ML19354D427

From kanterella
Jump to navigation Jump to search
Revised Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jan-June 1988.
ML19354D427
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/30/1988
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054B077 List:
References
NUDOCS 8911080516
Download: ML19354D427 (11)


Text

.. .. ..

(_ ;;; e ^~.. ,

s

.

  • j t'

y l i

II

- I I

ATTACHMENT Consumers Power Company Palisades Plant I Docket 50-255 l

,c SEMI ANNUAL RAI,10 ACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUCH JUNE 1988 l

' Revised 10/5/89 a

P I

h I

t

\ )

8911080516 891030 -

$DR ADOCK 05000255r/

PNV g IC0888-0179A-HP01 1

,- ,,n., , - - .~, --..n.-, , - - - - - , - - - , - . , - - , -

/t ' V. i 4

/

REVISED i

Palisades Nuclear Plant Semiannual ~'

Radioactive Effluent Release Report January - June 1988 .

.This report provides information relating to radioactive ef fluent releases and sclid radioactive waste processing at the Palisades Nuclear Plant during the period of January through June 1988. The report format is detailed in Plant i Technical Specification 6.9.3.la. Palisades has been on-line during this ,

reporting period since being returned to service January 27, 1988.

1. Supple 3 ntal Information A. Batch Releases .

i

'Information relating to batch releases of gaseous and liquid -

effluents is provided in Table HP 10.5-1.  !

B. Abnornal Releases  :

LER-PAL 88-002 On February 9, 1988 at 1630 an Auxiliary Operator (AO) identified I that the in-service waste gas decay tank (WCDT) T-68C (WEITK] had lost approximately 26 pai. The gas from the WCDT was released into the Auxiliary Building (NF] and ultimately to the atmosphere via the monitorea Plant stack. The gaseous release from the in-service tank is contrary to Technical Specification (TS) 3.24.6.1 which states, "the WCDT system shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days up to 60 days".

  • During the event, 6.032 curies of noble gas as Xe-133 were released over a period totaling one hour. The release was averaged over a one hour period resulting in an MPC fraction of 8.0E-3 at the site  ;

boundary. This value is a small portion of the one maximum permissible concentration fraction allowed at the site boundary.

The release was monitored by Plant stack radiation monitoring equipment. No alarms or annunciations were received in the Control Room due to the highest count rate seen being a factor of approximately five below the alert alarm setpoint. Therefore, due to the insignificant dose consequence, no adverse effects were 1 presented to the general public.

l IC0888-0179A-HP01 2

[ ."> \* .' 'l

' Y c

i e

2. Caseous Effluents '

Table HP 10.5-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 1.13E-06% of the total release. -

3. Liquid Effluents -

Table HP 10.5-3 lists and summarizes all liquid radioactive ef fluents released during the reporting period. There was no unidentified beta released. '

4. Solid Waste Solid radwaste classif cation, sources, volume shipped, curie and nuclide '

content are detailed in Table HP 10.5-4. All radwaste shipments were made to either Barnwell, South Carolina or Richland, Washington for.

burial.  ;

5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using i CASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and summarized as followst A. The maximum offsite air dose at the site boundary due to noble gases was 3.30E-02 millirad beta and 1.11E-02 millirad gamma for the first

' L' quartert and 4.72E-02 millirad beta and 1.59E-02 millirad gamma for the second quarter. .

B. The most restrictive organ dose to an individual in an unrestricted area (b'a sed on identified critical receptors) f rom gaseous ef fluents <

(tritium, particulates and lodine) was the infant thyroid. Doses were 9.01E-03 and 8.24E-03 millirem for the first and second quarters, respectively.

C. Integ -;-e i .nal body doses to the general population and average doses , a viduals (adults) within the population f rom gaseous effluent , oses within a distance of 50 miles from the site i boundary e.rs: 1.73E-02 manRem and 1.65E-05 millires for the first quartert and 2.12E-02 manRem and 2.02E-05 millirem for the second quarter.

