ML20235T124

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Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jul-Dec 1988
ML20235T124
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/31/1988
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18054A573 List:
References
NUDOCS 8903080161
Download: ML20235T124 (12)
v • d • e


Text

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 SEMIANNUALRADI0ACTIVEEFFLUENTbELEASE AND WASTE DISPOSAL REPORT /e6t JULY THROUGH DECEMBER-1988e 4i re,-"

February 28, 1989 c.e n i - -

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Palisedes Nuclasr Plant Semiannual Radioactive Effluent Release Report July - December 1988 This report provides information relating to radioactive affluent releases an'd solid radioactive waste processing at the Palisades Nuclear Plant during the period of July through December 1988. The report format is detailed in Plant Technical Specification 6.9.3.la.

Palisades has been off-line during most of

-this reporting period due to refueling and maintenance outages.

i 1.

Supplemental Information a

l 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 gaseous release from Palisades during the July - December 1988 reporting period. A brief description is provided:

On December 24, 1988, at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br />','approximately fourteen percent i (14%) of the gaseous content of Waste cas Decay Tank (WCDT) T-688 was 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-88-060-D) to'the NRC. -Cause of:thW unauthorized WCDT release 7

was Operator inattention to detail." When'the error was realized, the release was terminated (1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br />) and:the WCDT isolated and sampled. Calculation of T-688 contents indicated that a total of 1.16E-03 curies of Xe-133 was released. This resulted in an MPC fraction of 2.14E-06 at the site boundary. The released isotopic quantities are included in the fourth quarter totals. A copy of Event Report E-PAL-88-060-D is attached.

2.

Caseous Effluents Table HP 10.5-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified bets was 2.36% of the total (particulate) release.

3.

Liouid Effluents Table HP 10.5-3 lists and summarize's~ all'1~i' quid radioactive effluents released during the reporting period. The unidentified beta was 3.64E-03% of the total release.

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4.-

Solid Waste z.c a : ~.

m m atner e w-Y " Solid radwaste d ossification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.5-4.

All radwaste lA Y ahipments were made to either Barnwell, South Carolina or Richland, Washington for burial.

g.

IC0289-0043A-HP01 1

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.I 5.

Summary of Radiological Impact on Man j

Potential doses to individuals and populations were calculated-using

'CASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and summarized as follows:-

A.

'The offsite air dose at the site boundary (0.48 SSE) due to noble gases was 3.63E-02 millirad beta and 1.61E-02 millirad gamma for the third quarter; and 1.16E-03 millirad beta and 1.05E-03 millired gamma for the fourth quarter. The marimum noble' gas offsite. air dose to the nearest residence (0.5 mi S) occurred during the third quarter, being 2.54E-02 millicads beta and 1.12E-02 millicads gamma.

B.

The most restrictive organ dose to an individual in'an'unre-stricted area (based on identified critical receptors) from gaseous affluent releases (tritium, particulate and iodine) was the infant thyroid during the third quarter and child bone for ~.

the fourth quarter. Doses were 7.60E-02 and 3.37E-03 millires,e 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: 1.94E-02 manRen and 1.85E millires for the third quartert and 3.22E-03 manRem and 3.07E-06 millires for the fourth quarter.

D.

The maximum total body doce to an individual (adult) in unre-stricted water-related exposure pathways was 5.13E-03 and 3.38E-03 millirens for the third and fourth quarters, respec-tively. The maximum organ doses were 9.45E-03 millires (child bone) for the third quarter and 6.41E-03 millires (teenager bone) for the fourth 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 weret 1.95E-02 manRen and 1.86E-05 millires for the third quartert and 1.19E-02 manRen and 1.13E-05 millires for the fourth quarter.

F.

The' Selenium-75 present in the gaseous effluent releases and the entrained noble gases present in the liquid releases (first and second quarters) were not significant in either wholabody

orforgan doses..

o-6.

Process Control Program (PCP) y ThereberenochangestothePCPduringthereportingperiod.

IC0289-0043A-HP01 2

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Offsite Dose Calculation Manual (ODCM) 1 There were no changes to the ODCM during the reporting period.

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8.

Supplemental Information for the July-December 1988 Sejmiannual Radioactive Effluent Release Report

(

Revisions for the Palisader Nuclear Plant Semi-Annual Radioactive' J

Effluent Release Report; January -. June 1988, Tables HP 10.5-2 Caseous Effluents and Tables HP 10.5-3 Liquid Effluents are being submitted as an attachment:

A.

