Text

Revised Radioactive Effluent Rept for LACBWR (Jan-June 1989)
	ML20248C601
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/30/1989
From:	; DAIRYLAND POWER COOPERATIVE
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ML20248C597	List: ML20248C594; ML20248C601;
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	NUDOCS 8910030521
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RADI0 ACTIVE EFFLUENT REPORT FOR THE LA CROSSE BOILING WATER REACTOR (JANUARY 1,19t'9 TO JUNE 30,1989)

DAIRYLAND POWER COOPERATIVE Docket No. 50-409 8910030521 890921 RER PDR ADOCK 05000409 R PNU ,,

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TABLE OF CONTENTS TITLE PAGE I

Radioactive Effluent Report l'

-Introduction 1 Regulatory Limits 2 Maximum Permissible Concentration 4 Average Energy 4 Analytical Methods 4 Batch Releases 6 Abnormal Releases 7 Estimated Total Analytical Error 7 Offsite Dose Calculation Summary 14 11 RER

'a s- .

L: 'd TABLES l:

~ TABLE NO. TITLE PAGE l-1A Effluent and Waste Disposal Gaseous Effluent Release Summaries 8 1D Gaseous Effluents - Elevated Release 9 2A T.iquid Release Summary 11 2B Liquid Effluents 12 3 Solid Waste and Irradiated Fuel

. Shipments 13 l

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INTRODUCTION:

The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa Station No. 2, is located on the east bank of the Mississippi River near Genoa, Vernon County, Wisconsin. The plant was designed and constructed by the Allis-Chalmers Manufacturing Company. It was completed in 1967 and had a generation capacity of 50 MW (165 MW(th)). The reactor is owned by Dairyland Power Cooperative (DPC).

The reactor went critical in July 1967 and first contributed electricity to DPC's system in April 1968. After completing full power tests in August 1969, the plant operated between 60% and 100% full power, with the exception of plant shutdowns for maintenance and repair.

In April of 1987 plant operation was ceased. ?he reactor is presently defueled and work is progressing to place the plant into a SAFSTOR mode. In August of 1987 a possession-only license was received.

In accordance with LACBWR Technical Specifications 6.9.3.a & 6.9.3.b and in compliance with 10 CFR 50.36a(a)(2), this document is the Radioactive Effluent Report for the period January 1 through June 30, 1989.

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EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)

FACILITY: Lacrosse Boiling Water Reactor LICENSEE: DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409

1. REGULATORY-LIMITS

a. Gaseous Effluent Release Limits:

LACBWR's Technical Specifications for gaseous effluent releases of radioactive material limit the release rates of the sum of the individual radionuclides, in Curies per second, so that the dose rates to members of the public beyond the Effluent Release Boundary do not exceed 500 mrem / year to the whole body, 3000 mrem / year to the skin from noble gases, and 1500 mrem / year to a critical organ from H-3, I-131/133 and particulate with half-lives greater than 8 days.

Also, in accordance with 10 CFR 50, Appendix I, the Technical Specifications for gaseous effluent radioactive material limit the air dose to a member of the public from noble gases in areas beyond the i

Effluent Release Boundary to less than 5 mrad gamma and 10 mrad beta per calendar quarter, and less than 10 mrad gamma and 20 mrad beta per calendar year. The dose limits from H-3, I-131/133_and particulate with half lives greater than 8 days are less than 7.5 mrem per calendar quarter, and less than 15 mrem per calendar year to any organ.

I Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual.

I I 2 RER

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b. Liquid Effluent Release Limits:

LACBWR's Technical Specifications limits for liquid effluent releases are limited to those concentrations of individual radionuclides such that the diluted discharge does not exceed 1 MPC in a 168-hour week averaged over the calendar year. For dissolved or entrained noble gases, the concentration is limited to a total activity concentration of 2 x 10-" pCi/ml. For alpha emitting radionuclides, the concentration is limited to a total activity concentration of 4.9 x 10 8 pCi/ml, based upon an actual alpha emitting radionuclides analysis performed on a representative water sample. The values reported in tables 2A and 2B, Liquid Effluents, are based on dilution with the combination of LACBWR and Genoa Station No. 3 condenser cooling water flow prior to discharge to the Mississippi River. No credit is taken for further dilution in the mixing zone of the Mississippi River.

