ML19354D428

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Supplemental Palisades Nuclear Plant Semiannual Radioactive Effluent Release Release Rept (Revised) for Jul-Dec 1987
ML19354D428
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/31/1987
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054B077 List:
References
NUDOCS 8911080519
Download: ML19354D428 (8)
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. Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report (Revised) 1 JULY - DECEMBER 1987 J

This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Palisades Nuclear Plant I

during the period of July through December 1987. Ths report format is I

detailed in Plant Technical Specification 6.9.3.la.

During this reporting period, Palisades was off-line from October 1 - November 12, 1987 and December 4, 1987 - January 26, 1988 due to maintenance sutages.

1.

Supplemental Inf ormation A.

Betch Releases

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Information relating to batch releases of gaseous and liquid effluents is pruvided in Table HP 10.5-1.

B.

Abnormal Releases There were two. (2) reportable incidents of abnormal gaseous releases

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from the Palisades Plant during the July - December 1987 reporting period. A brief description of each is providedt L

1.

On July 8, 1987, at approximately 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, the gaseous

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contents of Waste Cas Decay Tank (WCDT) T-68A were accidentally released to the atmosphere without being held for a minimum of fifteen (15) days. This was contrary to Palisades Technical Specification 3.24.6.1 and resulted in an Event Report (E-PAL-87-029) to the NRC.

Cause of'the WCDT release was 1.

_ determined to be the performance of maintenance activity on the (then in-service) T-68A WCDT relief valve. Approximately 5.78 3m of noble gas escaped from the WCDT into the Ausiliary Building. The noble gas was vented from the Auxiliary Buildi..g via the ventilat.on system and out the plant stack. The i

release was monitored by the stack noble gas monitor (RIA 2326) i and occurred over an approximate thirty (30) minute time l

pe ri od. The release totaled 0.224 curies and is included in the third quarter gaseous effluent totals. No release limits were exceeded.

2.

On October 19, 1987, at approximately 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, the gaseous contents of Weste Cas Decay Tank (WCDT) T-1018 were released to the atmosphere without being held for a minimum of fifteen (15) days. This was contrary to Palisades Technical Specification 3.24.6.1 and resulted in an Event Report (E-PAL-87-047) to the NRC. Cause of the unauthorised WCDT release was inattention to detail and procedure non-compliance. The ac'.;vity of WCDT-1015 was known as it had been isolated and sampled prior en the release. No release limits were exceeded. A total of 7.20 IC0288-0022A-HP01 12 9911090519 891030 7

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e curies was released and is included in the fourth (4th) quarter f

gaseous effluent totals.

I 2.

Caseous Effluents

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l Table HP 10.5-2 lists and sununarizes all gaseous radioactive ef fluents 1

released during the reporting period. The unidentified beta was 4.10E-05% of the total release.

d 3.

Liouid Effluents Table HP 10.5-3 lists and sunenarizes all liquid radioactive ef fluents released during the reporting period. The. unidentified beta was y

4.46E-03I of the total retsase.

4.

Solid Weste Solid radweste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.5-4.

All radweste shipments were made to either garnwell, South Carolina or Richland, Washington for burial.

5.

Sunesary of Radiological Impact on Man Potential doses to individuals and populations were calculated using CASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follows:

A.

The maximum offsite air dose at the site boundary due to noble gases was 2.62E-02 millicad beta and 8.80E-03 millired gamma for the third i

quarterl and 2.73E-02 millirade beta and 9.21E-03 millirads gamma i

i for the fourth quarter.

l l-B.

The most restrictive organ dose to an individual in an unrestricted L

area (based on identified critical receptors) from gaseous effluents (tritium, particulate and iodine) was the child bone. Doses were

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6.63E-02 and 1.14E-01 millires for the t'hird and fourth quarters, respectively.

C.

The easimum total body dose to individuals (adult) in unrestricted water-related esposure pathways was 4.388-03 millires for the third quarter and 5.86E-02 millires for the fourth quarter. The maximua I

organ dose (teenage liver) was 7.83E-03 and 9.72E-02 millires for l

the third and fourth quarters, respectively.

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D.

Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent L

releases within a distance of 50 miles from the site boundary were:

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1.48E-02 manRen and 1.41E-05 millirse for the third quarters and 1.91E-01 manRen and 1.82E-04 millires for the fourth quarter.

IC0288-0022A-HP01 13 L

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E.

Integrated total body doses to the general population and average doses, to individuals (adults) within the population f rom gaseous effluent releases within a distance of 50 miles from the' site boundary were t 3.34E-02 manRem and 3.18E-05 millirem for the third quarter t and 4.94E-02 manRem and 4.70E-05 millirem for the fourth quatter.

F.

The Selenium-75 in gaseous ef fluent releases (fourth quarter only) and'the entrsined noble gases present in both the third and foutch quarter liquid releases were not significant in either wholabody or organ doses.