Table HP 10.5-2, Caseous Effluents - Summation of Releases, item C.2., 2nd Quarter only:

Change the Percent of Annual Avg Limit MPC from 1.90E-06 to 1.82E-06.

B.

Table HP 10.5-2, Caseous Effluents (isotopic Ci listings), item l

3, Particulate, 2nd Quarter only:

Change Sr-89 from 4.5E-07 Ci to 5.9E-07 C1 Change Sr-90 from 2.4E-07 Ci to 2.6E-07 Ci Change Net Unidentified Beta from 2.65E-06 Ci to 2.49E-06 C.

Table HP 10.5-3, Liquid Effluents - Summation of Releases, items A.1-3; D.1 and G., 2nd Quarter only:

Change Total (Fission and Activation Products) Release from 4.23E-03 Ci to 4.00E-03 Ci.

Change the Average Diluted Concentration During Period from 1.29E-10 pCi/mi to 1.22E-10 pCi/mi.

Change Percent of MPC from 2.52E-03 to 3.24E-03.

Change the Cross Alpha Radioactivity (Total Release) from 2.5E-06 Ci to 2.4E-06 C1.

Change the Cross Alpha Dilution Rate from 7.6E-14 pCi/mi to 7.3E-14 pCi/ml.

Change the Maximum Dose Commitment - Wholebody f rom 2.67E-03 millires to 2.59E-03 millires and change the Percent of Tech-nical Specification from 1.78E-01% to 1.73E-01%.

D.

Table HP 10.5-3, Liquid Ef fluents (isotopic Ci listings), item 1., Nuclides Released, 2nd Quarter only:

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-e Change Sr-89 f rom 5.9E-06 Ci to 2.6E-04 Ci

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Change Sr-90 from 1.5E-04 Ci to 1.4E-05 Ci IC0289-0043 A-HP01 3

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~ Change Net Unidentified Beta from NONE to 2.36E-04 Ci j

Change Fission and Activation Product Total from 4.23E-03'Ci to 4.00E-03 Ci 4

.E.

In the Palisades July - December 1987 Semiannual Radioactive Effluent Release Report Narrative, the following changes are i

also noted:

]

Item 2 - Caseous Effluents: change'from "the unidentified beta was 1.13E-06% of the total release" to'"the. unidentified beta was 13.0% of the total (particulate) release".

Item 3 - Liquid Effluents: change from "there was no unidenti-

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'l fied bata released" to "the unidentified beta was 1.66E-04% of the total release".

Item 5.D. - Summary of Radiological Impact on Mant change from

" water-related exposure pathways was 4.54E-03 and 2.67E-03 millireas...." to " water-related exposure pathways was 4.54E-03 and 2.59E-03 millirems...".

Item 5.E. - Summary of Radiological' Impact on Mant change from-

"1.02E-02 manRem 'and 9.71E-06 millires for the second quarter" to "9.82E-03 manRen and.9.35E-06 millires for the second quarter".

Reasons for the. above data revisions to the Palisades Semi-Annual Radioactive Effluent Release Report, January -' June 1988 was that the calculated Sr-89 and Sr-90 release quantities (gaseous and liquid effluents, 2nd Quarter only) were based on estimated values foe the months of May and June. Teledyne Isotopes Midwest Labora-tory had not yet completed the actual sample analyses prior to the Technical Specification Semi-Annual Report due date. All data changes are indicated by "f" in the right-hand margins. There were no significant dose changes to the public.

IC0289-0043A-HP01 4

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TABLE HP 10.5-1 PALISADES NUCLEAR PLANT SEMIANNUAL RADI0ACTIV8' EFFLUENT RELEASE REPORT BATCH RELEASES JULY 1988 to DECEMBER 1988 A.

CASEOUS Units 3rd Quarter 4th Quarter,1 Number of Releases 5

19

  • Total Release Time Minutes 1.65E+03 8.24E+03 r

Maximum Release Time Minutes 8.15E+02 1.31E+03 Average Release Time Minutes 3.29E+02 4.34E+02 Minimum Release Time' Minutes 1.76E+02 4.30E+01

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LIQUID Units 3rd Quarter 4th Quarter

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- Number of Releases

~72 68 4

Total Release Time Minutes 1.83E+04 6.20E+03 i

Maximum Release Time Minutes 3.44E+03-7.45E+02 Average Release Time Minutes 2.54E+02 9.12E+01 Minimum Release Time Minutes 2.50E+01 3.30E+01

  • Includes inadvertent release of WCDT T-68A on 12/24/88.

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PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS - SUMATION OF RELEASES ***

JULY 1988 to DECEMBER 1988 Est Total A.