Also, in accordance with 10 CFR 50, Appendix I, the dose commitment to a member of the public from radioactive materials released in liquid effluents to areas beyond the Effluent Release Boundary are limited to less than 1.5 mrem whole body and 5.0 mrem organ dose per calendar quarter, and less than 3.0 mrem whole body and 10 mrem organ dose per calendar year via the critical ingestion pathway.

Cumulative quarterly and annual dose contributions from liquid effluent releases are determined for the adult fish ingestion pathway in accordance with the LACBWR Offsite Dose Calculation Manual.

l l

RER 3 L_. _ __ . _ _ _ _ _ _ . _ _ ___ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _

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c. Solid Radioactive Waste All solid radioactive wastes are handled in accordance witn a Process Control Program as defined by LACBWR procedures in order to assure that all applicable transportation and burial site disposal requirements are met.

2 '. MAXIMUM PERMISSIBLE CONCENTRATION (MPC)

The MPC used to calculate permissible release rates are obtained from 10 CFR 20, Appendix B, Tables I and II. In addition, the following values are used:

. Tritium in Water = 3 x 10-3 pCi/ml.

Tritium in Air = 2 x 10'7 pCi/cc.

3. AVERAGE ENERGY The release-rate limits for LACBWR are not based on average energy.

4. ANALYTICAL METHODS

a. Liquid Effluents Liquid effluent measurements for gross radioactivity are performed by Ge-Li gamma isotopic analysis of a representative sample from each tank discharged. A composite sample is created by collecting representative aliquots of each sample from each tank batch discharged, and is analyzed monthly for Tritium, and quarterly for Iron-55 and Strontium 89 & 90. The iron and radiostrontium are analyzed by a contractor. In addition, each batch discharged tank is analyzed for alpha activity concentration.

RER 4

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tb V g.

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. b. Airborne Particulate

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sf Airborne particulate releases are determined by Ge-Li gamma isotopic analysis. This analysis is performed by analyzing a glass

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fiber filter paper taken from the stack monitor (Eberline SPING) which continuously isokinetic' ally samples and monitors the stack effluent.

i.;

.This filter is changed and analyzed on an approximate weekly basis and p analyzed within 7 days after removal. This filter is also analyzed for alpha activity.- A quarterly composite of these filters is sent to a contractor for Sr 89 and 9'O analysis.

c. Radioiodines Radiciodine releases are determined by Ge-Li gamma analysis of a TEDA impregnated activated charcoal cartridge taken from the stack monitor .which continuously isokinctically samples and monitors the stack i,

effluent. -This charcoal cartridge is changed approximately weekly and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after removal. Since the' plant shutdown in April 1987, the I-131/I-133 have decayed completely to stable elements.

'd. Fission and Activation Gases The gaseous releases converted into concentration (pCi/cc) are continuously sampled from the stack release flow by two stack monitors, which are inline monitors. These gas concentrations (pCi/cc) are averaged by the monitors microprocessor and flowrate/ pressure compen-sated te obtain the daily gaseous release of the plant. Since the plant shutdown'in April 1987, gaseous releases have been immeasurable. All fission gases except Kr-85 have decayed completely to stable elements.

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e.- Tritium j

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. Tritium releases are determined by taking'a grab sample of the 4, ' r

.:1 stack atmosphere at the effluent of the stack monitor. Tritium,^as

. tritiated water, is removed from the sample stream by condensation,

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.using a cold; trap containing an organic compound and dry ice. . The

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e < / condensed waterLvapor.is then distilled and the distillate is analyzed 3

-for;H-3' concentration, pCi/cc, by internal liquid scintillation s

spectrophotometry and the results are expressed in terms of tritium y release rates. The: tritium grab samples are obtained on at least a s

once/ month basis'unless the' upper reactor' cavity is flooded, at which

, , time'the sampling frequency is increased to at least.once per'7 days.

