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| number = ML20059B566
| number = ML20059B566
| issue date = 06/30/1990
| issue date = 06/30/1990
| title = Semiannual Radioactive Effluent Release Rept Jan-June 1990.
| title = Semiannual Radioactive Effluent Release Rept Jan-June 1990
| author name =  
| author name =  
| author affiliation = ALABAMA POWER CO.
| author affiliation = ALABAMA POWER CO.

Latest revision as of 22:36, 6 January 2021

Semiannual Radioactive Effluent Release Rept Jan-June 1990
ML20059B566
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/30/1990
From:
ALABAMA POWER CO.
To:
Shared Package
ML20059B512 List:
References
NUDOCS 9008290159
Download: ML20059B566 (60)
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Text

._.

ALABAMA POWER COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

, JANUARY l, 1990 THROUGH JUNE 30, 1990 l.

9008290159 900$$A '

ADOCK 05000348 PDR R PDC

CONTENTS ,

CHAPTER 1 INTRODUCTION  :

2 CHAPTER 2 SUPPLEMENTAL INFORMATION FOR EFFLUENT AND HASTE '

DISPOSAL 2.1 REGULATORY LIMITS . . . . . . . . . . . . . . . . 2-1 2.1.1 Fission And Activation Gases . . . . . . . . . . 2-1 2.1.2 Iodines And Particulates . . . . . . . . . . . . 2-1 2.1.3 Liquid Effluents . . . . . . . . . . . . . . . . 2-2 i 2.2 MAXIMUM PERMISSIBLE CONCENTRATIONS . . . . . . . . 2-2  ;

. 2.3 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . 2-2 /

2.4 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY 2-2 2.4.1 Fissiun And Activation Gases . . . . . . . . . . 2-3 2.4.2 Iodines And Particulates . . . . . . . . . . . . 2-3 2.4.3 Liquid Effluents . . . . . . . . . . . . . . . . 2-4 2.5 BATCH RELEASES AND ABNORMAL RELEASES . . . . . . . 2-5 2.6 ESTIMATE OF TOTAL ERROR . . . . . . . . . . . . 2-10 2.6.1 Liquid . . . . . . . . . . . . . . . . . . . . 2-10 2.6.2 Gaseous . . . . . . . . . . . . . . . . . . . 2-10 2.6.3 Solid Radwaste . . . . . . . . . . . . . . . . 2-10 2.7 SOLID HASTE . . . . . . . . . . . . . . . . . . 2-11 2.8 RADIOLOGICAL IMPACT ON MAN . . . . . . , . . . . 2-11 2.9 MINIMUM DETECTABLE CONCENTRATIGN (MDC) . . . . . 2-14 2.10 DEVIATIONS FROM LIQUID HASTE RELEASE PROGRAM . . 2-14 2.11 DFVIATIONS FROM GASEOUS WASTE RELEASE PROGRAM . 2-14 CHAPTER 3 TABLE 1A-1 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, i Farley Unit 1 - 1st Half, 1990 CHAPTER 4 TABLE 1A-2 GASEOUS EFFLUENTS--SUMMATION OF ALL RELEASES, .

Farley Unit 2 - 1st Half. 1990 L CHAPTER S TABLE IB-1 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley Unit 1 - 1st Half, 1990 l CHAPTER 6 TABLE IB-2 GASEOUS EFFLUENTS--ELEVATED RELEASE, Farley Unit 2 - 1st Half,-1990 L

CHAPTER 7 TABLE 1C-1 GASEQUS EFFLUENTS--CROUND RELEASE, Farley Unit 1 - 1st Half, 1990 1

CHAPTER 8 TABLE 1C-2 GASEOUS EFFLUENTS--GROUND RELEASE, Farley Unit 2 - 1st Half, 1990 i

Pogo 2 CHAPTER 9 TABLE 2A-1 LIQUID EFFLUENT 3--SUMMATION OF ALL RELEASES, Farley Unit 1 - 1st Half, 1990 CHAPTER 10 TABLE 2A-2 LIQUID EFFLUENTS--SUMMATION OF ALL RELEASES, Farley Unit 2 - 1st Half, 1990

. CHAPTER 11 TABLE 2B-1 LIQUID EFFLUENTS--BATCH AND CONTINUOUS, Farley Unit 1 - 1st Half, 1990 CHAPTER 12 TABLE 2B-2 LIQUID EFFLUENTS--BATCH AND CONTINUOUS,

'Farley Unit 2 - 1st Half, 1990 CHAPTER 13 TABLE 3 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS, 1st Half, 1990 CHAPTER 14 TABLE 4 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM,-Units 1 & 2 CHAPTER 15 TABLE 5 RADIOACTIVE LIQUID WASTE SAMPLING.AND ANALYSIS PROGRAM, Units 1'& 2 CHAPTER 16 TABLE 6 LIQUID DISCHARGES NOT MEETING SPECIFIED DETECTION LIMITS, Units 1 & 2 - 1st Half, 1990 CHAPTER 17 PROCESS CONTROL PROGRAM 4

e \

i l

CHAPTER 1 INTRODUCTION i

This semiannual radioactive release report, for the period January 1 through June 30, 1990, is submitted in accordance ,

with Appendix A of License No.'s NpF-2 and NPF-8. Appendix A  !

will hereinafter be referred to as the Technical Specifications or TS. J A single submittal is made for both units which combines those sections that are common.

Separate tables of releases and  !

release totals are included where separate processing systems exist.

1 All assessments of radiation doses are performed in accordance  !

with the OFFSITE DOSE CALCULATION MANUAL (ODCM). l

.1 v

l-1

f i

i i

CHAPTER 2 SUPPLEMENTAL INFORMATION FOR EF7LUENT AND NASTE DISPOSAL  !

I 2.1 REGULATORY LIMITS 2.1.1 Fission And Activation Gases

1) The dose rate from the site at any time due to noble gases l shall. be less than or equal to 500 arem/yr to the total body t and 3000 mrem /yr to.the skin.
2) The air dose from each reactor unit from tho sit'e during any .

calendar quarter due to noble gases shall be less than or equal  ;

to 5 arad for gamma radiation and 10 mrad for beta radiation. >

3) The air dose from each reactor unit from the site during any

' calendar year due to noble gases shall be less than or equal to .

10 mrad for gamma radiation and 20 mrad for beta radiation. '

2.1.2 Iodines And Particulates s

1) The dose rate'from the site at any time due to iodines, particulates and radionuclides with half-lives greater than B l

l days shall be less than or equal to 1500 mrem /yr to any. organ.

2) The dose from each reactor unit from the site during any

. calendar quarter due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be less than or equal to 7.5 mrem to any organ.

3)'The dose from each reactor unit from the site during any l calendar year due to iodines, particulates and radionuclides with half-lives greater than 8 days shall be less than or equal to 15 mrem to any organ.

2-1

SUPPLEMENTAL INFORMATION FOR EFFLUENT AND WASTE DISPOSAL REGULATORY LIMITS L

2.1.3 Liquid Effluents

1) The concentration of radioactive materials released in liquid effluents to unrestricted areas from all reactors at the site shall not exceed at any time the values specified in 10CFR Part 20, Appendix B, Table II, Column 2. The concentration cf dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall not exceed at any time 2E-4 uCi/ml in water.
2) The dose or dose commitment due to liquid effluents released from each reactor unit from the site during any calendar quarter shall be less than or equal to 1.5 mrem to the total body and 5 mrem to any organ.
3) The dose or dose commitment due to liquid effluents released from each reactor unit from the site during any calendar year shall be less than or equal to 3 arem to the total body and 10 mrem to any organ.

2.2 MAXIMUM PERMISSIBLE CONCENTRATIONS a) Airborne - The maximum permissible concentration of radioactive materials in gaseous effluents is limited by the dose rate restrictions of 10 CFR 20. In this case, the maximum permissible concentrations are actually determined by the dose factors in the ODCM.

b) Liquids - 10 CFR Part 20, Appendix B, Table II, Column 2.

Note: The MPC chosen is the most conservative value of either the soluble or insoluble MPC for each isotope.

