ML20217J499
| ML20217J499 | |
| Person / Time | |
|---|---|
| Issue date: | 08/05/1997 |
| From: | Lohaus P NRC OFFICE OF STATE PROGRAMS (OSP) |
| To: | GENERAL, OHIO, STATE OF, OKLAHOMA, STATE OF, PENNSYLVANIA, COMMONWEALTH OF |
| References | |
| IEIN-94-007, IEIN-94-7, SP-97-056, SP-97-56, NUDOCS 9708140302 | |
| Download: ML20217J499 (6) | |
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4 UNITED STATES.
'O
,j NUCLEAR REGULATORY COMMISSION g;
WASHINoTON, D.C. 30666-0001 August 5, 1997 ALL AGREEMENT STATES OHIO, OKLAHOMA, PENNSYLVANIA TRANSMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP 97 056)
Your attention is invited to the enclosed correspondence which contains:
INCIDENT AND EVENT INFORMATION..............
PROGRAM M ANAGEMENT INFORMATION.........
TRAINING COURSE INFORMATION...................
T ECH NIC AL INFORM ATION............................. XX Enforcement of Solubility Criteria OTH ER I N FO R M ATIO N....................................
Supplementary Information: Recently, questions have been raised about how a licensee would demonstrate compliance with the solubility provisions of 10 CFR 20.2003,
" Disposal by Release into Sanitary Sewerage." This Section states, in part, that a licensee may discharge licensed materialinto sanitary sewerage if it meets specified concentration limits and the materialis readily soluble (or is readily dispersible biological material) in water. To aid Agreement States in enforcing this regulation, we are providing background information pertaining to solubility criteria.
Following issuance of the new Part 20 rule, staff prepared and issued Information Notice 94-07, _" Solubility Criteria for Liquid Effluent Releases to Sanitarv Sewerage Under the Revised 10 CFR Part 20' (Enclosure 1). The information Notice provides acceptable approaches / procedures for determining solubility.'
As nuclear laundries have the potential to discharge insoluble materialinto sanitary
'[
V sewerage, a number of studies have been completed involving Interstate Nuclear Services (INS) operations. With respect to INS Royersford, Pennsylvania, a study was s
conducted by Scientech, Inc., at their request, in order to provide the supporting O
background information involving radioactive particulate releases into the wastewater at this facility (Enclosure 2). The results of this study, as well as other studies that b.J INS has conducted, indicate that successive filtration of the wastewater using smaller than 20 microns did not significantly lower the amount of radioactivity in the 71 water, in addition, as the NRC Inspector's field notes for the Royersford facility
- 02. Illustrate, specifically page E-8 of Enclosure 3, the licensee uses five different filter pA sizes (1,'5,10,30, and 60 microns) rather than just one filter size'of 20 or 25 microns pd to show that the gross radioactivity levels are statistically the same for solids retained W, for any of the five filter sizes (Enclosure 3).
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SP 97 056-2-
One example of a facility with a specific licensing action involving the authorization of a 20 micron filter is the INS Portsmouth facility. Enclosures 4 through.6 are copies of the NRC Region ll licensing files regarding the INS Portsmouth license requiring the use of a 20 micron _ filter for solubility determination.
J We suggest that if you have not already done so (e.g. as part of an inspection or license 5
amendment), you consider reviewing the procedures for determining solubility prior to
- discharge for licensees who have the potential to discharge insoluble materialinto sanitary sewerage.
If you have any questions regarding this correspondence, please contact me or the individual named below.
POINT OF CONTACT:
Lance J. Rakovan TELEPHONE:
(301)415 2589 FAX:
(301)415-3502 INTERNET:
LJR2@NRC. GOV Qat/
(Nr Y P'aul H. Lohaus, Deputy Director Office of State Programs
Enclosures:
As stated 1
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SP 97 056 2-AUG 0 61997 One example of a facility with a specific licensing action involving the authorization of a 20 micron filter is the INS Portsmouth facility. Enclosures 4 through 6 are copies of the NRC Region ll licensing files regarding the INS Portsmouth license requiring the use of a 20 micron filter for solubility determination.
We suggest that if you have not already done so (e.g. as part of an inspection or license amendment), you consider reviewing the procedures for determining solubility prior to discharge for licensees who have the potential to discharge insoluble materialinto sanitary sewerage.
If you have any questions regarding this correspondence, please contact me or the individual named below.
POINT OF CONTACT:
Lance J, Rakovan TELEPHONE:
(301) 415 2589 FAX:
(301)415 3502 INTERNET:
LJR2@NRC. GOV 4
OriginalSigned Dy:
PAULH.LOHAUS Paul H. Lohaus, Deputy Director Office of State Programs
Enclosures:
As steted Distributio.D:
DlR RF DCD (SP03): PDR (YES) -
SDroggitis DCool, INNS /NMSS Agreement State File
- See previous concurrence DOCUMENT NAME: G:\\LJR\\ SP97056.LJR Ts
. copy et tw. socum.ni. mac.i. w the hos: c - copy without ett cry.nt/.nciosurn t - Copy with ett chm.nt!.nclosue.
N - No copy OFFICE OSP l
OSP:DD l
OSP:D(/ K 9, l
NAME LRakovan:kk\\gd PHLohaus RLBangart,W i
[DATE 06/24/97*-
06/24/97*
08///'797 OSP File CODE: SP A 4
ALL' AGREEMENT STATES OHIO, OKLAHOMA, PENNSYLVANIA s
TRANbMITTAL OF STATE AGREEMENTS PROGRAM INFORMATION (SP 97
)
Your attention is invited to the enc!osed correspondence which contains:
INCIDENT AND EVENT INFORMATION...............
ROGRAM MANAGEMENT INFORMATION.........
TR ING COURSE INFORM ATION...................
TECHN AL IN FO R M ATIO N............................. XX Enforcement of Solubility-Criteria OTHER INF MATION.....................................
Supplementary Informh lon: Recantly, questions have been raised about 10 CFR 20.2003,
" Disposal by Release int Sanitary Sewerage." This Section states, in part, that a licensee may discharge licensed m erialinto sanitary sewerage if it meets specified concentration limits and the meterialis rea ily soluble (or is readily dispersible biological material) in water. In particular, question have been raised about how a licensee would demonstrate compliance with the solubility p visions of 10 CFR 20.2003, f
Following issuance of the new Part 0 rule, staff prepared and issued Information Notice 94-07, " Solubility Criteria for Liquid fluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20" (enclosed).
e information Notice provides acceptable approaches / procedures for determining tubility.
We suggest that if you have not already do so (e.g. as part of an inspection or license amendment), you consider reviewing the proc dures for determining solubility prior to discharge for licensees who have the potential discharge insoluble materialinto sanitary sewerage (e.g. nuclear laundries).
If you have any questions regarding this correspond ce,'please contact me or the individual named below.
POINT OF CONTACT:
Lance J. Rakov TELEPHONE:
(301) 415-2589 FAX:
(301) 415-3502 INTERNET:
LJR2@NRC. GOV Paul H. Lohaus, De ty Director Office of State Progi. s
Enclosure:
As stated Distribution:
SDroggitis Agreement State File DOCUMENT NAME: G:\\LJR\\ SOLUBLE.L(R l T3 teceive a topy of INe document, bd6cate in the boa; 'C' & ge y pvtthout attachment /enclosu,e "E* = Copy with attachment!anclosu,o
- N' No copy OFFICE OSP OSfi%l-OSP:D
\\
g NAME LRakovan:kk 4 PHLohetis, RLBangart
\\
DATE 06/zv/97 -
06Cl/97 -
06/- /97
\\
OSP FILE CODE: S P-
. March:11, 1997 1
MEMORANDUM T0:
John Madera,_ Chief Nuclear Materials Inspection Branch 1 Region !!!
FROM:
Donald A.: Cool. Director (orig, signed by)
Division of Industrial and Medical Nuclear Safety, NMSS
SUBJECT:
E CHNICAL ASSISTANCE REQUEST CONCERNING CERAC. INC., AND EFFLUENT RELEASES TO THE SANITARY SEWER I am responding to your technical-assistance request dated February 20. 1997.
(attached) requesting a determination-if passing radioactive material liquid effluents through a 0.45 micron filter is an adequate methodology to insure compliance with 10 CFR 20.2003(a)(1).
In a letter from Cerac. Inc., dated February 11, 1997. the licensee proposes to use a 0.45 micron filter, or smaller, and pass all liquid effluent in question through it prior to discharge to the sanitary sewer.
The filtration and radiometric analysis of suspended solids is described as an acceptable method for determining solubility of an effluent in Information Notice.94-07, " Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20."
The Notice cited as acceptable procedures using a 0.45 micron filter to determine the suspended solids in the effluent. The IN indicates "... activity -in the suspended solids portion of the effluent greater than that found in similarly processed background water would indicate the presence of insoluble radioactive material." Conversely, if the material passes through the filter, the portion that passes through should be. considered soluble.
Therefore, the proposal by the licensee in Cerac's' February 11, 1997, letter is deemed adequate to show compliance with 10 CFR 20.2003(a)(1).
It should be noted that a 0.2 micron filter, mentioned in their letter. is neither used in the standard analysis, nor is it required to show compliance.
Attachment:
As stated A
\\'
h p nM ENCLOSURE 1
.L
- REGIONAL TECHNICAL ~ ASSISTANCE REQUEST FORM i
betei Fahrvarv 20.1997 man or E-man to:
Donald A. Cnol(DAC), Mail Stop: 6H3-OWFN, If E-maH, cc: CLE.
Division of Inoustrial and Medical Nuclear Safety, NMSS from: John Acadern 2f d
- Region ill Chief, Nucles is inspection Branch i Ucensee: CERAC. Inc.
Ucense No. SMB 1402 o ControlNo.
Jif applicable) o letter dated:
(if applicable) a Suggested change in licensing procedure (enclosed):
i o Problem / Issue:
The licensee possesses an NRClicense to process natural thorium which results la radioactive liquid and air e))luent releases to the environment. On December 18,1996, the NRCidentified the licensee had not determined the activity or solubility ofliquid effluent discharges into the sanitary sewer system. The licensee's immediate corrective actio*s was to hold allliquid effluent discharges generatedfrom licensed.
activities in 55 gallon drums until the liquid could be analyzedfor activity andsolubility. Prior to placing the lig:Id effluent into 55 gallon containers, the licenseefiltered the water with a 0.45 micronfilter to remove suspendedsolids in the liquid. In addition, the licensee also possesses a water scrubber which removes licensed materialfrom air epluent discharges prior to release to the environment.
' The licensee sent afaxed letter to thc NRC dated February 19,1997 which contains analysis data of water s:nqples takenfrom 13 55 gallon (2.09E5 milliliter) containers (One samplefrom each container) and the scr:bber holding reservoir. According to the Ilcensee, each sample was analyzedfor dissolved (saluble) and suspended (insoluble) licensed material. The licensee stated that allgross alpha activity was assumed to be
- thorium-232 decay. According to the licensee, licensed activities generate approximately 14 55 gallon drums (2.93E6 milliliters)per month.
. la afaxed letter to the NRC dated February 11,1997, the licensee stated that approximately 5.44E5 gallons (2.07E9 milliliters) of water per month was used by the licensee and sent through the sanitary sewer system.
. According to the licensee's calculations in the above letter, one 55 gation container containing 3E5 microcuries per milliliter oflicensed material would be approximately 1 % of the monthly sanitary sewer release limit (see 10 CFR 20, Appendle B, table 3: thorium-232). In addition assuming the licensee generates approximately 14 55 gallon ofradioactive liquid effluent per month into the sanitary sewer system, a
the licensee's water dilutionfactor is approximately 3 orders of magnitude.
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- The licensee is requesting that radioactive liquid efpuentfiltered through a 0.45 micronpiter be placed directly into the sanitary sewer system withoutfurther testing. The licensee stated that NRCInformation Notice 94-07 referencing ASTAi D 1888-78 " Standard Test Aiethodsfor Particulate and Dissolved Aiatter, Solids, or Residue in Water" Infers that alllicensed materialpassing through a 0.45 micronfilter is considered solublefor the purposes ofreleasing licensed materialinto the sanitary sewer system and that the mentionedfiltering system can be used to demonstrate solubility ofradioactive liquid efpuent discharges into the sanitary sewer system.
O Action Required:
e Determine (fpassing radioactive liquid efpuents through a 0.45 micronfilter is an adequate methodology to insure compliance with 10 CFR 20.2003(a)(1), licensed materialis readily soluble in water.
O Recommended Action (with revisions): 0 Approve or a Reject The region believes thatpassing radioactive liquid efpuents through a 0.45 micronfilter is an adequate methodology to insure compilance with 10 CFR 20.2003(a)(1). As supporting evidence, NRC Information Notice 94-07 referencing ASTAi D 1888-78 " Standard Test b1ethodsfor Particulate and Dissolved Aiatter, Solids, or Residue in Water" does appear to infer waterpassed through a 0.45 micronfilter does not contain significant quantities ofsuspended solids. In addition, the region believes the small quantity of" suspended" licensed materialidentified by the licensee in the 55 gallon containers and scrubber holding reservoir combined with the S44,000 gallon dilution waterfrom the licensee'sfacility into the sanitary sewer system does not pose a significant health risk to members of the generalpublic.
