Text

Fort St Vrain Nuclear Station Semiannual Radioactive Effluent Release Rept for Jan-June 1992
	ML20114D153
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/30/1992
From:	Warembourg D; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	P-92271, NUDOCS 9209040214
	Download: ML20114D153 (61)
	v • d • e

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P 0 Bos NO Dower.co mm oMa Fort Gt. Vrain 11uclear Station 16805 WCR 19-1/2, Plattovil10, Colorado 80651 l

August 28, 1992 Fort St. Vrain Unit 11o. 1 P-92271 U.S. 14uclear Regulatory Commission ATT!it Document Control Dosk Washington, D.C.

20555 Docket lio. 50-207 SUIkTECT SE!4I-A1111UAl, RADIOACTIVE EFFLUEliT RELEASE REPORT Gentlement Attached pleaso find the Somi-Annual Radioactivo Effluent Roloaso Report for the Fort St. Vrain 11uclear Station.

This report covers the period January 1,

1992, through June 30, 1992. and in submitted pursuant tc Section 7.5.1.0 of the Fort St.

Vrain Technical Specifications.

Pleano contact Mr.

M.

11. liolmes at (303) 620-1701 if you have questions regarding this report.

Sincere

$'lt W [Oa ikht'lH) byQh%f Don W. Warembourg L

Program Director DWW/TES bj Attachments 10 i

.ena bh}

9209'40214 920630

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DR ADock osooogsy jd 1

PDR

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e cot w/ attachments Regional Administrator, Region IV Mr. J. B. Daird 4

Senior Resident Inspector Fort St. Vrain Dottio St.arman, ANI Library American Nuclear Insurors i

The Exchange, Suito 245 270 Farwington Avenuo Farmington, CT 06032 Mr. Robert Quillin, Director.

Radiation Control Division Colorado Department of Health 4210 East lith Avenue Denvor, CO 80220-3716 Mr. Milt Lammering, Chief Regional Representative,-Radiation Program U.S. Environmental Protection Agency Region VIII 999 18th Stroot, suito 500 Denver, CO 80202-2405 Mr. Farroll D.

Hobbs Environmental Managt,.ont EG & G Building 250, P.O._Dox 464 Golden, CO 80402' Dr. James E. Johnson Department of Radiation Diology MRB Building Colorado State University Fort Collins, CO-80523 l

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SEMI-A1111UAL RADIOACTIVE EFFLUENT

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RELEASE REPORT L

f January - Juno i

1 1992 h

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Nuclear Station August, 1992 1

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SUMMARY

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W This report summarizos radiological effluent released from the Fort St. Vrain Nuclear Generating Station for the period of January through June, 1992.

This information is provided pursuant to the requirements of Sections 7.5.1.0, 8.1. 2. d, e, and j, 8.1. 3. 0 and f,

and 8.2.1.h.1 of the Fort St. Vrain Technical Specifications.

This repor? Uma the reporting format recommended by Regulatcry Guido

1. 2 ?.

4 well as the requiremonts of the aforomontioned occtions of ur Technical Specifacations.

The following tables with a supplemental information section aro included with this report:

Tablo Description IA Gascous Effluents - Summation of All Releases 1C Gaseous Effluents - Ground-Level Roloasos 2A Liquid Effluents - Summation of Al'1 Releases 2B Liquid Effluents-3 Solid Maste and Irradiated Fuel Shipments 4A Ilot.rly Meteord ogical Data Please note that Table 1B (of Regulatory Guido 1.21) has been omitted from this report because all of our gaseous offluents are assumed to be ground-level releases as opposed to being elevated releases.

Fort St. Vrain Technical Specifications apply exclusively to the following radionuclidos Kr-87, Kr-88, Xo-133, Xo-133m, Xo-135, and Xe-138 for gaseous omissions, and Mn-54, Fe-59, Co-58, Co-60, l

Zn-65, Mo-99, Cs-134, Cs-137, Co-141, and Co-144' for particulato emissions.

This list does not mean that only Weso nuclidos are i

considered, other gamma emitting nuclidos that. c identifiable, together with the above nuclides, are analyzed ana included in this report.

Samplo 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 aro_in excess of true activities.

Where limit values aro-a combination of positive-and MDA values, the results are footnoted and differentiated from limit values produced from only HDA values..

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5 The lower limit of detection (LLD),

for the purposes of this report, is defined as the smallest concentration of radioactive material in a sample that will yield a not count above the system background, that will be detected with a 95% probability of being correct and only a 5% probability of falsely concluding that a blank observation represents a real signal.

The-LLD values specified in our Technical Specifications are as follows:

Limlid Principal Gamma Emitters 5.00E-07 pCi/ml Dissolved Noble Gases 1.00E-05 pC1/ml Tritium 1.00E-05 #Ci/ml Iodine-131 1.00E-06 4C1/ml Gross Alpha 1.00E-07 pCi/ml Strontium-89, 90 (Composite) 5.00E-08 #Ci/ml Gaseous Principal Gamma Emitters 1.00E-04 4Ci/cc (Gas)

Principal camma Emitters 1.00E-11 pCi/cc (Particulate)

Tritium (Gas) 1.00E-06 pC1/cc Iodine-131 (Charcoal) 1.00E-12 pCi/cc-Gross-Alpha (Particulate) 1.00E-11 pCi/cc Strontium-89, 90 (Particulate) 1.00E-11 pCi/cc Gross Beta (Particulate) 1.00E-11 #Ci/cc

- Where applicable, we have listed "less than" values for those nuclidos listed specifically in our Technical Specifications.