FISSION AND ACTIVATION CASES UNITS 3rd QUARTER 4th QUARTER Error Z 1.

Total release Ci 7.27E+02 1.68E+01 2.

Averane release rate for period uci/sec 9.14E+01 2.11E+00 6.00 j

3.

Percent of annual ava MPC 5.25E-02 2.13E-03 1

8.

IODINES 1.

Total Iodine Ci-1.87E-02 7.17E-04 2.

Average release rate for period

  • uCi/sec 2.31E-03 4.30E-05 5.00 3.

Percent of annual ava MPC 3.02E-03 4.33E-05 C.

PARTICULATE 1.

Particulate with half-life >

w 8 days ci 2.65E-04 6.54E-05 2.

Averste release rate for period -

uCi/sec 3.33E-05 8.22E-06 3.

Percent of annual ava limit MPC Z

7.24E-06 5.65E-06

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4.

Cross alpha radioactivity Ci 6.67E-06 2.82E-06 5.-

Cross alpha average release rate for period uCi/Sec 8.39E-07 3.55E-07 D.

TRITIUM 1.

Total release Ci 1.03E+00 7.30E-01 2.

Averste release rate for period uCi/sec 1.30E-01 9.18E-02 3.

Percent of annual ava MPC 1

9.29E-05 6.56E-05 E.

1.

Beta air dose at site boundary due to Noble Cases (TS 3.24.5.2a) mRade 3.63E-02 1.16E-03 2.

Percent limit 1

3.63E-01 1.16E 3.

Camms air dose at site boundary due to Noble Gases (TS 3.24.5.21) mRads 1.61E-02 1.05E-03 4.

Percent limit 3.22E-01 2.10E-02 F.

1.

Maximum organ dose to public based based on critical receptors (TS 3.24.5.3) mRee 7.60E-02 3.37E-03 2.

Percent of limit 1

1.01E+00 4.49E-02 o Notet : Data is reported for I-131 and I-133 only.

  • k Notet Large error factor due to small amount of particulate present in t

gaseous effluents.

      • Notet Fourth Quarter totals include release of WCDT T-68A on 12/24/88.

IC0289-0043A-HP01 6

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TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE 4

EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS JULY 1988 to DECEMBER 1988 1.

FISSION CASES Units 3rd QUARTER 4th QUARTER

  • Krypton-85 Ci 5.40E-01 8.92E-01 Krypt on-85m Ci 7.23E-01 6.60E-02 Krypton-87 Ci 1.61E+00 1.61E-01 Krypton-88 Ci 1.93E+00 1.20E-01 Xenon-131m Ci 3.43E-01 6.56E-02 Xenon-133 Ci 7.06E+02 1.37E+01 Xenon-133m Ci 6.72E-01 3.64E-03 '

2 Xenon-135 Ci 4.62E+00 9.70E-02 Xenon-135m Ci 6.38E+00 1.28E-01 Xenon-138 Ci 3.26E+00 1.15E+00 Argon-41 Ci 4.62E-01 4.47E-01 Total for Period Ci 7.27E+02 1.68E+01 2.

IODINES i

Iodine-131 C1 1.63E-02 2.07E-04

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Iodine-132 Ci 3.35E-04 3.75E-04 Iodine 133 Ci 2.11E-03 1.35E-04 i

I Iodine-135 Ci None None Total for Period Ci 1.87E-02 7.17E-4 i

0" Notes Fourth Quarter isotopic totals include release of WCDT T-68A on 12/24/88.

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TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE' EFFLUENT RELEASE REPORT CASEQUS EFFLUENTS JULY 1988 to DECEMBER 1988 3.- PARTICULATE

  • Units 3rd QUARTER 4th QUARTER Chromium-51 Cl 1.74E-05 None l

1 Manzanese-54 Ci 5.71E-06 None Cobalt-58 Ci 5.45E-05 1.08E-06 Cobalt-60 Ci 8.44E-05 8.77E-06 Niobium-95 Ci 4.84E-06 None Selenium-75 Ci

9. 04 E 4.46E-05 Cesium-134 Ci 1.05E-07 None

- -Cesium-137 Ci 5.93E-06 2.29E-06

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Strontium-89 **

Ci 5.4E-07 7.1E-07

~ Stroneium-90 **

Ci 3.0E-07 1.4E-06 Net Unidentified Beta ci 1.22E-06 6.57E-06 Total Ci 2.65E-04 6.54E-05

  • Note Particulate with half-lives > 8 days.. Fourth Quarter isotopic totals include release of WCDT T-68A'on 12/24/88.
    • Note: Calculated from vendor analysis of monthly stack gas filters. Reported net beta and vendor analyzed Sr-89/90 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 SEPIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JULt 1988 to DECEMBER 1988 Est Total A.