2.3 AVERAGE ENERGY Not applicable for Farley's TS.

2.4 MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY The following discussion details the methods used to measure and approximate total activity for the followings

a. Fission and Activation Gases
b. Iodines and Particulates
c. Liquid Effluents 2-2 1

SUPPLEMENTAL INFORMATION FOR EFFLUDfT AND HASTE DISPOSAL MEASUREMDTTS AND APPRbXIMAT30NS OF TOTAL- ACTIVITY Tables 4 and 5 give sampling frequencies and minimum detectable i concentration requirements for the analysis of gaseous and liquid effluent streams, respectively.

Values in the attached tables given as zero do not mean that  !

the nuclides were not present. A zero indicates that the nuclide was not present at levels greater than the sensitivity requirements shown in Tables 4 and 5. For some nuclides, lowsr -

detection limits than required may be readily achievable; when a nuclide in measLred below its stated limit, it is reported. .

l 2.4.1 Fission And Activation Gases

. (

The following noble gases are considered in evaluating gaseous .i airborne discharget Kr-87 Xe-133 Kr-88 Xe-135 Xe-133m Xe-138 Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. (See Table 4 for sampling and analytical requirements). Isotopic values thut obtained are used for release rate calculations as-specified in the ODCM.

Only those nuclides that are detected are used in this computation. During the period between grab samples, the amount of radioactivity released is based on the effluent munitor readings.

i The monitor meter response (epm /uCi/ml) and the background (cpm) are used to adjust the activity released for variations in monitor readings, as described in the ODCM.

To ensure isotopic distributions do not change significantly during major operational occurrences, the frequency of grab sampling is increased to satisfy the requirements of footnotes (b) and (d) of TS Table 4.11-2, ' Radioactive Gaseous Waste Sampling and Analysis Program".

2.4.2 Iodines And Particulates The radiciodines and radioactive materials in particulate forms to be considered are:

~

Mn-54 I-131 Fe-59 I-133 2-3

4 SUPPLEMENTAL INFORMATION FOR EFTLUENT AND NASTE DISPOSAL MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY l i

Co-58 Cs-134 i Co-60 Cs-137 l Zn-65 Ce-141 i Sr-89 Ce-144 Sr-90 *H-3 Mo-99 Other nuclides with half-lives greater than 8 days which are identified and measured are also considered. The MDC's will vary and are not required to neet the MDC limits of those isotopes listed specifically.

  • Tritium is cLasidered in the gaseous or water vapor form. 1 Continuous Releases: Continuous sampling'is performed- on the continuous release points (i.e. the Plant Vent Stack, Containment Pu ge and the Turbine Building Vent). Particulate material is collected by filtration. Periodically these l filtkra are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the .

filters. Particulate filters are then analyzed for gross alpha l and strontium as required. Gross alpha determinations are '

made using a 2 pi gas flow proportional counter. Sr-89 and 90 values are obtained by chemical separation and subsequent analysis using 2 pi gas flow proportional counters.

Batch Releases: The processing of batch typo releases (from Containment or Haste Gas D6;ay Tanks) is analogous to continuous releases, except that the release is not commenced until samples have been obtained and analyzed.

2.4.3 Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

Mn-54 I-131 Fe-59 Cs-134 Co-58 Cs-137 Co-60 Ce-141 Zn-65 Co-144 Sr-89 Mo-99 Sr-90 Fe-55 H-3 .

l Batch Releases: Representative pre-release grab samples are t obtained and analyzed per Table 5. Isotopic analyses are performed using the computerized pulse height analysis system 2-4 1

, , , , , - . - , + - -

SUPPLEMENTAL INFORMATION FOR EFTLUENT AND MASTE DISPOSAL MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY previously described. Aliquots of each pre-release sample i proportional to the waste volume released are composited in accordance with requirements in Table 5. Strontium  !

determinations are made by performing a chemical separation and-  !

counting the isotope thus separated using a 2 pi gas flow proportional counter. Gross beta and gross alpha determinations are made using 2 pi gas flow proportional I counters. Tritium and Iron 55 determinations are made using liquid scintillation techniques. Dissolved gases are .

determined employing grab sampling techniques and then counting -l on the pulse height analyzer.

Continuous Releases: Continuous releases (from the Steam Generator Blowdown) are analogous to that of the batch releases l except that they are analyzed on a weekly composite basis per [

Table 5. l l

I l

2.5 BATCH RELEASES AND ABNORKAL RELEASES  !

Batch releases and abnormal (non-routine) releases from units 1 and 2 are shown on the following pages.

i t

2-5

SUPPLEMENTAL INFORMATION FOR EFTLUDfT AND MASTE DISPOSAL BATCH RELEASES AND ABNORMAL RELEASES BATCH RELEASES - UNIT 1 QUARTER 1 QUARTER 2 i LIQUIDS RELEASE (S): ALL '

Number of batch releases 130. 116.

Total time period for batch releases (min) 11344. 9739.

Maximum time period for 113. 115.

a batch release (min)

. Average time period for it a batch release (min) 87. 84.

Minimum time period for a batch release (min) 66. 66, Average stream flow during periods of release (cfs)

  • 2.91Et04
  • 9.03E+03 GASES RELEASE (S): ALL >

Number of batch releases 6. ,

3.

Total time period for batch releases (min) 1763. 1141.

L Maximum time perir,d for ,

l a batch reles.se (min) 476. 475.

L Average time period for a batch release (min) 294. 380.

Minimum time period for a batch release (min) 98. 274.

l

  • Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.

2-6

SUPPLEMENTAL INFORMATION FOR EFTLUENT AND MASTE DISPOSAL l BATCH RELEASES AND ABNORMAL RELEASES l'

ABNORMAL RELEASES - UNIT 1 QUARTER 1 QUARTER 2 LIQUIDS Number of releases 0. O.

Total activity released 0.00E+00 0.00E+00 GASES Number of releases 0. O.

Total activity released 0.00E+00 0.30E+00 2-7 1

SUPPLEMENTAL INFORMATION FOR EFTLUENT AND HASTE DISPOSAL j

. BATCH RELEASES AND ABNORMAL RELEASES l

4 BATCH RELEASES - UNIT 2  ;

l QUARTER 1 QUARTER 2 LIQUIDS RELEASE (S): ALL l l

Number of batch releases 66. 77. ,

q Total time period f or batch releases (min) 6327. 7078.  !

Maximum time period for l a batch release (min) 150. 120. ]

l Average time period for t a batch release (min) 96. 92.

Minimum time period for'  ;

a batch release (min) 85. 76.

Average stream flow during l periods of release (cfs) A 2.91E+04

  • 9.03E+03 l

GASES RELEASE (S): ALL Number of batch releases 0. 3.

Total t2me period for batch releases (min) O. 1884.

Maximum time period for a batch release (min) O. 847.

Average time period for a batch release (min) O. 628.

! Minimum time period for

a batch release (min) O. 255.

l l-l A Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.

i 2-8

1

'i SUPPLEMENTAL INFORMATION FOR EITLUENT AND HASTE DISPOSAL i BATCH' RELEASES AND ABNORMAL RELEASES  !

i I

ABNORMAL RELEASES - Jh'T.T-?,

LIQUIDS ,

Number of releases 0. O, Tot,'.1 activity released 0.00E+00 0.00E+00 GASES Number of releases 0. O.

Total activity released 0.00E+00 0.00E+00 i 5

i i

i 5

2-9

-l

' SUPPLEMENTAL INFORMATION FOR EFFLUENT AND NASTE DISPOSAL a ESTIMATE OF TOTAL ERROR f 1

2.6 ESTIMATE OF TOTAL-ERROR I 2.6.1 Liquid

,- 1) The maximum error associated with volume :and flow

- -seasurements, based upon plant calibration practice. is '

i estimated to be + or - 10%.

2)-The average error associated with counting is

.. estimated to be less than + or -'15%.

, ]

2.6.2 Gaseous

1) The maximum errors associated with monitor readings sample

' flow, vent flow, sample collection, monitor calibration-and laboratory procedure are collectively estimated to bes Fission and Activation Gases Iodine Particulates Tritium q 75% 60% t0% -45% r

2) The average error associated with counting is estimated to bei Fission and Activation-Gases Iodine Particulates Tritium 19% 26% 20% 8%

2.6.3 Solid Radwaste  ;

The error involved in determining the contents of solid radwaste shipments is estimated to be less than +-or - 1**

l x

P o

0, ,

2-10 h

4 . i b; 3;<

SUPPLDENTAL INFORMATION FOR EFFLUENT 4 AND MASTE DISPOSAL. d ESTIMATE OF TOTAL ERROR d

UNIT

=

1

y,

, 1990 q

2.7 SOLID WASTE See Table 3 2.8 RADIOLOGICAL' IMPACT ON MAN-s

~ The doses from l'1 quid and gaseous releases for units 1 and 2  !