.These "less than" values were calculated using the observed LLD values and the total volume of the media.

The "less than" values were not included in the total values for the pathway.

5 The percent of Technical Specification limit on Table 1A is blank in some cases because this value could not be calculated from data which were at or below the minimum detectable activity.

On Table IC, the continuous release modo values are not reported because this release pathway is the same as the batch mode.

All other blanks on Tables 1C and 2B occur because no LLD values for these nuclidos are required to be calculated per Technical Specifications.

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 4d of the Supplemental Information-Section.

There were no abnormal or unplanned radioactive gaseous or liquid waste releases made during this reporting period.

j During the NRC inspection on February 18-21, 1992, (G-92084) PSC committed to perform additional calculations regarding tritium released from the Turbine Building Sump (TBS) and report -the results in the next Semi-Annual Effluent Report (G-92084).

The annual amount of tritium released from the TBS from 1985 to 1991 has been calculated and is provided below.-

Data was not available for 1984.

These calculations are based on (1) the average TBS tritium concentration for the year determined through sampling and (2) the volume of liquid effluent discharged from the TBS each year as determined from the TBS sump pump run timers.

v 7

TURBINE BUILDING SUMP TRITIUM DISCllARGES Turbine Bldg Sump Avg H3 Concentration Total 113 Curies Released Year Diccharge from in TBS for Year from-TBS for the Year Pump Timers through Sampling 1985 16,160,697 (Gal) 61,087,436 (L) 1.11E-9 C1/L 0.068 Ci 1986 16,905,516 (Gal) 63,902,850.(L) 2.63E-8 C1/L 1.68 Ci 1987 18,783,579 (Gal) 71,001,928 (L) 1.52E-8 C1/L 1.08 C1 1988 22,457,455 (Gal) 84,889,179 (L) 5.50E-8 Ci/L 4.67 C1 1989 17,142,558 (Gal) 64,798,869 (L) 2.77E-8 C1/L 1.80 C1 1990 12,444,342 (Gal) 47,039,612 ( L) 1.67E-9 C1/L 0.079 C1 1991 5,920,073 (Gal) 22,377,875 (L) 5.21E-10 C1/L 0.012 C1 The amount of tritium calculated above is compared below to the amount of tritium reported in Semi-Annual Effluent Reports to the NRC for each year.

Total Curies of-113

. Total-Curies of 113 Year-

-Reported as Being Released Calculated as Beine from TBS (C1)

Released from TBS (CA) 1985 0.066 0.068 1986 1.30 1.68 1987 1.02 1.08 1988 14.56

-4.67 1989 1.37 1.80 1990 0.049=

0.079 1991 0.011 0.012

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Four (4) shipments of solid wastos-were made during this reporting period.

Only one (1) of those shipments was directly for disposal / burial.

Irradiated compononts included irradiated, non-fuel bearing control rods, control rod drivo assemblies, and region constraint devices.

Dry compressiblo wastos included routino paper and plastic trash, resins, contaminated oquipment and hardware, wood and radioactive check sources.

Technical Specifications require that

"...shall include the following information for each class of solid wasto (as defined by 10CFR Part 61) shipped off site..."

The information below satisfies this requirement for wastos for which waste

- classification is-performed

-(i.e.,

wastos sont directly for disposal and R2t those sont to an offsite vendor for processing).

Accordingly, the activity, volume, and number of shipments will not agroo with information supplied in Table 3 which is prepared in accordanco with Regulatory Guido 1.21.

CLASS A:

None CLASS D:

8 1.

Container Volumo:

125.2 ft.

2.

Total Curio Quantity:

7496.824 Ci (estimated).

3.

Principal Radionuclides (estimated):

H-3, C-14, Mn-54, Fe-55, Co-60, Ni-59, Ni-63, Sr-90, I-129, Cs-134, Cs-137, S-35, Sr-89, and Co-58.

4.

Source of-Wasto and Processing Employed:

Irradiated reactor hardware, no processing.

5.

Type of containor:

Type D.

6.

Solidification Agent or Absorbent:

None.

CLASS C:

Hono, The last two (2) previous reports did not include all information as required by FSV Technical Specifications.

Accordingly, the below corrections are mado.

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- Technical Specifications require that

"...shall include the j

following information for each class of solid waste (an defined by J

10CFR Part 61) shipped off sito..."

The information below i

satisfies this requirement for wastes for which waste classification is performed (i.e.,-

wastes sont directly for disposal and Dat those sont to an offsite vendor for processing).

Accordingly, the activity, volumo, and number of shipments will not agree with information supplied in Table 3 which is prepared in accordance with Regulatory Guide 1.21.

