' NRCt LICENSEE? ACTIONS I
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f[);Q This refers toiRalphilleyer!sTrecentf telep 5?,
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On Octobe r 23,'11979,. TT!:S/RIllkaentya memorandum to the Division h'.'d Director, FT!!S 'Inspec tion "
of Parkvell Iaboratories'h,YIEN,'vithscopies.[of Scioscout1 survey : report
[yf4 In'cQ(Attachmentil)$7 hat bemorandum stated f
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that the licensee would ~ ship'lhisfradioactivcP.was te" to: a : commercial hy, I; burial site and that RII11h'adino objectionito rcicasing the':licensco's Q
On Iby 2.9, -1980g the<lic&) facility for unrcstrieted
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the vas te..had, not.';beenisj,i. informed !!r.'rSreniawskiIby :tclephon ensee i
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metal, and cone eteM AppendiQC;jy'6arici hl%st's'O.011pCij for '
o fi Pa rtf.20 kj.
A and 20. 304 pe rm ' n' 12, burials 3pe r offl000.timesjthe Appendix C c
quantity (10 'pci'of.'AM241%ei Eurial in" soll) y.:
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$yk ;, g$ 4 gs9;9;L."P ^
The licensee stated that he performcMtwo;buriali".
yjp{/IN Since the licensce' stated Lth,eyburia siwerofinf accordance with 20.304
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un res t ric te d use.;
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' tt ATTACHMENT C t u v 7 & 'T U ' ' /"
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'g 'h'(j'd/WTh5Sg$fg OiEIdb. NUCLEAR, REGULATORY Com(I ffif'. fcl$
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FMINS'PECTiO' hN'$NTDRCiI!ENT' l
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' Report;No.';79 02r,
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License No.fSN16134]
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7,l I,Priorit s
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I Ih2h f InspectionConducted@:/dAugust:61throug
, '1979 E.
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. %,fk Approved By: J '.
iPagliaro.ChiEfh; 7, h.y[%
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EProtcetion'Section*2hk' f
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. Inspection on Aur,ust~ 6-9,01979 (Report'Ho. 79-02)
Sf[fp$.
_ArcasInnpceted:,: Visual (inspectionigadiation;measurementsf7 air.sampics
.wr r P. %"
((M;$$N..t '
and evaluationsf of 'smearsr taken'.at.J.variouss' locations:lat the licensec's s
facility to verify 'esidu'aljonts 'i [ti6 MM}hdd.'ibcen.' disposed of and tha t.la11711conhed 'Imai.'ciial that t1rcre was noit Results: All" licensed MM%E@i V ' ~.
mn n
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authorized manner lcxecp{materidl;was disposed offby.,the licensce in.an i l
t for.) was te,Qhichl' 1sj to /,be'., shipped ; to the Richland, Washin'gton Xbu, rial'sitetoperated:byANucicar. Engineering Co.,
. 9 d,,,(P;.. Inc.
Thelicenseeisjtosedd?copf'esfof{thishippingpaperstoNRC-RIII.
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No residual contaminationivas dcted $d?
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OFFHCHAL USE ONLY
~
l SEALED SOURCE Manufacturer _
Model Designation i
Parkwell Laboratories, Inc.
PL-200 i
Croton, Ohio Isotope Use Cobalt 60 (110 mci maximum)
Moisture and Density Cesium 137 (550 mci maximum)
Gauges Americium 241 (2200 mci maximum) l
_ Description The Model PL-200 is a cylindrical, doubly encapsulated, stainless steel (Type 304) source for use in portable moisture and density gauges. The completed source is 0.356 inches in diameter and is 1.062 inches long.
The minimum wall thickness of both the inner and outer capsules is 0.025 inches. Americium sources are constructed by consolidating Am0 2
with a plug in an inner capsule under a 1,000-pound load. After closure l
of the inner capsule by inert gas fusion welding, the inner capsule is inserted into an outer capsule which is also closed by inert gas fusion welding. Construction of the cesium and cobalt sources is identical except that CsC1 or CoC1 is evaporated to dryness in the inner capsule prior to consolidation and capsule closure.
Prototype Testing l
l The following prototype tests were performed on the Model PL-200 source:
l 1.
A dummy source was sectioned and etched to determine the depth l
of penetration of the weld.
Both inner and outer containers had greater penetration than the 0.025-inch wall thickness.
2.
Three prototype sources were heated to 180*C. for two hours.
After cooling, the sources passed the helium pressurization leak test specified in Section B2.9 of the USASI Standard l
N5.10-1968.
l U. S. ATOMIC ENERGY COMMISSION
~ ^
OFFHCHAL USE ONLY
OFFHCHAL USE ONLY m
2 The same three sources used in the above temperature test were 3.
subjected to 300 psi water pressure f or f our periods of 15 minutes each. The sources then passed the same helium pres-surization leak test.
Labeling A serial number is legibly stamped or engraved on each source.
February 15, 3971
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U. S. ATOMIC ENERGY COMMISSION I
v OFFHCHAL USE ONLY 1
,