ML20054B998
| ML20054B998 | |
| Person / Time | |
|---|---|
| Site: | 07001156 |
| Issue date: | 02/17/1982 |
| From: | Deboer T NEW YORK, STATE OF |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20054B997 | List: |
| References | |
| NUDOCS 8204190359 | |
| Download: ML20054B998 (4) | |
Text
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O (Rockefeller Plaza e Albany. New York 12223 New York State Energy Research and Development Authority 518)465-6251 February 17, 1982 Mr. Ronald C. Haynes Regional Administrator United States Nuclear Regulatory Commission Region No. I 631 Park Avonuo King of Prussia, Pennslyvania 19406 Subjcct Locket No. 70-1156
Dear Mr. Haynes:
In your letter to Thomas J. Cashman, New York Stato Dopartment of Environmental Ccnsutvation, dated December 17, 1981, you indicated that with the exception of storago containcts Nos. D-0311, D-0032, D-0226, D-0256, D-0269, D-0285 and D-0318, all containcts in the former Plutonium Storaga Facility (PSF) may be disposed of as is.
In accordance with your recommendations, ERDA contracted for the required decontamination and survey with Mr. Harold L. Spector, Health Physicist, who is associated with the samo Department at the State University of New York at Buffalo that prepared the original "Closo Out Survcy Report" that your staff revicwed.
In an cffort to locate the containcts identified in your letter, Mr. Spector and a member of my staff, Mr. John C.
Dempscy, prococded to confirm the existence and identification of cach of tho 326 containcts in the PSF.
No container with a D-0311 labol was found, but a containct (designated and marked JD121181 by Spector) with the ID labol removed was found set aside from all the others. Sinco this container was the only one of the 326 that could not be positively identified by number, had been set aside with the label rcnoved, and was slightly contaminated, there is no doubt that container JD121181 is container D-0311.
As indicated in Mr. Spector's report (attached) confirmation contamination surveys worc conducted on six containers to assure that the inside and outside of these containcts moet the established critoria for unrestricted use or disposal.
One containct (JD121181) was surveyed beforc and after decontamination with a mild ammonia solution.
It is requested that you revicw the attached report and advise Mr. Cashman of your conclusions regarding the release of those containers for unrestricted use or disposal.
Sincorely, 8204190359 820409 PDR ADOCK 07001156 C
/
T.K.
DcBoer Program Director-West Valley TKD/cjm cc: J.C.
Dempscy T.J.
Cashman
u 4
fs Harold L. Spector 1201 Hertel Avenue Buffalo, New York 14216 (716) 873-5340 January 12, 1982 Mr. Jack Dempsey Nuclear Fuel Services Box 124 West Valley, New York 14171
Dear Mr. Dempsey:
Here are the results on the contamination survey I performed at the Plutonium Storage Facility on December 11, 1981.
As you requested, I tested a total of seven (7) storage containers and the transfer hood.
Testing consisted of taking filter paper smears of the container and inner hood surfaces with subsequent analysis of the smears for removable gross alpha and beta contamination. Analysis was performed on December 17, 1981 using a Canberra modified Beckman Low Beta II counter and P-10 counting gas.
Since testing sought gross contamination levels, efficiency factors for the conversion of count rate to disintegration rate were chosen for an alpha energy of 4 MeV and a beta energy maximum of 300 kev.
The efficiency factors deter-mined for such were 2.8 and 2.5 respectively.
In addition, both alpha and beta decay data was considered to have an intensity of 100% in the decay scheme of the radioactive material being_ analyzed.
Data is presented in terms of net cpm and dpm.
Analysis of the data was made to determine the statiscal basis for the actual presence of radioactive material on the smear as opposed to the probability of the analysis count being due to a normal fluctuation of count system background.
The null hypothesis having a confidence level of 95% was chosen for this purpose.
For the gross alpha determination, the
.necessary net count rate r, needed to ha considered significant was n
.97 cpm above background count rate rb, from:
r" S.E.r
~
where
> 2 for 95 % confidence, n
S.E.r n
\\
n+b b
t r
=.1 cpm, tn+b 5 minutes, tb = 5 minutes
=
b Similarly for the gross beta determination, having a background count rate of 17.2 cpm and using the same count times as above, the necessary set count rate needed to be considered significant was 5.7 cpm.
v s
neauttu vi concumiusciou outvey certurmeu 14/11/o1 concinueo....
rage z All values less than these respective minimum net count rates are not considered significant at the 95% confidence level and have been in-dicated appropriately using the symbol "NS" in the DEH column of the tabulated results.
As you can see, the results indicate levels of removable contamination to be below NRC requirements for release to unrestricted areas.
Storage container JD121181 was tested before and after cleaning with a mild ammonia solution.
If I can be of any further assistance to you, or if you should have any questions regarding these results, please feel free to contact me.
Very truly yours,
&t *W a
Harold L. Spector Health Physicist HLS:kt
Enclosures:
Three I
e
r v
.s a.
RESULTS OF CONTAMINATION SURVEY PERFORMED ON DECEMBER 11, 1981 ALPHA BETA ITEM NET CPM NET DPM NET CPM NET DPM D0032 Inside 0.1 NS
- 2. 9 NS D0032 Outside
- 0. 0 NS
- 1. 0 NS D0226 Inside
- 0. 3 NS 1.1 NS D0226 Outside 1.1 3.1
- 0. 3 NS D0256 Inside
- 0. 0 NS 3.4 NS D0256 Outside
- 0. 5 NS
- 1. 7 NS D0269 Inside
- 0. 0 NS
- 0. 0 NS D0269 Outside
- 1. 7 4.8
- 1. 3 NS D0285 Inside 0.1 NS
- 0. 0 NS D0285 Outside
- 0. 5 NS 0.0 NS D0318 Inside
- 0. 0 NS
- 0. 0 NS D0318 Outside
- 0. 3 NS
- 0. 0 NS JD121181 Inside
- 1. 7
- 4. 8
- 0. 7 NS JD121181 Outside
- 2. 3 6.4
- 0. 0 NS
- JD121181 Inside
- 0. 0 NS
- 0. 0 NS
- JD121181 Outside
- 0. 0 NS
- 1. 8 NS Hood A Plexiglass
- 0. 3 NS
- 2. 3 NS Hood B Shelf & Wall
- 0. 5 NS
- 0. 0 NS Hood C Top Vent
- 0. 3 NS 0.9 NS
- After cleaning with mild ammonia solution L