Please note that the l

information in Tablo 3 includos all shipments mado from FSV which includes shipments to off site radioactive waste processors and the j

i below information is for only those shipments mado directly from FSV to a disposal site (i.e.,

no report is made of shipments by j

offsite vendors to disposal sites after wanto proconsing).

For the period of January 1 through June 30, 19911 CLASS A:

None i

1 CLASS D:

8 1.

Container Volume:

125.2 ft.

2.

Total Curie Quantityt 4750.837 C1 (estimated).

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3.

Principal Radionuclides (estimated):

H-3, C-14, Mn-54, Fe-55, Co-60, Ni-59, Ni-63, Sr-90, I-129, F

Cs-134, Cs-137, S-35, Sr-89, and Co-58.

i 4.

Source of Waste and Processing Employed:

Irradiated reactor hardware, no processing.

5.

Type of Containor Typo B.

6.

Solidification Agent or Absorbent:

None.

t CLASS C:

3 1.

Container Volume:

26.2 ft.

2.-

- Total Curie Quantity:

360.19 C1 (estimated).

-3.

Principal Radionuclides (estimated):.

H-3, C-14, Mn-54, Fe-55, Co-60, Ni-59, Ni-63, Sr-90, I-129, Cs-134, Cs-137, S-35, Sr-89, and Co-58.

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Source of Haste and Proconsing Employed:

Irradiated reactor hardware, no-processing.

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Type of Containort Type D.

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Solidification Agent or Absorbent None.

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i For the period of July 1 through December 31, 1991:

I CLASS At Nono CLASS Bt

-1 1.-

Container Volumet 125.2 f t'.

4 2.

Total-Curio Quantity!

2719.872-C1 (estimated).

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3.

Principal Radionuclidos (estimated)t-H-3, C-14, Mn-54,_

Fo-55, Co-60, Ni-59, Ni-63, Sr-90, I-129,-

Cs-134, Cs-137, T-35, Sr-89, and_Co-58.

4.

Source of Waste and Processing Employed:

Irradiated reac.or hardware, no proconsing.

5.

Typo of container Type D.-

6.

Solidification Agent or Absorbent:

None.

CLASS C:

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11 Tabic 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1991)

SOLID WASTE AND IRRADIATED PUEL SHIPMENTS FIRST QUARTER, 1991 A.

SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL 1.

Type of Wasto Unit 6-Month Est.

Period Total Error, %

3 a.

Spont resins, filter m

0.00 E+00 0.00 E4 00 sludges, ovaporator Ci 0.00 E+00 bottoms, etc.

8 b.

Dry compressible wasto, m

2.77 E+00

-2.00 E+01 contaminated equip, etc.

Ci 5.63-E-02 c.

Irradiated components, m

7.42 E-01 2.00 E+01 3

control rods, etc.

Ci 3.60 E+02 d.

Other (describo) m 0.00 E400 0.00 E+00 3

Ci 0.00 E-00

2. Estimato of major nuclido composition (by type of wasto) a.

N/A

-0.0 %-

-0.00 E+00 -

b.

Fo-55 89.1 %

2.00 E+01 Co-60 5.8 %

2.00 E+01 H-3 3.4 %

2.00 E+01 All others

'1.7 %

2.00 E+01 c.

Fe-55 73.3 %

2.00 E+01 Ni-63 10.5 %

2.00 E+01 Co 17.5 %

2.00-E+01-H-3 5.4 %

2.00 E+01 Mn-54 3.3 %

2.00 E+01:

All Others

<0.1%

2.00'E+01 d.

N/A-0.0 %

0.00 E+00

12 3.

Solid Waste Disposition liumber of Mode of Destination Shipmento Trannportation 1

Public liighway RAMP Industries Denver, CO

{

1 Public liighway Barnwell Waste Management Darnwel1, SC D.

IRRADIATED TUEL S!!IPMEllTS (Dicposition) liumber of Mode of Destination Shipments Transportation

-o-5

13 Tilhle 3 EFFLUEllT AllD WASTE DISPOSAL SEMI-AliliUAL REPORT (1991)

SOLID WASTE AllD IRRADIATED FUEL SilIPME!1TS SECO!10 QUARTER, 1991 A.

SOLID WASTE SillPPED OFF-SITE FOR BURIAL OR DISPOSAL 1.

Type of Wasto Unit 6-Month Est.

Period Total Error, %

j a.

Spont resins, filter m

0.00 E400 0.00 E+00 3

sludges, ovaporator Ci 0.00 E400 bottoms, etc.

b.

Dry compressible wasto, m

5.32 E+00 2.00 E+01 8

contaminated equip, etc.

C1 1.68 E-01 Irradiated components, m

1.54 E401 2.00 E+01 3

c.

control rods, etc.

C1 4.78 E+03 d.