Remarks:
Enela:ed.are the documents, in whole or in part, as stated above.
Ifyou have any questions, please contact hilchael Af. LaFran:o byphone, 630-829 9865 or E-mail, address ofAIL.
AttachmentA:
Licensee letter dated February I9,1997 Attachment H:
Licensee letter dated February 11,1997 Attachment C:
NRCInformation Notice 94-07 Attachment D:
ASThi D 1888-78 " Standard Test Afethodsfor Particulate and Dissolved Afatter, Solids, or Residue in Water" lleadquarters Reviewer: Joseph DeCicco Regional Reviewer: Afichael LaFranzo Reviewer Code: Ai7L Reviewer Phone No.: (630) 829-9865 Fax No.: (708) 515-1259 Request Needed by:.JJ3 / 97 (date)
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C Pederson, Rill inspector, Rill Form TAR-101086
02/19/97 17:33 FAI 414 269 960f, CERAC INC.
'EV"l'uug Attachment A Quality Minufacturing Since 1964 P.O BOX 1178 MILWAUKEE W1 63201 1178 USA.- PHONE: 414 289-G800 FAX: 414 289 9805 February 19,1997 par.,e 1 of 2 Mr. John Madera U.S. Nuclear Regulatory Commission fax: 630 5151259 Region III voice: 630-829 9834 801 WarTenville Road Lisle, IL 60532-4351 Re Proposed Efiluent Releases to the Sewer
Dear Mr. Madera:
As reciucsted, following are the results of our sampling and testing of process and scrubber water. They were performed similu to the method discussed in APHA method 7110. Sample 14 represent a water sarnple take.n froc the scrubber holding reservoir. All nwnber are in un]ts of pCi/ml.
Dissolved Suspended Samole Gross Aloha Gross Alnha 1,
3.8E-06 2.4E-08 '
2.
1.5E-06 8.6E-07 3.
3.9E-06 1.2E 07 4.-
5.6E-06 6.2E-07 3.
2.3E 06 7.9E-08 6.
6.3 E-06 2.3E-07 7.
3.7E-06 2.3E-07 8
4.0E-07 2.4E-07 9
4.2E.06 3.5E-07 10.
7.4E-06 7.2E-07 11.
6.4E-06 3 OE-08 12.
6.3E-06 7.9E-08 13.
1.0E-06 3.1 E-07 14.
1.4E 06 2.3E-03 3
MDA 3.4E-07 pCi/ml 3.12 09 gCi/ml Gf$Yi 0*JY~k(3 E-Mall; marketina @ CERAC.com llRt.: httphww.ocroc.com Qwalty (norganect TNn Film Mate.% Sputtering T,wgats Product lon Quantity and Smalllot Manufacturing Custom Preparations
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02/19/97 17:33 FA1 414 ;*6W e695 otAw 4x.
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_CERAC, incorporeted page 2 Let me know what additional information you need to resolve this matter. I look forward to your quick ieply.
Sincerely, Dr. Mitchell C. Colton Radiation Safety Officet
02/jL/97 14:0s FAI 414 269 980$
CERAC INC.
Z001/003 Attachment B incorporated Quality Manufacturing Since 1964 P.O. BOX 1178
- MILWAUKEE. WI 53201-1tE8;.- U SI Y PHONE: 414 289-9800 FAX: 414 289-9805
~
February 11,1997 page 1 of 3 Mr Michael Lrfronra, Radiation Specialist Nuclear Materials Inspection, Section fax; 630-515-1259 U.S. Nuclear Regulatory Commission voice. 630-829-9865 Region III 801 Warrenville Road Linie, IT. 605U. 4151 Re.
EfLuent Releases to the Sewer Dear Mr.1.aFmnrx Dased on uus icvent telephone conversanons, I request your approval to release our collected liquid efIluent and our near term continuation as discussed below. This is for both our chemical process and our fume scrubber liquids. Longer term solutions will be discussed as we develop our plans.
The following qualifications apply:
Oualifications for Releasel 1.
It is sufficient to demonstrate compliance with 10 CFR 20.2003(a)(1) regarding solubility of matedal released to the sanitary sewer by passing allliquid efHuent in question through a 0.45p or smaller filter.
2.
Total activity levels of material released to the sewer will he within rele. ate limits. In the short term, we will sample every drum until we have an agreed upon sampling and testing protocol.
(As an example, the attached spreadsheet output represents typical activity and percent of limit for a SS-gallon drum of process water. If a sample of a 55-gallon drum has on the order of 3x10 pCi/ml or less of total activity, its release represents about 1% of our monthly limit assuming all activity is due to Th-232, which is a conservative assumption.
If you assume the activity is half from each of Th 232 and Th-228, the number becomes approximately 0.6%.
Includmg actmty trom any other isotopes reduces this number further.)
1
{A E Mall: marketing @ CERAC.com URL: http://www.cerac.com Speclaty hKtgaada
- Thire Pum Materials + Sputtering Targets Produccon Quantly and bman sot Manufactunng Custom Preparatons
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- CERAC, incorriorated pas 7 3.
For short term verincation of filter integrity, we will:
a)
Change the OA5p filter at least once per month (represents about 600 1000 gallons) b)
OI more often if deterrnined necessary (e.g. after ne process the drums we have collected) c)
or as we change pmcess streams, For example, process water is typically pH of 8 or higher and sembber water is a' bout pH of 1-2. We would change filters before filtering one after the oths.
d)
As an additional safety measure, we will put a 0.20g filter after the 0.45u filter and pass all ligtsds through it as well. This 0.20 filter will be changed wheneve: the 0.45 filter is changed.
I look forward to your quick reply on this matter.
. Sincerely, 4
Dr. Mitchell C. Colton i
Radistion Safety Officer 9
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. Calculations for RAM water disposal 3E 07 uCi/mi Th-232 morably average release to sewer 10 CFR, pg 447,1/1/93 (roost restrictive) 6E 07 uCl/ml U-232 monthly average release to sewer t O CFR, pg 447,1/1/93 (most restrictive) 3E46 is for U nat 6E-07 uCi/mi Ra 226 monthly average release to sewer
- 10 CFR, pg 447,1/1/93 1.110E-01 UC1/g Th nat activity 6.77E-01 uCl/g U-nat activity, depleted is less 3.00E 01 uCl/g, specific actMty for depleted U
-water results:
pCi/l x 1E D=uCi/ml each drum =
55 gal 216,216-or 208.191.81 ml water from:
2190 ccf 3 "N
g/ month allowable 4/93-7/93 1,039,120 galf-Th U
6.20E+09 ml Iow estimate 2.07E+09 ml/ month-avg 5586.293 1831.842 recent months have been higher 208191.800 ml process water / barrel (=55 gal) 2.0669E+09 mi sewor water / month vs Conc /Activtty Units uCl/ml/mont % of monthly limit
- 3E-05 uCl/mi 3.0218E 09 1.01 %
per 55 gal barrel
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-p UNITED STATES Attaclunent'C NUCLEAR REGULATORY COMMlSSION OFFICT OF NUCL DR HATERIAL SATETY AND SAFfGUARDS
-WASHINGTON, D.C.
20555
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January 28, 19'94 NRC INFORMATION NOTICC 94-07:
SOLUDILITY CRITERIA FOR LIQUID EfftVENT RELEASES TO SANITARY SEWERAGE UNDER THE REVISED 10 CFR PART 20
.(
Addressees
'All byproduct material and fuel cycle licensees with the exception of
-licensees authorized solely for sealed sources.
Eurpose The U.S. Nuclear Regulatory Comission 1s issuing this information notice to emphasize the changes in 10 CFR Part 20 with respect to liquid effluent relv4ses to sanitary sewerage and to encourage you. to prepare for these revisions.
It is expected that licensees will review this information for 4ppilcabl11ty to their operations,. distribute it to appropriate staff, and consider actions to prepare for, and incorporate, these changes.' Suggestions contained in this information notice are only reconnendations; therefore. no specific action nor written response is required.
-Background on December 21, 1984, NRC released an infonnation notice documenting several Instances of reconcentration of radionuclides released to sanitary sewerage (IN Ho. 84-94, " Reconcentration of Radionuclides Involvin Santtary Sewage Systems Permitted under 10 CFR 20.303'). g Discharges into Several other instances have since occurred in Portland, Oregon; Ann Arbor, Michigan; Erwin, Tennessee; and Cleveland, Ohio. The primary contributors, in some of these cases, appear to have been insoluble materials released as dispersible parttculates or flakes. This issue was addressed again on May 21, 1991, by HRC, when it published its revision of Part 20 in the Federal llegister (56 B 23360), which removed insoluble non-blological material from the types of material that may be released to sanitary sewerage. Relative to this issue, the HRC Office of Nuclear Regulatory Research is conducting a study to clarify the mechanisms unde.rlying reconcentration in sanitary sewerage and
-sewage treatment facilities.
9401240059 Sanitary sewerage is defined by 10 CFR 20.1003 as "a systein of pubife sewers, for carrying off waste water and refuse, but excluding sewage treatment faTilities, septic tanks, and ' leach fields owned or operated by the licensea
[ emphasis added)."
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IN 94-07 January 28, 1994 Page 2 of 5 DeKf_1P11ML0f Circum 1Dnm 10 help prevent further reconcentration incidents at public sewage treatraent facilities,10 CFR 20,2003(a)(1), effective January 1,1994, was written as follows:
$20,2003 Disposal by release into sanitary sewerage (4) A licensee may discharge licensed matertal into sanitary sewerage if each of the following conditions is satisfied:
(1) The material is readily solubic (or is readily dispersible biological material) in water; and...
Ilowever, this revision to Part 20 did not contain an operational definition of solubility, and this precipitated many questions, from Ilconsecs, concerning how the solubility of a material may be decionstrated.
Without the ability to demonstrate compliance, these licensees were unable to determine whether new procedures should be developed, new treatment systems installed, or whether they should apply for an exemption, based on the principle of maintaining all doses as low as is reasonably achievable (ALARA).
Discussian In some of the known reconcentration incidents, the greatest reconcentrations appear to have been due to compounds released to sanitary sewerage that were not soluble.
There are manj approaches that may be used to determine a chemical compound's solubility in water. The following discusses two of the more common approaches:
1.
Ditest Determinat. ion of Comonund_Solubilitv C1 ass, iormal Solubilitv.
OrSolubilityProduct(X)
This approach would be applicable whenever there is sufficient knowledge of the chemical form of all materials contained in the liquid effluent at the point of release. With this knowledge, it would be possible to use one (or more) of the following mathnds-(a) Solubility Class Determination:
The solubility class of the compound in ha released could be determined directly from common literature data (e.g., Han<! book of Chemistry and Physics - CRC press. and Unge's Handbook of Chemistry - ticGraw-lilli Book Company).
If a compound is classified as "y s" (very soluble) or "s" (soluble), this would indicate the compound is "readily soluble." On the other hand, if it is classified as "1" (insoluble). "sl s" (slightly solublo), or "v si s' (very slightly soluble), this would indicate materials that arn *not readily soluble." Certain compounds are designated as class "d" (decompose).
If the decomposed species of these coepnonds are classt flod as either "v s* or "s," this would indicate that the parent compound is "readily soluble."
If these decompnted species are simple ions, such compounds (clus "d")
should be considered 'readily soluble.'
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January 28, 1994 Page 3 of 5 (b) Solubility Product (K,,) Determination:
-The solubility product constant of the compound could also be used i
to determine if a compound is readily soluble in water. The solubility product constant, K,,, for a strong ehetrolyte %, is -
expressed ast--
4 (N]"(A)*
' K.,
where (ML and "m" are the ionic c.oncentration (mole / liter) and the number of moles, respectively, of the dissolved cation; and
-and "a" are the ionic concentration 4nd the number of moles,(A) respectively, of the dissolved anion.
For a simple electrolytic compound, with one mole of a dissolved cationspeciesandonemoleofagissolvedanionspecies,aK 2
greater than 1.00 E-05 mole / liter. would' indicate that a comp d
oun is "readily soluble." for other compounds with more complex.
dissolution reactions (i.e., more than one mole dissolved for each species _and/ur more anionic or cation 1c species present in the dissolved products), the K, constant would increase exponentially, b4 sed on the number of moles and/or the number of dissociated species. For example, if three moles are present (two for w
mole}/ liter,,and thg; corresponding Khe 4nion an 3
would be (1 E-or 3.2 E-08 sole / liter the same princ9ple could be applied for L
3 more complex dissolution reactions.
4 (c) Formal Solubility Determination:
Compound solubilities (g/100 ml or mole fraction per 100 ml) are also listed in the chemical literature, from a review of general scientific literature, " formal solubilities'" greater than 0.003 mole / liter would' indicate that a compound is 'readily soluble.'
- The general relation between the formal solubility, S. and the solubility product.