. are shown on the following pages.-

i t

4 s  !

i t

l y

o t 'bJ '

f 2-11

. 1

~ t

b .

SUPPLEMENTAL.INFORMATION<FOR EFFLUENT AND HASTE DISPOSAL-  !

-RADIOLOGICAL IMPACT ON MAN- g

,- p DOSES FROM LIQUID AND GAP 0US EFFLUENTS - UNIT l' 1 .

h I QUARTER 1 QUARTER 2-LIQUIDS (mrem) RELEASE (S): ALL-  !

iv. '

Bone 1.84E-02 2.52E-02.

3: Liver 2.78E-02 4.01E Whole body 1.93E-02 2.84E-02 Thyroid 3.91E-04 1.21E-03 I Kidney 5, : A -03 1.42E-02 Lung 3.40 93 5.57E-03 GI - LLI 1.35E-02 'l.43E p

c GASES RELEASE (S): ALL i

NOBLE GASES (MRAD)

Whole-body 3.67E-03 1.91E-03 l Skin -3.00E-03 9.83E-04 PARTICULATE AND IODINE (mrem)

Bone 0.00E+00 0.00E+00' Liver 8.60E-04 2.36E Whole body 8.60E-04 2.36E-03 Thyroid 8.60E-04 2.36E-03 Kidney 8.60E-04 2.36E ,

Lung- 8.60E-04 2.36E-03 "

l GI - LLI 8.60E-04 2.36E-03 l

'l Skin 0.00E+00 0.00E+00 l l

2-12 j i

l

_ _ _ _ _ _ _ _ _ _ _ _ - . - , . - - - - , e

. 'h 5

.8UPPLEMENTAL INFORMATION FOR EITLUENT AND HASTE DISPOSAL ~

RADIOLOGICAL IMPACT ON MAN  ;

, , . DOSES FROM LIQUID AND GASEOUS EFFLUENTS - UNIT 2-l f

QUARTER 1 QUARTER 2  ;

LIQUIDS (mrem) RELEASE (S): ALL Bone 1.04E-02 2.82E-02 .;

Liver 1.62E-02 4.57E-02 ,

.t Whole body 1.14E-02 -3.26E-02

  • Thyroid 6.73E-04 1.17E-03 Kidney 5.88E-03 1.60E-02 1'

Lung 2.43E-03 6.15E-03 l GI LLI 2.25E-03 ,9.95E-03' GASES RELEASE (S): ALL

. NOBLE GASES (MRAD)

Nhole body 2.82E-03 2.86E-03  ;

Skin 9.98E 1.02E-03 PARTICULATE AND IODINE (arem).

Bone 0.00E+00 0.00E+00 i

Liver 3.05E-03 ~3.13E-03  !

Whole body 3.05E-03 3.13E-03 Thyroid 3.05E-03 .3.13E-03 Kidney 3.05E-03 3.13E-03 i Lung 3.05E-03 3.13E-03  :

GI - LLI 3.05E-03 3.13E-03 s Skin 0.00E+00 0.00E+00-2-13 ,

-g .

G;b SUPPLEMENTAL INFORMATION FOR EFFLUENT'AND MASTE DISPOSAL

. MINIMUM DETECTABLE CONCENTRATION (MDC).

2.9 MINIMUM DETECTABLE CONCENTRATION (MDC) 1 Detectable limits for activity analyses are based upon. the technical feasibility and on the potential significance in-the environment of the quantities released. However, in practice,

, when an isotope's :a posteriori MDC could not be met due to other nuclides being present in much greater concentrations, the a^ priori MDC as defined in the.TS table 4.11-1 a. is relied upon.

2.10 DEVIATIONS FROM LIQUID HASTE RELEASE PROGRAM

< There were no deviations from the Liquid Waste Release Program dur.ing the first half of 1990.

i 2.11= DEVIATIONS FROM GASEOUS WASTE RELEASE PROGRAM A deviation from the Gaseous Waste Release Program-occurred on Unit 1 during Quarter l'in that a continuous sample was not -

l obtained on the' Unit 1 Containment Purge the week of January 22 due to the sample pump having Leen inadvertently unplugged..

l l

'l 1

l l

1 L i l

l l

i i

i 2-14 m

11 l .

I e CHAPTER 3

, , , TABLE 1A-1

- 10N RELEASE (S): ALL - UNIT 1 t GASE0US EFFLUENTS---________0F SUr________ ........ ....

l UNITS-l QUARTER' l QUARTER l l l 1 l 2 l A. FISSION AND ACTIVATION GASES l 1. TOTJ.L RELEASE- l C1 l 3.64E+01 l 1.26E+01 l l 2. AVERAGE RELEASE luci/SECl 4.68E+00 l 1.60E+00

'l RATE FOR PERIOD l l l l'3. PERCENT OF TECHNICAL l

% l 5.87E-03 l 3.06E-03 l (T. BODY) A-l SPECIFICATION LIMIT l l l l l 4. PERCENT OF TECHNICAL l  % l 8.00E-04 l 2.62E-04 i (SKIN) **

l SPECIFICATION LIMIT l l l .l

.B.-IODINES r 1. TOTAL IODINE-131 l Ci l 0.00E+00 l' O.00E+00 l l' 2. AVERAGE RELEASE luCi/SECl 0.00E+00 1 0.00E+00 l l RATE FOR PERIOD l l l l

.l 3. PERCENT OF TECHNICAL l  % 1 0.00E+00 1 0.00E+00 l (ORGAN) ***

l- SPECIFICATION LIMIT l

_________ _______________l________l____________l____________

A, C(Quarterly T. Body Dose x 4)/(250 mrem /yr limit)3 x 100

  • * ' C(Quarterly Skin Dose x 4)/(1500' mrem /yr limit)3 x 100
      • C(Quarterly I-131 Dose x 4)/(750 mrem /yr limit)3 x 100 3-1 i I

'l TABLE 1A-1

)

GASEOUS EFFLUENTS -- SUMMATION OF RELEASE (S): ALL - UNIT 1 l-UNITS l QUARTER l QUARTER l l l 1 l 2 l

-C. PARTICULATES l 1. PARTICULATES WITH l Ci l 0.00E+00 l 0.00E+00 l l HALF-LIVES >8 DAYS l l l l-l 2.-AVERAGE-RELEASE luc 1/SECl 0.00E+00 l 0.00E+00 l l- RATE FOR PERIOD l l l l l 3. PERCENT OF TECHNICAL l  % l 0.00E+00 l _0.00E+00 l (ORGAN) A i l SPECIFICATION LIMIT l l l l l i

l 4. GROSS ALPHA l Ci l 1.05E-07 l 5.48E-08 l i l RADI0 ACTIVITY l l l l  !

1 D. TRITIUM j

.l 1. TOTAL RELEASE .I Ci 4.87E+00 l 1.34E+01 l l

l 2. AVERAGE RELEASE luC1/SECl 6.26E-01 l 1.70E+00 l l

l. RATE FOR PERIOD l l 'l l 1

l 3. PERCENT OF TECHNICAL l  % l 2.75E-03-l 7.55E-03 l (ORGAN) AA l SPECIFICATION LIMIT l l l l  !

^ E(Quarterly Particulate Dose x 4)/(750 mrem /yr limit)J x 100

~

^^ [(Quarterly Tritium Dose x 4)/(750 mrem /yr limit)J x 100  !:

.f i

I

(

i I

?