Other (describo) m 0.00 E+00 0.00 E+00 Ci 0.00 E-00 l

2. Estimate of major nuclido composition (by type of vaste) a.

11/A 0.0 %

0.00 E+00 b.

Fe-' 5 5 89.1 %

2.00 E+01 Co-60 5.8 %

2.00 E+01 11 - 3 3.4 %

2.00 E+01 All others 1.7 %

2.00 E+01 c.

Fo-55 73.3 %

2.00 E+01 Ni-63 10.5 %

2.00 E+01 Co-60 7.5 %

2.00 E+01 H-3 5.4 %

2.00 E+01 Mn-54 3.3 %

2.00 E+01 All Others

<0.1%

2.00 E+01 d.

N/A 0.0 %

0.00 E+00

14 3.

Solid Waste Disposition Number of Modo of Destination Shipments Transportation 1

Public liighway U.S.

Ecology Boatty, NV 2

Public liighway Quadrox Recycle Contor Oak Ridge, TN 2

Public Highway RAMP Industries, Inc.-

Denver, CO l

B.

IRRADIATED PUEL SilIPMENTS (Disposition)

Number of Modolof-Destination Shipments

-Transportation !

3 l

o

15 Table 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANPUAL REPORT (1991)

SOLID WASTE AND IRRADIATED FUEL SilIPMENTS TilIRD QUARTER, 1991 A. SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR~ DISPOSAL 1.

Type of Wasto Unit 6-Month Est.

Period Total Error, %

3 a.

Spent rosins, filter m

0.00 E+00 0.00 E+00 sludges, ovaporator C1.

0.00 E+00 bottoms, etc.

m 2.55 E+00 2.00 E+01 8

b.

Dry compressible wasto, contaminated equip, etc.

Ci 1.11 E-02 c.

Irradiated components, 1n 1.77 E+01 2.00 E+01 8

control rods, etc.

ci:

3.59 E+01 d.

Other (describo) m 0.00 E+00 0.00 E+00 8

i 0.00 E-00

2. Estinate of major nuclido composition (by type of wasto) a.

N/A 0.0 %

0.00 E+00 b.

Fe-55 89.1 %

2.00 E+01 Co-60 5.8 %

2.00 E+01-11 - 3

_, 3.4 %

2.00 E+01 All others 1.7 %,

2.00 E+01 c.

Fa-55

-73.3 %

2.00 E+01 Ni-63 10.5 %

2.00 E+01 Co-60 7.5 %

2.00 E+01 H-3 5.4 %

2.00 E+01 Mn-54 3.3 %

2.00 E+01 All others-

<0.1%

2.00 E+01 d.

N/A

0. 0' % -

0.00 E+00

i 16

- t 3.

Solid Waste Disposition f

t i

Humber of Modo of Destination Shipments Transportation l

Public Highway RAMP Industries 1

Denver, CO I

1 Public Highway Quadrox Recyclo contor oak Ridge, TN D.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of-Modo of Destination Shipments Transportation 0-i I

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I 17 Table 3 I

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1991)

SOLID WASTE AND IRRADIATED TUEL S!!IPMENTS FOURTil QUARTER, 1991 A. SOLID WASTE SilIPPED OFF-SITE FOR BURIAL OR DISPOSAL 1.

Type of Wasto Unit 6-Month Est.

Period-Total Error, %

a.

Spent resins, filter m

0.00 E+00 0.00 E+00 8

aludges, ovaporator Ci 0.00 E+00-bottoms, etc.

b.

Dry compressible Wasto, m

1.94 E+01 2.00 E+01 8

contaminated equip, etc.

C1 1.48 E-01 c.

Irradiated components, m

-3.55 E+00 2.00 E+01 8

control-rods, otc.

Ci 2.92 E+03 d.

Other (doacribe) m 0.00 E+00 0.00 E+00.

8 Ci 0.00 E-00 j

Estimato of major nuclido composition (by type of wasto) 2.

a.

N/A 0.0 %-

0.00 E+00 b.

Fe-55 89.1 %

2.0^ E+01 Co-60 5.8 %

2.0i,E+01 H-3 3.4 %

2.00 E+01

{

All others 1.7 %

2.00 E+01 c.

Fo-55 73.3 %

2.00 E+01-Ni-63 10.5 %

2.00 E+01 Co-60 7.5 %-

2.00 E+01' H-3 5.4 %~

2.00 E+01-Mn-54 3.3 %

2.00 E+01 All Others

<0.1%

2.00 E+01 d.

N/A 0.0 %

0.00 E+00

m 18 3.

Solid Wasto Disposition Number of Mode of Destination Shipments Transportation 1

Public Highway I

U.S. Ecology Deatty, NV, 7

Public Highway RAMP Ind u 1,

Inc.

l Denver, CO D.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of Destination Shipments Transportation 3

Public Highway INEL Scovillo,-ID There have boon no major design changes to the_ radioactive wasto systems reviewed by the Plant Operations Roview. Committoo _ (PORC) during the period covered by this report.

There were no changos to the Process Control Program (SUSMAP-3),

Issue 2, offectivo dato November 13, 1984, during this reporting period.

Issuo 19 of the Offsite Doso Calculation Manual (SUSMAP-2) was reviewed by the Plant Operations Review Committoo (PORC) on April 2,

1992 and became offectivo-April 22, 1992.

