ML18053A546

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Revised Semiannual Radioactive Effluent Release Rept for Jul-Dec 1987
ML18053A546
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/31/1987
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18053A544 List:
References
NUDOCS 8809060283
Download: ML18053A546 (8)
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Text

Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report (Revised)

JULY - DECEMBER 1987 This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Palisades Nuclear Plant during the period.of July through December 1987.

The report format is 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 outages.

1.

Supplemental Information A.

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

8.

Abnormal Releases There were two (2) reportable incidents of abnormal gaseous releases from the Palisades Plant during the July - December 1987 reporting

  • period.

A brief description of each i1 provided:

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 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.

1bi1 va1 contrary to Palisades Technical Specification 3.24.6.l and re1ulted in an Event Report (E-PAL-87-029) to the HRC.

Cau1e of the WCDT release was determined to be the performance of maintenance activity on the (then in-1ervice) T-68A WCDT relief valve.

Approximately 5.78 m3 of noble 1a1 escaped fro. the WCDT into the Auxiliary Buildina. The noble ga1 vas vented from the Auxiliary Buildina

-.via the-ventilation 1y1tem-and out-the plant 1tack.* -The---*-- - ----

releaae va1 monitored by the 1tack noble gas monitor _(RIA 2326) and occurred over an approximate thirty (30) minute time period. The telea1e totaled 0.224 curies and is included in the third quarter 1a1eou1 effluent total1.

No release limits wre exceeded.

2.

On October 19, 1987, at approximately 1900 houri, the gaseous content* of Waste Cas Decay Tank (WCDT) T-1018 were released to the atmo1phere without being held for a miniaaun of fifteen (15) days. This was contrary to Palisades Technical Specification 3.24.6.1 and re1ulted in an Event Report (E-PAL-87-047) to the HRC.

Cause of the unauthorised WCDT relea1e va1 inattention to detail and procedure non-compliance.

11\\e activity of WCDT-1018 vas known as it had been isolated and sampled prior to the release.

No release limit* were exceeded.

A total of 7.20 IC0288-0022A-HP01 8809060283 880831 kDR ADOCK 05000255 PNU 12

curies was released and is included in the fourth (4th) quarter gaseous effluent totals.

2.

Gaseous Effluents Table HP 10.5-2 lists and surrmarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 4.lOE-05% of the total release.

H

3.

Liquid Effluents Table HP 10.5-3 lists and sunmarizes all liquid radioactive effluents released_ during the reporting period. The unidentified beta was II 4.46E-03% of the total release.

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 for burial.

5.

Sunmary of Radiological Impact on Han 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 millirad beta and 8.80E-03 millirad gamna for the third quarter; and 2. 73E-02 millirads beta and 9._21E-03 millirads gamma for *the fourth quarter.

B.

The mo1t restrictive organ dose to an in4ividual in an unrestricted area (based on identified critical receptors) from gaseous effluents

_ {_tdtium, particulate and iodine) ~H tM chi_ld b~ne! _ pos_es were ______________ _

6.63£-02 and l.14E-Ol millirem for tbe third and fourth quarters, rupectively.

C.

5**'aailllm total body dose to individuah (adult) in unrestricted

~er-related ezposure pathway* wa1 4.38E-Ol lli.llirem for the third quarter and 5.86E-02 millirem for the fourth quarter.

'nle maximum organ do1e (teenage liver) wa1 7.83E-03 and 9.72E-02 millirem for the third and fourth quarter1, respectively.

D.

Integrated total body doses to the general population and average dose1 to individuals within the population from liquid effluent releases within a distance of 50 miles from the 1ite boundary were:

l.48E-02 manRem and l.41E-05 millirem for the third quarter; and l.91E-01 manRem and 1.82E-04 millirem for the fourth quarter.

IC0288-0022A-HP01 13

E.

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 si~e boundary were:

3.34E-02 manRem and 3.lBE-05 millirem for the third quarter; and 4.94E-02 manRem and 4.70E-05 millirem for the fourth quarter.

F.

The Selenium-75 in gaseous effluent releases (fourth quarter only) and the entrained noble gases present in both the third and fourth quarter liquid releases were not significant in either wholebody or organ doses.

6.

Process Control Program (PCP)

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

7.

Offsite Dose Calculation Manual (ODCH)

There are no changes to the ODCH 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; January - June 1987, Table HP 10.5-2 Gaseous Effluents and HP 10.5-3 Liquid Effluents are being submitted as an attachment for the following revisions:

A.

Table HP 10.5-2, Gaseous Effluents - Sunnation of Releases, item C.3., 2nd Quarter only:

Change the Particulate Percent of Annual Average Limit HPC from 2.62£-06 to 2.64E-05.