K,,,, of a strong electrnlyte H,A, in water is give,n by:
K h-where K is the solubility product, (H) is the molar concentration of the metal
- lon-(cal' ion),- lA]d cation per mole of dissolved substance, and "a"
-is the molar concentration of the anion. :"m" is-the number of moles of disso ve
= of moles of the dissolved anion per mole of dissolved substance.
p for further discussion on the determination of. solubility products and foreal J
sojubility. refer to ' Chapter 6, '" Precipitation and Dilution,' fr'm Water o
[hemistry, by Vernon L. Snocyink~ and.0 avid Jenkins-(John Wiley and sons: 1981) or.. texts relating to physical _ and/or-analytical ch mistry.
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-gn 94 ny January 28, 1994 Page 4 of 5 formal-solubilities less than 0.003 mole / liter would indicate compounds that are "not readily soluble."
It should be pointed out that all values mentioned above (e.g.,
solubility class, formal solubility, and solubility product)-
correspond to measurements taken under standard conditions (e.g.,
25'C,101.3 kPa,. pit of 7 and f, of 0.
2.
filtration and Radiometric AnalV$li Of SuspeHded SUlldS This 4pprusch may be used if knowledge of the chemical form of all-materials contained in the liquid effluent at the point of release is incumplete. - It 13 mest applicable when releases are made in a batch mode.
This approach involves the use of standard laboratory procedures to test representative samples of the waste stream for the presence of suspended radioactive material.
The following two laboratory procedures were developed specifically to determine the suspended solids content of water: ASTM Nethod 0 1888-7fs, " Standard Test Methods for Particulate and Dissolved Matter, Solids, or Residue In Water," and the American Pubite ticalth Association's Method 7110, ' Gross Alpha and Gross Beta Radioactivity
-(Total, Suspended, and Dissolved)" from Et.agfard Nothods for the Exaniination of Water and Wastewater, it should be notud'that ASTM Method 0 1888-78 was developed to measure the total suspended solids content of water, not just the radioactive portion.
In either case, activity in the suspended solids portion of eftluent greater than that found in sitsilarly processed background water samples would indicate the presence of insoluble radioactive matertal.
Whettler one of the above approaches or a self-developed alternative is used, it is a good health physics practice to document this approach in the form of a procedure. Procedures-such as these usually include provisions for the documentation of.any models, calculations, analytical measurements and/or quality control measures used. This infonnation is usually maintained with the applicable release records, to demonstrate that the developed procedure will ensure compliance with the regulations.
If material to be released would not qualify as being "readily soluble,"
10 CFR 20.2003(a)(1) would prohibit release to sanitary sewerage unless an exemption has been granted.. Exemptions will be judged on a case-by-case basis, when it is demonstrated that release to sanitary seweraae is in accordance with the ALARA principle, consistent with applicable regulations, and in the public interest.
It is expected that licensees will review this information for applicability to their operations, and consider actions, as-appropriate to their licensed
-activities.. However, suggestions contained in this information notice are not NRC requirements; therefore, no specific action nor written response is required.
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IN 94-07 January.28. 1994 Page S of 5 if you hav6 any questions about the information in this infomation notice, pleato contact one of the forhnical contacts listed holow nr the apprnpriate regional office.
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Robert F. Burnett, Director Carl J. Paperiello, Director Olvision of Fuel Cycle Safety Olvision of Industrial and and Safeguards Medical Nuclear Safety Office of Nuclear Material Offico of Nuclear Material Safety and Safeguards Safety and Safeguards Technical contacts: Rateb (Boby) Abu-Eld, NHSS (301) 504 3446 Cynthia G. Jones, NMSS (301) 504-2629 Att achtnent s:
1.
List of References 2.
List of Recently issued NHSS Information Notices 3.
List of Recently issued tiRC Information Notices 1
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Pago 1-of 1 REFERENCES Annual-Book of ASTM Standards. Volt;me '11.01, " Water (!)." American Society for Testing-and Materials, Easton, MD, 1989.
CRC Handbook of Chemistry and Physics. CRC Press.-Inc., Boca Raton, FL, 65'"
ed, 1984 Lance's Handbook of Chemistry. McJraw-Hill, Inc., New York, NY,13* ed, 1985.
Snoeyink. Vernon L. and David Jenkins, Water Chemistry. John Wiley & Sons, Inc., New York, NY, 1980.
Standard Methods for the Examination of Water and Wastewater. American Public Health Association Washington, DC,17" ed,1989.
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April 24,1991 Mr. Mark Pony l , interstate Nuceear Servioes 295 Parker Street P.O. Box 51957 413 6434911
SUBJECT:
ML8 03341: Isotope Flitration Study /
Dear Mr. Perry:
i Following are the values toported 1 ou earter by telephone for'the solubility study performed on your wash water sam . The samg4e was counted for gamma prict to any Mration then counted again after ussing through a 20.10.1. 0.45 and finalty 0.1 micron her. Aker each Mration the fl trsie was speciflea#y monttored for 2n65. Co60, and Cs137 along with N43 and Fe55. The residue at each step was anatred for
- Cs137, Zn65 and gross beta with the following resub.
18efore Fikration 18o10pe WCFml 2n65 2.39E4 Co60 1.21E 6 Cs137 5.60E 7 il After Filtration i Dissoked Suspended isotope UCl/ml uCl/ml 20 mooron Attration (F 1) Zn65 1.88E4 3.72E 7 Co60 8.70E.7 2.48E 7 Cs137 8.70E.7 ND Fe55+Ni63 3.36E 6 4.38E 7 (gross beta) 10 micron mration (F 2) Zn65-2.15E4 ND Co60 9.56E.7 ND Cs137 6.44E 7 ND Fo55+Ni63 5.12E 6 4.70E 9 (grou beta) ENCLOSURE 2 g i ltt0 %.p 7 M Y M EM ww%e .w
- *t e I
1 micron Sitration (F 3) Zn65 1.90E 6 ND i 0060 8.W4E.7 1.24E 4 Cs137 8.82E.7 ND Fe55+N43 3.72E4 2.31E4 (gross beta) 0.45 mioron attration (F 3) Zn65 2.02E 6 ND 0060 8.51E 7 ND Cs137 5.55E.7 ND fee 5+Ni63 3.71E4 5.30E4 (gross bets) 0.10 micron fWtration (F.3) In65 1.97E4 ND Co60 8.45E.7 ND Cs137 5.55E 7 NO Fe55,NiS3 3.79E 6 5.75E 9 (Gross beta) M appears that some actMty may have been mechanically removed in the first Whration due to the inhlal high total suspended solds but all actMtles remain essentially the same on all successive filters which would lead you to believe that the contaminants are present in solution and not as a suspended solid. Mark N you should have any cluestions or Ike us to go further with this study please do not hesitate to cati me at 214 2471714 Sid:orely, .,, ys. 'chael L Buyinghaul n Deputy Lab Director File: C.5 TOTA F.CC f
O APPEN0!X E j NOTE: All areas indicated in field notes l are not required to be addressed during each inspection IISU$ TRIAL /ACADDl!C/RESEARCH INSPdCT10E FIELS NOTES Region _L Inspection Report No.: 030-20934/9f001 License No.: 37-23341-01 Docket No.: 030-20934 Licensee (Name & Address): Interstate Nuclear Services 401 North Third Avenue Royersford, Pennsylvania 19464 Licensee
Contact:
L. Nichael Rahilly, R50 Telephone No.: 610-948-9700 Last Amendment No.: 11 Date of Amendment: July 29, 1994 Priority: 2 Program Code: 03218 Date of Last inspection: October 1 & 2, 1992 Date of This Inspection: July 13 & 14, 1995 Type of Inspection: X Announced .f Unannounced X Routine Special Initial Reinspection Next Inspection Date: July 1997 (X) Normal ( ) Reduced ( ) Extended Summary of Findings and Action: X No violations cited, Clear issued Violation , 591 issued Violation . Regional letter issued Followup on Previous Violations Were non-cited violations identified during this inspection? ( ) Y (X) N Was proprietary information reviewed by or received by the inspector? ( ) Y (X) N Inspector:. 04ec,ss b Date k7 f/I ~T51gnature) Inspector: M 'M M Date [ (3 u g/ // 1\\ Approved: V 3 c-( (5rn.iure) ~ Date i u [ j 9 0 0 N 0,1 1 l D J y i Issue Dater XX/XX/95 E-l 97 72g g g9 J 16 ENCLOSURE 3 ene
.. s Q 0 1. INSPECTION HISTORY ( ) N/A - Initial inspection A. Violations were identified during any of the last two inspections or two years, whichever is longer ()Y(X)N B. Response letter s) or 591(s) dated January 12, 1993 Open violations (from previous inspections: none C, D. Explain any provIous violation (s) not corrected or repeated (X)N/A 2. DRGANIZATION AND SCOPE OF PROGRAM A. Organizational Structure t Plant operations and radiation safety are the responsibility of the Plant Manager /RSO Mike Rahilly. Mr. Rahilly reports to Mike Bovino in corporate on all ndf ation safety concerns.
- Mike Rahilly: RSO, Plant Manager
+ Nelson Houcks shipping t
- Mike Bovino: Corporate RSO
+ Pat Szilli: floor 'upervisor
- Kent Anderson: Corporate HP klohn Thompson: sorter
+ Shirley Landts: HP technician + Terry foulk: driver + Individuals contacted during inspection
- Individuals present at exit meeting 1.
Meetslicenserequirements[L/C? (X) Y ( ) N 2. Multiple authorized locations of use and/or laboratories ( ) Y (X) N If yes, may use ATTACHMENT A as a guide for l numbers where viola (tions are found. location (s) or lab s) inspected (X) N/A 3. Briefly describe scope of activities, including types and material, quantities of use involving byproduct frequency of use, staff size, etc. The licensee operates a standard nuclear laur, dry servicing ap)roximately a dozen nuclear power plants and Brookhaven National Lab. 40st work is seasonal (spring anti fall) which coincides with plant outages. Staffing varies between approximately 30 employees during the summer months and 100 employees during heavy outage periods. The licensee also recertifies air filter cartridges from clients. INS is currently discharging wash water into the Royersford sewerage system which is treated at a small waste treatment facility. The licensee's flow is approximately 2% of the total flow in the treatment plant. This significant quantity of effluent has resulted in reconcentration of radionuclides in the sludge. The licensee has obtained a discharge permit from the Comonwealth of Pennsylvania and is in the process of obtaining easements to install a discharge line into the Schuylkill River. The licensee estimates that the discharge line to the river will be completed by the end of 1995. B. Radiation Safety Comittee required [L/C) ( ) Y (X) N 1. RSC fulfills license requirements [L/C) ()Y()N 2. Recordsmaintained[L/C) ( )'Y ( ) N 87100, Appendix E E2 Issue Date XX/XX/95
Q 0 C. Radiation Safety Officer L 1. Authorized on license FulfillsdutiesasR50[L/C) (X))Y()N X N 2. ( Y() D. Usebyauthorizedindividuals[L/C) (X)Y()N Remarks: 3. TRAINING. AffRAINING. AM INSTRUCTIONS TO MRS s i A. Instructionstoworkers/studentsper[10CFR1g.12) (X)Y( N g. Training program required [L/C) (X) Y ( )) N a 1. If so, briefly describe training progrant f Training program required for all employees which is the same for all employees regardless of position. One aspect of the training program reviewed by the inspectors was a video which covered basic radia<; ion i concepts as well as the hazards at the licensee's facility. Information on radiation safety precedures are also shown. A quiz is [ ' given at the conclusion of the class. 1 2. Training program implemented X Y((q1N Y i 3. Periodic training program required Y XhN 4. Periodic training program implemented X 4N 5. Records maintained X YdhN i C. Individuals understanding of proceduras and Regulations is adequate (X) Y ( ) N l. Current operating procedures Y( N 2. Emergency procedures Y( N 3. Use of survey instrumentation Y( N l , Inspectors reviewed eight of the Itcensee's 51 operating and emergency procedures. l D. Revised Part 20 Workers cognizant of requirements for: I 1. Radiation Safety Program [20.11011 X Y N 2. Annualdoselimits[2G.1301,1302L X Y N 3. New forms 4 and 5 ( ) N/A Y N 4. 105 menitoring threshold [20.1502) X Y N 5. Dose limits'to embryo / fetus and declared pregnant worker l20.1208)1902) (X) N/A ((X) Y ( ) N 6. Grave Danger Pos<;ing [20. )Y()N 7. Procedures for open<ng packages [20.1906) ( ) N/A (X) Y ( ) N l 8. Sewer disposal limits [20.2003)- ( ) N/A (X) Y ( ) N 4 .,,- p Issue Date: XX/XX/95 E4 87100 Appendix E. ,i;-
0 h glIgt Deficiencies in this area while not always a violation should be brought to the attention o,f licensee management at the e,xit meeting and in the cover letter transmitting the inspection report or NOV. i Pomarks: 3 Inspectors interviewed a number of workers at the facility and found that they had sufficient knowledge of radiation safety principles and use of monitoring equipment. j Inspectors reviewed the training records of ten individuals. Inspectors discussed compliance of 20.1101 which r uires at least an annual review of the radiation safety program, particularl the need to review the number of contamination incidents related to th " flipping of gloves
- i (turning gloves right side out after launderin action "o minimize future contamination events.g) and taking some type of 4.