This issue perinanently incorporated the changes from PDR's 91-0200 and 91-0206 which woro described in the previous semi-annual offluent report, P-92061, covering the period fron July 1, 1991, through December 31,.1991.

On August 14,

1989, Amendment No.

71 to the FSV Technical Specifications became offective which revised ELCO-8.1.1.g, doloting-the requirement to report gaseous offluent activity monitbra or flow instruments - inoperable over thirty days in the Semi-Annual- ' Effluent Report.

The reporting requirements were changed to require a Special Roport if less-than the minimum required gaseous offluent activity monitors are operable for over sovon days.. It has not boon necessary to issue-any_such Special Reports since the requiremont became offectivo.

Thero were no liquid effluent activity monitors or their associated recorders inoperable for more than thirty days during this reporting period.

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.i 19 l

i Effluent and Waste Disnosal Semi-Annupl RenrIt j

SMpplemental Informatiot) f i

Facility:

Fort St. Vrain Nuclear Generatina Stat.ign t

Licensool Public Servico Company of Colorado i

i 1.

Reaulatary Limits All results of radioactivity analysou of gaseous and liquid offluent are used in accordanco with the methodology and paramotors listed in the Offsite Doso Calculation Manual (SOJMAP-2) to assure that the concentrations at the point of release are maintained within the limits set forth in the Technical Specifications.

Thoso limits will-ensure the quantity of radioactivo offluent released from the plant is maintained as low as reasonably achievable and in any event,

[

within the limits of 10CPR20 and in accordance with 10CFR50.

l The air doso due to noble gases released in gaseous offluent at the unrestricted area is limited to:

l a) 5 millirads gamma and 10 millirads beta during any I

calendar quarter, and, b) 10 millirads gamma and 20 millirads bota during any calendar year.

The dose to a member of the public due to I-131, tritium, and radioactivo particulates with half-livos longer than eight days in gaseous effluents will be limited to:

a) 7.5 millirems to any organ during any calendar quarter, and, b) 15 milliremo to any organ during any calendar year.

1 The dose rato due to radioactive gaseous effluent istlimited

~

[

to-the followings a)

For noble

gases, less than-or equal to 500 millirems por year to tho-total-body and less than or equal to 3000 millirems.por, year to the-skin,

and, I

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3_,,

20 b)

For 1-131, tritium, and radioactivo particulates with half-lives greater than eight days, loss than or equal to 1500 milliroms por year to any organ.

The dono or doso commitmont to a member of the public from radioactivo materials in liquid offluents released to Mr.costricted aroas is limited as follows:

a)

During any calendar quartor to loss than or_ equal to 1.5 millirems to the total body and to loca than or equal to 5 millirems to any organ, and, b)

During any calendar year to loss than or equal to 3 millirems. to the total body and to loss than or equal to 10 millirems to any organ.

2.

Maximum Permissiblo Concentrations (MPC's)

All MPC's used in determining allowable roloaso rates from tho-gas and liquid wasto systems are those listed in Tablo II, Columns 1 and 2 respectively, of Appendix B to 10CFR20.

In

addition, for the MPC of dissolved noble gases in liquid of fluent, the value of 2.00E-04 microcuries por milliliter was used.

For the purposes of calculating allowable release rates, the MPC for halogons and particulatos with half-lives longer than eight days are reduced by a factor of 700 from their listed value in Tablo II, Column 1, of Appendix B to-10CFR20.

3.

byerano Enoray The average energy (E-Bar) of the radionuclido mixture in releases of fission and activation gases is not calculated or used at_this facility.

4.

Measurements and Apurgxitnations of Total Radioactivity a)

Fission and Aptivation Gases Batch releases from tho gas waste holdup system are performed af ter sampling and analysos for noble gases and tritium.

These analytical results are used (along with atmospheric dilution factors) to _determino the allowable release rato.- _The gas is then released-on a~ continuous basis through a gas wasto header which is monitored by a -

noble gas monitor _ and an iodino_ monitor.

In the ovent of-high activity in the continutos release, heador control functions are initiated which divert the gas back-to the-gas wasto holdup system.

A

-21 All radioactive gases are released to the Reactor Building oxhaust ventilation system which has a flow rate of approximately 20,000 cubic foot per minute. The full-flow of this exhaust is directed through high officiency 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 noblo gas monitors, particulato monitors, and iodino

monitors, b)

LQIllDEQ For gaseous

iodino, the Reactor Duilding exhaust ventilation is monitored and recorded on a continuous basis.

The 2-inch iodino cartridges used in those monitors are removed from corvico after one week of service and quantitatively analyzed on a

gamma spectroscopy system.

The quantity of radiciodino released during the porlod is calculated based on the integrated flow during the collection period.

c)

Particulates As in the caso of iodine, discussed in b) above, a 2-inch particulate filter is removed and analyzed cach week.

Gross beta analysis,- as well as gamma spectral analyses, is performed to identify and quantify any radionuclides.