D. The maximum total body dose to an individual (adult) in unrestricted water - related exposure pathways was 4.54E-03 and 2.67E-03 millirems for the first and second quarters, respectively. The maximum organ doses were 7.90E-03 millires (teenage bone) for the first quarter and 4.42E-03 millirem (teenage liver) for the second quarter.

IC0888-0179A-HP01 3

_ ~_ _ _ _ _

i y. .

t?* ,

i l,

E. . Integrated total body doses to the general population and average dosts to individuals (adults) within the population from liquid '

effluent releases within a distance of 50 miles from the site boundary were: 1.63E-02 manRem and 1.55E-05 millirem for the first -

quartert and 1.02E-02 manRem and 9.71E-06 millirem for the second ,

q ua rt e r .

, F. Both the Selenium-75 present in the gaseous effluent releases and the entrained noble gases present in the liquid releases (first and I second quarters) were not significant in either wholebody or organ doses.

6. Process Cont rol Program (PCP)

There were no changes to the PCP during the reporting period. .

7. Of f site Dose Calculation Manual (ODCM)

There were no changes to the ODCM during the reporting period.

8. Supplemental Information for the July-December 1987 Semiannual 5 Radioactive Effluent Release keport l

' The Palisades Nuclear Plant Semiannual Radioactive Effluent Release Repo rt i July - December 1987, Tables HP 10.5-2 Caseous Effluents and Tables HP 10.5-3 Liquid Ef fluents are being submitted as an attachment with the following revisions:

A. Table HP 10.5-2, Caseous Effluents - Summation of Releases, items C.1. and C.2., 4th Quarter only:

Change the Particulates with half-life > 8 days from 4.45E-04 Ci to 4.44E-04 Ci. +

Change the average release rate for period from 5.60E-05 uCi/se: to 5.58E-05 uCi/sec. t B. Table HP 10.5-2, Caseous Ef fluents (isotopic Ci listings), item 3 Particulates, 4th Quarter only' Change Sr-89 from 4.8E-06 Ci to 2.6E-06 Ci Change Sr-90 from 1.6E-06 Ci to 9.2E-07 Ci Change Net Unidentified Beta from 2.88E-04 Ci to 2.90E-04 )

Change particulate isotope total from 4.45E-04 Ci to 4.44E-04  ;

C. Table HP 10.5-3, Liquid Effluents - Summation of All Releases, items  !

, A.3. and D., 4th Querter only: I i

Change the Percent of MPC from 6.17E-02 to 5.86E-02.

1 Change the Crosa Alpha Radioactivity (Total Release) from 2.7E-05 to l 8.2E-06. l IC0888-0179A-H?01 4 l

l

t; n/' -

y_ w-f .

P Change the gross alpha average diluted concentration during period from 8.9E-13 to 2.7E-13.

i.

D. Table HP 10.5-3, Liquid Ef fluents (isotopic Cl listings), item 1. ,

Nuclides Released, 4th Quarter only!

Change Sr-89 from 5.6E-06 Ci to 3.3E-04 C1 Change Sr-90 from 6.lE-04 Cl to 4.3E-04 Cl Change Net Unidentified Beta from 3.73E-03 Cl to 3.59E-03 Ci E. In the Palisades July - December 1987 Semi-Annual Radioactive Effluent Release Report Narrative, the following changes are also x- noted:

Item 2 - Caseous Effluentst change from "the unidentified beta was 4.09E-05% of the total release" to "the unidentified beta was 4.10E-05%" of the total release".

Item 3 - Liquid Effluents: change from "the~ unidentified bets was 4.60E-03% of the tstal release" to "the unidentified oeta was 4.46E-03% of the total release".

Raasons for the above data revisions to the Palisades Semi-Annual Radio-at ti ve Ef fluent Release Report, July - December 1987 was that the calcu '

la:ed Sr-89 and Sr-90 release quantities (gaseous and liquid effluents.

4th Quarter only) were based on estimated values for the months of November and December. Teledyne Isotcpve Midwest Laboratory had not yet completed the actual sample analyses priae to the Technical Specification-Semi Annual Report due date. All dats. changes are indicated by "#" in the right-hand margins. There were no significant dose changes to the i public.