U, 5. ' BATCH RELEASES .

& 'a. Airborne All airborne effluent releases at LACBWR are from a single

, - Continuous-Elevated Release Point.

' b .' -Liquid

.All liquid effluent releases at LACBWR are batch releases. This is summarized as follows:

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i-a.

(1) Number of Batch Releases: 19 (2) Total Time Period for Batch Releases: 120.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

" 12.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months (3) Maximum Time Period for a Batch Release:

(4) Average Time Period for Batch Releases: 6.36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

[ '(5) Minimum Time Period for a Batch Felease: 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (6) Average Stream Flow Rate During Periods of Release of Effluent into a Flowing Stream: 26,330 ft 8/sec

6. ABNORMAL RELEASES There were no abnormal releases of radioactivity in plant effluents as summarized as follows:

a. Liquid (1) Number of Releases: None (2). Total Activity Released: N/A

h. Gaseous (1) Number of Releases: None (2) Total Activity Released: N/A

7. ESTIMATED TOTAL ANALYTICAL ERROR The reported analytical results contain the following estimated errors:

Counting Error 1 Standard Deviation Sampling Volume Error i 5%.

The lower limits of detection (LLD) are expressed in terms of a 4.66 o as defined in Technical Specifications.

RER 7

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TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l l UNIT l QTR j QTR ! QTR l QTR ! TOTAL l A. FISSION & ACTIVATION GASES l l l l l l 1. TOTAL RELEASE l l l ! Ci ! 0.00 t 0.00 ! ! ! 0.00 l l 2. AVERAGE RELEASE RATE l l l l l l FOR PERIOD l pCi/Sec ! --

l l ! l l

B. IODINE.I-131 l l l l l l 1. TOTAL 10 DINE-131 l l

! ! ci l' O.00 ! 0.00 ! ! ! 0.00 l l l l l l 2. AVERAGE RELEASE RATE l l l FOR PERIOD ! pCi/See ! --

1

! ! l C. PARTICULATE l l l l l 1. PARTICULATE W/ HALF- l l l l LIVES > 8 DAYS i Ci 17.88E-6!3.40E-8! ! !7.91E-6l l l l l l l 2. AVERAGE RELEASE RATE l l FOR PERIOD ! pCi/See 11.00E-6!4.33E-9l 1 ,_l l l l l l l 3. GROSS ALPHA l l ' RADIOACTIVITY ! Ci 19.00E-8! 0.00 ! ! l

~D. TRITIUM l l l l l l l 1. TOTAL RELEASE l l ! Ci 14.41E-1!2.21E-1! ! l6.62E-1l l l l l l l 2. AVERAGE RELEASE RATE l l FOR PERIOD ! pCi/Sec 15.67E-212.81E-2! ! l E. PERCENTAGE OF (APPENDIX I) TECHNICAL SPECIFICATION LIMITS

1. NOBLE GAS RELEASE

! QTR l QTR l QTR i QTR l YEARLY l l GAMMA i % l 0.J0 l 0.00 l l l 0.00 l l BETA l 7. l 0.00 l 0.00 ! l l 0.00 l

2. I-131, I-133. H-3, AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS I QTR l QTR l QTR ! QTR l YEARLY l l HIGHEST ORGAN l % l 0.26 l 0.02 l l l 0.14 l RZR 8 1

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TABLE IB EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989

, GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE l NUCLIDES RELEASED l UNIT l QTR l QTR l QTR I QTR l TOTAL l

1. FISSION GASES l KRYPTON-85' l Ci l l

l l t l

l KR'fPTON-85M l Ci !

l l l t l

l KRYPTON-87 l Ci ; --

l l l l l

KRYPTON-88 l Ci l l l l l l

l XENON-133 i Ci l l

l l l l

l XENON-135 l Gi !

