W3P89-1551, Semiannual Radioactive Effluent Release Rept 27,Jan-June 1989
| ML20246J838 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/30/1989 |
| From: | Holsopple K, Hunger G, Knapp W LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3P89-1551, NUDOCS 8909050277 | |
| Download: ML20246J838 (24) | |
Text
{{#Wiki_filter:._ ._ .. _ b f. f . .. _,
- P. O. BOX 60340 LOUISI POWER &AN A / 317BARONNESTREET LIGHT NEW ORLEANS, LOUISIANA 70160 * (504) 595-3100 INENlysM W3P89-1551 A4.05 QA August 29, 1989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semiannual Radioactive Effluent Rely se Report Enclosed is the subject report of effluent releases which encompasses the period of January 1 through June 30, 1989. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specification (NUREG-1117) of Appendix A to Facility Operating License No. NPF-38 and 10CRF50.36a(a)(2), pursuant to 10CFR50.4. Very truly yours, 4a R.F. Burski Manager Nuclear Safety & Regulatory Affairs RFB/0PP/pi Enclosure cc (w/ enclosure): R.D. Martin, NRC Region IV NRC Resident IP 71ctors Office cc (w/o enclosure): F.J. Hebdon, NRC-NRR D.L. Wigginton, NRC-NRR E.L. Blake W.M. Stevenson 89090502778906gg2 DR ADOCK 0500 f "AN EQUAL OPPORTUNITY EMPLOYER" )
l. Semiannual Radioactive Effluent Release Report January 1, 1989 - June 30, 1989 Waterford 3 SES Louisiana Power & Light W350897HP
TABLE OF CONTENTS 1.0 SCOPE
'2. 0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0 GASEOUS EFFLUEhTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES l .8.0 FFLATED INFORMATION j 8.1 Changes to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling S.4 Report of Technical Specification Required Instrument Inoperability 8.5 Potential Secondary Release Pathways 9.0 TABLES 10.0 ATTACHMENTS
,f l
l l l l W350897HP 1 _______---------____--------------------J
.. 4 l.0, .$ COPE '
'This Semiannual Radioactive Effluent Release Report is submitted es required by Louisiana Power and Light's Waterford 3 Steam Electric Station (SES) Technical Specification 6.9.1.8. It covers the period from January 1,1989 through June 30, 1989. Information in this report is presented in the format outlined in Appendix B of Regulatory C-uide 1.21.
The information contained in this report includes: (1) A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period; and (2) A discussion regarding potential secondary release pathways identified during the reporting period. The summary of meteorological data and results from the assessment of radioactive doses due to the release of liquid and gaseous radioactive effluents will be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1,1990. - ( W350897HP 2 4
, , *2.0' StIPPLEMENTAL INFORMATION 2.1. Regulatory Limits The Technical Specification Limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble Gases) The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin. The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 -
mrad for beta radiation and,
- b. During any calendar yea : Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Iodines; Particulate, Half Lives > 8 Days; and Tritium 1 The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to 1500 mrem /yr to any organ. I U350897HP 3
- e
4 .
^ '
C ' The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following: '
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ. f W350897HP 4
N, ' ,4 ^ /
.. ..- 2/1.41 Uranium Fuel Cycle Sources '
)
The dose or dose commitment to any member of the public dua-to releases:of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal'to 25 mrem to the total-body or any organ-(except the thyroid,
.which shall be limited to less than or equal to 75 mrem)'over 12 consecutive months.
s 2.2 Maximun Permissible Concentrations 2.2.1 Fission and Activation ' Gases; Iodines; and Particulate,- Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations.are not directly.used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary. 2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified , in 10 CFR Part 20, Appendix B, Table II, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents. 2.3 Average Energy E This is.not applicable to Waterford 3 SE3's radiological effluent technical specifications. f 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.11-1 and 4.11-2 of the Waterford 3 SES Technical Specifications.