INTERNAL AUDITS. REVIEWS OR INSPECTIONS 3 A. Audits are required Auditsorinspections[L/C) ( ) Y (X1 N B. are conducted (X)Y(h N (1) Audits conducted by Corporate HP and Engineering Department (2) Frequency: annual C. Content and implementation of the radiation protection programreviewedannually'bythelicensee[20.1101(c))((X)Y())N Y( N D. Recordsmaintained[20.2102) X) Facility manager is required to respond to corpurate audit and take appropriate corrective action as per corporate procedures. 5. FACILITIES i A. Facilities as described in license application Describe any Self-contained dry-source-storage [L/C)(X)Y()N B. irradiators Part 36 and/or survey instrument calibrators ((model,r)adionuclide, activity,use,etc.) (X) N/A 1. Maintenance of safety-related com>onents performed by authorized persons Access to keys and/or material co[n/C)lled ()Y()N i 2. tro
- 20.1801,1802,L/C)
()Y()N 3. Access to high/very high radiation areas controlled
- 20.1601,1602,L/C)
()Y()N 4. Adequate protection of shield integrity, fire protection [L/C) ()Y()N Remarks: . n o0, 4,,endix e a 1:a.e oatei xx,xx,s. s
6 6. MATERIALS A. Isotope, chemical form, quantity and use as authorized L Licensed man le/C)ls secured to prevent unauthorized rta (X) Y ( ) N B. removal or access 20.1801, 1802 LeaktestsandInve[ntories[L/C)) (X) Y ( ) N C. 1. Perfonood as 6pquired 2. Adequate analysis methodology and ()N/A(X)Y()N sensitivity 3. Recordsmaintained[L/C) ( ) N/A (X) Y ( ) N (X) Y ( ) N Remarks: See attached letter dated August 21, 1995 for sumary of inventory. 7. B@lATIONSURVEYS 2 A. Instruments and equipment: 1. Appropriate operable survey instrumentation possessed and readily accessible [L/C) iX) Y )N N 2. Calibrated as required Ca'ibrationrecordsmain[20.1501,L/Cl tained[20.2l03(a)) (;Xj) Y h> N <X Y 3. B. Briefly describe area survey requirements [20.1501(a), L/C): Licensee performs daily surveys of the laundry areas daily and performs more facility wide surveys including wipes on a weekly basis. Licensee has a portal monitor located at the single ingress / egress point from the laundry area. With regard to removable contamination, the following action levels, the following are used at the facility: (in dps/100 ca') 119h1 bill contaminated areas 20 potentially contaminated 1000 areas 20 500 non-contaminated areas 20 200 C. Perfonned as required [20*.1501(a) L/C) (X) Y ( ) N 1. Contamination found 2. Corrective action taken and documented (X Y )N (X Y )N D. Recordsmaintained[20.2103,L/C) (X) Y ( ) N Issue Date: XX/XX/95 E4 87100, Appendix E
O E. Protection of members of the public 1. Licensee made aviecente surveys to demonstrate either (1) that the il0E to the individual likely to rece<ve the highest dose does not e1ceed 100 mren in a year, or (t) that if an individual were continuously present in an unrestricted area, the external dose would not exceed 2 mme in any hour and 50 mren in a year Unrestrictedarearadia[20.1301(a)(1),1302(b))d(X)Y()N 2. tion levels de not excee I aren in any one hour '20.1301(a) 'X Y )N Recordsmaintained[10.0103,2107)(2)) kX))Y()N 3. ( Remarks: Licensee maintains logs of each individual contamination event. - Approximately 100 events each year for the last two years. Based on the inspectors review of the licensee's records and discussion with the HP staff, most of the contaminations are just in excess of the trigger levels for portal monitor due to the "fli sweating and foot contamination, pping of gloves"; shirt contamination from inspectors reviewed the calibration of th'e portal monitor which is approximately 25% efficient for Cs-137 and detemined that at a 3 second count time, the instrument was sufficient sensitive to measure contamination with an areal concentration of 5,000 dps/100 co'. Health Physics technician prepares a weekly report which summarizes such items as the highest concentrations of effluents, removable contamination
- levels, radiation levels, instrumentation parameters and changes in isotopes. This report also includes action levels.
8. RADIDACTIVEWASTE ()N/A A. Disposal ()N/A 1. Decay-in-storage (X) N/A a. Procedures approved 20.2001(a)(2),L/C) Y N b. In accordance with /C Y N Labels removed or de[ ace)d [20.1904(b)) c. Y N 2. Special procedures perfomed as required 'L/C) (X) Y ( ) N 3. Liquid scintillation (LS) media and animal carcasses per (20.2005)isposals
- 20,2001)(X) N/A Y
N 4. Improper / unauthorized d Y X N 5. Recordsmaintained-[20.2103(a),3108,L/C) X Y N B. Effluents ()N/A 1. Release into sanitary sewer [20,2003) ( ) N/A (X) Y ( ) N a. Material is readily soluble 9r readily dispersible[20.2003(a)(1)] (X) Y ( ) N b. Monthly average release concentrations do notexceedAppendixBvalues[20,2003) (X) Y (-) N-87100, Appendix E E4 Issue Date XX/XX/gl
o o c. No more than 5 C1 of H-3,1 C1 of C-14 and 1 Ci of all ether radienuclides combined released in a year Procedurestoensurerepresen[20.2003) (X)Y()N d. tative sampling (and analy:is properly 1aplemented [20.1501a)(2),L/C) (X)Y()N 2. Releasetoseptictanks[20.2003) ()N/A()Y(X)N a. Withinunrestrictedlimits[AppB, Table 2)()Y()N 3. Waste incinerated (X)N/A()Y()N a. Licenseauthorizes(20.2004(a)(3)) ()Y()N b. Licensee directly monitors exhaust Airbornereleasesevaluatedandcontrolled()Y()N c. [20.1501,1701) ()Y()N 4. Control of effluents and ashes '20.1201,1301, 1501, 2001, L/C) (See also IP 8/102, RG 8.37) (X)Y()N a, Compliance with air emissions requirements in Part to: Licensee has demonstrated comsliance with air emission requirements in 10 CtR Part 20 (X) Y ( ) N Basis for compliance determination (circle one ormore;providebasisbelow) Thismethodused.(1) Measured concentrations of radionuclides in air effluents are below Appendix B, Table 2 concentrations (andexternal dose < 50 mres/yr) (2) Bounding calculations show that air effluents could not exceed Appendix B. Table 2 concentrations (and external dose < 50 mrem /yr) (3) Dose modeling shows that dose equivalent to the individual likely to receive the highest dose does not exceed 10 mres/yr (4) Licensee does not possess sufficient radioactive material to exceed Part 20 requirements Basis for Determination: Review of licensee's airborne effluent records b. Description of effluent monitoring program 1. Monitoring system hardware equipment adequate (X) Y ( Air samples / sampling technique (charc 2. Equipment calibrated as appropriate (X Y )N 3. HEPA, etc.) analyzed with appropriate equipment (X) Y ( ) N !ssue Date XX/XX/95 E7 87100, Appendix E
( p-O Q j Re.orks, Licensee typically discharges I to 3 tanks per 8 hour shift. Typical dische es durint busy times (I to 3 shifts working) would be 6 tanks during an eigh hour sh ft. One tank holds 5,000 gallons. l i 101 ABILITY l The inspectors reviewed the licensee's response to Infomation Notice 94-07 which provides two methodelagtes for detensining if material released into the sewer is readily soluble as required by 10 CTR 20.2003 a) 1 The i second protocol (yze their effluent using the a methodo i licensee did anal to the j filtration and radiometric analysis of suspended solids) listed in IN 94-07. The total sus > ended solids precedure used by the i licensee can be found in 5tnidard Met gods for the Examination of Water a'id i Was".ewater (1989 edition). "le l' consee also has a standard procedure (RD-033J for demonstrating compliknce with NRC solubility requirements. The results of the licensee's evaluation from samples taken in early July 1995 are attached. The results show that gross radioactivity levels were statistically the same for solids retained for any of the 5 different filter sizes (1, 5, 10, 30, and 60 microns) as well as the composite sample. Based on the results of the licensee's data, the inspectors concluded that material in the licensee's effluent released into the sewer meets the j definition of readily soluble. This conclusion was based on the observation that the radioactivity levels for each filter size and in the composite was statistically the same. This would appear to indicate that the radioactive species present were not associated with any suspended solids present and thernfore were a soluble state. 8 The licensee stated that the reasons for the increase in the total quantity 2 of material discharged into the sewer were as follows: l. Clients are using less tyvek and more laundrable clothing to i reduce the amount of radioactive waste. I 2. Clients are using more laundrable clothing in high contamination areas which would obviously pick up more contamination. 3. A general increase in the radiation levels in contaminated .aterials from their clients. .The licensee also stated that they except total quantity levels to continue to decrease after their peak in 1993 as a result of new sand beds and a sludge dryer being used as well as the change in chemical vendors in January 1994. 4 ~ 87100, Appendix E E4 Issue Date: XX/XX/g5
g 3 C. Waste Management ()N/A 1. Wastecompacted[L/C) ()Y(X)N 2. Storagearea(s) ( ) N/A a. Protectionfromelementsandfire[L/C) (X)Y()N (X)Y( N b. Containers properly labeled a[nd area) Control of waste maintained 20.1801 ) c. pro >erly posted [20.1902 1904) (X)Y()N (X)Y )N d. Pac cage integrity maintalned [L/C) ( 3. Packaging,ControlandTracking[ App.F.!!!) [20.E006(d)): Note: The licensee's waste is likely to be Class A. a. Not packaged for disposal in cardboard or fiberboard boxes 1:61.56(a):' Liquid wastes so11dified, <.e., less than (X) Y ( ) N 4 b. 1% freestanding liquid, and void spaces minimized [61.56(a), (b)i vapors [61.50) 1 (X) Y ( ) N (X) Y )N Does not generate harmfu ( c. d. Structurally stable (will maintain its physical dimensions and forn under expected disposal conditions) [61.56(b)) X)Y Packages properly labeled (App. F.!!!.A.2)(X) Y ( ) N ( ()N e.f. Licensee conducts a QC program to ensure compliance with and includes managementevalua[61.55,56)dits tion of au ,J, App. F.!!!.A.3] knowledged within 20 days (X) Y ( ) N hipments not ac g. after transfer are investi reported [ App. F.!!!.A.8) gated and (X) N/A ( ) Y ( ) N 4. Transfers to land disposal fact 11 ties (X)N/A (Barnwell facility only recently re-opened) a. Transferred to person specifically licensed to+eceivewast.t(30.41,20.2001(b): ()Y()N b. Eact shipment accompanied by a manifest prepared as specified in Section I of AppendixF[20.2006(b), App.F.I!!.A.4) ()Y()N c. Manifests certified as specified in Section11ofAppendixF[20,2006(c)) ()Y()N D. Records of surveys and material accountability are maintained [20.2103,2108] (X) Y ( ) N Remarks: Licensee plans to sent waste to Barnwell now that the facility has reopened. l l l Issue Date XX/XX/95 E8 87100, Appendix E
p. o o 9. RECEIPT Als TRANSFER! 0F RADIQACTIVE MATERIAL A. Describe how packages are received and by whost ()N/A Licensee receives packages in the shipping & receiving department. The HP toch perfors the required surveys & wipes. t B. Written packay opening rocedures established and fellowed 20.1906 e Allincomingpackages(w)ihDUTlabelsu. (X)V()N C. , unless exempted (gases and special form) 2 0. 11 ft)) (X Monitoring'20, 906(c)3) above[20[.1906(b) thintime(X))Y()N D. Incoming packa es surveyed per Y()N E. in C)and(0 , performed specified (X) 'i ( ) N Transfer (sjbetween1<conseesperformedper[30.41 F. Allsourcessurveyedbeforeshipmentandtransfer) (4 Y ( ) N G. (20.1501(a),49CFR173.475(1),L/C) (X)Y()N H. kocords of surveys and receipt / transfer maintained "ran.2103(a)lthinl'consee'sauthorizedusers '.v.) Y ( ) N 20 30.51D 1. sfers w or locations performed as required [L/C) ()N/A(X)Y()N 4 J. Arrangements made for packages contatning quantities 1 of radioactive material in excess of Type A quantity [20.1906Ca)ibutionactivitiesevaluated ()Y()N N/A K. Package receipt /dts r for compliance with 20.1301[20.1302) ( ) N/A ( ) Y ( ) N Remarks: 10. IRANSPORTATION fl0 CFR 71.5fa) and 49 CFR 170-189) ( ) N/A A. Licenses shipments ares i delivered to cosmon carriers Xhtransportedinlicensee'sownprivatevehicle both )j no shipments since last inspection i B. HAZMAT training [172.700-704) (X) Y ( ) N i C. Packages ( ) N/A 1. Authorizedpackagesused[173.415,416(b)) (X) Y ( ) N 2. Performance Test records on file (X) N/A Special Forn Sources (173.476 Y N DOT-7A packages [173.415(a)) (a)) none a. b. Y N N/A 3. COCsonfilewithNRCforTypeB[71.12(c)(1 Two labels (White-1, Yellow-II, Yellow-I!!) w);'th( ) Y ( ) N 4. TI, Nuclide Activity, and Hazard Class [172.403,173.441) (X) Y ( ) N 5. _ Properly marked (Shipping Name, UN Number, Package Type, RQ, "This End Up" (liquids) Name and Addressofconsignee)[172.301,306,310,312.324['(X)Y())N Y( N 6. Closed and sealed during transport [173.475(f) (X) 87100, Appendix E-E10 Issue Date: XX/XX/95 l l _ _, _..,. _ _.,.. ~ _., _., _ _.. _ _, _ -,.. _ _ _,,
f O O D. Shipping Papers ()N/A 1. Prepared and used (172.200(a)) Class UN Number, (X) Y ( ) N Proper (Shipping name Hazard 2. Quantity, Package Type, Nuclide RQ Radioactive Material, Physical and chemical, fore,, Activity, Category of label TI, $ hipper's Name, Certification and Signature, Emergency Response Phone Number, ' Limited Quantity' (if applicable), ' Cargo Aircraftonly'(leduringtransport[177.718ce))(X)Y(()N if applicable)) [172.200-204? (X)Y )N Readily accessib 3. E. Vehicles ()N/A 1. Placarded [172.504) (X)Y()N (X) Y ( N 2. Cargo blocked and braced [177.842(d)) ) 3. Proper overpacks (shipping name, UN Number, labeled, statement indicating that inner ru.kage complies with specif cation packaging) [173.25) N/A ()Y()N F. Any incidents reported to DOT [171.15, 16) ( ) Y (X) N Remarks: Licensee's shipping papers all have 'RQ' listed although not required. i According to the licensee, this was caused by a computer error and will be corrected. Inspectors reviewed the a portion of the shipping pa years for five facilities (Hope Creek, Brookhaven,pers front that last two sales," Limerick, and OysterCreek). Licensee maintains their own fleet of vehicles including tractor trailers. Since nearly all shipments are exclusive use, inspectors reviewed training for drivers to ensure compliance with applicable portions of 49 CFR Parts 390-397. lhe inspectors reviewed the training and qualifications of drivers, maintenance of vehicles, and emergency equipment in the vehicles. The inspectors noted that the licensee's vehicles are equipped with portable phones and appropriate radiation equipment in case of an accident. One driver was interviewed and he demonstrated an understanding of the steps to take in case of an accident in which contaminated cloths were separated from their package.