FISSION AND ACTIVATION PRODUCTS UNITS 3rd QUARTER 4th QUARTER Error %

1.

Total release (not including tritium, asses, alpha)

Ci 1.42E-02 8.75E-03 2.

Average diluted concentration durina' period-uCi/ml 5.24E-10 3.77E-10 16.1 3.

Percent of MPC 4.46E-02 3.20C-02 B.

TRITIUM 1.

Total release Ci 1.25E+02 1.58E+01 2.

Average diluted concentration durina period uCi/mi 4.60E-06 6.81E-07 13.6 3.

Percent of MPC I

1.53E-01 2.27E-02 C.

DISSOLVED AND ENTRAINED CASES

  • 1.

Total Release Ci 9.31E-02 6.77E-06 2.

Average diluted concentration durina period uCi/mi 3.42E-09 2.92E-13 14.2*

3.

Percent of MPC 1.72E-03 1.46E-07 1

D.

CROSS ALPHA RADIOACTIVITY

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(Total Release) **

Ci 1.4E-05 5.0E-06 1.

Cross alpha average diluted concentration durina period uci/mi 5.1E-13 2.2E-13 E.

VOLUME OF WASTE RELEASED (Prior to Dilution)

Liters 3.22E+06 1.43E+06 F.

VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.72E+10 2.32E+10 C.

MAXIMUM DOSE COMMITMElff - WHOLEBODY mRes 3.13E-03 3.38E-03 Percent of TS 3.24.4.la limit I

3.42E-01 2.25E-01 j

H.

MAXIMUM DOSE COMMITMENT - ORCAN mRes 9.45E-03 6.41E-03 i

Percent of TS 3.24.4.la limit Z

1.89E-01 1.28E-01 1

  • Notes Data is reported for Xe-133, Xe-133m, Xe-135 and Kr-85m

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    • Notet Calculated from vendor analysis of monthly radwaste composite samples.

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IC0289-0043A-HP01 9

TABLE HP 10.5-3 PALISADES WUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS

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JULY 1988 to DECEMBER 1988 l

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- NUCLIDES RELEASED Units 3rd QUARTER 4th QUARTER Cesium-137 C1 1.69E-03 1.16E-03 Cobalt-58 Ci 2.59E-03 2.88E-03 Manganese-34 Ci 1.00E-04 7.16E-05 Cobalt-60 Ci,

2.70E-03 1,95E-03 Cesium-134 Ci 1.93E-04 1.33E-04 Niobium-95 Ci 8.94E-06 2.89E-05 Rubidium-88 Ci 2.98E-03 None Chromium-51 Ci 2.43E-04 3.31E-04 Iodine-131 Ci 4.31E-04 1.82E-06 Strontium-89***

Cl 1.9E-04 1.7E-05 Strontium-90***

Ci 1.2E-04 4.4E-05 Net Unidentified Beta C1 3.00E-03 2.13E-03 Fission & Activation Product Total Ci 1.42E-02 8.75E-03 Noble Cases Ci 9.31E-02 6.77E-06 Tritium Ci 1.25E+02 1.58E+01 Crand Total Ci 1,25E+02 1.58E+01 NOTES-Calculated from vendor analysis of monthly radwaste composite samples.

Reported net beta and vendor analyzed Sr-89/90 were input to LADTAP code as Sr-90 to yield conservative dose estimates.

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TABLE HP 10.5-4 PALISADES ' NUCLEAR PLAlfr SEMIANNUAT, RADI0 ACTIVE EFFLUENT RELEASE REPORT SOLID RADI0 ACTIVE WASTE JULY 1988 to DECEMBER 1988 Waste Source of - Solidification Container Volume Total Principal.

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Class Waste Agent Type

'(Cu.ft.)

