ML20082N401
| ML20082N401 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/30/1991 |
| From: | Crawford A PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-91273, NUDOCS 9109090141 | |
| Download: ML20082N401 (39) | |
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F w> LSeer 91 h Pubile Service' . 22";."la,..... P.O. Box 840 Denver CO 80201 0840 August 28, 1991 A. Clegg Crawford Fort St. Vrain Vice President UMt h. I ""*"'"*''"' P-91273 U. S. Nuclear Regulatory Commission Attn: Document Control Desk
-Washington, D. C. 20555 Docket No. 50-267
SUBJECT:
Semi-Annual Radioactive Effluent Release Report Gentlemen: Attached please find the Semi-Annual Radioactive Effluent Release Report for the Fort St. Vrain Nuclear Generating Station. This report covers the period January 1, 1991 through June 30, 1991, and is submitted pursuant to Section 7.5.1.e of the Fort St. Vrain Technical Specifications. Please contact Mr. M. H. Holmes at (303) 480-6960 if you have any questions regarding this report. Sincerely, (Y 6 l$l A. C. Crawford Vice President Nuclear Operations ACC:SC/skd Attachments
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s_ . cc w/ attachments: Regional Administrator, Region IV Mr. J. B. Baird - Senior Resident Inspector Fort St. Vrain Dottie Sherman, ANI Library American Nuclear Insurers The Eachange, Suite 245 270 Farmington Avenue Farmington, CT Mr. Robert Quillin, Director Radiation Control Division Colorado Department of Health 4210 E. lith Ave. Denver, CO 80220 Mr. Milt Lammering, Chief Regional Representative, Radiation Program V. S. Environmental Protection Agency Region VIII-999 18th Street, Suite 500
. Denver, CO 80202-2405 Mr. Farrell D. Hobbs Environmental Management Rockwell International Building 250, P.O. Box 464 Golden, CO 80402 Dr. James E. Johnson Department of Radiation Biology MRB Building Colorado State University Fort Collins, CO 80523-n i
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SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
' January - June 1991 3 --
J. Public Service Company'of-Colorado 1 Fort St. Vrain Nuclear Generating Station August, 1991 I k t t h [._ j. l .
s . 4 1.0
SUMMARY
This report summarizes radiological effluent released from the Fort St. Vrain Nuclear Generating Station for the period of January through June, 1991. This information is provided pursuant to the requirements of Sections 7.5.1.e, 8.1.2.d, e and j, 8.1.3.e and f, and 8.2.1.h.1 of the Fort St. Vrain Technical Specifications. This report uses the reporting format recommended by Regulatory Guide 1.21 as well as the requirements of the aforementioned sections of our Technical Specifications. The following tables with a supplemental information section are included with this report: Table De sc ript_ ion, IA Gaseous Effluents - Summation of All Releases 1C Gaseous Effluents - Ground-Level Releases 2A Liquid Ef fluents - Summation of All Releases 2B Liquid Effluents 3 Solid Waste and Irradiated Fuel Shipments 4A Hourly Meteorological Data Please note that Table IB (of Regulatory Guide 1.21) has been omitted from this report because all of our gaseous effluents are assumed to be grounc-level releases as opposed to being elevated releases. Fort St. Vrain Technical Specifications apply exclusively to the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are considered. Other gamma emitting nuclides that are identifiable, together with those of the above nuclides, are analyzed and included in this report. Sample activities that are less than the detection capabilities of our equipment are entered in this report using the value resulting from the calculation of the lower limit of detection (LLD) or minimum detectable activity (MDA). This results in reporting upper limit values that are in excess of true activities. (2)
i
<e.
f The lower limit of; detection _ (LLD), for the purpose of this report, i
-is defined'as the smallest concentration of-radioactive material in a- l sample that.will yield a net count, above the_ system background, that ;
will be detected with a 95% probability of being correct and- only a- _ i 5% -probability- of _ falsely _ concluding that a blank observation represents a real signal. :The LLO values specified in our Technical _j
; Specifications are as-follows: !