' W350897HP 5
. _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _____m._____ .________.__._____.__.______.__________.m_________
2/4.1 Fission end Activation Gases (Noble Gases) For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was calculated according to the following equation: GR = Average Weekly Noble Gas Monitor Reading Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch. In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclides present and the total volume discharged. 2.4.2 Iodines and Particulate Iodines and particulate discharged were aampled using a continuous sampler which contained a charcoal cartridge and a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclides concentrations and effluent volume discharged were used to calculate the previous week's activity released. The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes) Particulate gross alpha activity was measured weekly using alpha scintillation counting techniques. The determined activities were used to estimate effluent concertraticus in subsequent releases until the next scheduled analysis wa's performed. W350897HP 6
t
. Grab semples of continuous and batch releases were analyzed
- monthly. for. tritium. The determined concentrations were
.used to estimate tritium activity in subsequent. releases until the. next scheduled analysis was performed.
2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and-analyzed using gamma spectroscopy. The measured concentra-
-tions were used to determine radionuclides concentrations in.
the' previous week's' releases. For batch releases, gamma analysis was performed on the sample prior to release. For both continuous and batch releases, composite samples-were analyzed quarterly by a contract laboratory (Teledyne Isotopes)ffor Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting techniques,. respectively. For radionuclides measured in the composite; samples,hthemeasuredconcentrationsinthecompositesamples from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents , during the current month or quarter. The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclides present and the total volume of the effluent discharged. 2.5 Batch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1. t W350897HP 7
ie I *
- 2[6 1 Abnormal Releases .
c U. There were no abnormal releases 'during the' reporting period. . 3.0 GASEOUS EFFLUENTS
-The quantities of radioactive material. released in gaseous effluents are
-summarized in Tables IAi IB, and IC. Note that there were ru) elevated releases, since all Waterford 3 SES releases are considered to be-at ground level.
.4. 0 LIQUID EFFLUENTS
'The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.
5.0- SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3. s 6.0 METEOROLOGICAL DATA ' The summary of the hourly meteorological data for this reporting period will be included on the Semiannual Effluent Release Report to be submitted within 60 days after January 1, 1990. 7.0 ASSESSMENT OF DOSES The summary of doses due to gaseous and liquid effluents for this reporting period will be included in the Semiannual Effluent Release Report to be submitted within 60 days after January 1, 1990. ( 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Control Program for the period covered by this report. W350047HP 8 j
8'. 2 Ch'anges to the Offsite Dose Calculation Manual !s There were no changes to the Offsite Dose Calculation Manual for the period this report covers. ~ 8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Specification Table 3.12-1. Milk is collected, when available, from the control location and three identified sampling locations as indicated in Waterford 3 offsite Dose Calculation Manual, Table 2 and Table 3. 8.4 Report of Technical Specification Required Instrument Inoperability Technical Specification, Limiting Condition for Operation (LCO), 3.3.3.10 and 3.3.3.11 requires the reporting in the Semiannual Radioactive Effluent Release Report of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement. During the reporting period, there were no cases when instrumentation was not restored to - operability within the time specified. 8.5 Potential Secondary Release Pattways At 1030 hours on January 6, 1989, management determined the report-ability of a potential unmonitored release point (refer to License Event Report 89-001). The filtered ventilation exhausts of the hot machine shop (HMS) and equipment decontamination room (DCR) had not been monitored for airborne radioactive effluents. Without a radia-tion monitor to check the performance of the Pre-filter and HEPA filter, their operation to minimize the release of radioactive , f material could not be confirmed. This event was reported because the potential existed for an uncontrolled radioactive airborne release path.
.W350897HP 9
._____-_________O
m. Q
- l, ae Anaextensiva documentation review revealed that the general area-airborne radiation monitors in these areas were once to be connected to the. ventilation exhaust ducts. An extensive documentation search was performed to locota the justification for the as-built configura- '
. tion'of-the unmonitored filtered exhaust. No specific documentation I was. located;'therefore, the root cause of this event was attributed Eto. inadequate documentation during initial construction to establish' l the-qualification of the as-built configuration. The IDfS'and DCR ventilation exhaust systems were secured until a 10CFR50.59 safety analysis could be performed.