The quantity of any radionuclides on this filter with half-lives greator than eight days is similarly correlated _to total flow during the collection period.

d)

Liquid Effluents All liquid offluent discharged from the site reaches the unrestricted area at the Goosequill Ditch.

From that point, the affluent can be diverted to the St. Vrain Creek 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 approximatnly 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, l

Liquid offluent in released from the sito us o'

continuous and batch modo.

The contin

/

(automatic dischargo mode) is used on th wk Building Sump offluent wheru the only aed radionuclido is tritium.

This dischargo path utin.os a-continuous sampler and an aliquot of this cr>mposito sampler is taken three timos per wook and analyzed for gross bota, gross alpha, tritium, and gamma emitters.

Calculations utilizing pump run timers and -measured dischargo rates 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.

The batch releano mode is used on the Roactor Building Sump offluent and the liquid wasto system.- The Reactor Building Sump area can hold several hundred thousand gallons of waste-water from various sources which could

- be contaminated. The liquid wasto system consists of two 2000 gallon receivers, one 2000 gallon monitoring tank, and associated filters and demineralizers.

This system is designed to collect and process contaminated waste water resulting from reactor and laboratory operations.

Prior to each liquid batch release, duplicate sam?los are quantitatively analyzed for their.

rad:.oactive constituents.

These analyses include gross beta, gross alpha, tritium, and gamma spectral analyses. The results of those analyses, and other analyses as dictated by the gross beta results, are used to determino the maximum release rato from the sito.

The liquid offluent, normally released at or less than 60 gallons per minuto,.

is diluted with cooling tower blowdown which runs at or more than 1100 gallons por minute. The resulting mixture is sampled during the release period to confirm compliance with regulatory limits.

The liquid effluent from the batch roloaso modo is monitored continuously by redundant gamma activity monitors.

All tank level indicating devices, flow monitoring and recording devices, and radiation monitoring equipment are calibrated and maintained. at scheduled. intervals in accordance with established procedures.

l l

23 Composito samples from batch rolenses and continuous releaso-are analyzed quarterly for Sr-89 and Sr-90.

All samplo results are conservatively decay-corrected to the start of the composito period.

Sulfur-35 analysis was discontinued beginning with Quarter 1.

The reactor has been shut down sinco 1989 and any sulfur produced prior to that timo has undergono a decay of over 12 halflives.

lio positivo S-35 results have been observed since the fourth quarter of 1989.

o)

O V e r a U __.E r I pf ji The overall error associated with determining the total activity released from the site for both gaseous and 11guld offluent 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.

liittsll_Ro_lsnen a)

Idquid 11 umber of Datch Rolenses 42 Total Time Period for Batch Releases 2.34E+02 IlOURS Maximum Time Period for

_ a Datch Releaso 9.03E+01 liOURS Avorago Timo Period for a Batch Releaso 5.58E+00 llOURS Minimum Timo Period for a Batch Release 1.62E+00 llOURS Averag-Stream Flow During Periods of Release of Effluent into a Flowing Stream 1.74E+0S GPM*

Gallons Per Minuto

24 b)

Gaseoug llumber of Batch Rolcanes 23 Total Time Period for Batch Release 6.16E+01 IlOURS Maximum Timo Period for Batch Roleaso 4.13E+00 IIOURS Average 2.68E+00

!!OURS Minimum 1.75E+00 llOURS 6.

Abnormal Releases a)

Liquigl Number of Releases Total Activity Released N/A CURIES b)

Enceous Number of Releases Total Activity Released N/A CURIES

25 TABLE 1A EFFLUEliT A11D WASTE DISPOSAL SEMI-A!114UAL REPORT (1992)

GASEOUS EFFLUEllT - SUMMATIOli OF ALL RELEASES a...

Estimated Unit Quarter Quarter Total 1

2 Error

=

A.

Fission and activation gates 1.

lione detected B.

Iodinc 1.

Total iodine-131 C1

<3.53E-06

<3.53E-06 1.73E401 2.

Average release rato Ci/sec

<4.49E-07

<4.49E-07 for period 3.

Percent of Technical Specification Limit C.

Particulates 1.

Particulates with Ci

<1.18E-07

<1.30E-07 1./3E+01 half-lives >8 days 2.

Average release rato Ci/sec

<1.50E-08

<1.66E-08 for period 3.

Percent of Technical Specification Limit 3.

Gross alpha

<2.?uE-08

<3.00E-08 radioactivity R

26 TABLE 1A (Continued)

Estimated Unit Quarter Quarter Total 1

2 Error D.

Tritium

1. Total Release C1 1.83E-02 1.44E-02 1.73E+01 2.

Average release rate C1/sec 2.33E-03 1.83E-03 for period 3.

Porcent of Technical 3.88E-05 3.05E-05 Specification Limit C

6

_~

27 TABLE 1C EFFLUENT Al4D WASTE DISPOSAL SE!41-A1111UAL REPORT (1992)

GASEOUS EFFLUEliTS -- GROUl4D-LEVEL RELEASE CollTIliUOUS MODE BATCil 140DE 11uclides Released Unit Quarter 1 Quarter 2 1.