4 l

l  !

i 1

IC0888-0179A-HP01 5

/*

v .

t TABLE HP 10.5-1 PALIS ADES NUCLE AR PLANT SEMI AMWUAL RADIOACT!'.'E l EFFLUENT RELEASE REPORT BATCH RELEASES  ;

JANUARY 1988 to JUNE 1988 ,

A. CASEOUS Units '

lst Quarter 2nd Quarter Number of Releases 14 18 -

Total Release Time Minutes 2.72E+03 7.54E*03 Maximum Release Time Minutes 3.41E+02 1.77E+03 Averaae Release Time Minutes 1.94E+02 4.19E+02 Minimus Release Time Minutes 1.13E+02 9.00E+01

8. LIQUID Units let Quarter 2nd Quarter .

Number of Releases 20 16  !

Total Release Time Minutes 4.37E+03 6.71E+03 -

l  ;

Maximum Release Time Min"tes 5.67E+02 i 6.95E+02  !

1  !

A'terate Release Time Minutes 2.19E+02 4.20E+02 i

sfinimum Release Time Minutes 4.90E+01 6.10E+01 '

l I

1 l

l i

l l

1 I

IC0888-0179A-HP01 5 I

l l

__ _ - _ - - - _ - _ _ _ ,. _ . , _ _ _ _ _i

g. .

TABLE HP 10.5-2 PALIS ADES NUCLEAR PLANT SEMI ANNUAL RADIOACTIVE EFFLUSNT RELEASE REPORT CASEOUS EFFLUENTS - SUMMATION OF RELEASES JANUARY 1988 to JUNE 1988 r

l Est Total A. FISSION AND ACTIVATION CASES f UNITS 1st QUARTER 2nd QUARTER: Error !

1. Total release ci 6.93E+02 9.91E*02 '
2. Averane release rate for period uct/sec 8.81E+01 1.26E+02 1 7.20 >
3. Percent of annual ava MPC i  % 4.20E-02 1 6.01E-02 i I B. IODINES
1. Total ledine i Ci 3.81E-03 2.75E-03
2. Averane release rate for period
  • i uCi/sec 4.21E-04 3.50E-04 4.37*
3. Percent of annual ava MPC
  • l  % 4.11E-04 3.63E-04 C. PARTICULATES  ?
1. Particulates with half-Life > j '

8 days I Cl 1.27E-04 1.78E-05  ;

2. Averane release rate for period I uCi/see 1.62E-05 2.26E-06
3. Percent of annual ava limit MPC i  % 1.09E-05 1.90E-06 7 5 .1 **

i 4 Cross alche radioactivity ' Ci 3.86E-06 5.36E-06

5. Cross alpha average release rate l for period I uci/Sec 4.91E-07 6.82E-07 ,

i D. TRITIUM '

i 1. Total release Ci 9.18E-01 8.98E-01

2. Average release rate for period i uCi/sec 1.17E-01 1.14E-01
3. Percent of annual ava MPC I  % 8.36E-05 8.14E-05 I E. *
1. Beta air dose at site boundary due to Noble Geses (TS 3.24.5.2a) mRads 3.30E-02 4.72E-02
2. Percent limit  % 3.30E-01 4.72E-01
3. Camma air dose at site boundary due j to Noble Cases (TS 3.24.5.21) mRads ! 1.11E-02 1.59E-02 4 Percent limit  % 2.22E-01 3.18E 01 F.
1. Maximum organ dose to public based . >

based on critical receptors l (TS 3.24.5.3) mRes 9.01E-03 ! 8.24E-03

2. Percent of limit I  % 1.20E-01 i 1.10E-01
  • Note Data is reported f or I-131 and I-133 only.
    • Notet Large error f actor due to very small amount of particulates present in gaseous effluents.