l

! l l l

XENON-135M ! Ci !

l l ! l

-- j l

j XENON-138 ! Ci l l

l l l l

l KR-89 l Ci !

l l l t l

XE-133M l Ci l l l l l l

l XE-131M l Ci !

l --

l l l --

l l XE-137 l Ci l l

l l l l

l AR-41 i Ci l l --

! l l l

l Ci l l l l l l l

l l Ci l l t l l l l TOTAL FOR PERIOD l Ci ! 0.00 l 0.00 l ; i 0.00 l

2. IODINES j 10 DINE-131 l Ci !

l i l t l

10 DINE-133 l Ci !

l

! l ! l l --

l 10 DINE-135 l Ci l l

l l l l l TOTAL FOR PERIOD l Ci l 0.00 l 0.00 l l ! 0.00 l

3. (SEE FOLLOWING PAGE FOR PARTICULATE.)

RER 9

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TABLE IB - EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 GASECUS EFFLUENTS - ELEVATED RELEASE - (cont'd)

CONTINU0US MODE l NUCLIDES RELEASED t UNIT l QTR l QTR l QTR ! QTR l TOTAL l

3. PARTICULATE l STRONTIUM-89 l Ci !

l i ! l 0.00 l l STRONTIUM-90 l Ci !

l ! l 0.00 l l CESIUM-134 l Ci j --

l l l l 0.00 l l CESIUM-137 l Ci l3.55E-6l3.40E-81 l l3.58E-6l l BARIUM-LANTHANUM-140 l Ci l l

l l l 0.00 l l

CO-5, j Ci l l

! l l 0.00 l l CO-58 ! Ci l i

l l l 0.00_l l_ CO-60 l Ci l4.04E-61 --

l l 14.04E-6l l CE-14* i Ci l l

! l t 0.00_l l CE-141 ; Ci 1 I

l l l 0.00 l l CR-51 i Ci !

l t i l 0.00 l MN-54 i Ci l2.90E-7l --

l l l2.90E-7j l

l FE-59 i Gi l

! J l 0.00 l Ci --

i ! l 0.00 j l ZN-65 l !

l ZR-95 l Ci !

l l t ! 0.00 l l NB-95 i Ci l l

l l ! 0.00 l l_ RU-RH-106 i Ci !

l l l l' O.00 l l RU-103 i Ci !

?

l l l 0.00 l l t Ci l l l ! l l

' i Ci l t ! ! l l t Ci l l l l l l l

l l Ci l l l l t l l l Ci l i l l l l RER 10

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l l UNIT l QTR l QTR l QTR l QTR ! TCTAL l A. FISSION & ACTIVATION PRODUCTS l l l l l l l 1. TOTAL RELEASE (NOT INCL l !1.04E-lj l

TRITIUM, GASES. ALPHA) ! Ci 16.01E-2!4.34E-2! !

j l l l l 2. AVERAGE DILUTED CONCEN-l l

TRATION DURING PERIOD !pCi/ml !5.62E-8!5.14E-8! ! __l-E. TRITIUM l l l l l l l 1. TOTAL RELEASE l l Ci ! 1.12 17.20E-1l l ! 1.84 l l

l l l l 2. AVERAGE DILUTED CONCEN-j l l

! l l TRATION DURING PERIOD luci/ml l1.05E-6!8.54E-7!

C. DISSOLVED AND ENTRAINED GASES l l l l l l l 1. TOTAL RELEAEE l l Ci ! 0.00 1 0.00 ! ! ! 0.00 l l

l l l l l l 2. AVERAGE DILUTED CONCEN-l l

TRATION DURING PERIOD !pCi/ml ! --

! ! l D. GROSS ALPHA RADIOACTIVITY l l l l l l 1. TOTAL RELEhSE l l

!5.92E-5!4.00E-5! ! 19.92E-5j l

l Ci l l l l l l

lE. VOLUME OF WASTE RELEASED l !2.29ES l l (PRIOR TO DILUTION) ! Liters (1.17E5 !1.12E5 ! !