Fission Gases krypton-85 Ci

<6.94E-01

<8.79E-01 krypton-85m Ci krypton-87 Ci

<5.28E-03

<6.69E-03 krypton-88 Ci

<6.64E-03

<8.41E-03 1

xenon-133 C1

<6.79E-03

<8.60E-04 xenon-135 Ci

<1.82E-03

<2.31E-04 xenon-135m Ci xenon-138 Ci

<3.31E-02

<3.81E-02 xenon-133m Ci

<1.69E-02

<2.13E-02 xenon-131m Ci argon-41 Ci Total for period **

Ci Iodines iodine-131 Ci

<1.59E-10

<2.02E-10 iodine-133 Ci iodino-135 Ci Total for Period **

- Total values do not include "<" data.

28 TABLE 1C (Crntinued)

CO!1TIliUOUS 140DE DATCll 140DE pe-l Iluclidos Released Unit Quarter 1 Quarter 2 Particulates strontium-89 Ci strontium-90 C1 cosium-134 Ci y{1. 67E-10

<2.11E-10 conium-137 Ci

<1.80E-10

<2.27E-10 barium-lanthanum-140 Ci i

h

29 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1992)

LIQUID EFFLUENT - SUMMATION OF ALL RELEASES Est.

Units

-Qtr 1 Qtr 2

-Total Error A.

Fission and Activation Products

_-u

1. Total Release.

l Ci-3.39E-OS*

6.88E-05*

1.73E+01 2.

Average diluted'

Ci/ml 6.21E-11 1.26E-10 concentration 3.

% of Applicable 2.07E-04 4.20E-04

?

Limit i

1 B.

Tritium 1

?D'

1. Total Release C1 2.72E+00*

1.20E+00*

1.73E+01

2. Average diluted-pCi/ml 4.99E-06 2.20E-06 concentration 3.

% of Applicable 1.66E-01 7.33E-02 Limit o combination of analysis results of less than MDA values and. positive values.

J

30 TABLE 2A (Continued)

Est.

Units Qtr 1 Qtr 2 Total Error i

C.

Gross Alpha Radioactivity.

1. Total Release C1 1.54E-05*

6.58E-06*

1.73E+01 D.

Volume-of Waste Released prior.to dilution Liters 6.87E+06 6.34E+06 1.00E+01 E.

Volume of Dilution Water Used-During Release Liters S.46E+08 5.46E+08 1.00E+01 Combination of analysis results of less than MDA values and positive values.

I.........

--A

4 31 1

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1992)

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released st{ontium-89 Ci

<3.91E-05

<2.22E-05

<3.63E-06

<3.82E-06 strontium-90 Ci

<1.19E <8.94E-06

<1.09E-06

<1.54E-06 cosium-134 Ci

<3.64E-04

<3.09E-04

<2.57E-05

<5.05E-05 cesium-137 ri

<3.84E-04

<3.27E-04

<2.72E-05

<5.35E-05 iodine-131 Ci

<2.81E-04

<2.39E-04

<1.99E 05

<3.90E-05

.i 3

Ci

<3.49E-04

<2'.97E-04

<2.47E-05

<4.86E-05 co' A

Ci

<4.84E-04

<4.12E-04 3.39E-05*

6.88E-05*

j Ci

<7.82E-04

<6.65E-04

<5.53E-05

<1.09E-04 Ci

<8.78E-04

<7.47E-04

<6.22E-05

<1.22E-04 I

(

,e-54 Ci

<3.67E-04

<3.12E-04

<2.59E-05

<5.10E-05 chromium-51 Ci 2

zirconium-Ci niobium-95 molybdenum-99 Ci

<2.49E-03

<2.12E-03

<1.77E-04

<3.47E-04 technetium-99m Ci barium-Ci lanthanuia-14 0 cerium-141 Ci

<4.65E-04

<3.95E-04

<3.29E-05

<6.46E-05 tritium C1 2.53E-03*

2.21E-03*

2.72E+00

'1.20E+00 Total for period Ci 2.53E-03*

2.21E-03*

2.72E+00 1.20E+00 (above) o Combination of analysis results of less than MDA value s. and pos:.tive values.

9---

32-TABLE 2B (Oontinued)

CONTINUOU3 MODE BATCH MODE Nuclides Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Released a

xenon-133 Ci

<7.89E-04

<6.70E-04

<5.58E-05

<1.10E '

xenon-135 Ci

<2.48E-04

<2.11E-04

<1.76E-05

<3.46E-05 l

l 1

i 1

J b

4 W

33 Table 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1992)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FIRST QUARTER, 1992 A.

SOLID WASTE SHIPPED OFF-SITE FOR BURIAL OR DISPOSAL i

1 4

1.

Type of Waste Unit 6-Month Est.

1 Period Total Error, %

3 a.

Spent resins, filter m

0.00 E+00 0.00 E+00 sludges, evaporator Ci 0.00 E+00 i

bottoms, etc.

~

b.

Dry compressible waste, m

1.12 E+02 2.00 E+01 f

3 contaminated equip, etc.

Ci 3.36 E-01 l

8 c.