- 11. -
PERSONNEL RADIATION PROTECTION A. Licensee perfors.ed exposure evaluation [20.1501) (X) Y ( ) N B. Licensee incorporated ALARA considerations in the Radiation Protection Prograra [20.1101(b)) (X) Y ( ) N C. External Dosimetry ( ) N/A 1. Licensee monitors workers [20.1502(a), L/C) (X) Y ( ) N 2. External exposures account for contributions from airborne activity (20.1203) (X) N/A ( ) Y ( ) H 3. Supplier Landuarer Frequency: Quarterly Issue Date: XX/iX/P5 Ell 87100,AppeNixE
e 4. Supplier is NVLAP-approved [20.1501 X)Y Dosimeters exchanged at required fre(c))quency[L/C)(X)Y(1N ( (hN 5. D. Internal Dosimetry ()N/A 1. Licevee monitors workers Briefly describe licensee's[20.1502(b), L/C) (X)Y()N 2. program for j monitoring and controlling internal exposures [20.1701,1702,L/C): Licensee does entry, exit and annual chest counts. They also perform monthly urine analysis. 3. Air sampling perfomed X Y N t 4. Nonitoring/ controlling program implemented X Y N 5.. Respiratoryprotectionequ<pment[20.1703,L/C) Y X NR E. Reports ()N/A 1. Reviewed by R50's assistant Frequency: Quarterly 2. Inspector reviewed personnel monitoring records i for period January 1, 1994 to Narch 31, 1995 3. Prior dose detemined for individuals likely to receive doses 20.2104) Maximumex>osur[esTEDE440mR (X) Y ( ) NA i 4. Other 5. Maximum CDEs N/A Organs N/A 6. Maximum CEDE N/A 7. Licenses suas internal and external [20.1202) ( ) Y (X) NA 8. TEDEsandTODEswithinlimits[20.1201] (X)Y()N 9. NRCFormsorequivalent[20.2104(d),2106(c)) a. NRC-4 ()Y())N Complete: ()Y()N b. NRC-5 ()Y( N Complete ()Y()N f 10. Worker declared her pregnancy in writing during inspection period (review records) (X) N/A Y N If yes, licensee in compliance with Y N andrecordsmaintained[20.2106(e))[20.1208) l Y N F. Who perfomed PSEs at this facility (number of people 4 involved and doses received) [20.1206, 2104, 2105, 2204) (X)N/A 2 G. Records of exposures, surveys, monitoring, and evaluations maintained _[20.2102, 2103. 2106, L/C) (X) Y ( ) N Remarks: 1 Inspectors noted that some individuals may be exposed to airborne material during some maintenance activities (i.e. cleaning out dryer ducts). The licensee stated that they had perfomed fixed and grab air samples and determined that the DACs were less 10% of the most restrictive radionuclide ($r-90). The licensee documented this letter in the attached August 3,1995 letter. 1 47100, Appendix E' E42 1ssue Date: XX/XX/95 s ,e ,w.- ---,,,-,,,-e,------a -+ ...-.---.--n,,------
O O The licensee performs quarterly chest counts in-house using a 2 inch by 2 inch sodium todine detector coupled to a Ludlum scalor. Calibration is performed using a chest phantom with a Co 60 source. Co-60 is used since it is the most restrictive radionucIlde typically used. Typical efficiency is t; proximately 13 percent. The basis of the 11consee's procedure is based on ICRP-30 limits Information Bulle(inhalation as the most probable pathway) and AN!/MAELU tin 80-1A, Revision 3. The 11consee uses an action level of 2E6 dpa and corrects for chest thicknes's '(determines if additional CT). Comparison of the individual chest count to the scalor readout evaluation is required. The operational tetion level is calculated for each individual as follows: Action Level (cpe)in cpe) + (2E6 dpe)(efficiency)(CT correction fact (Background 12. NRC INDEPENDENT MEASUREMENTS A. Sur"ey 'nstrument Ser'al NL .ast calibrat4on Lud' un L9 033bL5 ibruary 6, L995 B. inspector's measurements were compared to licensee's (X)Y()N C. Describe the type, location, and results of measurements: 1. Ambient gama radiation measurements (all readings in mR/hr)
- a. Tank room top floor area: 0.5 bottom of tank: 1
- b. Sorting room tab e area: 0.6 ramp (to table) area: 0.3 Area TLD Sortin 0.3
- c. Rewash area:(0.5 g):
1.0
- d. Small washers: 4
- e. Waste processing Lamella unit: 4 general aren: 1-2
- f. Large Washer and Driers: 0.3 - 0.4
- g. Shipping area: 0.1 - 0.2
- h. folding room general area: 0.1 - 0.2 Area TLD 1.Respiratorro(om: Folding room #2): 0.14 0.05 J. Change room: 0.05 k Radwaste cage: 1-2
- 1. Pit area: 3 - 4 Highest reading accessible to workers was in a trench under washer fl.
Reading of 10 mR/hr on top of bolted down grate (measurement made with licensee's Model 3 with GM probe). Issue Dater XX/XX/95 E43 - 87100, Appendix E
O a 2. Removable contamination in unrestricted areas within the facility I Location itgn Aloha Gross Beta Conference Room fixtures 0.5
- 0.5 3*2 Time clock 1.0
- 0.7 2*2 MSDS book 0*0 0*O HP Office door handle 1.4
- 1.0 4*2 Lunchroom door 1.9
- 1.0 4*2 Soda machine 1.9
- 1.0 7
- 3' Floor near rear area entrance and exit 1.0
- 0.7 0*2 Pay phone 1.4
- 1.0 4*2 Ladies room door 0.5
- 0.5 3*2 Mens room door 1.4 z 1.0 4*2 Water fountain 1.4 1.0 3*2 Forklift seat 1.9
- 1.0 0*2 Exit door bar 0.5
- 0.5 8*3 Office entrance handle 1.9
- 1.0 3
2 Water cooler 0.5
- 0.5 0
2 File cabinet in HP lab 0*0 1*2 Conference room door handle 1.0
- 0.7 1*2 Storage room door handle 1.9 i 1.0 1*2 Table in HP Area 0.5
- 0.5 7*3 Coffee pot 2.9
- 1.0 3
2 Results are reported in units of dpe/lf,0 co' at an uncertainty of one sigma. Samples were counted for lo minutes on a Tennelec Model LB 5100 low background proportional counter. Counting efficien:y for alpha activity was 20.9% and 26.5% for beta activity. 3. Wastewater sample taken from holding tank A. Gross alpha: -0.1 t 1.4 E-8 pCi/ml Gress beta: 4.41
- 0.07 E-6 pC1/ml Results are reported at an uncertainty of one sigsa.
A five milliliter sam >1e was dried and counted for 400 minutes on a Tennelec Model LB 5100 low bac(ground proportional counter. B. Gama spectroscopy JLtdionuclide Concentration (oCi/ml) Cr-51 0.9
- 0.3 Mn-54 0.96
- 0.06 Co-58 0.46
- 0.04 Co-60 2.83
- 0.08 Zn-65 1,77
- 0.12 Cs-134 0.49
- 0.05 Cs-137 1,79
- 0.06 Results are reported at an uncertainty of one sigma.
The 500 milliliter sample was counted for 10,000 second on an intrinsic germanium detector coupled to computerized multi-channel analyzer. 87100, Appendix E E14 Issue Date: XX/XI/95 i
O O 13. NOTIFICATION AND REPORTS (X)N/A A. Licensee in compliance with (19.13, 30.50) (reports to individuals.public and occupational, monitored to show compliance with Part 20) ()N/A()Y()N B. Licensee in coe L(theft or loss)pitance with [20.2201, 30.50) ( ) None()Y()N C. icenseeincompliancewith[20.2202,30.50) (incidents) Licensee in compliance with [20.2203, 30.50) ( )~ None ( ) Y ( ) N 0. (overexposures and high radiation levels N LicenseeawareofNRCOpsCenterphor.snu)mber()None()Y()N E. ()Y() 14. POSTING AND LABELING A. NRC-3 ' Notice to Workers' is posted (19.11)Section206ofEnergyReorgan 8. Parts 19, 20, 21, Act, procedures adopted pursuant to Part 21, and license documents are posted or a notice indicating where documents can be examined is posted :19.11, 21.6) (X)Y()N C. Otherpostingandlabelingper[20.1902,1903,1905) 1904) andthelicenseeisnotexemptedby[20. (X)Y()N Remarks: 15. RECORDKEEPING FOR DECOP991SSIONING ()N/A I A. Records of information important to the safe and effective decommissioning of the facility maintained in an independent and identifiable location until ficense terstnation Y()N Records include all [30.35(g))4nformation outlined in (30.35(g))(()) Y ( ) N 9. Remarks not investigated 16. BULLETINS AND INFORMATION NOTICES () A. Bulletins, Infonnation Notices, NNSS Newsletters, etc., received by the Licensee (X) Y ()N 8. Licensee toon appro)riate action in response to Bulletins, Generic.etters, etc. (X) Y ()N Remarks: See discussion in Section 88. on Information Notice 94-07. 17. SPECIAL LICENSC CONDITIONS OR ISSUES ( ) N/A I A. Special license conditions or issues to be reviewed: 1. LC 16 requires that the licensee maintain discharges to 10% of the limits of 10 CFR 20.106 averaged over a year into unrestricted areas. 2. LC 17 requires the submission (if a quarterly report on the discharges from the facility into the sewer system. 4 Issue Cate: XX/XX/95 E45 87100, Appendix E
O 3. LC 13 requires the licensee not to package or possess radioactive waste except for that waste generatH as a result of the laundering activities performed at their facility. 4. LC 14 requires the licensee to only launder contaminated items at their pomanent factitty and not at their client's. l 5. Evaluation: 1. The licensee is currently discharging liquid effluent into the sanitary sewer and not into unrestricted areas. Licensee is in the design phase of constructing a discharge line from their facility to the river. The licensee agreed to amend their license to incorporate this new discharge system into their Itcense. 2. Licensee is submitting the required reports. 3. Licensee is only packaging their own radioactive waste. 4. Licensee is only laundering contaminated items at their Royersford facility. 18. CONTINUATIONOFREPORTIT(M (X) N/A Ig. VIOLATIONS. NCVs. AND OTHER ISSUES (X) N/A Note: Briefly state (1) the requirement and (2)iolations, indicate why the how and when the licensee violated the requirement. For non-cited v violation was not cited. No violations were identified. 20. DE8RIEF WITH LICENSING STAFF l Inspection findings discussed with licensing staff ( ) N/A (X) Y ( ) N Items discussed: 1. Items identified in deficiency letter dated May 30, 1995 were discussed with licensee. 2. Discharge in unrestricted areas. 21. EPA REFERRAL FORN EPA referral form for air effluents sent to appropriate EPA regional office per IP 87102 ( ) Y (X) N Not necessary. Licensee discharges below 10% of the effluent limits, l 87100, Appendix E E16 Issue Date: XX/XX/95
l A f4 ,e 22. ffRFORMANCEEVALUATIONFACTORS Licensee (name & location) Inspectors: White and Shaffer Interstate Nuclear Services Inspection Date: July 13 and 14, 1995 401 North Third Avenue Royersford, Pennsylvania 19468 i A. Lack of senior management involvement with the radiation safety program and/or Radiation Safety Officer (R$0) oversight Y N B. R$0 too busy with other assignments Y N C. Insufficient staffing Y N D. Radiation Safety Committee fails to meet or functions inadequately (X) N/A ( ) Y ( ))N E. Inadequate consulting servic6s or inadequate audits ( ) N/A ( ) Y (X N Remarks (consider above assessmnt and/or other pertinent PEFs): Regional follow-up on above PEFs citations: END Issue Date: XX/XX/95 E47 87100, Appendix E
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n '3 1 Order O 93-07-051 controls est Environmental Page 2 07/12/93'11:29 l n 7{ Que reports are eendered upon the cenditten that they are not to se reproduced sho119 et in part for advertising and/or f; other purposes over our signature er in car.nection eith our name without special permission in writing. 2a certt+t.s av 4 l Rerusinder of maple (s) for roadme analysis will be disposed of shree weeks from finsi seport date. Sampie(s) far bact ria ansfysis only, wit be disposed of immediately aber j j analysis. This is not applicable if other strangements have been m,uje. o 1 s-5 i ( 7.y. ~ I ll l t [. L y. 'Y f. j