Liquid : t Principle Gamma Emitters 5.00E-07 pCi/ml l Dissolved Noble Gases 1.00E-05 pCi/mi ! i Tritium 1.00E-05 pCi/mi j Iodine-131 1.00E-06 pC1/ml Gross Alpha 1.00E-07 pC1/ml i Strontium-89, 90 (Composite) 5.00E-08 pCi/mi l i Gaseous- i Principle Gamma Emitters 1.00E-04 pCi/cc f (Gas) '; f 4 Principle Garrma Emitters 1.00E-11 pC1/cc j (Particulate) ! Tritium (Gas) 1.00E-06 pCi/cc j Iodine-131(Charcoal) 1.00E-12 pC1/cc !
)
Gross A.pha 1 (Particulate) 1.00E-11 pC1/cc j i
-Strontium-89,90(Particulate) 1.00E-11 pCi/cc ;
i Gross-Beta (Particulate) 1.00E-11 pC1/cc . Where. applicable, we have listed "less-than" values for those [ nuclides listed specifically in our Technical Specifications, These t "less-than" values.were calculated using the observed LLO values and f the total volume of the media. ~The "less-than" values were not [ included in the total values for the pathway. -t e The percent of Technical Specification limit on Table 1A is blank in l some cases because this value could not be calculated from data which l were at or below the minimum detectable activity. On Taole IC, the :! continuous release mode values are not reported because this release ! pathway is the same as the batch mode. All other blanks on Tables 1C l and 2B occur because no LLD values for these nuclides are required to j be calculated per Technical Specifications. ; (3) ; r f
. . . . - - . ~ - . . - - _ - - - . - , _ -_
There has been some confusion in the past as to the total volume of water used for dilution of radioactive liquid effluent. All average diluted concentrations are based on the activity at the unrestricted area. Although this effluent could eventually reach one of two rivers (St. Vrain Creek and South Platte River) which converge approximately one and one half miles downstream of the plant, no further dilutions were assumed. Additional discussion on river flow is contained in section 4a of the Supplemental Information Section. There were no abnormal radioactive effluent releases (liquid or-gaseous) made during this reporting period. There- were no unplanned radioactive liquid waste releases made from the Liquid Waste System 62 or the Reactor Building Sump during this reporting period. There were no unplanned radioactive gaseous waste releases made during this reporting period. There were 7 shipments of radioactive material for disposal this ; re,.orting period. There were two shipments of radioactive wastes shipped directly to a disposal site during- this period consisting primarily of irradiated hardware. A total of five shipments of radioactive wastes consisting of irradiated haroware (IH) and uncompacted dry activated wastes (DAW) have been sent to various vendors for volume reduction. The information on the following page summarizes all waste shipments as required by Technical Specification
- 7. 5.1. e .. with -the shipments sent for volume reduction being identified as not having been classified. Cata for these shipments has also been provided in Table 3. There have not been any shipments of irradiated reactor fuel .
There have been no major design changes to the radioactive waste systems reviewed by the Plant Operations and Review Committee (PORC) during the period covered by this report. One. minor Change Notice, CN-3047, was-initiated during the reporting period, The change involved the installatior of a- pipe and 3 way
' ball valve in the common line upstream of u e Reactor Building Sump (RBS) discharge. filter trains' inlets. The installation was recommended to allow a given filter train to remain in service longer by elimination of the initial surge of sludge which normally blocks-
-the inservice filter train almost immediately. The modification is intended to prolong the interval between RBS effluent system filter changes,- but' ,iill not affect the function of the filters or requirements associated with a release from the RBS. No new accident modes are created. The modification did not require review by the Plant Operations Review Committee because it was non-safety related, nor did it have the potential for creating an unreviewed environmental question.
There were no changes to the Process Control Program (SUSMAP-3), Issue 2, effective date November 13, 1984, during this reporving period. [ (4)
7-c .
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- Total Curie Principle lSourceofWaste Type of Soliditication I' Waste Container:
C1assification Volume Ouantity Radionuclides and Processing Container Agent or l (f t') :(Ci) (Estimated) Empicyed Absorbent. ( (Estimated) , i 0 None' N/A N/A N/A Class A 0 125.2 ,4750.84 11-3, C-14, Mn-54. Irradiated Type B None Class B .
