ML18057A431

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Semiannual Radioactive Effluent Release & Waste Disposal Rept Jan-June 1990. W/900831 Ltr
ML18057A431
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/30/1990
From: Slade G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009060026
Download: ML18057A431 (15)
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Text

consumers Power GB Slade General Manager POWERiNii MICHlliAN'S PROliRESS

. Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 August 31, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JANUARY THROUGH JUNE 1990 Attached is the Semiannual Radioactive Effluent Release and.Waste Disposal Report for the Palisades Plant covering the period from January through June 1990. This submittal is .made in accordance with 10 CFR 50.36a and Technical Specifications 6.9.~.1a. *

£fa~

Gerald B Slade

  • Gene~al Manager CC - Administrator, Region III, USNRC NRC Resident Inspector - Paiisades Attachment 9009060026 9006301  : I PDR ADOCK 050002$5 R _ _______ PDJ:: :J OC0890-0404-NL02 A CMS' ENER5Y COMPANY

Attachment Consumers Power Company Palisades Plant Docket 50-255 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUGH JUNE 1990 August 31, 1990 IC0890-0178A-NL02

Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report January - June 1990 This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Palisades Nuclear Plant during the period of January through June 1990. The report format is detailed in Plant Technical Specification 6.9.3.lA. Palisades Plant was offline April 16 to May 21 (MAOUT) and June 9 to June 17 (Pressurizer Heater Transformer repair).

/

1. Supplemental Information A. Batch Releases Information relating to batch releases of gaseous and liquid effluents is provided in Table HP 10.5-1.

B. Abnormal Releases There was one (1) reportable incident of an abnormal liquid release from Palisades during the January - July 1990 reporting period. A brief description is provided:

On March 27, 1990, approximately 150 gallons of radioactive water was pumped from the C-bus electrical pit to the Turbine Building Sump without prior sampling and analysis. The Turbine Building Sump discharges via a monitored flowpath to Lake Michigan. Cause for this abnormal release was identified as mis-communication and reliance on past history that the electrical pit water contained very low activity. When the error was realized, the release was terminated and the water was then sampled and analyzed. Analysis of the electrical pit water indicated that 9.60E-06 total curies had been released. The isotopic quantities are included in the first quarter totals of this report. A copy of RIR 90-010 which documents this occurrence is attached.

C. Lower Limits of Detection (LLD's) for gaseous and liquid effluents is provided on page 10.

2. Gaseous Effluents Table HP 10.5-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was l.09E-05%

of the total release.

3. Liquid Effluents Table HP 10.5-3 lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 6.21E-04%

of the total release.

IC0890-0178A-NL02 1

4. Solid Waste Solid radwaste classification, 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.

S. Sununary of Radiological Impact on Man Potential doses to individuals and populations were calculated using GASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and sununarized as follows:

A. The offsite air dose at the site boundary (0.48 SSE) due to noble gases was 4.36E-04 millirad beta and 2.65E-04 millirad ganuna for the first quarter; and l.59E-03 millirad beta and 6.56E-04 millirad gamma for the second quarter. The maximum noble gas offsite air dose to the nearest residence (0.5 mi S) occurred during the second quarter, being l.llE-03 millirads beta and 4.59E-04 millirads ganuna.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate and iodine) was the child thyroid for the first quarter and the child bone for the second quarter. Doses were l.67E-03 and l.77E-03 millirem, respectively.

C. Integrated total body doses to the general population and average doses to individuals (adults) within the population from gaseous effluent releases within a distance of 50 miles from the site boundary were: 3.98E-03 manRem and 3.78E-06 millirem for the first quarter; and 4.13E-03 manRem and 3.92E-06 millirem for the second quarter.

D. The maximum total body dose to an individual (adult) in unrestricted water-related exposure pathways was 7.45E-04 and 3.77E-04 millirems for the first and second quarters, respectively. The maximum organ doses were l.37E-03 millirem (teenage bone) for the first quarter and S.59E-04 millirem (teenage liver) for the second quarter.

E. Integrated total body doses to the general population and average doses to individuals (adults) within the population from liquid effluent releases within a distance of 50 miles from the site boundary were: 2.BSE-03 manRem and 2.71E-06 millirem for the first quarter; and l.69E-03 manRem and l.61E-06 millirem for the second quarter.

6. Process Control Program (PCP)

No changes were made to the Process Control Program.

7. Offsite Dose Calculation Manual (ODCM)

No changes were made to the ODCM.

IC0890-0178A-HP01 2

TABLE HP 10.5-1 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES January 1, 1990 to June 30, 1990 A. GASEOUS Units 1st Quarter 2nd Quarter Number of Releases 10 9 Total Release Time Minutes 3.44E+03 2.7SE+03 I Maximum Release Time Minutes 8.1SE+02 4.63E+02 I

~

Average Release Time Minutes 3.44E+02 3.06E+02 I Minimum Release Time Minutes l.40E+02 1. 90E+02 B. LIQUID Units 1st Quarter 2nd Quarter Number of Releases 2 2 Total Release Time Minutes l.36E+03 l .13E+03 Maximum Release Time Minutes 7.30E+02 S.6SE+02 Average Release Time Minutes 6.80E+02 S.63E+02 Minimum Release Time Minutes 6.30E+02 S.60E+02 IC0890-0178A-HP01 3

~ .

TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS -SUMMATION OF RELEASES January 1, 1990 to June 30, 1990 Est Total A. FISSION AND ACTIVATION GASES UNITS 1st QUARTER 2nd QUARTER Error %

1. Total release Ci 8.23E+OO 3.21E+Ol
2. Average release rate for period uCi/ sec 1. 06E+OO 4.08E+OO 12.9
3. Percent of annual avg MPC  % 7. 94E-04 2.25E-03 B. IODINES
1. Total Iodine (I-131. 133. and 135) Ci 6.95E-04 4.38E-04
2. Average release rate for oeriod
  • uCi/ sec 7.80E-05 5.57E-05 10. 7*
3. Percent of annual avg MPC *  % 5.40E-05 5.59E-05
c. PARTICULATES
1. Particulates with half-life >

8 days Ci 3.16E-05 7.92E-05

2. Average release rate for period uCi/sec 4.06E-06 l.OlE-05
3. Percent of annual avg limit MPC  % 2.69E-06 3.79E-06 17.1
4. Gross alpha radioactivity Ci 7.74E-07 l.23E-06 D. TRI TI UM 1
  • Total release Ci l.38E+OO l.18E+OO
2. Average release rate for period uCi/ sec 1. 77E-Ol l.50E-Ol
3. Percent of annual avg MPC  % l.26E-04 l.07E-04 E.
1. Beta air dose at site boundary due to Noble Gases (TS 3.24.5.2a) mRads 4.36E-04 l.59E-03
2. Percent limit  % 4.36E-03 l.59E-02
3. Gamma air dose at site boundary due to Noble Gases (TS 3.24.5.21) mRads 2.65E-04 6.56E-04
4. Percent limit  % 5.30E-03 l .31E-02 F.
1. Maximum organ dose to public based based on critical receptors (TS 3.24.5.3) mRem l.67E-03 1. 77E-03
2. Percent of limit  % 2.23E-02 2.36E-02

~ Note: Data is reported for I-131 and I-133 only.

IC0890-0178A-HP01 4

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TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS January 1, 1990 to June 30, 1990 f 1. FISSION GASES Units 1st QUARTER 2nd QUARTER t Argon-41 Ci 4.22E-02 5.16E-02 Krypton-85 I' Ci !i 6.31E-02 l.59E-Ol I

I!

Krypton-85m l Ci l.25E-02 l.20E-02 Krypton-87 Ci 2. 77E-02 2.64E-02

' i I

Krvoton-88 Ci 3.28E-02 3. llE-02 Xenon-13lm Ci 2.08E-02 5.95E-02 Xenon-133 Ci 7.51E+OO 3.lOE+Ol *-

Xenon-133m Ci 7.03E-03 9.13E-02 Xenon-135 Ci l.50E-Ol 3.52E-Ol Xenon-135m Ci 2.67E-Ol 2.48E-Ol Xenon-138 Ci l.OOE-01 9.26E-02 Total for Period Ci 8.23E+OO 3.21E+Ol

2. IODINES I Iodine-131 Ci l.90E-04 2.64E-04 Iodine-133 Ci 4.17E-04 l.74E-04 Iodine 135 Ci 8.82E-05 <LLD Total for Period Ci 6.95E-04 4.38E-04 IC0890~0178A-HP01 5

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TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS January 1, 1990 to June 30, 1990

3. PARTICULATES **,'(

Units 1st QUARTER 2nd QUARTER Chromium-51 Ci <LLD 3.64E-06 Manganese-54 Ci <LLD <LLD Cobalt-58 Ci <LLD 2.18E-05 Iron-59 Ci <LLD <LLD Cobalt-60 Ci 7.83E-07 4.66E-06 Zinc-65 Ci <LLD <LLD Selenium-75 Ci 4.26E-06 l.33E-OS Strontium-89 Ci 9.0E-07 8. 7E-07 Strontium-90 Ci 6.3E-07 7.6E-07 Niobium-95 Ci <LLD 4.84E-07 Zirconium-95 Ci <LLD 2.22E-06 Molvbdenum-99 Ci <LLD <LLD Antimony-125 Ci <LLD 2.82E-06 Cesium-134 Ci 3.78E-06 4.64E-06 Ces ium-13 7 Ci l.91E-05 l.97E-05 Cerium-141 Ci <LLD <LLD Cerium-144 Ci <LLD l.74E-06 Net Unidentified Beta Ci 2.12E-06 2.56E-06 Total Ci 3.16E-05 7.92E-05

  • Note: Particulates with half-lives > 8 days.