1-?

l i

G A

i t

c t

i P

CHAPTER 4 e s TABLE 1A-2 l

, '_ GASEOUS EFFLUENTS -- SUMMATION OF RELEASE (S): ALL - UNIT 2 1 l UNITS l QUARTER l QUARTER l u l l 1 l 2 l

'A.' FISSION AND ACTIVATION GASES

'l.l. TOTAL RELEASE l Ci l 8.95E+00 l 9.56E+00 l  ;

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . a

.'l 2. AVERAGE FELEASE' luCA/EECl 1.15E+00 l 1.22E+00-l- ,

I l1 RATE l l l l

__________FOR-PERIOD _____________________.._________________________

l.3.. PERCENT-OF TECHNICAL l  % l 4.51E-03 1 4.58E-03 l (T. BODY)

  • 4 l- SPECIFICATION LIMIT l l l l l 4.. PERCENT OF TECHNICAL l  % l 2.66E-04 l 2.72E-04 l (SKIN) . **

t< l- SPECIFICATION LIMIT l -l l -l B. IODINES l 1. TOTAL 10 DINE-131 l Ci l 0.00E+00 l 0.00E+00 l  ;

l'2.-: AVERAGE RELEASE luC1/SECl 0,00E+00 l 0.00E+00.I
l RATE FOR PERIOD l l l l l-:3. PERCENT OF TECHNICAL l  % l 0.00E+00 l 0.00E+00 l (ORGAN) ***
l. SPECIFICATION LIMIT l l l l E(Quarterly T; Body. Dose x 4)/(250 mrem /yr-limit)3 x 100 [
  • *1 E(Quarterly Skin Dose x 4)/(1500 mrem /yr limit)3 x 100
  • AA [(Quarterly I-131 Dose x'4)/(750 mrem /yr limit)].x 100 1

4-1 i e

, y._4 - - , ---e

TABLE 1A-2 CASE 00S-EFFLUENTS -- SUMMATION OF RELEASE (S)s-ALL - UNIT 2 l= UNITS l -QUARTER .l QUARTER  !

! I 1 l -2 l C. PARTICULATES 1

l 1...PARTICULATES WITH l Ci l 0.00E+00'l 0.00E+00 l l HALF-LIVES >8. DAYS l l l l l 2. AVERAGE RELEASE luC1/SECl 0.00E+00 l- 0.00E+00 l l RATE FOR PERIOD l l l l 1 I 3. PERCENT OF TECHNICAL l  %~ l 0.00E+00 l 0.00E+00 1 (ORGAN) A

-l SPECIFICATION LIMIT l l l l l 4. GROSS ALPHA l Ci l 1.55E-07 l 0.00E+00'l l RADIOACTIVITY. l l l l ,

i D. TRITIUM l 1. TOTAL RELEASE I C1 l 1.72E+01 l 1.77E+01 I i l.2. AVERAGE' RELEASE luCi/SECl 2.21E+00 l 2.25E+00 l .

I RATE FOR PERIOD l l l l l 1.3.-PERCENT OF TECHNICAL l  % l 9.76E-03 l 1.00E-02 l (ORGAN) ** [

l SPECIFICATION LIMIT l l l l  !

^ _E(Quarterly Particulate Dose x 4)/(750 mrem /yr limit)J x 100

^^ C(Quarterly Tritium Dose x 4)/(750 mrem /yr limit)] x 100 l t

i.

1 i

i

(

4-2

t7 CHAPTER S TABLE IB-1 h

, . GASEOUS _ EFFLUENTS - Elevated Releases RELEASE (S): ALL - UNIT'l y j

CONTINUOUS MODE BATCH MODE NUCLlDESL i UNITS :

=

QUARTER  : QUARTER : QUARTER  : QUARTER :

- RELEASED  :  : 1  : 2  : 1 2  :

, l.. FISSION AND-ACTIVATION GASES

___...________________________________________________________________ 1 AR-41 Ci 6.80E+00 5.38E+00 0.00E+00 0.00E+00 KR-85M C1 0.00E+00 0.00E+00 0.00E+00 ~1.59E-03 0 KR-85 Ci 0.00E+00 0.00E+00 2.56E-01' 4.64E-01  !! '

KR-88 Ci- 0.00E+00 0.00E+00 '0.00E+00. '7.36E-04 XE-131M Ci -0.00E+00 0.00E+00 1.'30E-02 1.09E-02 .

.XE-133M Ci 0.00E+00 0.00E+00 2.13E-03 2.64E-02  !

XE-133 C1 1.36E+01 3.02E+00 8.67E-01. 1.44E+00 .i XE-135 Ci- 1.48E+01 2.llE+00 1.24E-04 9.42E-02 j

-i i

i

. i_

1 i

TOTAL FOR  :  :  :  :  :  :  !

PERIOD  : Ci  : 3.52E+01  : 1.05E+01  : 1.14E+00  : 2.04E+00  :

(ABOVE)  :  :  :  :  :

5 5-1 J

]

i s_

^

nc -

l-c

'  : TABLE 1B-1 c '

e

GASE0US EFFLUENTS 1-; Elevated Relfases RELEASE (S): ALL - UNIT 1 '

'i

y e

CONTINUOUS-MODE -BATCH: MODE- i NUCLIDES  : UNITS : < QUARTER ~  : ' QUARTER

- QUARTER  :. QUARTER- :

s' RELEASED- s '..  : 1 2  : 1  : 2  :-

_______________......___.._____.= ..___. .__________..________________

2.-IODINES '

t t,

+ < 'b I

TOTAL FOR  : a -:  :  :  :

PERIOD  : Ci  : 0.00E+00  : 0.00E+00  : 0.00E+00  : 0.00E+00  : ,

(ABOVE).  :  :  :  :  :  :

_ ____________ .______________________________________________________ s a

13 * 'A i

r t

5-2

/.

. TABLE'1B-1 i ,

[ -

GASEOUS EFFLUENTS - Elevated Releases RELEASE (S): ALL - UNIT 1 CONTINUOUS MODE BATCH MODE-NUCLIDES  : UNITS :

QUARTER- : QUARTER .: QUARTER  : QUARTER :

RELEASED  : 1-  : 2  : 1  : '2  :
3. PARTICULATES H-3 ^Ci 4.86E+00 1.34E+01 0.00E+00 0.00E+00
13. ALPHA- C1 1.05E-07 5.48E-08 0.00E+00 0.00E+00 g i
  1. l TOTAL FOR  : .:  :  :  :  : 1 PERIOD =: Ci  : .4.86E+00  : 1.34E+01. : 0.00E+00  : 0.00E+00  : q (ABOVE).  :  : a.  :  :  :

______________________________________________________________________ l 1

l 4

t 4

5-3

+

i i

o i:'

s.

b.

i 1

CHAPTER 6  !

TABLE IB-2  :

i

1 's -

+

n:. GASEOUS EFFLUENTS - ALL - UNIT 2' n.

-__________________________________________ Elevated Releases _____ RELEASE (S):__________..___ ..__________ =:

e 4 c

CONTINUOUS MODE BATCH MODE. .!

n i - i- NUCLIDES  : UNITS : QUARTER .: ' QUARTER  : QUARTER' : ' QUARTER  :  !

RELEASED  :  : 1  : 2  : 1  : 2  : 9

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i_

i L 1. FISSION AND ACTIVATION-GASES

- AR-41: Ci 8.85E+00 8.98E+00 0.00E+00 0.00E+00 j

'KR 'Ci 0~00E+00~ 0.00E+00 0.00E+001 -1.54E-02'  !!

XE-133M: Ci 0.00E+00 '0.00E+00 0.00E+00 1.51E t XE-133 C1 1.00E-Ol' -2.70E-01 0.00E+00  : 2.' 9 4E-01

! l e

a c

i 1

i i

.i l

______________________________________________________-_______________ i

' TOTAL FOR- :-  :  :  :  :

PERIOD.  : C1  : 8.95E+00  : 9.25E+00  : 0.00E+00  : 3.11E-01 '

l.

(ABOVE) a
:  ::  : l 6-1 L

i I

Y ~

o TABLE IB-2.

4 GASEOUS EFFLUENTS -- -Elevated Releases- RELEASE (S):-ALL - UNIT 1 2 J L . CONTINUOUS MODE BATCH MODEi J

_______________. ______________________________________________. ____. 1

NUCLIDES QUARTER  : QUARTER : QUARTER s' QUARTER-
-RELEASED  : . : UNITS :  : 1  : 2  : l'  : -2 s' 'r

.2. 10 DINES

__.______.. _____.____________________________________.__...._________ i

'e (

2 1  ;

.w.. t

?

i

- l.