.2-55, Co-60, Ni-59, lia rdware/None Ni- 63, Sr-90, I-129, ,
Cs-134 and Cs-137 Class C 26.2 360.19 11-3, C-14, Mn-54, Irradiated Type B .llione ! Fe-55, Co-60, Ni-59, liardware/None , Ni-63, Sr-90, 1-129, . Cs-134 and Cs-137 i ; ui ; g i Wastes not 98 0.056 Cr-51, Mn-54, Fe-59, DAW /none j STC .None f ' I I i c1 1ssified due Co-57. Co-60, Cs-to awaiting 134, Cs-137, S-35, results of Sr-89, Sr-90, Fe-55, volume l Ni-63, Pu-238, 11-3 reduction and Pu-241 g I I i 90 0.097 Same DAW /none STC None 98 0.071 Same DAW /none STC. None l t I i 209.04 11.3 Mn-54, Co-60, Cs- Irradiated ! STC None i 137, 11- 3, C-14, S - Ila rdwa re/none ' 35, Fe-55, Ni-63, f l Sr-89 and Sr-90 l 1 l 209.04 16.3 Itradiated STC None Same liardware/none , i
]
i. There were no changes to the Offsite -Dose Calculation. Manual ($USMAP-2), Issue 18, ef fective date August 29, 1990, during this reporting period. o On August 14, 1999, Amendment No. 71 to the FSV Technical Specifications became effective which revised ELCO 8.1.1.g. deleting the requirement to report gaseous ef fluent activity monitors or flow instrut.ients inoperable over thirty days in the Semi-Annual Effluent Report. The reporting requirements were changed to require a Special Report if less than the minimum required gaseous effluent activity monitors are operable for over seven days. It has not been necessary to issue any such Special Reports since the requirement became effective. No liquid effluent activity monitors were inoperable for over thirty days during the period of January 1, 1991 to June 30, 1991. No recorders associated with the liquid effluent activity monitors were out of service over thirty days. An annual land use .xntis is performed as part of the Fort St. Vrain Radiological Envi- evital Monitoring Program. Changes made to environmental samp- a locations as a result of the annual land use census are reportt< in the annual Radiological Environmental Mor ' *ing Program report. I, i i f i P (6)- : i i _ , . ; .. -,,,,r..,.._,._-.,_.- -..,-,,_,_,,._,._._2.__...~. -
...a,_..-._, _
t Effluent and Waste Disposal Semiannual Report Supplemental Information Facility-fort St. Vrain Nucle.r Generating Station Licensee Public Service Comgany of Colorado
- 1. Regulatory Limits All results of radioactivity analyses of gaseous end liquid effluent _ are used in accordance with_ the methodology and parameters listed in the Offsite Oose Calculation _ Manual
($USMAP-2) to assure that the concentrations at -the point- of release are maintained within the limits set forth in the Technical Specifications. These limits will ensure the quantity of radioactive effluent released from the plant is maintained as low as reasonably achievable and in any event within the limits of 10CFR20 and in accordance with 10CFR50. The air dose due to noble gases released in gaseous effluent at the unrestricted area is limited to: a) 5 mil 11 rads gamma and 10 millirads beta during any calendar quarter, and, b) 10 millirads gamma and 20 millirads beta during any calendar year. The ~ dose to a member of the public due to I-131, tritium, and radioactive particulates with half-lives longer than eight -days in gaseous effluents will be limited to: a) 7.5 mi P1 rems to any organ-during any calendar quarter, and, b) 15 millirems to any organ durinn any calendar year. The dose rate due to radioactive gaseous ef fluent is limited to the following: a) For noble gases, _ less tb . or equal to 500 millirems per year to the total body and less than or equal to 3000 millirems per year to the skin, and, 1 (7)
- - - - - . - - - - - . _ - - - . _ . . . - - - . . . ~ - _ _ - -_
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i b) For 1-131, tritium, and radioactive particulates with ! half-lives greater than eight days, less than or equal j to 1500 millirems per year to any organ. The dose or dose commitment to a mehber of the public from ; radioactive materials in liquid effluents released to ! unrestricted areas are limited as follows: l
- 4) During any calendar quarter to less than or equal to [
1,5 millirem to the total body and to less than or l' equal to 5 millirems to any organ, and, b) During any calendar year to less than or equal to 3 [ millirems to the total body and to less thaa or equal ! to 10 millirems to any organ. !
'2. Maximum Permissible Concentrations !