Irradiated components, m

1.18 E+01 2.00 E+01 1

control rods, etc.

C1 2.50 E+01 1

3 d.

Other (describe) m 1.91 E+00 0.00 E+00 Contaminated Oil C1 2.66 E-02 n

2.

Estimate of major nuclide composition (by type of waste)

I a.

N/A 0.0 %

0.00 E+00 i

b.

Fe-55 89.1 %

2.00 E+01 l'

Co-60 5.8 %

2.00 E+01 i

H-3 3.4 %

2.00 E+01 All others 1.7 %

2.00 E+01 c.

Fe-55 73.3'%

2.00 E+01 i

Ni-63 10.5 %

2.00 E+01-Co-60 7.5 %

2.00 E+01 H-3 5.4 %

2.00 E+01 I

Mn-54 3.3 %

2.00 E*01 i

All others

<0.1 %

2.00 E+01 d.

N/A 0.0 %

0.00 E+00 1

i l

34 3.

Sol.id Waste Disposition Number of Shipments Mode of Transportation Destination 3

Public Highway RAMP Industriec Denver, CO 4

Public Highway Quadrex Recycle Center Oak Ridge, TN B.

IRRADIATED FUEL SIIIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination < =, a-O b

N

>V fa:,'

~-

A 35 Table 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1992)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND QUARTER, 1992 A. SOLID WASTE SilIPPED OFF-SITE FOR BURIAL OR DISPOSAL 1.

Type of Waste Unit 6-Month Est.

Period Total Error, %

a.

Spent resins, filter m

0.00 '

O 0.00-E+00 3

sludges, evaporator Ci 0.00 t+00 bottoms, etc.

b.

Dry compressible waste, m'

0.00 E+00 0.00 E+00 3

contaminated equip, etc.

Ci 0.00 E+00 c.

Irradiated components, m

2.13 E+01 2.00 E+01 8

control rods, etc.

Ci 7.54 E+03 d.

Other (describe) m 0.00 E+00 0.00 E+00 3

Ci 0.00 E-02

2. Estimate of major nuclide composition (by type of waste)

]

a.

N/A 0.0 %

0.00 E+00 b.

N/A 0.04, 0.00 E+00 c.

Fe-55 73.3 %

2.00 E+01 Ni-63 10.5 %

2.00 E+01 Co-60 7.5 %

2.00 E+01 H-3 5.4 %

2.00 E+01 Mn-54 3.3 %

2.00-E+01 All others

<0.1 %

2.00 E+01 d.

N/A 0.0 %

0.0,0 E+00

J l

36 i.

3.

Solid Waste Disposition Number of Shipments Mode of Transportation-Destination 1

Public Highway U.S.

Ecology 4

Beatty, NV 3

Public Highway Quadrex Recycle Center Oak Ridge, TN

],

B.

IRRADIATED FUEL SHIPMENTS (Disposition) 1 Number of Shipments Mode of Transportation Destination 4

4 s

2 -

[

4 4

4 i

-..... -. ~.. -..-. -... - - -..

.,= ~..

N s

- 37'-

d I

1.

1 TABLE 4A HOURLY METEOROLOGICAL DATA a

T -

e 4

4 t

4 5

I i

+

l d

T' 4

4 d

'k 7

4-4 t

w s, -

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p-

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63URI A! EADI WIND ItEED AND DIRECTION FERIOD OF RECDP3 72/ l/ 1 TEtl 92/ 6/30 ITABILITY CLAII:

A WIND IFEED - 101 WIND DIfiCTION 0.75-3 4-7 8-12 13-18

!?-24 124 TOTAL N

41.34 31.43 61.34 11.08 12.34 3.03 220.55 NE 44.70 73.82' 33.57 22.?5 8.83 2.78 191.63 iiE 48.67 89.01 35.80 it.63 0.76 0.3 187.13 EE 42.16 92.29 30.51 3.54 0.25 0.00 168.75 E

32.52

?0.72 24.43 7.32 OM 0.00 155.49 EIE 31.52 83.40 35.54 4.77 0.50 0.00 155.75 IE 32.50 85.62 34.54 4.77 0.25 0.25 153.24 IIE 37.37 62.03 26.24 7.56 1.01 0.25 136.43 I

19.74 86.00 21.20 4.23 0.00 0.00 160.23 IIW 47.16 74.41 10.61 0.75 0.00 0.00 132.93

..U 40.68 73.73 11.09 1.77 0.25 0.C0 i27.52 WIW 32.85 53.22 14.37 3.28 0.50 0.00 104.72 U

i1.37 17.37 8.89 3.53 f.91 0.50 45.68-WNW 6.57 8.57 6.06 8.57 1.52 2.27 33.56 Ird

'91.09 27.95 12.12 4.51 3.03 0.76 59.76 NNW 22.69 44.38 37.03 33.06 7.32 1.01 147.4?

TOTAL 537.24 1923.L 408.85 i 7.17 39.57 11.11 2187.93 IIE MRATION OF CAIN = 35.07 EI.

TIME IN ITABILITY CLACI = 2223.00 IFJ.

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