6.

Process Control Pronram (PCP)

There are no changes to the PCP during this reporting period.

7.

Of fsite Dose Calculation Manual (ODCM)

There are no changes to the ODCM during this reporting period.

8. '

Supplemental Information for the January-June 1987 Semiannual Radioactive Effluent Release Report The Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report l January - June 1987, Table HP 10.5-2 Caseous Effluents and HP 10.5-3 Liquid Effluents are being submitted as an attachment for the following revisions:

t A.

Table HP 10.5-2, Caseous Effluents - Summation of Releases, item C.3., 2nd Quarter onlyt Change the Particulate Percent of Annual Average Limit MPC from 2.62E-06 to 2.64E-05.

i B.

Table HP 10.5-2, Caseous Effluents (isotopic Ci listings), item 3 Particulates, 2nd Quarter only Change Sr-89 from 3.2E-07 Ci to 5.9E-07 Ci.

Change Sr-90 from 2.8E-07 Ci to 5.5E-07 C1.

Change Wet Unidentified Beta from 4.31E-05 Ci to 4.26E-05 C1.

C.

Table HP 10.5-3, Liquid Ef fluents - Summation of Releases, item A.3., 2nd Qaurter only:

Change the Fission and Activation Cases Percent of MPC from 2.31E-02 to 2.19E-02.

IC0288-0022A-HP01 14

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Table HP 10.5-3,, Liquid Ef fluents (isotopic Ci ' list ings ), 'i tem 1.-

Nuclides Released, 2nd Quarter only:

Change Sr-89 from 5.4E-05 Ci to 2.6E-05 Ci.

t Change Sr-90 f rom 9.lE-05 Ci to 5.5E-05 Ci.

Change Net Unidentified Beta from 1.93E-03 Ci to 1.99E-03 Ci.

Reasons for the above data revisions to the Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report, ' January - June 1987 was that the calculated Sr-89 and Sr-90 release quantities (for both gaseous and liquid effluents) were based on estimated values for the month of June. Teledyne Isotopes Midwest Laboratory had not yet completed the actual sample analyses prior to the Technical Specification Semiannual re po rt due date. All data changes are indicated by "$"

in the-right-hand margins. There were no reportable changes in doses to the public.

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TABLE HP 10.5-2 (Revised) i PALISADES MUCLEAR PLANT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1:

CASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1987 to DECEMBER 1987 Est Total l l 3rd QUARTER A.

FISSION AND ACTIVATION CASES UNITS I

4th QUARTERI Error % !

1.

Total release ci 1 5.49E+02 5.70E+02 2.

Averane release rate for period uCi/sec l 6.09E+01 7.17E+01 24.0 l

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3.

Percent of annual ava MPC i

I 3.29E-02 3.43E-02 B.

IODINES 1.

Total Iodine ci i 5.49E-03 1.49E-02

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2.

Averane release rate for period

  • uCi/sec 6.90E-04 1.8EE-03 4.66*

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Percent of annual ava MPC 1

7.71E-04 2.59E-03 i

C.

P ARTI CU' ATES 1.

Particulates with half-Life >

8 days Ci 1.80E-04 4.44E-04 i

2.

Aversas release rate for period uCi/sec 2.26E-05 5.58E-05 3.

Percent of annual ava limit MPC 1.03E-04 1.76E-04 20.8**

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Cross alpha radioactivity Ci 6.15E-06 6.40E-06 5.

Cross alpha average release rate l

for period I

uCi/Sec 7.74E-07 8.05E-07 I

D.

TRITIUM 1

1.

Total release I

Ci 8.25E-01 7.56E-01 l C

2.

Averste release rate for period i

uCi/see 1.04E-01 9.51E-02 1 3.

Percent of annual ava MPC l

7.41E-05 6.79E-05

' E.

1.

Beta air dose at site boundary due to Noble Cases (TS 3.24.5.2a) mRads 2.62E-02 2.73E-02 2.

Percent limit 1

2.62E-01 2.73E-01 3.

Camma air dose at site boundary due to Noble Gases (TS 3.24.5.21) mRads 8.80E-03 9.21E-03 4

Percent limit 1.76E-01 1.84E-01 F.

1.

Maximum organ dose to public based based on critical receptors (TS 3.24.5.3) mrem 6.63E-02 1.14E-01 2.

Percent of limit 8.84E-01 1.52E00

  • Notet Data is reported for I-131 and I-133 only.
    • Notes Large error factor due to very small amount of particulates present in gaseous affluents.

IC0288-0022A-HP01 16

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TABLE HP 10.5-2 i

PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

CASEOUS EFFLUENTS JULY 1987 to DECEMBER 1987 x (:

3.