I All MPCs used in determining allowable release rates from the gas l waste holduo system and the liquid waste system ata those listed in Table 11, Columns 1 and 2, respectively, of Appendix B to [ 10CFR20. In addition, for the MPC of dissolved noble paes in liquid effluent ti.e value of 2.00E-04 microcuries per milliliter . was used. l For the purpcses of calculating allowable release rates, the MPC I for halcgens and particulates with half-lives longer than eight '
- days will be reduced by a factor of 700 from their listed value .
in Table II, Column 1, of Appendix B to 10CFR20. j
- 3. Average: Energy i The average energy -(E-Bar) of the radionuclide mixture in !
releases of fission and activation gases is not calculated or ! used at this facility. j
- 4. Measurements and Approximations of Total Radioactivity !
i a) Fission and Activation Gases ! Batch releases from the gas . waste holdup system are [ performed after sampling and analyses for noble gases and } tritium. These analytical results are used along with i atmospheric dilution factors to determine the allowable release rate. Gas is released on a continuous basis through , a gas waste header which is monitored by a noble gas monitor r and an iodine monitor. in-the event of high activity in the ; continuous release, header control functions are initiated ; which divert the gas to the gas waste holdup system, [ (8) i . . . - . . _ .,-.._,-y7,---,.._,_ - _ , , . 9 ,.,j7_ ,_.,_._n,,_.1_.g.,
,,~_..,_w.-e,,_w-rmt---- --ew -i- .v.e e---- +<,-ett ------==ir-ire - - = - - -
4 All radioactive gases are released to the Reactor Building
-exhaust ventilation system which has a -flow rate- of approximately 20,000 cubic feet per minute. The full-flow of this exhaust _ is directed through high efficiency
-particulate filters (HEPA) and activated charcoal beds prior to the release to the environment.
Downstream of the activated charcoal beds the gas stream radioactivity is- continuously monitored and recorded by noble gas monitors, piirticulate monitors, and iodine monitors, b) Iodines For gaseous iodi_ne, the Reactor Building exhaust ventilation is monitored and recorded on a continuous basis. The 2-inch iodine cartridges used in these monitors are removed from service- after one week of service and quantitatively analyzed on a gamma spectroscopy system. The quantity of radioiodine_ released during that period would be calculated based on the integrated flow during the collection period. c) Particulates As in the case of-iodine discussed in b) above, a 2-inch particulato filter is removed and analyzed each week, Gross-beta analysis .as-well as gamma spectral analyses are perforn:ed to identify and quantify any radionuclides. The quantit/ of any radionuclides on this filter with half-lives greater than eight days would similarly be correlated to total flow during the collection period, d) 1.iquid Effluents All liquid effluent discharged from the site reaches the unrestricted area at the Goosequill Ditch. From that point the effluent can be diverted to the St. Vrain Creet via the St. Vrain Slough, or, more commonly diverted to the Goosequill Pond which is approximately one mile north of the plant site._ Outfall from the Goosequill Pond reaches the South platte River. Both rivers converge approximately
-1 1/2 miles from the plant site. The average stream flow reported in section 5a of this supplemental report is a summation of both rivers and was received and tabulated from data provided by the Colorado Department of Natural Resources in Greeley,_ Colorado.
(9).
I t Liquid effluent is released from the site using both a i continuous and batch mode. The continuous mode-(automatic discharge.rnode) is used on tne Turbine Building Sump l effluent where the only expecteo radionuclide is tritium, f This discharge path utilizes a continuous sampler and an i aliquot of this composite sampler is taken three times per [ week and analyzed for gross-beta, gross-alpha, tritium, and l gamma emitters. Total flow integrators enable us to ; calculate the total activity released via this pathway based ' on composite sample results. Discharge from the Turbine Building Sump is made directly to the unrestricted area with [ no dilution. I The batch release mode is used on the Reactor Building Sump ; effluent -and the liquid waste processing system. The [ Reactor Building Sump area can hold several hundred thousand i gallons of waste water from various sources which could be I' contaminated. The liquid waste system consists of 2-2000 gallon receivers, 1-2000__ gallon monitoring tank, and associated filters and demineralizers. This system is designed to collect and process contaminated waste water i resulting from reactor and laboratory operations, i
?