IC0890~0178A-HP01 6

TABLE HP 10.S-3 PALISADES .NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES January 1, 1990 to June 30, 1990 Est Total A. FISSION AND ACTIVATION PRODUCTS UNITS 1st QUARTER 2nd QUARTER Error %

1. Total release (not including t ri ti um. gases. alpha) Ci 9.06E-04 6.37E-04
2. Average diluted concentration during period uCi/ml 2. 96E-ll 2.12E-ll 13.3
3. Percent of MPC  % 2.94E-03 6.78E-04 B. TRITIUM
1. Total release Ci 1. 97E+Ol 3.12E+Ol
2. Average diluted concentration during period uCi/ml 6.44E-07 l.04E-06 4.0
3. Percent of MPC  % 2.lSE-02 3.47E-02
c. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci <LLD <LLD
2. Average diluted concentration during period uCi/ml N/A N/A N/A
3. Percent of MPC  % N/A N/A D. GROSS ALPHA RADIOACTIVITY (Total Release)
  • Ci 4.40E-07 3.90E-07 E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 3.9SE+OS 3.89E+OS F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 3.06E+l0 3.00E+lO G. MAXIMUM DOSE COMMITMENT - WHOLEBODY mRem 7.4SE-04 3.77E-04 Percent of TS 3.24.4.la 1 imit  % 4.97E-02 2.SlE-02 H. MAXIMUM DOSE COMMITMENT - ORGAN mRem 1. 37E-03 5.59E-04 Percent of TS 3.24.4.la limit  % 2.74E-02 1.12E-02
  • Note: Calculated from vendor analysis of monthly radwaste composite samples.

IC0890-0178A-HP01 7

TABLE HP 10.5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS January 1, 1990 to June 30, 1990

1. NUCLIDES RELEASED Uni ts 1st QUARTER 2nd QUARTER Manganese-54 Ci <LLD <LLD Cobalt-58 Ci l.24E-04 2.99E-04 I ron-59 Ci <LLD <LLD Cobalt-60 Ci 2.18E-04 l.21E-04 Zinc-65 Ci <LLD <LLD
  • st ron ti um-89 Ci 9.lOE-07 l.20E-06 Strontium-90 Ci 2.lOE-06 l. lOE-06 Molybdenum-99 Ci <LLD <LLD Iodine-131 Ci <LLD <LLD Cesium-134 Ci 9.60E-07 <LLD I Cesium-137 Ci 2.99E-04 l.59E-04 I

Cerium-141 I Ci <LLD <LLD I

Cerium-144 I Ci <LLD <LLD Net Unidentified I Beta I Ci 2.61E-04 5.53E-05 Fission & Activation I II Product Total Ci 9.06E-04 I

lI 6.37E-04 i

' i I Tritium Ci l.97E+Ol  ! 3.12E+Ol Grand Total Ci  ! l.97E+Ol 3.12E+Ol  !

IC0890-0178A-HP01 8

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  • TABLE HP 10.5-4 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE January 1, 1990 to June 30, 1990 Waste Source of Solidification Container Volume *Total *Principal Class Waste Agent T:n:!e (cu ft) Curies Rad iocl ides AU DAW N/A LSA 1670.4 9.5735 Mn-54, Co-58, Co-60, Cs-134, Cs-137 AU Dewatered Resin N/A LSA 124.2 0.0420 Mn-54, Co-58, Co-60, Cs-134, Cs-137 AS Dewa te red N/A HIC 194.1 5.3764 Mn-54, Co-58, Filters Co-60, Ni-63, Sb-125 AU Evap Bottoms Asphalt LSA 298.0 2. 6830 Mn-54, Co-58, (Concentrates) Co-60, Cs-134,
  • '<NOTE: Gamma isotopes are measured quantities; all other isotopes are estimated.

IC0890-0178A-HP01 9

Attachment 1 Lower Limits of Detection (LLD's) for Palisades Effluents Gaseous Effluents LLD (µCi/cc)

Cr-51 8.05E-13 Mn-54 l.34E-13 Co-58 7.98E-14 Fe-59 2. 74E-13 Zn-65 3.09E-13 Nb-95 l.22E-13 Zr-95 2.20E-13 Mo-99 5.05E-14 Sb-125 3.60E-13 Ce-141 9.13E-14

  • Ce-144 4.39E-13 Liquid Effluents LLD ( µCi/ ml )

Mn-54 5.48E-08 Fe-59 1.12E-07 Zn-65 1.27E-07 Mo-99 2.07E-08 I-131 3.94E-08 Cs-134 .5 .30E-08 Ce-141 3.74E-08 Ce-144 l.80E-07 IC0890~0178A-HP01 10

_-./ Form HP 1.3-1 Pt'OC .lfo HP l. l Attachment 4 Revision l

  • Page l of 3 RADIOLOGICAL INCIDENT ll!PORT AUTH DOC I l> ~

Form HP l. 3-1 Proc tio HP l. 3 Attachment 4 Revision 3 Page 2 of 3 RADIOLOCICAL INCIDENT REPORT III. INVESTIGATIVE ACTIONS hpll82-0029e-91-89

Form HP l.l~l Proc No HP l.)

  • Attachment 4 Revis ion l Page 3 of 3 RADIOLOCICAL INCIDENT REPORT
1. Approved By:

Title:

Health Physics Superintendent

2. Approved By: Date:

Title:

(Cognizant Superintendent)

1. Approved By: Date:

Title:

Radiological Services Manager

4. Approved By: Date:

Title:

. Plant General Manager Distribution:

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