IC0888-0179A-HP01 6

1 TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMI ANNUAL RADI0 ACTIVE t i

EFFLUENT RELEASE REPOE  ;

CASE 0VS EFFLUENTS I JANUARY 1988 to JUNE 1988

1. FISSION CASES Units let OUARTER I 2nd QU ARTE R i i Krypton-85 Ci I 7.90E-01  !

4.24E-Cl I Krypton-85m Ci 1.16E-02 1 5.79E-03 I

i I Krypton-87 Cl 1.42E-02 2.39E-03 Krypton-88 Ci 1.71E-02  ! 5.96E-03 ,

1 l Xenon-131m Ci 2.13E-01 1 7.37E-02

, Xenon-133 Ci 6. 9 2 E.+0 2 9.91E+02 l Xenon-133e ci 1.91E-02 1.92E-02 i Xenon-135 l Ci 6.30E-02 5.95E-02 Xenon-135m Ci 3.84E-02 8.49E-03

!- Xenon-138 Ci 2.62E-02 3.61E-03 Arnon-41 Cl 9.20E-04 None

, i

' l Total for Period Ci 6.93E+02 i 9.92Ec02

2. IODINES Iodine-131 Ci 1.91E-03  ! 1.75E-03 l i Iodine-132 Ci . None '

None 1 e n .

1 i Iodine 133 Ci  ! 1.40E-03 8 9.96E-04 Iodine-135 Ci I 5.04E-04 None l

Total for Period C1 3.81E-03 2.75E-03 l, IC0888-0179A-HP01 7 l

f . .. .

p , .

TABLE HP 10.5-2 '

PALISADES NUCLEAR PLANT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CASE 00S EFFLUENTS JANUARY 1988 to JUNE 1988

3. PART!CULATES
  • Units  ! let QUARTER t 2nd (UARTER

~

Chromium-51 Cl None None '

Manganese-54 i Ci None I None Cobalt -58 Ci 1.32E-05 None Cobal t -60 C1 2.55E-06 4.64E-07  !

f Selenium-75 Ci 9.32E-05 1.34E-05 l

Cesium-134 Ci ,

t Wone None  !

  • Cesium-137 C1 1.08E-06 5.98E l l 3 Strentlue-89 ** I Ci -

6.35-07 4. 5 E-0 7 <

{ I St ronc lue-90 ** . Ci 3.4E-07 l 2.4E-07 Net Unidentified I

Seta {

C1 1.64E-05 2.65E-06 Total Cl 1.27E-04 1.78E-05

  • Notet Particulates with half-lives > 8 days.
    • Notet Calculated from vendor analysis of monthly stack gas filterst 2nd quarter result includes data estimates for May and June due to unavailability of completed sample analyses. Reported not beta and vendor analysed Sr-89/90 were input to CASPAR code as Sr-90 to yield conservative dose estimates. I 1

l 1

l 1

l l

IC0888-0179A-HP01 8 j

l i

1

va .

1

, l TABLE HP 10.5-3 PALISADES NUCLEAR PLANT SEMI ANNUAL RADIOACTIVE j EFFLUENT RELEASE REPORT l LIQUID EFFLUENTS - SUMKATION OF ALL RELEASES JANUARY 1988 to JUNE 1988 l Est Total A. FISSION AND ACTIVATION PRODUCTS UNITS let QUARTER 12nd QUARTER Error %

1. Total release (not including tritium. Rases, alpha) Ci 7.31E-03 4.23E-03 I l l I
2. Average diluted concentration l durina period I uCi/ml 2.56E-10 '1.29E-10 14.4
3. Percent of MPC i  % 9.35E-03 1 2.52E-03 1 _

l B. TRITIUM H

1. Total release ci 3.49t+01 1.07E+02 i
2. . Average diluted concentration l durina period uCi/ml 1.22E-06 3.28E-06 22.3
3. Percent of MPC I I 4.07E-02 1.09E-01 l

C. DISSOLVED AND FNTRAINED CASES [

1. Total Release Ci 1.93E-03 7.55E-02 ;
2. Average diluted concentration '

durina period uCi/ml 6.75E-11 2.31E-09 4.0*

3. Percent of MPC I  % 1 3.38E-05 1.16E-03 D. '

t

. CROSS ALPHA RADIOACTIVITY '