Prior to each liquid batch release duplicate samples are f quantitatively analyzed for their radioactive- constituents. l These analyses include gross-beta, gross-alpha, tritium, and { gamma spectral analyses. The results of these analyses, and ! other analyses as dictated by the gross-beta results, are j used to determine the maximum release rate from the site. > The liquid effluent, nortrally released at or less than 60 i gallons per minute, is diluted with cooling tower blowdown, ; which runs at or more than 1100 gallons per minute, The : resulting mixture is sampled during the release period to [ confirm compliance with regulatory limits, , i The liquid effluent from the batch release mode is monitored i continuously by redundant gamma activity monitors. : All tank level indicating devices, flow monitoring and i recording _ devices, and radiation monitoring equipment are ; calibrated and maintained at -scheduled intervals in accordance with established procedures. l t Composite samples from batch releases and continuous ! releases are analyzed quarterly for Sr-89 and Sr-90. ! Composite samples from batch releases from the liquid waste ! processing system are analyzed quarterly ior S-35. All i sample results are conservatively decay-corrected to the ! start of the composite period. ' (10) , , - _ , _ _ _a,_ _ _ _ . _ __ . _ . _ . , _ _ , _ _ , , . . . .__,..ua -
e) Overall Er_rors The overall error associated with ' determining the total activity celeased from the site for both gaseous and liquid effluent is estimated to be 17.3 percent. This value is the square root of the sum of squares of counting statistics and associated calibration errors, sampling errors, and tank volume estimates, each considered to be plus or minus 10 percent.
- 5. Batch __ Releases a) Liquid l l l Number of Batch Releases 1 51 l
" Total Time PE Hod for l l Batch Releases j 2.60E+02 HOURS J.
I Maximum Time Period I f or la Batch Release 1.53E+01 HOURS l Average Time 7eriod for la_ Batch'Rel_ ease I __ 5.10E+00 -HOURS ! IMinimum Time Period for l La Batch Release l 1.50E-01 HOURS IXverage stream FT5 a uring l l Periods of Release.of I l l Effluent-into a Flowing j jStrcam __ l 1.46E+05 GPM*
- Gallons Per Mint.te b) Gaseous i i !
JNumber of Batch Releases
- L 37 [
IT5tal Time PeriodTo~r l l JBatchRelease 1 1,08E+02
~
HOURS j' liaximum Time Perioffor l l 1 Batch Release 1 4.75E+00 HOURS I l i l (Average j 2.93E+00 HOURS j. i l l l Minimum i 1.92E+00 HOURS I
- 6. Abnormal Releases a) _ Liquid I .
I l
-JNumberofRelea_ses 1 1 I I I JTotal Activity Released 1 N/A CURIES I (11) m
b) Gaseous
! I l l
, Nu.mber of Releases : Total Activity Released. . N/A. CURIES J t
6 [ T p 4 i (12)
-+e***y +-p- .q rwwsmg-uu'7"?**"a.T*"W-vv'*M'N3-S-="*:8D-M-C S*g-m e t'y*'-'W'TM--t- Y "PEM M4 W9""'F"'P"' "'vT-* "*MF-7"h
TABLE 1A ! EFFt.UENT AND OASTE DISPOSAL SEMIANNUAL REPORT (1991) t GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES e [
~
l Unit l Quarter l ~ Quarter l Est. T'otal ! [ l 1 l 2 l Error. % l !
- l. .l. - l_ l !
1 A. Fission and activation products l
- 1. None detected l B. Iodine'
- 1. Total iodine-131 l C1 l <1.7Bf;DF l <EWf!DFj 1. 71U6f~'l l l \ I
- 2. Average release rate for lECi/seclTf3DFDTl l I <236FUTI j period l l l l L l l l
- 3. Percent of technical 4 l l l l specificatio1 limit -l _l l !
l_ C. Particulates l i
- 1. Particulates with half-lives
> 8 days l71 < [f9F 67 l <1.f6E!D? l 1,71FDl-l ,
l l l l l
- 2. Average release rate for lZi/sec W6TF581 U 47FDrl f period l l l l ;
I l' l l [*
- 3. Percent'of technical l % l l l specification limit l l l l !