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. g. d Order e M -OSI Controls for Environmental Page 4 C7/12/93 12:27 TTBT pe TR BY SAEFLE Bemple
Description:
079-95-14.13 16 5 Micron Lab No: 034 Test
Description:
Gross Alphs/ Beta (dis) Method: Test Code: AR_ DIS Collected: 07/06/95 Category: MATER 7; b* .~ , a o' Type aF Antivsts Detection RESULT 5 L1mst Cross Alpha (dissolved) e I ? Gross Beta (dissolved) 7 W1 +/--31 All results reported in: tMITS - aCi/ lite _e Analyzed C7/10/93 s, _,gg l Semple DescriptIan: 079-95-14 13,Idr 10 Micron Let No: 04A Test
Description:
Gross Alpha / Beta (dis) Method: Test Code: A8__ DIS Collected: 07/06/93 Category: WATER b .s { J Type of Analgete Detection MESULT j 1, Lisai t j w Oross Alpha (disselved) 3 <3 e Gross Beta (dissolved) 7 3295 + /-3') V All results reported in; Um178 aC1/14ter Analgrad _ 07/10/95 8e CR h 7 .f 1 i t
f - o Order # 93-07-051 Centrols N? Environmentet Page 3 _ TEST EEEULT9 BY SA& M 07/12/93 11:29- - Sample
Description:
079-95-14,15,16 30 Micron Lab Ne: OSA Test Deecription: Gross Alpha / Beta (dis) Method: Test Code: AB_ DIS g ~ Co13ected: 07/06/95 Category: WATEN ,g s* fin Type of Analysis Detection RESULT o Limit 7 Cross Alphs (dissolved) 5 - ;11 Gross Beta (dissolved) JE _3499+/-36 Att results reported in: ~ UNITS eC1/11ter Analyzed 07/10/95 8v _ER 3 ample
Description:
079-95-14,15,16 60 Micron Let Mo: 06A Test
Description:
Gross Alpha / Bete { dis) Method: Test Code: A8_ DIS Collected: 07/06/93 Categorg: 4ATER $a TL Tgpe of Analysis Detection RESULT Limit ,,4mf bt Cross Alpha (dissolved) Oross Beta (dissolved) 7_ 3538+/~36 m All results reported in: y,' S UNITS act/ lite _v R Analyzed 07/10/95 t as _gg e s e ~ f i
b a' Ordor O 95-07-051 Centrolo Ccr Eavirtnmental . PC(O O .01/12/M 11:29 __ TEST RESULTE BY M Sample.Descrip tion: 079-95-14,15,16 Lab Ne: 07A Test
Description:
Gross Alpha /Seta -Method: Test Code: A9 Collected: 07/06/95 Categorg: WATER n w h n Type'of Aneigsts Detection RESULT .O Linit
- h Otoss Alpha 5
<3 Oross Beta J Sb73+/-37 All results Toport in: UNITS _ _aci/1 iter Analgted. 07/10/93 By,GR Sample
Description:
079-95-14 15 16 1.0 Micron Lab No: OBA Test
Description:
Gross Alphe/ Bets tdis) Methed: Test Code: AB_D1B Collected: 07/06/93 09:00 Category: WATER E Type of Analysis Detection REBOLT Limit ..4 $[ Gross Alpha (dissnived) _6 <6 Gross Beta (dissolved) 7 354S+/-36 'g; All results reported in: h UNITS e C1__/l i t e r_ Analgred 07/10/95 f". Bq _GD L i d i
.g i: Drder # 95-07-051 Controls for Environmental Pcte 7 - 07/12/95 11:29 TERT RESULTS BY GANPLE Sample
Description:
079-95-14,15,16 3 Micron Lab No: 09A Test
Description:
Oress Alpha /Seta (disa Method: Test Code: AB_DTS ' Collected: 07/06/95 09:00 Category: MATER n v,. I;". Type of Analysis Dstection RESULT Limit .S i o Cross Alpha (dissolved) ____2 <S Oross Beta (dissolved) 7 .3536+/-36 I All resvits reported in: UNITA oCittiter_ Analgrad 07/10/95 sv _Gn Semple D9seviption: 079-95-14,15,16 20 Micron Lab No: 10A Test
Description:
Gross Alphe/Rets (dis) Method: Test Code: AB_ DIS Collected: 07/06/93 09:00 Category: WATER T J E Type of Analysis Detection RESULT Limit ..6 $[ Cross Alpha (dicsolved) B <B Gross Data (dissolvedt 9 3137+/-49 All results reported in: eC1/ liter _ UNITS _ 07/10/93 Analgted h Bg _GQ 7 2 i o O
y 6:
- a Ord r N 63-07-051 Casatrels f or Envitensontal.
Page O 07/12/95 11:29 Trgr REstLTE EY__tigte,LE 3 ample
Description:
079-95-a4,15,16 30 Micron Lab No: 11A Test
Description:
Cross Alphs/ Beta (dis) Method: Test Code: AE_p!S n Collected: 07/06/93 09:00 Categorg:' WATER
- 8. '
v. (T n . Type of Analysis Detection RESULT O Llett 'b s Otoss AIpha (dissolved) B <R Gross Bete (dissolved) (L __3569+/-02 All results reported in: 1 UNITS eC1/11tse Analyzed 07/10/95 8v GR ' Sample
Description:
079-95-14,15,16 60 Micron Lab No: 12A Test
Description:
Gross Alphs/ Bete (dis) Mstbod: Test Code: AB_ DIS Collected: 07/06/95 09: 00 Cateterg: WATER i E Type op Analysis Detection RESULT b Limit -4 $[ Orcss Alpha (dissolved: .._ 10 <20 Orcss Beta (dissolved) _._ 1 1 3469+/ 4 All results reported in: UNITE . sci / liter Anelgred 07/10/93 h By .fR 7
- 2 b<
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3 ~ a Orser C 95-07-051 Contralo P t Envitenmental Pags 9 07/12/93 11:29 TERT REEtJLTE EY_SgjptE Sample Descrip tion:. 079-95-14,15 16 Lab No: 13A Tes t Descrip tion: Oross Alpha / Rete Method: g Co11ected: 07/06/95 09: 00 Categorg: WATER, Test Code: AB bo I"n Type of Analysis Detection RESULT g Limit .D Gross Alpha 7 <7 Gross Bete ___LL 3596+/-52 All results report in: UNITE mci / liter Analyzed 07/10/95 av GR Sample Descrip tion: 079-95-14,13,14 1.0 Micron Lab No: 14A Te s t. Desc r ip t i on: Cross Alpha / Beta (dis) Method: Test Code: AB_ DIS Collected: 07/06/95 09:00 Categorg: WATER Ta g Type of Analveis Detection RESULT Limit ,,i g{ Gross Alpha (dissolved) B <B Gross Beta (dissolved) 11 3560+/-52 g All results reported in: l3 UNITS - act/_ liter Analyzed 07/10/95 fi, Bg _GR
- P h
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7 _g Order O 95-07-051. C'intecle'far Envivoneer.tc1 Pego 20 07/12/95 11:29 TEfET M* mutts BY _SAe1P_L,E Sample Descript1en: 079-95-14 15,le 3 Nicron Lab No: 15A Test
Description:
Cross Alpha /3ete (dis) Methos: Test Code: A3_018 Collected: 07/04/95 09:00 Category: WATER n 8v. f; s' Type of Analysis Detection REir*JLT o Limit 'a Cross Alpha (dissolved! 9 <9 Gross Beta (dissolved) _ _ 11 3531+/-51 All results reported in: tmITS act/ liter Analgrad 07/10/95 s, _.gn Sample
Description:
079-95-14 13,16 to Micron Lab No: 1&A Test Destef ption: Otoss Alpha / Beta (dis) Method: Test Code: AB_ DIS Collectet: 07/06/95 09:00 Categeev: WATER Y s g Type of Analusis Detection REBULT Limit G, g{ Oeces Alpha (dissolved) B <B Gross Beta (dissolved) 11 3533+/-31_ All results reported in: tRITS sCf/11ter Analgaes 07/1D/95 V, Rg ,9& 2 h ,s I m
o n 1 Dedce O 9S-07-051 . COctrolo for EAvironmental PCgo il 7 07/12/95 11:29_ TEST RES' ATE RY W Sample Descrip tiets: 079-95-14,15 16 30 Micron Lab No: 17A Test
Description:
Cross Alpha / Beta (dis) Method: Test Code: AB_p15 8 Co1!ected: 07/07/95 09:00 Categorg: WATER ,3 v g_ N -Type of Ana!gsts Detectf'n MESULT o, Limit 'O Cross Alpha (dissolved! B <8 Dross Beta Idissolved) LL 3463+/-31_ All results reported in: UNITS sC1/_3t h Analgrad 07/10/95 ag _gn Eample
Description:
079-95-14 15 16 60 Micron Lab No: IBA Test
Description:
Cross Alpha / Beta (dis) Method: Test Code: AB_ DIS Collected: 07/07/95 0Y: 00 Category: MATER T J y Type oP Analysis Detection RESULT Limit 1 3 Gross Alpha (dissolved) 9 (9 Gross Sete (dissolved! 11 3622+/-52 g All results reported in: d 3 UNITS p C_i /11_t e r Analysed 07/10/95 fp By _gg 7 2 Sa O h
\\ CLEAR RE U T Y COMMISSION I e REGloN 11 AT NTA, dtA 1 !O / rj,c p IBM C0C0 MEMORANDUM FOR: Douglas M. Collins, Chief Nuclear Materials Safety and Safeguards Branch THROUGH: John P. Potter, Chief Nuclear Materials Licensing Section FROM: David J. Collins Health Physicist SUBJEC1: INTERSTATE NUCLEAR SERVICES LICENSE (
REFERENCE:
CONTROL NO. 254978, DOCKET NO. 030-32981) I am ready to issue License No. 20-25222-01 for the INS Portsmouth VA facility. The license as written supersedes License No. 39-19727-01. The license also incorporates the provisions of 10 CFR 20.2003 as regards solubility of materials discharged to a sanitary sewer. As related to me by Bruce Mallett on December 21, 1993, the Division Directors' conference call agreed to, for this license, to maintain solubility at 20 microns particle size. The licensee has no objection to this requirement. I am prepared to issue the termination for License No. 39-19727-01 concurrent with this issuance. The Massachusetts (State Code 20) license is to be retained here for control and inspection. Region V has completed their initial review (letter to INS dated November 23,1993) of the decommissioning issues with the licensee and has released the license for issue. I have not included the NEW LICENSE condition requiring notification prior to beginning operations, or abandonment, since this facility is operational. G h id J. Coll bec: h Docket File e gqWCMMhe /, I l ENCLOSURE 4 i i
). 1 l- / OOlR Docket No. 030-19161 License No. 39 19727-01 INS Corporation g ATTN: Mr. William Moser Southern Regional Manager P. O. Box 50164 2903 Millwood Avenue Columbia, SC 29250-0164 Gentlemen:
SUBJECT:
CONFIRMATION OF ACTION LETTER 030-19161/91-01 RESPONSES This refers to the Confirmation of Action Letter (CAL) dated September 20, 1991, and your response letters dated October 16, 1991, December 20, 1991, and t April 21, 1992. In your letters you described actions taken to date to reduce the accumulation of radioactive material in the City of Portsmouth waste water treatment system as a result of operations at your Portsmouth facility. To sumarize, (1) you have modified your filtration system and will filter all waste water prior to discharge into the sanitary sewage system with no larger 1 than 20 micron filters (reference your April 21, 1992 letter, (2) you have modified your procedures and sampling system to obtain repres)entative samples of liquid effluents released as described in your October 16, 1991 letter, (3) you will restrict liquid affluents released to the sanitary sewage system to 1/100 of the 10 CFR Part 20 limits as described in your October 16, 1991, letter, and (4) your staff will accompany City of Portsmouth maintenance personnel during strainer maintenance activities at the pump station downstream of your Portsmouth facility. Based on the information provided and the results of our inspection conducted on May 28, 1992, we have determined that your actions satisfy the basis of the CAL. The CAL did, however, discuss two isse?* that remain outstanding: (1) . your evaluation of compliance with solubiltu requirements described in the revised 10 CFR Part 20 (effective January 1, 1994) and (2) your developing a plan to decontaminate portions of the sewerage lines. With regard to the solubility issue, we understand that your request to the NRC for a definition ef solubility for materials released to sanitary sewers is under review by our Office of Nuclear Materials Safety and Safeguards. With regard to decontamination of.the sewerage lines, you indicated you did not see a basis for decontamination of the system at this time based on the 4 results of measurements taken. We agree at this time, however we will i continue to monitor the le~vels of licensed material in the sewe, rage system and, if_ conditions change, we will discuss this issue further with you in the future. g ENCLOSURE 5