)
}
An analysis was performed to determine the offsite radiological ' impact resulting from the continuous operation of the IDiS and DCR l ventilation systems. The analysis and calculations-performed assumed I i an extremely conservative source term. The calculated maximum. -{ critical organ dose was 0.031 mrem per year to the liver 'of 'an t { infant. This' dose is only 0.2% of the design basis limit in 10CFR-Part 50 Appendix I and was considered to be extremely conservative. 1 Therefore, this release pathway was not considered significant enough i to be included'in the Radiological Environmental Technical-Specifica- ' tions (RETS). Samples of the actual Pre-filters and HEPA filters removed from the 1 { HMS and DCR ventilation srystems after four years of continuous .I operation were analyzed-by gamma spectroscopy. While small amounts i l of activity were detected on the pre-filters, none was detected on ! the downstream HEPA filters. A realistic source term was estimated l using the Pre-filter sample results. The offsite doses calculated using the realistic source term were two to three orders of magnitude j below the values initially calculated using the assumed source term. 1 These results support the conclusion that if any release of radio- ! activity occurred from these ventilation exhaust systems it would have been negligible. e i l W350897HP 10
fL. . M,y , To demonstrate that the Pre-filters and HEPA filters continue func-
~
~
tioning properly, a temporary-passive sampling system has been placed
'downstreamoftheHEPAfiltersintheHMSandDCRventikationsystems.
This sampling system will be used.to verify proper ~ operation of the filtering system.l As a result-of'this reported event, other areas of the plant were examined to determine if similar pathways' exist. Other less signi-ficant' potential release ~ paths were identified. -These pathways are currently being evaluated. -An evaluation of these release pathways will be documented in Problem Evaluation /Information Request 71098. In addition, temporary passive sampling systems were. installed on the
, pathways to. collect data. The evaluation of these potential pathways was not complete at the end of the period' covered by this report.
Follow-up information will be included in subsequent Semi-annual Radioactive Effluent Release Reports. 0 l' W350897HP 11 L_______________________________.___________________________________________________
~
9.0 TABLES 1 Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents
-1B Semiannual Airborne Continuous Elevated and Ground Level Releases 1C Semiannual Airborne Batch Elevated and Ground Level Releases 2A Semiannual Summation of All Releases by Quarter - All Liquid Effluents 2B Semiannual Liquid Continuous and Batch Releases 3 Solid Waste Shipped Offsite for Disposal 10.0 ATTACHMENTS None l
f W350897HP 12
3 l~ . i=. .,
* ~
j* TABLE 1 (1 of 1) IEPRT CATEBRY : MTQiIELEAK SLf91ARY 90 INT : ALL F IELEAE : MTCH LIEJID Ale ONEOLS PER!Wi START TIE : 0:00 ift6 = 12:00AM JAIAIARY 1 1989 PERIOD Ele TIE 4343:59191B = 11:59PM JWE 30 1989 LIEJID IELEASES life 3t 0F IELEMES 56 TOTAL TIE FWt ALL IELEAES : 14730.0 M!lt1TES MAIIM TIIE FGt A IELLAE : 328.0 MiltlTES AYERAGE TILE FWt A IELENE 263.0 MI M ES MINIM TIIE FM A IE11ASE : 20.0 MlltJTES AYERNE STIEAM FLOW 817006.4 OPM GASEOUS IELEASES Mf9ER OF IELEASES 0 TOTAL T!!E FGt ALL IELIAGES : 0.0 MIMITES MAIIM TIE FWt A lELEASE : 0.0 MIIRITES AYERNE TIE FWt A RELEASE : 0.0 MIItJTES ' MINIM Tile FGt A IE11ASE : 0.0 Mll8JTES I f W350897HP 13
+' ' .