I I
- 4. Gross alpha' radioactivity l71 l <2.86FDrlI7237FliflI -
l l l l [ i D. Tritium
- 1. Total release 17T l 2.89E-02 l THF02 l 1.73E+01 l :
I i i I I
- 2. Average release rate for l21/ seclTfFoT)l 3.9!i[ TOT l~ j period l l l l ;
I l l l
- 3. Percent of tech, spec. l % l 6.2DFDTl 6,6fFUfl !
limit l l l_ l [ i. I l l j l (13) 1
TABLE 10 f i
, EFFLUENTANDWASTEDISPOSALSEMIANNUALREPORT(1991)
GASEOUS EFFLUENTS--GROUND-LEVEL RELEASE CONTINUOUS MODE DATCH MODE' lheleased i Unit l l l Quarter 1 I Quarter Tl I l- I L_ l l l Fission gases , l kryptoa-8F l Ci l l l <7.8Tif-l)1 l <8 MF6T) . l l 1 l l 1 i l krypton-Em l CT l l I I l l ~ l l~ l l Ikrypton 57 -l C1 l l c6.25E-03 IlTGliF6TI ! l ~ l i l !
-lIrypton-88 l~~Ci~l l l l<9.9.E!6TI<1J6F0T. i i l i l l I I i lxenon-133 l Ci l l l <8J!if-13 l <9.31E-03 l i I l l I I f
-l xenon-1E- I~tT il-l l l <2.62E-0 Tl7f76E-03 l l E I I I i 1 lxenon-135m l Ci i l l l l 1 1 I I I I f lxenon-138 l C i~l I l I <3 HFUTl7B7FDrl ;
I l l l 1 I i lxenon-133m l~CT 1 l l l <2.24F0TI <2.37st-02 l l: l- I I l__ I i lxenon-131m l _.t i I l- 1 l l l l 1 l argon-41 1 11 I I~ I I l 1 l l- l l l 'l ! l I l - l- 1 l ! I ITotal for period
- l Ci l l l 1
I j l 1 I I I I I i t i lodine 5-liodine-131 l Ci l l l <1.44E-10 l <1.52FIFl ! I I i _. l . I --- I I l l1odine-133 i C1 l l l l l l l 1 I I I l 1 l iodine-135 I Ci l l l l l-l I I I l- 1 ITotal for period * - l CT Il l l l 1
'l- l l l 1 l- I 3 I
I i
- Total values do not include "<" data !
(14) !
. - ..... _...,~_,-_..._,. _.,_ _ ...._,__ -.,_ __,. _,_....,_ __.___._.. .- ~ -..,-_ .-_,. __._,-
i ,. . l I TABLE 10(Continued) CONTINVOUS MODE BATCH MODE i l Released j Unit l l l Quarter FT~ Quarter 2 I l l l 1- I- __ l .__._ - _. l l Particulates l strontium-89 l Ci l l l l l 1 l ~l l- l ! lstrcntium-90 I ~tT~j l' l l l l l l l -l liesium-114 l l~tT~~l l l l <1MFID~lTEDTEITO l l 1 - l l l ll l cesium-ID l Ci l l l <1.6fFirl71~7it l T6'l l 4- l ~I I I I ,' l barium-lanthanum-14b 1~CT l lI l l l l
- I I i ! 1 I- l l
l } I l l-i
- Total values do not include '!<" data l (15)
L _. ._.
4 4 TABLE 2A l, EFFLUENT AND tfASTE DISPO5AL SEMIANNUAL REPORT (1991) ! LIQUID EFFLUENT-SUMMATION OF ALL RELEASES i
~
l Iiu~cTide i Units l Quarter j Quarter l Est. Tota ri ! l- l l 1 1 2 l Error. % i ! l _. I l- l l l [ A. Fission and activation products ! I
- 1. Total release Irsi-T37 i Ci l l 4.si1 fur l f.73E751 1 !
I I I I I -_ I !
- 2. Average diluted luCT7iWl l 93iDFfri l concentration l l l 1 ;
I I I !
- 3. Percent of-applicable _ limit l
. I I T 5Dt-06 I l l l l l l 'i I
- 1. Total release lCo-6(F l C1 l l 6.90ET US I 1.73E+01 l [
l 'i ' I I l-
- 2 . -- Average diluted - lZi7 intl ~I i 1.2EE IF l !
concentration l l l l I I I I i
- 3. Percent of - I % l I ~T258-~0TI-l !
applicable limit l l l l [
- 8. Tritium- !
i
- 1. Total release ITF3' I C1 1 4.T6t+00 l <4 3E 02 I 1.73E+01 i i l I l I
- 2. Average diluted luci/ml I T 7TE~6F I <7Jir-Nil ,
concentration l l l l ! l 1 !