J TOTAL FOR  :  :  :  :  :  :

PERIOD  : .Ci  : 0.00E+00 0.00E+00 : 0.00E+00  : 0.00E+00- :

(ABOVE)  :  :

:  :  : ]

l1

(

h 1-l .- i l o

l 6-2

m ,

1 TABLEElB .

, j -.

u', -

i-GASEOUS-EFFLUENTS - Elevated' Releases- RELEASE (S): 3 ALL - UNIT 2- -

CONTINUOUS MODE BATCH MODE NUCLIDES . UNITS : QUARTER : QUARTER : QUARTER :. QUARTER- s' -

RELEASED- :  : 1-  : 2  :- 1  : 2-  :

-3 . PARTICULATES

, H-3 Ci 1.72E+01 1. 7 7E+ 01: 0.00E+00 0.00E+00-G.~ ALPHA C1 1.55E-07 0.00E+00 0.00E+00 0.00E+00

'4 i

i P

TOTAL-FOR  :  :  :  :  :  :

PERIOD  : Ci  :-1.72E+01  : 1.77E+01  : -0.00E+00  : 0.00E+00 't

-(ABOVE) .  :  :  :  :

=!

i b

k 6-3

t 3

e t

CHAPTER 7 TABLE 1C-1

-- GASEOUS ~ EFFLUENTS - Ground Level Releases RELEASE (S): ALL - UNIT 1  !

CONTINUOUS MODE BATCH MODE NUCLIDES  : UNITS :- QUARTER  : QUARTER  : QUARTER - : QUARTER :

1 RELEASED  : . 1  : 2  : 1  : 2  :

-1. FISSION AND ACTIVATION GASES XE-135- Ci 1.22E-01 0.00E+00 '

O.00E+00 0.00E+00 TOTAL FOR  :  :  :  :  :  :

PERIOD  :- C1  : 1.22E-01  : 0.00E+00  : 0.00E+00 0.00E+00  :

(ABOVE)  :  :  :  :  :

7-1

TABLE IC-lc RELEASE (S'): ALL.- UNIT 1 I GASEOUS; EFFLUENTS -; Ground Level Releases ~......_.............................__....________________...__'__.........

i CONTINUOUS MODE: BATCH MODE s'LNUCLIDES' : UNITS : QUARTER s' QUARTER  : QUARTER -: ' QUARTER  :

RELEASED- 3:- 1- 2  : 1- 's~ 2  :

+ 2.- IODINES

~ \

Y TOTAL FOR-  :  :  :  :  :-

PERIOD  : C1'  : 0.00E+00  : 0.00E+00  :-0.00E+00 0.00E+00  :

(ABOVE)  :  :  :  :  : -:

7-2

- r

. TABLE 1C -GASE00S' EFFLUENTS - Ground-Level' Releases

- RELEASE (S):-ALL - UNIT 14 CONTINUOUS P.0DE BATCH MODE s'- NUCLIDES- : UNITS : QUARTER  : QUARTER  : QUARTER  : QUARTER-

. RELEASED  :.  : 1  : 2. l'  : 2-  :

3.- PARTICULATES

.H-3 Ci 9.10E-04 1.65E-03 0.00E+00 0.00E+00 4

,8

. TOTAL ~FOR  :  :  :  :  :

PERIOD  : C1  : 9.10E-04  : 1.65E-03 0.00E+00 :-0.00E+00  :

(ABOVE)  :  :  :  : 1. s 7-3

.1%.

J. , y ,

n

'l i

I I

4.

.i CHAPTER 8 l 1

TABLE 1C-2 1 t

- GASEOUS-EFFLUENTS - Ground Level Releases RELEASE (S): ALL,- UNIT 2 i k

lT CONTINUOUS MODE BATCH MODE'

NUCLIDES  : UNITS : QUARTER  : QUARTER : QUARTER  : QUARTER  :

RELEASED  :- i, 1-  : 2  : 1  : 2 .:-

m 1. FISSION.AND. ACTIVATION GASES

-t t

.i r $

1 l ',

t t

. TOTAL FOR  :  :  :  :  :  :

PERIOD . C1 .
0.00E+00 0.00E+00 : 0.00E+00 0.00E+00  :

(ABOVE)  :  :  :  :  : -

r . ..-____.__.____.. ________________________________-__________________

i l'

8-1 q

t

I L TABLE IC-2 t

GASEOUS EFFLUCWTS - Ground Level' Releases'_____ _ _ _ _RELEASE (S):

_ _ _ _ _ _ _ _ _ _ _ _ _ ALL

_ _UNIT

_ _ _ _ .2-CONTINUOUS MODE BATCH MODE

. .NUCLIDES : UNITS's QUARTER  : QUARTER : QUARTER  : QUARTER ~ -'

= s. RELEASED- :  : 1  : 2  : 1 s. 2  :

2. 10 DINES

______________________________________________________________________1

'l TOTAL FOR'  :  :  :  :  : l PERIOD  : Ci  :=0.00E+00 0.00E+00 s'O.00E+00  : 0.00E+00 La-(ABOVE).  :  :  :  :  : .: d

______________._______________________________________________________ i l

i l

1 L i e

e I '- k

>l I+

1 i 1

)[

.i R f i

9 J

)

i

. r n

)

8-2

TABLE 1C l GASEOUS _, EFFLUENTS.-' Ground Level Releases -RELEASE (S)::ALL - UNIT-2 CONTINUOUS MODE BATCH-MODE-

NUCLIDES-: UNITS-: QUARTER  :: -QUARTER.:: ' QUARTER

-  : QUARTER :

RELEASED s'  : 1-  :. 2  : .1 -: 2  : --
3. PARTICULATES H-3 C1 7.13E-03 1.10E-03 0.00E+00 0.00E+00 I t t

-TOTAL FOR' :  :  :  :  :

PERIOD'  : C1  : 7.13E-03  : 1.10E-03 0.00E+00 0.00E+00  :

(ABOVE)= i  :  :  :-  :

V I:

8 >

m _

e.  :

t I

m b

CHAPTER 9 a

TABLE'2A-l' 1

+ -- LIQUID EFFLUENTS -- SUMMATION OF RELEASE (S): ALL -~ UNIT 1

.______________________________________________ l l UNITS l QUARTER l QUARTER l j 1

l l 1 l 2 1.

t

.A.. FISSION AND ACTIVATION PRODUCTS

__________________________________________________._______. 1 L .l 1. TOTAL RELEASEL(EXCL.I Ci l 2.08E-02 l 1.62E-02El '!

l TRIT.,. GASES, ALPHA)l l l l l

__________________________________________________________ l 4 ll 2. AVERAGE DILUTED 'luC1/ml l 1.57E-09 l 1.20E-09 l l l .l. CONC. DURING PERIOD l- l l l g ~

l 3~. PERCENT OF l  % -l 2.85E-03 l 3.00E-03 l A .!

l APPLICABLE LIMIT l l l l 1

___________________________ ______________________________ _ y l b' B.LTRITIUM

__________________________________________________________ j l.l. TOTAL RELEASE C1 l- 5.52E+01 l 1.89E+02-l l <

.l luci/ml l 4.15E-06 l 1.41E-05 l

l 2. AVERAGE DILUTED

'l CONC. DURING PERIOD l -l l l q

.l 3. PERCENT OF l  % l 1.37E-01 l 4.66E-01 l ^^ l l APPLICABLE LIMIT l l l l  ;

1 i

A (Summation of Fission and Activation Products C/MPC) x 100 l

9-1 1 ~ - - - - _ _. _ - - _ . . . _ . . -

3

g , M- . TABLE 2A-11

-y, ,

i,

(; 1 LIQUID EFFLUENTS - . SUMMATION'0F RELEASE (S)i'ALL-- UNIT,15  !

.._.... --.... .....--____.-_...-_......__.... 1

! UNITS l _ QUARTER l QUARTER l .}'

l l l' l <

-2' 'l t'_

m. .- y

' C. DISSOLVED:AND ENTRAINED GASES ,

t /'

lL1.LTOTAL~ RELEASE l. Ci l 2.08E-031l 1.74E-03 l luC1/ml l -1.56E-10
l ly2. AVT.: RAGE DILUTED 9.20E-11 l.

l CONC. DURING~ PERIOD l l l l

, ' 'l 3. Pi:RCENT OF. l .% l 7.77E-05 l 4.57E-05 l A g l -APPLICABLE LIMIT' l l l l D.; GROSS ALPHA RADIOACTIVITY y ..._...__-- ..........---_ ..--...-............-----_..... , a 6

lol. TOTAL-RELEASE.- l Ci l 2.55E-05 l 7.31E-06 l- q a

'1

- E. VOLUME WASTE RELEASED:. l LITERS l 8.95E+07 l 9.61E+07..l  !