TABLE 1A (1 of 1) fEPORT CATEGORY OPE OF ACTIVITY SEMIAlffML St#PATION OF ALL fE1EAES BY GUARTER
- ALL AlfBONE kirl.lENTS IEPORTING PERIOD QUARTER C 1 Ale RMRTER R 2 S : LMIT IGUARTER 1 IGlMRTER 2 *EST. TOTAL:
- :HolftS IHolftS EMOR I TYPE OF EFFLLENT : : 1-2160 12161-4344 : :
A. FISSI(D! #El ACTIVATI(M PRWUCTS
- 1. TOTAL fELEASE ICLRIES : 1.67E 02 7.7 % 01 1.50E 01:
- 2. 4WER4(E fELEASE MTE FOR PERIOD IUCI/SEC 2.14E 01 9.86E 00 8
- 3. PERCENT OF APPLICABLE LIMIT 1 : N/A N/A B. RA0!010011ES
- 1. TOTAL 100!IE-131 ClRIES : 2.84E-05 e 2.52E-05 1.50E 01:
- 2. AVERA(E IELEAIE MTE FWt PERICE IUCI/SEC 3.66E-06 3.20E-06
- 3. PERCDfT F APPLICABLE LIMIT I : N/A N/A C. PARTIC11ATES
- 1. PARTIC1LATES(HALF-LIVESM DAYS) ICtRIES : 4.50E-06 1.31E-06 1.50E 01:
- 2. AVEM(E IELEAIE MTE FOR PERIOD IUCI/SEC 5.79E-07 8 1.67E-07
- 3. PERCD(T F APPLICABLE LIMIT I : N/A N/A :
- 4. ORDSS ALPM MDI(MCTIVITY ICLRIES : 3.24E 05 e 2.16E-05 :
D. TRITILM
- 1. TOTAL lELEASE CLRIES : 7.A4E 00
- 2.94E 01 1.50E 01:
- 2. AVEMOE JELEASE MTE FOR PERIOD IUCI/SEC 9.57E-01 3.74E 00
- 3. PERCENT OF APPLICABLE LIMIT I : N/A N/A W350897HP 14
TABLE IB l i (1 of 1) l
}
1 i 1 flEPGti CATEDGty SEM140AML AfflI0lWE CONT!IIJOUS E.EVATED AS GIOLAW t LEVEL IELEABES. TOTALS FOR EACH 14JCLIE lELEASED. TVPE (F ACT!v!TY FISSIGi 04ES.10011ES. Ale PNtTICLAATES IEPGtTIE PERIOD euMtTUt I 1 Als GUARTUt t 2
- ELINATED fElIAIES : GIOLDS lELEAES LIilf IBMRTER 1 samRTER 2 teflRTER 1 IGUMtTER 2 8 g a fMOtftS IMOlftS *WLIIS 82L515 :
IUX.I!E : I 1-21 2 2161-4344 1-2160 t2161-4344 : FIS$1Gl GASES XE-133 XE-135
- MIES I 0.00E41 0.00E41 1.50F 02 8 6.97E 01
- (1 STIES 0.00E-01 0.00E-018 8.41E 00 8 7.7E 00 TOTAL FGt PERIOD (Xft!ES 0.00E-01 0.00E-01 1.67E 02 8 7.71E 01 x 10DIIES I-131 CLft!ES : 0.00E-01 : 0.00E41 2.94E-05 t 2.52E-05 :
PARTICtLATES H-3 : MIES : 0.00E-01 0.00E41 7.44E 00 8 2.94E 01 ? 79Hl4 1- (15t!ES : 0.00E41 0.00E41 2.9E47 8 0.00E-01 : C0-58 8 QAt!ES 0.00E4110.00E-0181.64E46 1.66E47 C0-60 Clft!ES 0.00E4110.00E41 : 1.2E4 8.76E47 : CS-134 : (15 TIES : 0.00E4110.00E-01 2.03E47 0.00E41 : CS-137 Ctft!ES I 0.00E41 : 0.00E-01 1.12E-06 8 2.67E471 0 4.PH4 : MIES 0.00E41 0.00E-018 3.24E-05 t 2.16E-05 : TOTAL FOR PERIOD CLRIES 0.00E-01 0.00E418 7.44E 00 t 2.94E 01 i f W3508971fP 15
+ . TME IC (1 of 1) TYPE F ACTIVITY
' E"a#S ?MWEL%h.