- 3. Percent of l % ll2~79F61-l 1 l !
applicable limit l l l l ! I C. Gross alpha radioactivity }
~~ !
- 1. Total release l Ci l<4.25E 66 l <f 6W-05 l 1.73E+0T 1 !
l l _.- 1 I I ! 1
' O. Volume of waste released i (priortodilution) l Liters l 4.5360Tl 3.89Ei66~l 1. 06F0T-~~ l i l l I .l - -l j E. Volume of dilution water ~
I used during release l Liters l 5.40E408 ll 5.46E+08_l 1.05Cidi ;l ! I __ l I L- I i I 4 4
~
(16) { i - - . . . _ _ , .__,..a___-.,_,___,-._-.._,..._. . _ . . . . . _ . . _ , . - _ _ _ - . _ , . . - _ . _ _ _ _ _ . . . _ . _ _ _; _ . _ _ . . . _ . . _ , .'
j
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TABLE 2B l
, EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT (1991)
L10U10 EFFLUENTS ' I CONTINUOUS MODE BATCH MODE i i INuclides Released i Unit l Quarter 1 l Quarter T~l Quarter 1 I Quat *ter 2 I ! I I 1 I I I i I strontium-89 I~C1 ITDi4F6FI <1.09FFITf.T6f~6Fl73~0'8E-06 I l l l I I I I I ( I strontium-9D l Ci 175~III~0Tl7EdTF0TI <1.68E 0 FIT 1717F6FI l l- l 1 I I I - l cesium-134 I ci l71.21F0Tl <1.1TF0Tl <4.06E-0Fl' <2.61E-05{ 1 l l I I I I I : I cesium-137 l Ci l <1.19E-OFI <1.1TF0TITD6t~6FITf ffiF0TI l l 1~ I I I I iodine-T31 ll CF-lI <959E-0Fl <T13F0T1 73~.Y4F6T172~0Vt~6Fl ' I I I I I I I I cobalt-58 I Ct I <1.1FE-04 l <1.07E-04 l <3. FEE-05 l <2JfFOTI ! I I I I I I I t I cobalt-60 i C1 1 <1.24Fbrl' <1.TSFWI TG E~6FI <9.IIFdri 6 ! I tron-51 I I I I I- I i I l Ci I T 2.04F6FI <1.89t-04 I <6.67FWl <4: 29tr0FI i l i I I I I I l zinc-63 1- C1 ITi~71F6FI T 23Tt76FI <8.87F0FI (5.70E-0FI ; I " I I ~I I l l ; I manganese-50 I Ci ! <1.06E-04 l <9.86'E35~l <3.4ifF0FI <1.94Fdri 1 l I I I I I 1~tIl '~ ! I chromium-5T~ l l l I I : l l l ___._l l l l ! I zirconium-niobium-95 1 Ci l l l l l ! l' I I I I i I~~Ci~~IT7]E-04 l' (6.91E-04 1 <2.4EF6fl <1.55F0',
~
l molybdenum-99 l l l._ l I _ l' I l_. I ; I technetium-99m _ I ci j I I l .! I I I I I ! l l barium-lanthanum-140 1 Ci l [ l l l : I - l l l ! l- cerium-141 l C1 1 <1.73E-04 1l7 1 - 76dF04 1 l75T65E-0Fl f <3.64F6FI : I - L._ l 1. I I I i
- 1. trittum l Ci I <1.49E!03 l <1T3tF631 237FdfI Cf3F0TI I I I I I I l- I !
sulfur-35 I I ci 17 C19E-04 l <6.91E-04 1 72.59E-04 l <1.6TL-04 I -
- f. l- I l -. 1 l i I t
I _ j i _l Total for period (above)*l Ci i l l 2.97E-02 1 4.13E-02 l [ l I- l 1. I I I i i I i Total values do not include "<" data i (17) ; 5
.--_.-.e,-.c .,~,,.,..c,.2 ~ . _ , - - ,,,,y. ..mm,---, -,-.-. - -
* . l l
l TABLE 2B(Continued)
~ ~
, l xenon I33 l Ci i <3.41[~04 l <3.17t-04 l <1.12E-04 <7,19E W I l~~ l I I~ I i l xenon-135 l Ci I~T972EEWlWJE06Fl <3.02E-0Tl <1.9R-05 l l 1 l l .I I l l J ( I l l
- Total values do not include "<" data l
l (18)
. j TABLE 3 [
_, EFFLUENTANDWASTEDISPOSALSEMIANNUALREPORT(1991) [ SOLIO WASTE AND 1RRA01ATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) ! l 1. Type of waste l Unit ! 6-month l Est. Tota fl l l l Period l Error. % l j l -- l 1 -- 1 I t i l i i I ! l a. Process waste, i.e., I m' I 0.00E+00 l l ! l spent resins, filter l Ci l 0.00E+00 1 0.00E400 l l l sludges, evaporator j l l l l l bottoms, etc. l l l l -{ l_ _ .I _l_ l l ! I I I I I ; l b. Dry active waste i.e., I m8 l 8.10E+00 l l l l_ dry compressible waste, l Ci l 2.24E-01 1 2.00E401 l i l contaminated equip. etc. l. l l l ! L_ l I I I !