, -(PRIOR TO DILUTION). -l- l l l 'l

.._......_. ........--..._.--.........-----............__- ) o F.~ VOLUME, DILUTION' HATER ~l LITERS l 'l.33E+10-l 1.34E+10 l.

l USED DURING PERIOD- l l l .l' d l

A-(Dissolved and Entrained Gaser Concentration)/(2.00E-04) x 100.

~

j u o i -;

1 M

~  !

p l

q s

7 l'

v 9-2 i

___.__I._E______

-__________.__.__.__.______[.__ . 2.

I CHAPTER 10 TABLE 2A-2

- LIQUID EFFLUENTS -- SUMMATION OF RFLEASE(S): ALL - UNIT-2  !

l UNITS l QUARTEF. l QUARTER l l~ l 1 l 2 l A. FISSION AND ACTIVATION PRODUCTS l 1. TOTAL RELEASE (EXCL.l Ci l 1.68E-02 l 1.61E-02 l-l TRIT., GASES, ALPHA)l l l l

. l 2. AVERAGE DILUTED luCi/ml l- 1~.13E-09-l 1.08E-09 l l CONC. DURING PERIOD l l l l l 3.. PERCENT OF l  % l 1.43E-03 l '2.42E-03-l A l APPLICABLE LIMIT l l l l B.' TRITIUM

.l 1. TOTAL RELEASE l Ci l 1.09E+02 l 1.91E+02 l l 2.' AVERAGE DILUTED luC1/ml l 7.28E-06 l 1.29E-05 l

~l. CONC. DURING. PERIOD l l l l l 3. PERCENT OF l  % l 2.41E-01 l 4.26E-01 l **

l APPLICABLE LIMIT l l l l k:

A .(Summation of Fission and Activation Products C/MPC) x 100 AA (Tritium C/MPC) x 100 10-1

_:_ ____ _ =_ ____ ____- __ - - _ -__________ _ _

TABLE 2A 1 ,

= LIQUID EFFLUENTS -- SUMMATION OF RELEASE (S): ALL - UNIT 2 l' UNITS I QUARTER l QUARTER 1;

..l -l 1 1 2 l

'C. DISSOLVED AND ENTRAINED GASES i i,

l'l.= TOTAL: RELEASE.

l Li l 8.99E-04 l 1.90E-03-l  !

li2. AVERAGE DILUTED luCi/ml l 6.03E-ll l- -1.28E-10 l-l- l

_____ CONC. DURING PERIOD l________l'____________l-a

, l 3. PERCENT OF l  % l 2.99E-05 l 6.35E-05 l-A f j

l- . APPLICABLE LIMITz -1 l l l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _j _ _ -

D. GROSS ALPHA RADIOACTIVITY

-l 1. TOTAL RELEASE l Ci l 3.96E-06.l '2.03E-06 l E.-VOLUME WASTE RELEASED ! LITERS 1. ole +08 '

l.11E+081

'l- .( PRIOR TO DILUTION)-

F. VOLUME DILUTION WATER l LITERS-l "1.49E+10 l 1.48E+10 l

~l -USED DURING PERIOD l l. I i

'A'-(Dissolvedland Entrained Gases Concentration)/(2.00E-04) x 100 10-2 a

0 a

4 n 1 F

CHAPTER 11

, TABLE 2B-1

. LIQUID-EFFLUENTS. RELEASE (S): ALL - UNIT 1 i CONTINUOUS MODE BATCH MODE

--NUCLIDES .: UNITS : QUARTER : -QUARTER : QUARTER : :- QUARTER :-

RELEASED :  : 1  : 2  : 1  : 2  :

H-3 C1 2.80E-01 2.13E-03 5.49E+01 1.89E+02

'CR-51 Ci 0.00E+00 0.00E+00 7.42E-05 3.65E-04

-MN-54' Ci 0.00E+00 0.00E+00 4.00E 9.07E-05 '

FE-55 C1. 1.68E-03 2.88E-03 -1.84E-03 1.22E-03 FE-59 Ci 0.00E+00 0.00E+00 6.23E-06 6.03E-04 CO-58 Ci 0.00E+00 0.00E+00 3.92E-03 2.63E-03 CO-60 Ci 0.00E+00 0.00E+00 2.71E-03 3.04E-03 ZN C1 0.00E+00 0.00E+00- 0.00E+00 4.27E-06 RB-88 Ci 0.00E+00 0.00E+00 5.63E-05' O 00E+00 SR Ci 0.00E+00 0.00E+00 9.99E-06 5.68E-06 SR-92 Ci 0.00E+00 0.00E+00 0.00E+00 2.05E-05 ZR C' O 00EiOO 0.00E+00 7.31E-05 9.65E-05 NB-95' Ci 0.00E+00 0.00E+00 2.64E-04 2.59E-04 TC-99M Ci 0.00E+00 0.00E+00 1.13E-06 0.00E+00 l RU-103 Ci 0.00E+00 0.00E+00 5.35E-06 1.28E-05 RU-105~ Ci 0.00E+00 0.00E+00 0.00E+00 1.06E-05 RU-106 C1' O.00E+00 0.00E+00 2.82E-05 1.59E-04 AG-110M C1 0.00E+00 0.00E+00 6.70E-04 1.31E-03 I-131- Ci 0.00E+00 0.00E+00 1.01E-06 2.08E-06 03-134 Ci 0.00E+00 0.00E+00 2.62E-04 5.40E-04' CS-137' Ci 0.00E+00 0.00E+00 1.36E-03 1.93E-03 G. ALPHA .Ci 1.74E-05 4.06E-07 8.18E-06 6.91E-06 11-1

.u TABLE 2B-1 m 1 RELEASE (S)s'ALL . UNIT.12

___' LIQUID EFFLUENTS ______..__ .__..___.._________'_ ____________ ,

CONTINUOUS MODE BATCH [

____..___________......______________...._________________' MODE ___ ........

- NUCLIDES  : . UNITS : QUARTER  : QUARTER : QUARTER -QUARTER  ::

s RELEASED  :  : 1  : 2  : 1  :  : -

___..___..________________.........____________ ___.______ .._2_______ . .

9B-124 Ci 0.00E+00 0.00E+00 1.40E-05 0.00E+00

.s -97 C1 0.00E+00 0.00E+00 4.13E-05 1.74E-05 SB-125 Ci 0.00E+00 0.00E+00 7.78E-03 9.83E-04 o CO-57 C1 0.00E+00 0.00E+00 0.00E+00 7.79E-07 3 1

F 1

.i

'r .

4

i

. TOTAL FOR  :  :  :  :  : , t

-PERIOD  : Ci  : 2.82E-01 3 5.01E-03 .: 5.49E+01 - : --l . 89E+0 2  : i,

(ABOVE)  :  :  :  :  :  !

L F

a-l 1.

l 11-2 l

w h

i TABLE 2B-1 LIQUID EFFLUENTS - DISSOLVED AND ENTRAINED GASES --UNIT 1

. RELEASE (S): ALL CONTINUOUS MODE BATCM MODE- l

-- NUCLIDES  : UNITS :. QUARTER  : QUARTER  :- QUARTER  :- QUARTER  :
RELEASED  : 's 1  : 2  : 1-  : 2  :

KR-85M C1 0.00E+00 0.00E+00 1.93E-06 0.00E+00 XE-133M 'Ci 0.00E+00 0.00E+00 0.00E+00 3.90E-06 XE-133 C1 4.06E-04 0.00E+00 6.14E-04 1.23E-03 c XE-135 C1 1.01E-03 3.00E+00 4.25E-05 6.13E-06 i TOTAL FOR  :  :  :  :  :  :

PERIOD

Ci  : 1.42E-u3  : 0.00E+00 i 6.59E-04  : 1.24E-03  :

(ABOVE) a  :  :  :  :  :

i i

11-3

. u -.

. f,((

p CHAPTEP 12 i

TABLE 2B-2 s

LIQUID EFFLUENTS RELD.SE( S ) : ALL - UNIT 2 , (

CONTINUOUS MODE BATCH MCiE 5 NUCLIDES  : UNITS : QUARTER  : QUARTER  : QUARTER  : QUARTER  :

[

- RELEASED :  : 1  : 2  : 1  : 2  : ;

l 4

H-3 C1 '2.97E+00 2.32E+00 1.06E+02 1.89E+02 CR-51 Ci 0.00E+00 0.00E+00 5.01E-05 9.82E-04 MN-54 Ci 0.00E+00 0.00E+00 1.41E-05 5.79E-05 .