i U x ( ) INS Corporation 01Jg 2 If you have any questions, please give me a call. O Sincerely, O J. Philip Stohr, Director Division of Radiation Safety and Safeguards cc: Jim Spacek, Director Public Util., City of Portsmouth, VA
- 80) Crawford Street P.O. Box 490 Portsmouth, VA 23705 Commonwealth of Virginia State of South Carolina bec: Document Control Desk R. Cooper, RI R. Cunnin J. Clenn,gham, NMSS NHSS S. Ebneter, RII L. Reyes, RII 4
h I I
~.) ^1TER57AliilUCLEAR i:RVIW a.:lVIS C% 01 DiittsI(CarotallCN April 21, 1992 Mr. Douglas M. Collins, Chief Nuclear-Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards USNRC, Region II 101 Marietta Street, N.W. Atlanta, Georgia 30323
SUBJECT:
RESPONSE TO NRC INSPECTION REPORT NO. 39-19727-01/91-01 Docket No. 030-19161 License No. 39-19727-01
Dear Sir,
This letter is in response to an NRC Inspection Report dated April 1,1992 (henceforth, " audit") conducted at our Portsmouth, Virginia facility. Although a formal response was not required due to the low severity of the findings, there are several issues that surround the audit and preceding events that need to be addressed. 1) Under the section entitled, " Effluent Monitoring" (page 12,
- 7),
the audit correctly recognized cur method of ensuring compliance with 10 CFR 20.303 by employing the most limiting nuclide concept. In this method, we conservatively assume that the entire contents of a wastewater hold up tank contain 100% of the nuclide with the most limiting MPC. However, the audit infers that there is a conflict in what permissible discharge concentrations are allowed in our license compared to that in Appendix B of 10 CFR 20.- Specifically, the audit reports that we should be employing a discharge concentration of 4 x 10" uCi/ml instead of 6 x 10*8 uCi/ml as is presently used. The audit states, "This differs from the requirement specified in Footnote 2 of Appendix B of 10 CFR, Part 20, that reenses of radioactive material to the sanitary sewer system 4 be limited to 4 x 10 uCi/ml when the concentrations and identities of radioactive materials released are not known" (page 13, first paragraph). We contend that the number selected by INS; 6 x 10*8 uCi/ml is correct and is in compliance with Footnote 3 of Appendix B. Footnote 3 is reiterated in our radioactive material license. While we do not possess the ability to do spectral analysis at the Portsmouth facility, we maintain that we do know the identity of the isotopes in our wastewater based on the following practices: t t i. ,,nn ENCt.0SURE 6 C t3 uM Q()J u J bl(
- 93 Parner i:reet
?.0.8c151957 Scrinarield. hfassacnusetts 0ll51. (41315136911 Mx:(J13)343 6989
l. l, ' Mr. Douglas M. Collins April 21, 1992 page 2 a) In accordance with the Portsmouth radioactive materials license, INS uses DOT cartified shipping papers received from our customers to ascertain the identity of nuclides 'in our wastewater. This method is described in the Portsmouth license and has been accepted at all INS facilities (four NRC licenses, nine agreement state licenses). While not a quantitative method, it provides a qualitative identification of the nuclide composition in our water. 49 CFR 172. 203, b.l. requires, "The description for a shipment of radioactive material must include the following additional entries as appropriate: (i) The name of each radionuclide in the radioactive material that is listed in $173.4385". We maintain that use of dot shipping papers is in accordance with federal regulations and has high reliability. It is certainly a defensible method to be used to establish a most limiting nuclide MPC. b) We collect a wastewater composite comprised of an aliquot of each discharge. The composite is then analyzed at an off site laboratory using alpha and gamma spectroscopy. The spectroscopy results are then compared to the isotopes chosen as the most limiting for discharge. In over ten years of such comparison, the nuclide chosen as most limiting was consistent with that identified by spectroscopy. Although a retrospective method, the spectral analysis serves to confirm our assertion that we do in fact know the nuclides in our vastewater. e Thus, we contend that the Portsmouth facility is and has been in compliance with Footnote 3 as is required in the present license, not Footnote 2 as was identified in the audit. 2) We are concerned by the requirement of having to clean out the Portsmouth sewer system. This expectation was recently reinforced by a letter to the NRC from the Director of the City of Portsmouth Department of Public Utilities (dated April 10, 1992).- The Confirmation of Action Letter (CAL) issued by your office (dated September 20, 1991),
- stated, "Upon completion of the podifications or other corrective measures, we understand that you will develop and submit to the NRC's Region II
- office, for our information, a plan for the decontamination of the municipal sewerage system lines leading to and including the well of the first pump station downstream from your Portsmouth facility".
While not fundamentally ' opposed to a clean out of the system, we ask: that the following be considered:
a- .s +~.a,v...~... ..--.~~.-.m.ne-~ - i l_* Mr. Douglas M.-Collins - April 21, 1992 1 -Page 3 o -a) INS had responded to the sewer clean out request when we - J; were initially faced with incomplete data. These data included erroneously high dose rate re.adings taken by.the 3 City. Subsequent to that data, in INS' response to the CAL (dated october 16,1991), we asked for a copy of the. NRC's report on the data collected in the sewer system as vas-promised by your inspectors. We were never afforded a copy of that-report and had never seen the analyses until we received a copy of the audit response on April 1,- 1992. . It is difficult for INS to respond to i accusations-in the absence of real data. If we had been provided the correct information, our response would have been more restrained. b)- We believe that the City of Portsmouth is exaggerating their workload in regards to the pump station well (reference-the City of Portsmouth letter). In discussions with' city sewer personne1, it was indicated that the well is cleaned out an average of'once per year, not once per week as is stated in the letter. To date, INS has been asked-only once by the sewer department to i assist in the survey of rags and materials for any part of the sewer. No loose contamination or elevated dose rates were found on any of.the materials used in the sewer well maintenance. c) It is assumed-if we were required to clean out the sewer, it would be to satisfy a limit or regulation that we have been found to be in violation. Based on review of the audit and regulations, we are hard pressed to find such
- a. violation. _Further, if we were to prepare a plan for decontaminating the-sewer as was asked in the CAL, guidelines would have.to be followed.
We do not believe that the document-cited by the eudit, "NMSS Guidelines for Decontamination of Facilities and Equipment Prior to i Release:for Unrestricted Use or Termination of Licenses for -Byproduct, ' Source - or Special Nuclear Material" applies. to y a sewer. -Sewerage systems are - generally considered restricted areas and are not, " free released" l to the general public as is intended by the guideline. - Even 'if INS were to decontaminate the sewer to NMSS 4 guideline limits, we-would already-have had satisfied the limits (reference page 9 of your audit). To supplement, or-in lieu.of specific guidance, an. analysis. .would have to be performed for this scenario. Considering that the manhole is rarely entered and that dose rates in the manhole were found to read a maximum of less than 0.2 I mR/hr, it is difficult Lto technically understand a request to clean out the sewer system. Further, there is a real risk to the health and safety of a worker entering I' T f ' r .,..~r ,,, _,~ ,-.,._m ,.m...
i m
- c. -
Mr.-Douglas-M. Collins-April:21, 1992 PageL4 e a confined space.such as: a ' sewer that handles human wasta.- Weighed against the perceived risk from barely l detectable radiation _ compared to the. actual risk to a
- worker, it is difficult to comprehend the action in question.
f In short, we feel that all parties initially over-responded to the sewer " problem" and that the city of Portsmouth should be helped to better understand the true magnitude of the issue. t 3)- As part of_the confirmation of Action Letter, we were asked to, " evaluate the feasibility of using filters of smaller [ porosity to treat all discharges -prior to discharge". considering-that a response was due within 30 days, INS i~ installed five micron filters without having an opportunity to truly study the alleged problem. Since that time, we have conducted a detailed investigation into the characteristics of the solids content of our wastewater. Enclosed are the results of a filtration study performed by an independent laboratory on the Portsmouth facility's wastewater. In the study, raw wastewater was passed through i successively smaller sized filters.
- Filtrate, (water that passed through the-filters) and the filters (suspended solids retained) were then analyzed using gamma spectroscopy. The data shows a clear and precipitous drop of radioactive solids at the 20 - 25 micron pore size range (please note that datum that has an apparent positive result may. be considered e
questionable because the analytical result is less than three times the standard deviation). Similar results were obtained at-two other INS facilities. Five micron filters have seriously impacted our business productivity due to. lessened flow rates as the filters become quickly fouled with non-radioactive. materials.
- Moreover, because the filters require frequent replacement, the amount a-of radioactive waste generated has increased along with worker-j
-dose.from-handling the filters. In addition, there-_has been i no_significant reduction-in effluent concentrations,since the incorporation of the five micron filters. We believe that the commission's-concerns regarding solids _ retention can be addressed while still allowing INS; to maximize the efficiency i: of our operations and, maintain worker dose as low as? is r reasonably achievable. Therefore, in consideration of the findings, we request to ~'i; amend the CAL response to allow a trial use of filters not to . exceed 20 micron porc size at the Portsmouth facility. J-1; .v, 7 +,,,m ~,-,m, m.