! (Tot al Rel ea se ) ** Ci 3.0E-06 2.5E-06

1. Cross alpha average diluted concentration durina period uCi/ml 1.0E-13 7.6E-14 l

l E. VOLUME OF WASTE RELEASED (Prior to Dilu' tion) Liters 8.27E+05 1.03E+06 F. VOLUME OF DILUTION WATER USED DURING l PERIOD Liters 2.86E+10 3.27E+10 t

i C. KAXIMUM DOSE COMMITMENT - WHOLEBODY mRes 4.54E-03 2.67E-03 Percent of TS 3.24.4.la limic  ! 3.0 3E-01 1.78E-01 H. MAXIMUM DOSE COMMITMENT - ORGAN mRee 7.90E-03 1 4.42E-03 Percent of TS 3.24.4.la limit  % 1.58E-01 1 8.84E-02

  • Note Data is reported f or Xe-133, Xe-133o, Xe-135 and Kr-85m
    • Notet Calculated from vendor analysis of monthly radweste composite samplest 2nd quarter result includes data estimates for May and June due to unavailability of completed sample analyses.

IC0888-0179A-HP01 9

TABLE HP 10.5 s PALISADES NUCLEAR PLANT SEMI ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT '

LIQUID EFFLUENTS JANUARY 1988 to JUNE 1988

1. NUCLIDES RELEASED Units 1st QUARTER 2nd QU ARTER I

Cesium-137 Cl 1.71E-03 9.80E-04 '

Co ba l t -58 Cl 1.30E-03 5.60E-05 i Manaanese-54 Cl 1.14E-04 2.03E-04 Coba l t -60 Ci I 1.38E-03 2.13E-03 Cesium-134 Cl 1.62E-04 1.21E-04 '

fodine-131 Ci 2.37E-05 None I

I Strontium-89*** 1 C1 2.1E-03 5.9E-04 I

Strontium-90*** Ci 5.2E-04 1. 5 E '

Net Unidentified >

Beta Ci None None Fission & Activation Product Total Ci 7.31E-03 4.23E-03 Noble Casos Ci 1.93E-03 7.55E-02 l

Tritium Ci I 3.49E+01 1.07E+02 Crand Total - Ci  ! 3.49E+01 1.07E+02

      • WOTE: Calculated f rom vendor analysis of monthly radweste composite samplest 2nd quarter result includes estimates for May and June due to unavailability of completed sample ' analyses. Reported not beta and vendor analyzed Sr-89/90 were input to LADTAP code as Sr-90 to yield conservative dose estimates.

l l

l i

I 1

IC0888-0179A-HP01 10

7 .

een * ~ -

M r D ..,

  • e
1. I TABLE HP 10.5-4 ,

' PALISADES NUCLEAR PLANT SEMI ANNUAL RADI0 ACTIVE i

EFFLUENT RELEASE REPORT SOLID RADICACTIVE WASTE JANUARY 1988 to JUNE 1988 Waste Source of Solidification Container Volume Total Principal Class Waste Atent Type (Cu.ft.) Curies Radionuclides

Cs-134,Cs-137,Sr-90, Tc-99, C-14,'!-129 A Eva po ra tor Asphalt Metal drum 661.5 7.9 H3 ,Mn-54,Fe-55,Co-57, Bottoms Co-58,Co-60,Ni-63 C s - 134 , C s- 13 7, S r-90, i Tc-99, C-14. I-129 Sb-125

, B Irradiated N/A Steel liner 14.6 149.0 Mn-54,Fe-S5,5b-125, l Hardware co-58,co-60,Ni-63 C. Irradiated N/A' Steel liner 14.6 1097.7 Mn-54,Fe-55,Sb-125 ,

Hardware Co-58,Co-60,Ni-63 Total Shipped 1864.7 1257.7 1

  • NOTE: Camma isotopes are measured quanticits; all other isotopes are estimated.

l l

l l.

l

  • l l

l L IC0888-0179A-HP01 11 l-l l

l' 1' . - . . . - . . - . . . . , - - - , - , - - - . - - - - - - -