FE-55 C1 1.41E-03 3.05E-03 2.48E-03 9.26E-04 i TE-59 Ci 0.00E400 0.00E+00 'l 22E-06 9.67E-04 f CO-58 Ci 0.00E+00- 0.00E+00 E.12E-04 2.98E-03 i CO-60 Ci 0.00E+00 0.00E+00 8.330-04 2.10E-03' RB-88 Ci 0.00E+00' O.00E+00- 0.00E+00 1.46E-05 SR-92 Ci 0.00E+00 0.00E+00 1.07E-05 4.88E-06 ,

ZR-95 Ci 0.00E+00 0.00E+00 6.48E-06 7.33E-05 NB-95 Ci 0.00E+00 0.00E+00 2.79E-05 1.58E-04 RU-103 C1 0.00E+00 0.00E+00 0.00E+00 4.24E-06 i RU-106 Ci 0.00E+00 0.00E+00 0.00E+00 4.84E-05 ,

AG-110M Ci 0.00E+00 0.00E+00 4.10E-04 9.60E-04 CS-134' C1 0.00E+00 2.50E-04 1.71E-04 4.58E-04 '

CS-137 Ci 0.00E+00 5.12E-04 8.56E-04 1.59E-03 ND-147 Ci 0.00E+00 0.00E+00 0.00E+00 1.50E-06 t Gs. ALPHA Ci 0.00E+00 0.00E+00 3.96E-06 2.03E-06 e

12-1 l L I

TABLE 2B-2 LIQUID EFFLUENTS RELEASE (S): ALL - UNIT 2 CONTINUOUS MODE BATCH MODE NUCLIDES  : UNITS : QUARTER  : QUARTER  : QUARTER  : QUARTER  :

RELEASED  :  : 1  : 2  : 1 i 2 .

I

___........................ .............................. _.......... 1 SB-124 C1 0.00E+00 0.00E+00 8.13E-06 0.00E+00 NB-97 Ci 0.00E+00 0.00E+00 9.32E-05 5.67E-06 SB-125 Ci 0.00E+00 0.00E+00 9.81E-03 9.19E ,

CO-57 Ci 0.00E+00 0.00E+00 0.00E+00 9.78E-07

(

i I

P TOTAL FOR  :  :  :  :  :  :

PERIOD  : C1. 2.97E+00  : 2.32E+00  : 1.06E+02  : 1.89E+02  :

(ABOVE)  :  :  :  :  :  :

I t

12-2 L

l 1

J.

TABLE 2B-2 k

t LIQUID EFFLUENTS - D7SSOLVED AND ENTRAINED GASES - UNIT 2 RELEASE (S): ALL CONTINU0US MODE BATCH MODE NUCLIDES  : UNITS : QUARTER  : QUARTER  : QUARTER  : QUARTER  :

RELEASED  :  : 1 2  : 1  : 2  :

XE-133 Ci- 0.00E+00 0.00E+00 8.99E-04 1.89E-03.

XE-135 Ci 0.00E+00 0.00E+00 0.00E+00 6.81E-06 t

TOTAL FOR  :  :  :  :  :  :

PERIOD  : Ci  : 0.00E+00 0.00E+00 3.99E-04  : 1.90E-03  :

(ABOVE)  :  :  :  :  :  :

s I

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e

  • 12-3 -

l I

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i i _ 1

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i CHAPTER 13 TABLE 3 SOLID HASTE AND IRRADIATED FUEL SHIPMENTS  !

Ist Half, 1990 SOLID NASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

\

(not irradiated fuel) '

l l 1. Type of Haste UNITS PERIOD I

! Jan. 1 - June 30 3

a. Spent res!.ns, filter sludges, m 3.250E+00 evaporator bottoms, etc. Ci* 6.592E+00 3
b. Dry compressible waste, m 2.477E+01 contaminated equipment, etc. Ci* 6.100E-01 0

3

c. Irradiated components, m NONE control rods, etc. Ci NONE 3

l d. Other m None Ci None

  • Measured and/or estimated by correlations in a ccordance with 10 CPR 61.55.

13-1

n .

TABLE 3 n

t i~ . .

(2. Estimate of major nuclide composition ISOTOPES  %

, t f a. Fe-55 50.2 i 00-60 31.9 Ni-63 10.7 i C-14 2.2 Pu-241 1.0 j

b. Fe-55 37.2  :

Co-58 29.6 Co-60 8.0 Ni-63 5.7  !

- Cr-51. 5.2 l H-3 3.7 Mn-54 2.9 Nb-95 2.8 Zr-95 1.5 J

13-2 l

E 1 L -i-TABLE 3

'l

!. I l

TABLE 3 (con't) I SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l

1st Half, 1990

3. Solid Waste Disposition I 1

. Number of Shipments 12

. . 1

b. Mode of Transportation Highway
c. Destination Chem-Nuclear Systems, Inc. 1 Barnwell, South Carolina '
4. Type of Containers
a. ( la ) High Integrity Containers,
b. ( lb ) Strong Tight Containers.
c. ( Ic ) N/A 5.- Solidification Acents
a. ( la ) No solidifications during this period. All items.(spent resin and charcoal) that are categorized for item la were shipped dewatered.
b. ( lb ) N/A B2 IRRADIATED FUEL SHIPMENTS (Disposition)
1. Number of Shipments None
2. Mode of Transportation N/A
3. Destination N/A i.

l 13-3  !

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CHAPTER 14 TABLE 4 i

b TABLE 4 ,

RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ,

FARLEY NUCLEAR PLANT - UNITS 1 & 2 a,h Gassous Release Sampling Minimum Type of Minimum Type Frequency Analysis Activity Detectable Frequency Analysis ' Concentration (MDC) (uCi/ml) 9,j I A. Haste Gas Each Tank Each Tank Principle 1E-04 Storage Tank Grab b Gamma Sample P P Emitters j g,j ,

B. Containment ~ Each Purge Each Purge Principle 1E-04 Purge Grab b Grab b Gamma Emitters (

Sample P Sample P H-3 1E-06 9,j C. Condenser M-b,c,e b Principle Steam Jet' Air Grab M Gamma Emitters 1E-04 Ejector Plant Sample Vent Stack H-3 1E-06 14-1

TABLE 4 TABLE 4 (Continued) a,h G2ccous Release Sampling Minimum Type of Minimum Type Frequency ~ Analysis Activity Detectable Frequency Analysis Concentration (MDC) (uCi/ml) f D. Plant Vent Continuous Charcoal I-131 1E-12

, Stack Charcoal Sample d Containment H I-133 lE-10 Purge f g Continuous Particulate Principle Sample d Gamma Emitters lE-11 W (I-131, Others) f Continuous ~ M i Composite Gross Alpha lE-11 Particulate Sample f

Continuous 0 1 Composite Particulate Sr-89, Sr-90 1E-11 Sample f

Continuous Noble Gas Noble Gases Gross 1E-06 '

Monitor Beta and Gamma 14-2

- I

TABLE 4 t

TALLE 4 (Continued)

TABLE NOTATION

o. The MDC is the smallest con' centration of radioactive material in a sample that will be detected with 95% probability with 5%

probability of falsely concluding that a blank observation .

represents a "real" signal. i For a particularfmeasurement system'(which may include l radiochemical separation): .

j 6 j MDC = 4.66 s /EA VA 2.22X10 A YA exp (-lat) l b

1

'where j a

MDC is the "a priori" lower limit of detection as defined I above (as microcurie per unit mass or volume), i s is the standard-deviation of the background counting rata l I

b '

or of the counting rate of.a blank sample as appropriate (as counts per minute), .