l l l l l lF. VOLUME OF DILUTION WATERj l j l Liters 11.07E9 !8.44E8 ! ! !1.91E9 l USED DURING PERIOD h

G. PERCENTAGE OF (APPENDIX I) TECHNICAL SPECIFICATION LIMITS FOR LIQUID RELEASES

! QTR l QTR ! QTR l QTR ! YEARLY l l % ! 0.40 ! 0.26 l l l 0.33 l l HIGHEST ORGAN l 0.73 l WHOLE BODY l % l 0.89 l 0.57 l ! l 11 RER

TABLE 2B EFFLUENT AND VASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 LIQUID EFFLUENTS l UNIT-! QUARTER t QUARTER l QUARTER ! QUARTER l l NUCLIDES RELEASED l STRONTIUM-89 l Ci l --

1 l l l l STRONTIUM-90 l Ci ! 3.05E-4 ! 2.91E-4 ! ! l l CESIUM-134 i Ci ! 1.80E-4 l 5.27E-5 l l l j CESIUM-137 l Ci l 1.37E-2 l 6.89E-3 l ! l l 10 DINE-131 i Ci ! --

l l ! l l Ci l --

l l l l l COBALT-58 j COBALT-60 l Ci l 2.93E-2 l 2.38E-2 l l l l IRON-59 i Ci ! --

l

___,,[ ! l l ZINC-65

Ci ! --

l

! l l l MANGANESE-54 l Ci ! 2.54E-3 l 1.07E-3 i l l l Ci l --

l l ! !

l CHROMIUM-51 l Ci l -- --

l ! l j ZIRCONIUM-NIOBIUM-95 t i Ci l --

l l l l MOLYBDENUM-99 l Ci !

l l ! l l TECHNETIUM-99M l l BARIUM-LANTHANUM-140 l Ci l l

l l Ci !

l l CERIUM-141 i l Ci j 7.44E-5 l l l l l CE-144 l Ci l 1

! ! ._ ___ l l CO-57 -- l l i Ci --

l l I-133 l 1

! l l

l I-135 i Ci !

l l Ci !

l l l l l NP-239 -- l l

i Ci l j RU-103 i Ci l l

l l l l RU-RH-105 -- l l l Ci !

l l l RU-RH-106 -- --

i l l l Ci l l l SR-91 l j SR-92 ! Ci !

l l !

l AG-110M __

i Ci ! 9.49E-5 l

! ! l l FE-55 l Ci i 1.39E-2 l 1.13E-2 i l l t Ci l t i ! l l ' ', ' '

' ' Ci ', , i i l Ci l l l l l l

l 1 l l t Ci l l i

4 l TOTAL FOR PERIOD ( ABOVE)l Ci ! 6.01E-2 l 4.34E-2 l ! l Ci !

l { l l

l XENON-133 --

l l l Ci l l l l XENON-135 -- ! l i Ci !

1 l l XE-131M l l i Ci !

i l XE-133M -- l l

! Ci !

! t l KR-85M -- --

l t l l Ci ! !

l KR-87 I l l t Ci l 1 f C1 l l l l t

l RER 12 o_ _

9 t ,

TABLE 3 1

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. - SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT 1RRADIATED FUEL) l l l 6-MONTH l 6-MONTH l l l 1. TYPE OF WASTE l UNIT l FERIOD l PERIOD l TOTAL l l a. SPENT RESINS, FILTER SLUDGES, l m 3 j 4.62 l l 4.62 l l

EVAPORATOR BOTTOMS, ETC. ! Ci l 3.19El l l3.19El l l

b. DRY COMPRESSIBLE WASTE, j m3 l l l l

-l CONTAMINATED EQUIPHENT, ETC. l Ci l l l l j c. IRRADIATED COMPONENTS, l m* l l l- l l