FISSIGI GES,12!IES. MS PWITICLA.ATES REPWITIIIGPERIS : ENtTER 81 NS GUARIUt 8 2
- ELEYnTEDIE.EAES WEMS IRfAES :.
- LSIIT tamtfER 13GUARTBt 2 #GUARTER 1 IENtTER 2 :
- :Muts IHulptB IHRIES HDiplS IllCLIIE 1 1-2160 82161-4344 : 1-2160 82161-4344 :
FISSI(pl GASES
. IDE 10DIlES IDE PARTI (14.ATES NOIE W350897HP 16
l . i l
~
- t. \
~ .
(1 of 1) I IEPWtf CATE0WtY !EMIN0tl4. SL59RTIChi F ALL IELIAES BY RWITER TWE OF ACTIVITY : ALL LIQUID EFFLABffS IEPORTING PERIOD t GUARTER 0 1 Ale GUARTER I 2 LIIIT :RIARTUt 1 RIARTER 2 *EST. TOTAL
- :HOLftB tH0LstS :DOWR 1 :
TYPE OF EFPLLElli 1-2160 12161-4344 : A. FISSION AlO ACT!YATION PRODUCTS
- 1. TOTAL IELIAE(110T INCLtBING t t I :
TRITILM. 0AES. AU4WL) ICLRIES 1.37E41 7.64E-02 1.50E 01
- 2. AWERADE DILiffED C0lGNTRATION : I :
DLRING PERIOD UCI/ft. t 5.49E49 3.69E49
- 3. PEllCENT OF APPLICAILI LIMIT t I t N/A : II/A B. TRITRPI
- 1. TOT 4. IELEASE :CLRIES : 9.20E 01 8 4.75E 01 1.50E 01:
- 2. AWERAGE DILtffED CONCENTRATION I : :
DURIIG PERIOD IUCI/lL : 3.70E-06 8 2.30E-06 :
- 3. PERST F APPLICAILE LIMIT I : N/A N/A t C. DISSOLVED A10 ENTRA!IED GASES
- 1. TOTAL IELEASE ICURIES 2.13E 00 t 3.23E-01 1.50E 01 _
- 2. AWERAGE DILUTED (DCENTRATION I :
- 8 DLRING PERIOD :UCI/R. t 8.57E-08 1.56E-08 3, PDIST F APPLICAILE LIMIT 1 : N/A N/A D. GROSS AUH4 RADI0 ACTIVITY
- 1. TOTAL IELEASE 80 RIES I 0.00E-01 7.70E-05 8 1.50E 01:
E. WASTE VOL RELEASED (PRE-DILUTION) 80AL 3.96E 05 t 2.64E 05 1.50E 01: F. V(LUPE OF DILUTION WATER USED tGAL 6.57E 09 5.46E 09 1.50E 018 f W350897HP 17
4 e TABLE 2B (1 of 2) IEPRT WE00RY SEMIAIOUIL LISIID C!Bff!IllDUS Alt MTCH IELEAES
- TOTALS FR EACH I41CLIE lE11 AGED.