PARTICULATES**

  • Unit 3rd QUARTER 4th QUARTER Chromium-51 Cl None None Manaanese-$4 Ci None None Co ba l t-58 Ci None 6.77E-05 Cobalt-60 Cl 7.44E-06 6.48E-06 l

Selenium-75 Ci i

None 6.56E-05 Ntobium-95 Ci None 1.10E-06 Cesium-134 Ci None None Cesium-137 Ci None 9.35E-06 Strentiue-89****

Ci 1.7E-06 2.6E-06 Scrontium-90****

C1 4.1E-07 9.2E-07 Net unidentified Cl 1.70E-04 2.90E-04 beta l

Total Ci 1.80E-04 4.44E-04

      • NOTE Particulates with half-lives >8 days.
        • NOTE Calculated from vendor analysis of monthly stack 8as filters.

Reported not beta and vendor analysed Sr89/90 results were input to CASPAR code as Sr-90 to yield conservative dose estimates.

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TABLE HP.10.5-3

' PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

LIQUID EFFLUENTS - SUhhATION OF ALL RELEASES JULY 1987 to DECEMBER 1987 Est Total i i

A.

FTSSION AND ACTIVATION PRODUCTS I

UNITS 3rd QUARTER 4th QUARTER Error % 1 1.

Total release (not including t ri ti um. as ses, al pha )

Ci 8.80E-03 6.88E-02 8

2.

Average diluted concentration durinn period uCi/ml 2.62E-10 2.27E-09 15 3.

Percent of MPC 1.06E-02 1 5.86E-02,

B.

TRITIUM l.

Total release ci 5.73E+01 4.47E+01 i

2.

Average diluted concentration i

durina period uCi/et 1.71E-06 1.47E-04 16 3.

Percent of MPC i

1 5.68E-02 4.92E-02 C.

DISSOLVED AND ENTRAINED CASES 1.

Total Release ci 7.97E-02 3.76E-02 2.

Average diluted concentration durina period uCi/ml 2.37E-09 1.24E-09 5.6*

3.

Percent of MPC 1

1.19E-03 6.20E-04 D.

CROSS ALPHA RADIOACTIVITY (Total Release) **

Ci 2.6E-05 S.2E-06 1.

Cross sipha average diluted concent ration durina period uCi/ml 7.7E-13 2.7E-13 E.

VOLUME OF WASTE RELEASED (Prior to Dilution)

Litors 9.55E+05 1.40E+06 F.

VOLUME OF DILUTION WATER USED DURINC PERIOD Liters 3.36E+10 3.03E+10 C.

MAXIMUM DOSE COISIITNEFF = WHOLEBODY mRee 4.38E-03 5.86E-02 Percent of TS 3.2A.A.la limit 2.925-01 3.91E00 H.

MAXIMUM DOSE COMITMElff - ORCAN mRee 7.83E-03 9.72E-02 Percent of TS 3.24.4.la limir 1.57E-01 1.94E00

  • Notet Data is reported for Xe-133
    • Notet Calculated from vendor analysis of monthly radweste composite samples.

IC0288-0022A-HP01 18

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e TABLE HP 10.5-3

, PALISADES NUC' EAR PLANT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE _ REPORT (Revi sed)

LIQUID EFFLUENTS JULY 1987 to DECEMBER 1987 1.

NUCLIDES RELEASED Units I

3rd QUARTER 4th QUARTER Cesium-137 Ci i

1.65E-03 2.20E-02 Cobalt-58 Ci 9.85E-05 1.77E-03 Mannenese-54 Cl I

5.62E-04 9.70E-03 Cobalt-60 Ci 4.39E-03 2.42E-02 Ceslum-134 Ci 2.46E-04 5.94E-03 Rubidium-88 Ci 8.58E-04 None t

Molybdenue-99 Ci None 2.95E-05 j

1 Strontium-89***

Ci I

7.2E-06 3.3E-04 Stroneium-90***

Ci 3.5E-06 4.3E-04 Cobalt 57 Ci None 1.13E-05 l

Antimony-125 Ci None 1.90E-04 Todine-131 Ci 5.51E-06 4.67E-04 Todine-133 Ci 2.49E-06 None Chromiuer51 Cl None 1.04E-04 t

Net Unidentified l

l' Beta Cl 9.72E-04 3.59E-03 I f Fission & Activation I

Product Total (Above)

Ci i

8.80E-03 6.88E-02 l

1 Noble Cases Ci 7.97E-02 3.76E-02 i

Tri t i um Ci 5.73E+01 4.47t+01 l.

Crand Total Ci 5.74E+0!

4.48E+01 l'

      • NOTEI Calculated from vendor analysis of monthly radweste composite samplest Reported net beta and vendor analyzed Sr89/90 results were input to 1.ADTAP dose as Sr-90 to yield conservative dose estimates.

IC0288-0022A-HP01 19 1.

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