je Mr. Douglas M. Collins April 21, 1992 Page 5 Thank for your review of the issues described above. INS takes great care to ensure that our facilities meet or exceed regulatory requirements. We take pains to understand the regulations and believe in aggressive pursuit and remedy of problems. Please consider this letter an expression of INS' intent to operate our programs in a sound and prudent manner. Many of these issues may be better understood if they were discussed in person.. Please inform me if a meeting at Region II can.be arranged. In the interim if you or your staff have any questions regarding this response,,please contact me at (413) 543-6911. Sincerel, / Mick el J. Bovino, CHP Manager, Health Physics and Engineering enclosure cc: G. Bakevich B. Moser B. Mock file
l-1 0 ) LABORATORY RESULTS OF INS WASTEWATER CHARACTERIZATION STUDY l PoRTSMOUTH, VIRGINIA E 4 1 - 4 1 4 i I ) 1 /- -~. I ~
s BARRINGER LABORATORIES INC 15000 W. 6TH AVE., SUITE 300 GOLDEN. CO 80401 (303) 277 1687 FAX (303) F771689 21-Feb-92 Mark Perry INTERSTATE NUCLEAR SERVICES Page 1 2001 Laigh Road copy 1 of 2 Portsmouth, VA 23701 Set : 1 Attna Bill Hock Received: 17-Jan-92 12:20 Project: PO f Job 923105E Status: Final samp1m Type Water TSS Samole Id ma/1 209-91-022 20-25pm 59 209-91-022 10-20pm <1 209-91-022 Sym 2 209-91-022 3pm <1 ,j 209-91-022 0.8pm 2 1 209-91-022 0.45pm <1 a Meetine The Analvrical Chattennee nr t ri,m,~i..- ~t'
L 0 t c e e BARRINGER LABORATORIES INC. 15000 W 6TH AVE., SUITE 300 GOLDEN. CO 80401 (303) # 7 1687 FAX (303) U71689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 2 copy: 1 of 2 Portsmouth, VA 23701 Set : 2 Attn: Bill Hock Received: 17-Jan-92 12:20 Project PO f: Jobt 923105E St'atust Final GAMMA SPEcntOSCOPY/ FILTRATE Sample Type: Water Bi-214* Error Co-58* Error Co-60* Error Cs-134* Sannle Id DCi/l 2a oci/l 2a ,DCi/1 2a g1 209-91-002 <230 1100 1100 3600 t200 <80 209-91-002 20-25pm <140 <?7 42 21 <46 209-91-002 10-20pm <120 G3 137 36 126 <55 209-91-002 Spm <120 <72 <57 <38 209-91-002 3pm 190 i60 <66 <64 <47 209-91-002 0.8pm NA NA NA NA 209-91-002 0.45pm <120 <73 <83 <48 3 Cs-137* Error Eu-155* Mn-54* Error Pb-212* Samole Td eCi/l 2a oci/l DC1/1 2a oci/l 209-91-002 960 i100 <88 190 60 <86 209-91-002 20-25pm 41 125 <58 <35 <56 209-91-002 10-20pm <66 <50 <45 <56 209-91-002 5pm <56 <49 <36 <47 209-91-002 3pm <50 <48 42 i24 <55 209-91-002 0.8pm NA NA NA NA 209-91-002 0.45pm <62 <67 <36 <51 Pb-214* Error Ra-226* Nb-95* Error Sb-125* Th-234* Samole Id DCi/l 2a DC1/1 DCi/l 2e __ DCi/l DCi/l 209-91-002 120 70 <1100 100 150 <190 <600 209-91-002 20-25pm 88 i34 <690 <24 -<8 3 <340 209-91-002 10-20pm <68 <650 <28 <100 <450 209-91-002 Spm <81 <810 <29 <120 <600 209-91-002 3pm <78 <680 <39 <95 <560 209-91-002 0.8pm NA NA NA NA NA 209-91-002 0.45#m <77 <740 <43 <94 <600 Meetine The A nalvrical l'hn!'* ~,., nr.s n.n.,-i.. w-... >
o BARRINGER LABORATORIES INC 15000 W, STH A1L. SUITE 300 GOLDEN, CO 80401 (303) 771 1657 FAX (303) M 1689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 3 Portsmouth, VA 23701 Copy: 1 of 2 Set : 2 Attn: Bill Mock Project: Received: 17-Jan-92 12:20 PO f Job! 923105E Statust Final GAMMA SPEcrxOSCOPY/ FILTRATE Sample Type ~ Water T1-208* Samole Id _DC1/1 ~ 209-91-002 <630 209-91-002 20-25pm <240 209-91-002 10-20pm <440 209-91-002 Sum <310 209-91-002 3pm <400 209-91-002 0.8pm NA 209-91-002 0.45pm <400 Meetine The Analvrical Chalt,.,,n,, nr.s rI,~,-i..- w-. * *
.o ARRINGER LABORATORIES INC 1$000 W. ETH AVE., BUITE 300 OOLDEN, CO 90401 (303) 2T11687 FAX (303) 7771689 Hark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 4 Portsmouth, VA 23701 copy: 1 of 2 Set i 4 Attn: Bill Hock Project: Received: 17-Jan-92 12:20 PO f: Jobs 923105E Status: Final GAMMA SPECTROSCOPY / SUSPENDED sample Types Water Bi-214* Error Co-58* Error Co-60* Error Sanole Id _DCi/l 2a DCi/l 2a DCi/l 2a '209-91-022 20-25nm 420 i70 950 t80 2600 i100 209-91-022 10-20ym <18 <8.8 <B.8 209-91-022 Sym <14 <10 8.4 i3.8 209-91-022 3pm <19 <14 4.9 12.9 209-91-022 0.8pm <15 <12 9.1 d3.9 209-91-022 0.45ym <17 <9.9 <7.8 Cs-134* Error Cs-137* Error Eu-155* Error sannle Id e01/1 2a oci/l 2a oci/l 2a 209-91-022 20-25pm 140 t30 1500 1100 55 124 209-91-022 10-20pm <5.1 <5.9 <6.6 209-91-022 Sum 4.5 2.5 <7.1 <10 209-91-022 3pm 5.8 i2.9 <11 <10 209-91-022 0.8pm 5.8 i3.7 <8.7 <7.9 209-91-022 0.45pm <7.3 <8.1 <8.0 Mn-54* Error Pb-212* Pb-214* Error Ra-226* Error Sanole Td .0C1/1 2a _gC1/1 nC1/1 2a _201/1 20 209-91-022 20-25pm 150 140 <78 380 50 1400 f400 209-91-022 10-20pm <5.6 <7.1 <11 <92 209-91-022 Sym <5.6 <7.0 <9.5 <110 209-91-022 3pm <5.6 <9.2 <9.2 <95 209-91-022 0.8pm <10 <6.7 <9.6 <110 209-91-022 0.45pm <8.1 <7.5 <10 <90 Meetine The Analvrical Chatte,,~., nr s rr,m ~:..~ w-..u
v BARRINGER LABORATORIES INC 15000 W. OTH AVE., SUITE 300 00LDEN. CO 80401 (303) 777 1687 FAX (303) 2771689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 5 Portsmouth, VA 23701 Copy: 1 of 2 Set 4 Attn Bill Hock Pro 4ect: Received: 17-Jan-92 12:20 PO ft lobt 923105E Status! Final GAMMA SPECTROSCOPY / SUSPENDED sample Type Water Hb-95* Error Sb-12'5* Error Th-234* Error Samole Id oci/1 2a oci/1 2a _oci/1 2o 209-91-022 20-25pm 97 i31 310 i60 500 1240 209-91-022 10-20pm <6.3 <9.7 <110 209-91-022 5pm <4.1 <19 <140 --= 209-91-022 3pm <7.3 <13 <160 209-91-022 0.8pm <4.8 <14 <170 209-91-022 0.45pm <3.8 $13 <200 T1-208* Error Samole Id ecl/l 2a 209-91-022 20-25pm 390 i160 209-91-022 10-20pm <51 209-91-022 Sym <61 209-91-022 3pm <72 209-91-022 0.8pm <44 ~~~ 209-91-022 0.45pm <46 Meetine The Analvtical Clon!!o o,.,n n! 1 r!.~.<~; n'- u \\
~ BARRINGER LABORATORIES INC 15000 W. 6TH AVE., SUITE 300 ootDEN. Co 80401 (303) m.1687 FAX (303) m.1689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 6 Portsmouth, VA 23701 Copy: 1 of 2 Set : 5 Attn: Bill Mock Project: Received: 17-Jan-92 12:20 PO (: Jobt 923105E Status Final GAMMA SPECTROSCOPY / SUSPENDED Abbreviatiqua.i. Parameters: TSS
- Total Suspended Solids Bi-214*
Bismuth 214-MDA Reported at 1.645 sigma Co-58*
- Cobalt 58-MDA Reported at 1.645 signa Co-60*
- Cobalt 60-MDA Reported at 1.645 sigma Cs-134*
- Cesium 134-MDA Reported at 1.645 sigma Cs-137*
Eu-155* Cesium 137-MDA Reported at 1.645 signa Mn-54* Europium 155-MDA Reported at 1.645 sigma Pb-212* Manganese 54-MDA Reported at 1.645 sigma Pb-214* Lead 212-MDA Reported at 1.645 sigma Lead 214-MDA Reported at 1.645 sigma Ra-226* Nb-95* Radium 226-MDA Reported at 1.645 sigma Sb-125* Hiobium 95-MDA Reported at 1.645 sigma Th-234* Antimony 125-MDA Reported at 1.645 sigma T1-208* Thorium 234-MDA Reported at 1.645 sigma Thallium 208-MDA Reported at 1.645 sigma Am-241*
- Americium 241-MDA Reported at 1.645 sigma Np-237*
- Neptunium 237-MDA Reported at 1.645 sigma Be-7*
Beryllium-7 Reported at 1.645 sigma Cd-109*
- Cadmium-109 Reported at 1.645 sigma K-40*
Potassium 40-MDA Reported at 1.645 sigma Units: mg/l
- milligrams per liter pCi/l
- picocuries per liter 20 Counting error at the 95% confidence level, 2a Meetine The Analvrical Chattersno., nr 1 ri,~. :..- en'~u
o 0-BARRINGER LABORATORIES INC 15000 W. STH AVE., SUITE 300 GOLDEN, CO 80401 (303) m 1667 FAX (303) 2771689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Iaigh Road Page: 7 Copy: 1 of 2 Portsmouth, VA 23701 Set : 5 Attn: Bill Hock Received: 17-Jan-92 12:20 Project: PO f: Job! 923105E Status! Final GAMMA SPECTROSCOPY / SUSPENDED ouality codes;
- Not Detected-below detection limit.
NA
- Not Available Job approved by:
I *"'*4?..f!18%uJ R.h &.... s y1e R Euem a vrere Laboratory Managers \\1retirre TI,e t om!vrient rr.-n~-. nr, er.-.. r n-c*
e t BARRINGER LABORATORIES INC 16000 W. 6TH AVE., SUITE 300 GOLDEN. CO 80401 (303) 277 1687 FAX (303) 2771689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page 1 Ccpy 1 of 2 Portsmouth, VA 23701 Set : 3 Attn:-Bill Hock Received: 17-Jan-92 12:20 Project: PO f Jobt 923105E Statust Final QUALITY CONTROL REPORT sample Type Water Ah-241* Error Np-237* Error Be-7* Cd-109* Co-60* Sanole Td DC1/1 2a DCi/l 20 DCi/l __DCi/l _DCi/l Duplicate <100 <83 <15 Duplicate <84 <80 <10 Duplicate % diff. +--- 0.0 0.0 0.0 Std (found value) 331 i23 351 i33 Std (true value) 309 334 Std % diff. 7.1 5.1 K-40* Error Mn-54* Samole Id DC1/1 20 0C1/1 Duplicate 330 120 <10 Duplicate 360 illo <10 Duplicate % diff. 4.3 0.0 Std (found value) Std (true value) Std % diff. Meetine The Analvrient rlmII ><
- n! s t - -: - n'-
1 O s BARRINGER LABORATORIES INC 4000 W. 6TH NE., StilTE 3n0 00LDEN. CO 60a01 (303) 277 1687 FAX (303) F71689 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 2 Portsmouth, VA 23701 copy: 1 of 2 Set : 5 Attn: Bill Hock Project: Received: 17-Jan-92 12:20 PO f: Job! 923105E Statust Final QUALITY CONTROL REPORT Abbreviations Parameters TSS
- Total Suspended Solids Bi-214*
Bismuth 214-MDA Reported at'1.645 sigma Co-58*
- Cobalt 58-MDA Reported at 1.645 sigma Co-60*
- Cobalt 60-MDA Reported at 1.645 sigma Cs-134*
- Cesium 134-MDA Reported at 1.645 sigma Cs-137*
- Cesium I.37-MDA Reported at 1.645 sigma Eu-155*
Mn-54* Europiu'.a 155-MDA Reported at 1.645 sigma Pb-212* Mangarase 54-MDA Reported at 1.645 sigma Lead 272-MDA Reported at 1.645 sigma Pb-214* Ra-226* Lead 214-MDA Reported at 1.645 sigma Nb-95* Radium 226 MDA Reported at 1.645 sigma Niobium 95-MDA Reported at 1.645 signa Sb-125*
- Antimony 125-MDA Reported at 1.645 sigma Th-234*
T1-208* Thorium 234-MDA Reported at 1.645 signa Thallium 208-~DA Reported at 1.645 sigma M Am-241*
- Americium 241-MDA Reported at 1.645 sigma Np-237*
- Neptunium 237-MDA Reported at 1.645 sigma Be-7*
Cd-109* Beryllium-7 Reported at 1.645 sigma K-40* Cadmium-109 Reported at 1.645 sigma Potassium.40-MDA Reported at 1.645 signa Unitst 2g/1
- milligrams per liter pci/l
- picocuries per liter 20 Counting error at the 95% confidence level, 2a Ouality codest
- Not Detected-below detection limit.
Job approved by: . h.................. Approved .WCC15!!e Tire horalvrient rim!!~.~ n' 3 r' - ~:
f ~ i BARRINGER LABORATORIES INC 15000 W. 6TH AVE SUITE 300 GOLDEN, CO 80401 (303) 277 1687 FAX (303) 2771649 Mark Perry 21-Feb-92 INTERSTATE NUCLEAR SERVICES 2001 Laigh Road Page: 3 copy: 1 of 2 Portsmouth, VA 23701 Attn: Bill Hock Project: Received: 17-Jan-92 12:20 PO ft Job! 923105E Status Final QUALITY CONTROL REPORT QUALITY CONTROL DATA SEEET Received by: gr Via: Federal Express Sample Container Type: 2 P1 L btls Sample Type: Water Preservative When Received: none Additional Lab Preparation: none Preser-Date(s) of Parameter Method LLD
~~---- -- ------ --~~--- ----- -- ---
vative Analyst Analysis ---. ----------- ~~-----~~~ TSS 160.2 4 mg/l none Ryman 2/21 Bi-214* 901.1 ~~- pCi/l none La Riviere 1/29-2/19 Co-58* 901.1 20 pCi/l none La Riviere 1/29-2/19 Co-60* 901.1 25 pCi/l none La Riviere 1/29-2/19 Cs-134* 901.1 30 pCi/l none La Riviere 1/29-2/19 Cs-137* 901.1 25 pCi/l none La Riviere 1/29-2/19 Eu-155* 901.1 20 pCi/l none La Riviere 1/29-2/19 Mn-54* 901.1 25 pCi/l none La Riviere 1/29-2/19 Pb-212* 901.1 --- pCi/l none La Riviere 1/29-2/19 Pb-214* 901.1 --- pCi/l none La Riviere 1/29-2/19 Ra-226* 901.1 --- PCi/l none La Riviere 1/29-2/19 Nb-95* 901.1 20 pCi/l none La Riviere 1/29-2/19 Sb-125* 901.1 20 pCi/l none La Riviere 1/29-2/19 Th-234* 901.1 110 pCi/l none La Riviere 1/29-2/19 T1-208* 901.1 --- pCi/l none La Riviere 1/29-2/19 An-241* 901.1
pCi/l none La Riviere 1/29-2/19 i
-Np-237* 901.1
pCi/l none La Riviere 1/29-2/19
~ ..\\... Mark Burkhardt, Ph.D. Laboratory Director Meetine The AnalvticalChattenen nr.s r!.. :.. w-u -}}