TVPE F ACTIVITY .t.L ltA0!!BRELIES IEPRTIE PERIOD Gu MTR 9 1 100 GUARTS I 2 CtBITlalRIS IELEAIES BATCH IELEASES t i 1811T tafutTER 1 touRRTE 2 taunRTS 1 IGUETER 2
- setets IMuts tHOLftS IMMIS IllCLIE : 8 1-2160 82161-4344 1-2160 t2161-4M4 :
ALLltELIES H-2 Oft!ES 0.00E-018 0.00E-018 9.20E 018 4.7E of 16-24 aftIES t 0.00E418 0.00E-0115.1E44 0.00E41 : Ot-51 : CLft!ES t 0.00E-418 0.00E41 2.9M-04 8 9.31E-05 10F54 : Oft!ES 0.00E-01 0.00E418 2.1E-03 3.54E44 : FE-55 CLftIES : 0.00E41 0.00E-0114.36E-02 2.71-02 : FE-59 : Ctft1ES i 0.00E41 0.00E412 4.6K-05 0.0E41 : CXHIB aftIES I 0.00E4110.00E-01 2.6E-02 8 2.31E 03 : 00-60 Ctft!ES : 0.0E41 0.00E41 1.20E42 8 2.64E-03 19-08 : CLft!ES
- 0.00E41 0.00E41 0.00E41 2.10E44 SR-92
- QA!!ES
- 0.00E4110.00E41 2.46E45 8 2.30EMI5 8 ZR-95 CLftlES 0.00E41 0.00E411 1.24E-03 8 7.41E45 t 10-95 : Clft!ES : 0.00E41 0.00E-018 2.74E-03 8 2.96E-04 IILF106 : GRIES 0.00E41 0.00E418 4.70E44 a 0.0E41 :
AG-110M Cl# TIES 0.00E41 0.00E418 9.64E-04 8 0.00E41 1-131 : CLft!ES 0.00E4110.00E418 2.31E-03 8 3.SE-04 8 1-133 Cl# TIES 0.00E-01 0.00E-01 6.15-05 8 2.24E-05 . CS-134 : CLft!ES 0.00E41 1 0.00E-01 1 1.14E-02 1 1.31E42 : CS-137 t Cl# TIES : 0.00E418 0.00E-018 1.69E-02 8 2.2E42 : LA-140 t aft!ES 0.00E-01 0.00E41 0.00E418 2.1K-05 : CE-144 CLftIES 0.00E41 0.00E412 3.9E-04 3 0.00E41 : Cl-4!DI CLft1ES 0.00E4110.00E-01 2.64E-04 8 5.01-05 : IGt-65 aft!ES 0.00E 41 0.00E418 6.37E-03 1.5M-03 1 KR-eg
- Ctst!ES 0.00E-01 0.00E-41 2.01E-05 4.2E-05: J XE-131R I aft!ES : 0.00E-01 0.00E-018 2.90E-02 8 5.01-03 :
XE-133 : Cl#t!ES : 0.00E418 0.00E-0181.20E-02 1.25-03 XE-133 ClftIES : 0.00E418 0.00E-01 2.07E 00 t 3.11E41 : IE-135 : CtftIES : 0.00E41 0.00E-011 1.81E42 8 4.17E43 : AR-41 CLRIES t 0.00E-01 : 0.00E-01 0.00E-01
- 9.10E46 8 f
W35089711P 18
o.. , , . TABLE 2B (2 of 2) t . F ACTIVITY ALA. ARDIWRELitES I m PERIS I GuRRTUt 81 As EARTER 4 2 COWTIILIOUS IELIAIES I BRTCH IELEASES
- (MIT IGWARTER 1 samRTUt 2 tamR19t 180URRf9t 2 IMDLftB IMOLftB tHolftS *WlftS :
MIE : I 1-21 M 82161-4344 1-21M 2161-4344 : AL1. ISKI.IES CONTIltB C ALPH4 C0-57
- QatlES : 0.00E-01 0.00E41 0.00E418 7.70E-05 :
- Ctst!ES 0.00E 41 0.00E418 8.686-05 2 3.34E-07 8 9-124 8 aft!ES 8 0.00E4110.00E418 8.2E-04 8 5.06E-05 :
Ss*113 aft 1ES e-97 0.00E-01 0.00E-018 3.87E-04 8 1.81E-05
- Clft!ES 0.00E-01 0.00E418 7.22E-0413.12E-04 SD-122 i CLRIES 0.00E 01 0.00E411 1.06E-05 8 2.70E-05 SB-125 CUR 1ES 0.00E418 0.00E-01 1.30E-02 8 6.3143 :
TOTAL FDit PUt!OD CLRIES 0.00E-01 0.00E418 9.41018 4.79E 01 t l l W350897KP 19
)
l
P . . * + a TABLE 3 (1 of 3) Solid Waste Shipped Offsite for Disposal During Period 1-1-89 thru 6-30-89 s container waste Total 7. Error Waste Type Volume (ft3) Volume (m3) Activity (Ci) (C1)
- Compacted Dry 390 9.97 .13 125%
Active Waste Shipped to Scientific Ecology Group for Volume Reduction
- Non-Compacted Dry 5595 140.29 .54 1257.