CONTROL RODS, ETC. ! Ci l l ! l 8

d. OTHER (DESCRIBE) l m l ! l l l

l l Ci ! ! ! l

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION l l 6-MONTH l 6-MONTH l (BY TYPE OF WASTE) l PERCENT l PERIOD ! PERIOD l

a. Co-60 ! 55.73 l 1.78E1 l l Cs-137 l 9.42 l 3.01 l l Mn-54 l 3.60 l 1.15 l l H-3 l5.32E-3l 1.70E-3 l l C-14 l1.31E-2l 4.17E-3 l l Fe-55 l 25.17 l 8.04 l l Ni-59 l5.70E-2! 1.82E-2 l l Ni-63 ! 5.01 l 1.60 l l Sr-90 l5.89E-11 1.88E-1 l l Tc-99 !6.11E-5l 1.93E-5 l l I-129 l2.94E-3l 9.38E-4 l l U-235 l2.45E-6l 7.81E-7 l l U-238 l2.07E-6l 6.60E-? l l Pu-239/240 l4.48E-3! 1.43E-3 ! l

! > Am-241 l3.22E-3l 1.03E-3 l l Cm-243/244 !1.41E- 3l 4.51E-4 l l Pu-238 l7.98E#3! 2.44E-3 i l Pu-241 l3.57E-1l 1.14E-1 l l Cm-242 l1.80E-2! 5.76E-3 l l l l l l l l l l

! ! l l l l l l l l l l

3. SOLID WASTED DISPOSITION NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1 Sole Use Barnwell, S.C.

B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

NO. OF SHIPMENTS NODE OF TRANSPORTATION DESTINATION RER 13

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I l

l

. 8. OFFSITE DOSE CALCULATIONS

SUMMARY

AND CONCLUSIONS:

a. Gaseous Effluent Releases The maximum quarterly offsite gamma dose due to noble gases was 0.00 mrad. The cumulative 1989 annual offsite gamma dose due to noble

. gases was 0.00 mrad.

The maximum quarterly offsite beta dose due to noble gases was 0.00 mrad. The cumulative 1989 annual offsite beta dose due to noble gases was 0.00 mrad, l' The maximum quarterly offsite dose to any organ from the release of I-131, I-133, H-3 and all radionuclides in particulate form with half-lives greater than 8 days was approximately 1.95E-2 mrem. The cumulative 1989 annual maximum organ dose from these radionuclides was approximately 2.10E-2 mrem.

The highest historical monthly and annual average X/Q's for the period 1985-1987 for the worst case offsite receptor location, in accordance with the ODCM, were used to calculate these offsite dose values.

b. Liquid Effluent Releases The maximum quarterly organ dose from liquid releases was approximately 0.02 mrem. The maximum cumulative 1989 annual organ dose was approximately 0.033 mRen. The maximum quarterly whole body dose for liquid releases was approximately 1.34E-2 mrem, and the cumulative 1989 annual whole body dose was approximately 0.022 mrem.

c. Conclusion All calculated offsite doses were below Technical Specification limits.

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p H

g ATTACHMENT 1 l

Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of the capabilit

The acceptance limits are based on the uncertainty (standard deviation)ofy the tests.

ratio of the licensee's mean value'(X) to the NRC mean value'(Y), where (1) Z = X/Y is the ratio, and (2) S is the uncertainty of the ratio determined from the -

pfopagationoftheuncertaintiesoflicensee'smeanvalue, Sx , and of the NRC's mean value, S .1 Thus, y

S2 z

S2 x S2 ,

_ so that Y'Y*

5 2Y1 S

2

=Zel[S*2+ 1--

(X2 y2)

The results are considered to be in agreement when the bias in the ratio (absolute value of difference between unity and the ratio) is less than or equal to twice the uncertainty in the ratio, i.e.

I 1-Z { $ 2*S 7 1.

National Council on Radiation Protection and Measurements, A Handbook of Radioactivity Measurements Procedures, NCRP Report No. 58, Second tdition, 1985, ? ages 322-326 (see Page 324).

4'6/87

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ML20248C601

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SUMMARY

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