E is the counting efficiency (as counts per transformation), j V is the sample size (in units mass or volume), ,

6 2.22X10 is the number of transformations per minute per  ;

nicrocurie,-

Y is the fractional radiochemical yield (when applicable),

A is the radioactive decay constanc for the pac *.icular radionuclide, and  ;

at is the elapsed time between midpoint of sample collection .

and time of. counting (for plant effluents, not environmental  ;

samples).  ;

The'value of a used in the calculation of the MDC for a b'

detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified .

theoretically predicted variance. Typical values of E, V, Y, .'

and At shall be used in the calculation.

l 14-3

I TABLE 4 l TABLE 4 (Continued)

TABLE NOTATION

- b. Analyses shall alsc be performed following shutdown from ) or = l 15% RATED THERMAL POWER, startup to > or = 15% RATED THERMAL l p0WER or a THERMAL POWER change exceeding 15% of the RATED THERMAL 1 POWER within a one hcur period. ]

c. Tritium grab samples shall be taken from the plant vent stack ct least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded. l
d. Samples shall be changed at least once per 7 days and analyses i shall be completed within 48shours after changing (or after ,

, removal from sampler). Sampling shall also be performed at  ;

least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from ) or = 15% RATED THERMAL POWER, startup to > or =

15% RATED THERMAL POWER or THERMAL POWER change exceedine, 15%

of RATED THERMAL POWER in one hour and analyses shall be ,

completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding MDC may be increased by a factor of 10.

o. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. ,
f. The ratio of the. sample flow rate to the sampled stream flow

. rate shall be known for the. time period covered by each dose or dose rate calculation made in accordance with Specifications 1 3.11.2.1, 3.11.2.2 and 3.11.2.3.

g. The principle _ gamma emitters for which the MDC specification cpplies exclusively are the following radionuclides: Mn-54, ,

-Fe-59, Co-58, Co-60, Zn-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 to be detected and reported. Other i l Which are measurable and identifiable, together with the above nuclides, shall also be' identified and reported.

h. Deviations from MDC requirements of Table 4.11-2 shall be reported per Specification 6.9.1.8 in lieu of any other report.

' i. A composite particulate sample is one in which the quantity of cir sampled is proportional to the quantity of air discharged.

Either a specimen which is representative of the air discharged ray be accumulated and analyzed or the individual samples may ,

be analyzed and weighted in proportion to their respective  !

Lvolume discharged.

14-4 f

- r- p

TABLE 4 (

Il TABLE 4 (Continued) .i

j. The principle gamma e,witters for which the MDC speciff. cation cpplies exclusively are the following radionuclides: ht --87,  :)

Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous  ;

c issions. This does not mean that only these nuclides are to I b], detected and. reported. Other peaks which are measurable and i; identifiable together with the above nuclides, shall also be l identified and reported.  ;

b 14-5 4

-- -- - -- k

TABLE 4 r

4. ,;, -

TABLE 4 (Continued)

TYPICAL GAS MDC'S FOR RCLS

, COUNTING SYSTEM Nuclide MDC ( uCi/ml ) Nuclide - MDC ('uC1/ml )

Mn'-54 1.46E-14 Ce-144 5.08E-14 Y Fo-59 4.51E-14 Kr 3.44E-08 Cc-58 1.55E-14 Kr-88 4.71'E-08 Co-60 2.81E-14 Xe-133 6.3r,E-08 Zn-65 3.04E-14 Xe-133M 1.54E-07 M3-99 1.02E-13 Xe-135 1.91E-08 Cs-134 4.08E-11 Xe-138 5.04E-08 Cs-137 1.31E-14 1 131 3.20E-14 Ce-141 1.13E-14 I-133 2.87E-14 i

14-6 i i

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h l

CHAPTER 15

,e TABLE 5 t

+

TABLE 5 '

RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM FARLEY NUCLEAR PLANT - UNITS 1 & 2 ,

-i a,g l Liquid Release Sampling Minimum Type of Minimum i Type Frequency Analysis Activity Detectable Frequency Analysis Concentration H (MDC) (uC1/ml) ,

c P P e Ao Batch W'ste Each Each Principle Release Batch Batch Gamma SE-07 Tanks Emitters I-131 1E-06 One Batch /M M Dissolved &

Entrained Gases 1E-05 (Gamma Emitters)

P Each b Batch M H-3 1E-05 Composite Gross Alpha 1E-07 15-1

, TABLE 5 TABLE 5 (Continued) agr Liquid Release Sampling Minimum Type of Minimum 17pe Frequency Analysis Activity Detectable-Frequency Analysis Concentration (MDC) (urz/ml)

P Each b Batch Q Sr-89, Sr-90 SE-08 Composite Fe-55' 1E-06 {

d,f D b e B. Continuous Grab W Principle Releases Sample Composite Gamma SE-07

. Emitters I-131 1E-06 M

1. Steam Grab M Dissolved &

Generator Sample Entrained Gases lE-05 Blowdown (Gamma Emitters)

D b Grab M H-3 1E-05 Sample Composite i

_ Gross Alpha 1E-07 D b-Grab Q Sr-89, Sr-90 5E-08 Sample Composite Fe-55 1F P b e i 2.-Turbine Grab W Principle SE-07 Building Sample Composite Gamma Sump Emitters H-3 lE-05 L

i l

15-2

i i TABLE 5 i

TABLE 5 (Continued)

TABLE NOTATION

c. The MDC is the smallest concentration of radioactive material in.a sample that will be detected with 95% probability with 5%

probability of falsely concluding that a blank ooservation l rcpresents a "real" signal. l For a particular measurement system (which may include  ;

rcdiochemical separation):

- 6 S MDC. = 4.66 s / E

  • V
  • 2.22X10
  • Y
  • exp (-AAt) i b

where: ,

MDC is the "a priori". lower limit of detection as defined above (as microcurie per unit mass or volume),

i s is the standard deviation of the background counting rate -

l b -

or of the counting rate of a blank sample as appropriate.(as ,

counts per minute),

E is the counting efficiency (as counts per' transformation), l V is the sample size (in units mass or volume),

.6 2.22X10 is the number of transformations per minute per

. microcurie, ,

Y'is the fractional radiochemical yield (when applicable),

A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental

. samples).

  • The value of s used in the calculation of the MDC for a b ^

detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the ~

blank. samples-(as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y,

.and At shall be used'in the calculation.

P 15-3

l TABLE 5 i TABLE 5 (Continued)

TABLE NOTATION i

b. A composite sample is one in which the quantity of liquid sampled  !

is proportional to the quantitr of liquid waste discharged and in j which the method of sampling employed results in a specimen which i is_ representative-of the liquids released. I I

c. A batch release is the discharge of liquid wastes of a discrete l volume. Prior to sampling for analyses,-each batch shall be .

isolated, and'then thoroughly mixed, by a method described in the q ODCM, to assure representative sampling.

'd.fA continuous release is the discharge of liquid wastes cf a g nondiscrete volume; e.g., from a volume of system that has ,

an input flow during the effluent release.

O. The principle gamma emitters for which the MDC specification ,

.cpplies exclusively are the following radionuclides: Mn-54, i Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137,Ce-141, cnd Ce-144. This list does not mean that only these nuclides

, cre to be detected and rcported. Other peaks which are ,

teasurable and identifiable, together with the above nuclides,

, shall also be identified and reported, f, Sampling will be performed only if the effluent will be discharged to the environment.  ;

g. Deviation from the MDC requirements of Table 4.11-1 of the TS shall be reported per Specification 6.9.1.8 in lieu of cny-other report.

5 l

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T 15-4

r, TABLE 5 l-i TABLE 5 (Continued)

TYPICAL LIQUIP MDC'S FOR RCLS COUNT 2WG SYSTEM l

Nuclide MDC ( uCi/ml ) Nuclide MDC ( uC1/mi )

Mn'-54 2.98E-08 I-131 2.13E-08 CD-58 2.15E-08  ;-134 1.75E-08  !

Fa-59 4.43E-08 Cs-137 2.67E-08  !

CO-60 3 86E-08 Ce-141 3.40E-08

, Zn-65 7.94E-08 Ce-144 1.65E-07 M3-99 1.88E-07 I i

i l

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i 15-5 1

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37 . .; . - - _ _

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CHAPTER 16 TABLE 6 i

  • t TABLE 6 LIQUID DISCHARGES NJT MEETING SPECIFIED DETECTION LIMITS ,

Farley Units 1 & 2 - 1st half, 1990 i

Batch # N/AA Date N/A Count Time in Seconds N/A

. Volume Discharged in Gallons' N/A ',

Dilution Water in Gallons N/A i Total Isotopic Activity ( uCi/ml ) N/A Isotope of Interest N/A .

MDC Measured N/A

.% of Total Isotopic Activity N/A

% of Total Dose N/A ,

  • No liquid discharges made that did not meet specified detection limits.

16-1 L

CHAPTER 17 PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the first half of 1990.-

+

17-1 A

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