Curies Radionuclides

Co-58,Co-60,Ni-63, Cs-134,Cs-137,Sr-90, Tc-99,C-14,I-119 A

Evaporator Asphalt Metal drum 105.0 0.94 H3,Mn-54,Fe-55,co-57, Bottoms Co-58,Co-60,Ni-63, Cs-134,Cs-137,Sr-90,

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Tc-99, C-14,I-l'29,Sb-12 5 A

Dewatered N/A Steel liner 1235.4 4.6 H,Cs-137,Cs-134,Co-60 3

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C Dewatered N/A HIC 205.8 35.4 Mn-54,co-58,Co-60,H3 Resin beads Ni-63,Cs-134,Cs-137, Tc-99 C

Filters N/A HIC 56.0 50.1 Co-60,Cs-137,Sb-125, Ni-63,Mn-54 Total Shipped 4748.4 117.8

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

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Abstract At 0955 on December 24, 1988 approximately 14 percent of the contents of waste gas decay tank T-68A [WE;TK] were released contrary to Plant Technical Specifications (TS). TS 3.24.6 requires that the waste gas decay tank system be used to reduce radioactive gaseous effluent concentration by holding gaseous waste collected by the system for a minimum of 15 days. The reactor was sub-critical with the Plant in hot shutdown condition (primary coolant system: 2175 psi and 535 degrees F) and a primary coolant system leakage test in progress. at the time of the event.

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The event has been attributed to operator. error as an, Auxiliary Operator (AO) inadvertently opened T-68A outlet valve CV-111M versus CV-1120A for T-688. T-685hadbeensampledand"authorizeffoFrelease. The

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release was terminated by the A0 at 1038,when he discovered his error while reviewing the discharge flow rate. During 1.G' event; l'.16E-3 curries of Xe-133 were released. When averaged over the release l

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y Procedures governing wast'e gas releases,;are beg @ns re%kylo. required an,,

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v3se independent verification of valve line ups..

A" human performance evaluation is also being conducted.

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Description At 0955 on December 24, 1988 approximately 14 percent of the contents of waste gas decay tank T-68A (WE;TK] were released contrary to Plant Technical Specifications (TS). TS 3.24.6 requires that the waste gas decay tank system be used to reduce radioactive gaseous effluent concentration by holding gaseous waste collected by the system for a minimus of 15 days. The reactor was sub-critical with the Plant in hot shutdown condition (primary coolant system: 2175 psi and 535 degrees F) and a primary coolant system leakage test in progress at the time of the event.

The event occurred when an Auxiliary Operator (AO) inadvertently opened the outlet control valve CV-1119A [WEIPCV) for T-68A instead of that for waste gas decay tank T-688. The AO was to have opened the outlet control valve CV-1120A for T-68B which had been approved for release.

The error was discovered by the AO at 1038 when he went back to review the release flow rate. Upon discovery, CV-1119A was closed, thereby terminating the release. T-68A was in-service at the time of the event.

When the release was initiated, T-68A contained approximately 93 psi of l

radioactive gas. At the time of isolation it contained 80 psi. this i

pressure differential corresponds to approximately 2.89 cubic meters and 1.16E-3 curies (Ka-133) of gasecus waste. During the release, the alarm setpoint of 13,000 counts per minute for waste gas discharge process monitor RIA-1113 [WEiEI] was not reached.

Cause Of The Event This event was attributed to operator error, as the espected level of attention to detail was not achieved.

Corrective Action Standard Operating Procedure 18A, " Radioactive Waste System - Caseous" is being revised to1 require independent verification that the correct waste gas decay tank outlet control valve has been opened. The vaste gas decay tank release authorir.ation form, Attachment 3 of Health Physics Procedure 6.6, " Evaluation and Release of Wasta Cas Tank" is also being revised to reflect and document this independent verification. A human performance evaluation of this incident is being performed to determine if additional controls are warranted to enhance performance of waste gas released.

A management review of this event was held with the Operations

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Department Superintendent and Manager, and the Plant Ceneral Manager.

1 The A0 involved in this event was consulted as to the seriousness of the event and the expected level of attention to detail during job performance.

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included within the Plant's Semi-Annual Operating Effluent Report.

Analysis Of The Event The Xe-133 concentration in T-68A was 4.02E-4 micro-curries per cubic centimeter versus the authorized release concentration in T-688 of 4.03E-4 micro-curries per cubic centimeter. The 1.16E-3 curries of Xe-133 released, when averaged over the time of the release, results in a maximum permissible concentration fraction of 2.14E-6 at the site boundary. This value represents a small fraction of the release limits specified in 10CFR20.106 and the reporting requirements of 10CFR50.72.

Had a Plant transient occurred that produced higher level radioactive gas while CV-1119A was open, Control Room operators would have been eterted by both the waste gas discharge and Plant stack gas monitors alarming. These alarms would prompt operators to review existing valve line-ups and terminate the release. Therefore, no threat to the health and safety of the public was present by this event.

This event is being reported per 10CFR50.73(a)(2)(1)(6) as an operational condition prohibited by Plant TS.

Additional Information

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For additional information regarding inadvertent waste gas releases, reference Licensee Event Reports87-017, 87-020,87-036 and 88-002 4

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