Active Waste Shipped to Scientific Ecology Group for Volume Reduction
- Weste Oil Shipped 277.5 7.33 .017 125%
for Processing by l Scientific Ecology ) Group l Steam Generator 561.7 15.9 .0046 125% ' B10wdown Resin-l Dewatered-? hipped 3 to Scientific Ecology Group for Volume Reduction l Liquid Waste 181.7 5.145 121.00 125% Management and Resin Weste Management Resins Solidified with Cement f
- Waste volumes shipped for volume reduction do not reflect final burial waste volumes.
W350897HP 20 ( \ _. _ _ _ . - _ - .
TABLE 3 (2 of 3) Estimates of Major Nuclides By Waste Type Waste Type Nuclide Name Percent Abundance C1 Compacted Dry Mn-54 Active Weste 1.5 1.96E-03 Fe-55 10.9 Shipped to Co-SS 1.42E-02 Scientific 59.4 7.75E-02 Co-60 3.4 Ecology Group Ni-63 4.44E-03 5.5 7.10E-03 for Volume Reduction Sb-125 1.4 Cs-134 1.82E-03 7.5 1.02E-02 Cs-137 10.1 1.32E-02 Non-Compacted Dry Mn-54 Active Waste 1.5 9.03E-03 Fe-55 9.9 Shipped to Co-SS 5.83E-02 Scientific Ecology 57.1 3.3sE-01 Co-60 3.3 Group for Volume Ni-63 1.9aE-02 Reduction 3.0 2.92E-02 Sb-125 (1% Cs-134 4.10E-03 9.5 5.57E-02 Cs-137 13.0 7.61E-02 Waste Oil Mn-54 Shipped for 1.5 2.57E-04 Fe-55 39.0 Processing by Co-SS 6.33E-03 Scientific 14.0 2.24E-03 ' Co-60 12.0 Ecology Group Ni-63 1.95E-03 20.0 3.20E-03 Sb-124 3.5 5.71E-04 Sb-125 4.7 7.74E-04 Cs-134 1.7 2.71E-04 Cs-137 4.1 6.73E-04 LWM & RWM Mn-54 1.6 1.98E+00 Resins Solidified Fe-55 3.7 4.43E+00 with Cement Co-SS 5.9 7.18E+00 Co-60 3.7 4.50E+00 Ni-67 9.9 1.20E+01 Cs-134 27.2 0.29E+01 Cs-137 47.4 5.73E+01 f Steam Generator Fe-55 10.9 5.06t'-04 Blowdown Resin Co-SS 57.7 2.66E 03 l Shipped to Scientific Co-60 3.4 l Ecology Group for 1.56E-04 Ni-63 5.5 2.56E-04 Volume Reductf-" Cs-134 9.1 4.22E-04 Cs-137 13.0 6.00E-00 W350897EP 21
--__._----_n._.______-____...--_n_.___ . - . - _ _ _ - - - - _ _ _ . - - - - _ _ _ -
,d 3
P 3 .. . o'- . TME 3 (3 of 3) Solid Waste Disposition Summary i Number of Shipments Destination Tran r im S Truck 1 - Richland, WA 4 - Oak Ridge, TN Waste # of Class Type of Shipments Type Container Moce Destination A 4 LSA Strong-tight Truck Oak Ridge B 1 LSA Type A Truck Richland e f V350897EP 22
- _ _ _ _ _ _ _ _ _ _ - - - _ . _ - _ _ _ . _ . _ _}}