) -
I l l l ! l c. Irradiated components, l m' l 1.61E+01 l 2.00E401 l ! I control rods, etc. l - Ci j 5.14E+03 l l l l- I _L l- I ! I I I l l e l d. Other (describe). l m' l 0.00E+00 0.00E400 l l [ l l Ci l l l ; I I l_ l l l
- 2. Estimate of major nuclide composition (by type of waste)
{
!P Type of Waste l1sotopel Content l CIiiies I frror 5 l i l I %_l l 1 [
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- b. Dry active waste I H-3 j ~65.94 1 IMF61 1 2T65tT61 J i i Mn-f4J 0.07 ~f.T6tT64 - ~ l 2T66E+01 1 !
l Fe-$5 l 16.8$j ! 3.78E-02 1 ! 2.0btT61_j;
~ ~
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~CF ST~jl_ 6T230.13 i 1 f.54tT~4 0 l 2.00E+01 l l Fe-59' O 04 1 9T11276'$ 1 2.66t+01 -I CF$~7~ 0.'01 1 2T6 BET 66 1 2T6ifETO'1 I i V23T dl01 1 2Tf7FT66 l 2.002761,_[ l Pu-2411 0.30_l 6.76E-04 1 2.00E+61 _[ ;
[ i (19) , e t
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Page 2 ! TABLE 3(Continued) ! I i i lype of Waste lIsotopelContenti _ Curies Error % 1 ! l L % l I i
- c. Irradiated Compo- l H-3 6.11 3.30EiO2 2T56E401 l l nents
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~ Ni-6MUT74 $TsDET62 1 23bf+01 1 [
- d. Other ! I I l ;
- 3. Solid Waste Disposition
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- ITABILITY CLAII:
TOTAL - ALL CLAIShfE IFEEP - PfE WIND
- DIRECIDN 0.75-3 4-7 B-12 13-10 t?-24 124 TOTAL N 16f.19 174.43 79.E9 37.9? 5.95 9.25 4?8.72 NE 32.81 182.67 50.4? 24.22 2.53 0.09 2?2.72 NE 7.97 88.58 39.95 737 1.09 9.49 154.68 EE 4.77 45.49 43.12 12.62 0.50 0.00 105.48 E 2.01 17.14 2?.2? 8.58 9.59 9.M 57.53 EIE 3.78 15.12 22.92 14.87 1.01 9.06 57.71 IE 5.54 19.69 29.69 14.97 5.04 2.27 59.10 IIE 3.78 13.89 15.92 13.61 8.83 8.32 44.35 I 5.95 16.41 12.63 9.33 6.81 7.31 57.56 IIV 7.39 16.67 13.36 9.65 3.05 0.25 50.28 IW 4.29 23.71 16.E8 2.77 f.92 9.25 48.92 WIV 2.52 24.98 17.17 4.29 0.75 1.01 59.71 V 3.27 17.13 11.37 4.95 1.26 9.25 37.33 W4 2.31 25.98 5.80 5.54 f.77 0.25 41.66 s
NV 29.99 73.02 !?.42 29.42 6.E2 1.01 159.67 PNV f7?.25 161.72 37.61 12.62 4.04 0.25 337.50 TOTAL 454.89 847.45' #49.41 291.79 49.?? 21.44 2915.E3 IIE DURATION 0F CALFJ = 122.?? IFJ. tit'E IN ITABILITY CLAII = 2139.87 HRI. LOIT TIE ALL CLAIIEI = 45.00 P?l. e A.' ]}}