8.

Table HP 10.5~2, Gaseous Effluents (isotopic Ci listings), item 3, Particulates, 2nd Quarter only:

~----------- -----

Change Sr-89 from 3.2E-07 Ci to 5.9£-07 Ci.

Cbanae Sr-90 from 2.8£-07 Ci to 5.5£-07 Ci.

~*Met Unidentified Beta from 4.31£-05 Ci to 4.26E-05 Ci.

c.

T!bl* HP 10.5-3, Liquid Effluents - 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

U

-l_i I

(.'

D.

Table HP 10.5-3, Li~uid Effluents (isotopic Ci listings), item l, Nuclid~s Released, 2nd Quarter only:

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

Change Sr-90 from 9.lE-05 Ci to 5.5E-05 Ci.

Change Net Unidentified Beta from l.93E-03 Ci to l.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 report due date.

All data changes are indicated by "#" in the right-hand margins.

There were no reportable changes in doses to the public.

IC0288-0022A-HP01 15

e TABLE HP 10.5-2 (Revised)

A.

8.
c.

D.

E.

F.

PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1987 to DECEMBER 1987 FISSION AND ACTIVATION GASES UNITS 3rd QUARTER

1. Total release Ci 5.49E+02
2.

Avera2e release rate for oeriod uCi/sec 6.89E+Ol

3.

Percent of annual av2 HPC 3.29E-02 IODINES

1. Total Iodine Ci 5.49E-03
2.

AveraRe release rate for period

  • uCi/sec 6.90E-04
3.

Percent of annual avR HPC

7. 71E-04 PARTI Cl'T.ATES
1. Particulates with half-life >

8 davs Ci l.80E-04

2.

Avera2e release rate for oeriod uCi/sec 2.26E-05

3. Percent of annual av2 limit MPC l.OJE-04
4. Cross alpha radioactivity Ci 6.15E-06
5. Cross alpha average release rate for period uCi/Sec 7.74E-07 TRITIUM
1. Total release Ci 8.25E-Ol
2.

Averaae release rate for oeriod uCi/ sec l.04E-Ol

3.

Percent of annual avR MPC 7.41E-05

1.

Beta air dose at site boundary due to Noble Cases (TS 3.24.5.2a) mB.ads 2.62E-02 2 *.-- Percent limit*

~

~ -* -

" - --1--- -

- - -2.62E-Ol---

3.

Camma air do1e,at 1ite boundary due to Noble~1 (TS 3.24.5.21) mllads 8.SOE-03

4. Percent '
  • t l.76E-Ol
  • .~*'~.*
1.

Maximum organ do1e to public based based on critical receptors (TS 3.24.5.3) mlem 6.63E-02

2.

Percent of limit 8.84E-Ol

  • Hote:

Data is reported for I-131 and I-133 only.

4th QUARTER 5.70E+02 7.17E+Ol 3.43E-02 l.49E-02 l.88E-03

2. 59E-03 4.44E-04 5.58E-05 l.76E-04 6.40E-06 8.05E-07 7.56E-Ol 9.51E-02 6.79E-05 2.73E-02

-- 2. 7 3E-O-l -

9.21E-03 l.84E-Ol 1.14E-Ol l.52EOO

    • Note:

Large error factor due to very small amount of particulates present in gaseous effluents.

IC0288-0022A-HP01 16 I

I Est Total Error %

24.0 4.66*

20.8**

I I

3.

PARTICULATES**

  • Chromi um-51 Hanaanese-54 Cobalt-58 Cobalt-60 Selenium-75 Niobium-95 Cesiwn-134 Cesiwn-137 Strontium-89****

Strontium-90****

Net unidentified beta Total TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

GASEOUS EFFLUENTS JULY 1987 to DECEMBER 1987 I

Units i

3rd QUARTER I

Ci None Ci None Ci None Ci 7.44E-06 Ci None Ci None Ci None Ci None Ci

1. 7E-06 I

Ci 4.lE-07 Ci

1. 70E-04.

I T

i Ci l.SOE-04 i

  • '** NOTE:

Particulates with half-lives >8 days.

    • '*"* NOTE:

Calculated from vendor analysis of monthly stack gas filters.

4th QUARTER None None

6. 77E-05 6.48E-06
6. 56E-05
l. lOE-06 None 9.35E-06 2.6E-06 9.2E-07 2.90E-04 4.44E-04 Reported net beta and vendor analyzed Sr89/90 results were input to CASPAR code as Sr-90 to yield conservative dose estimates.

IC0288-0022A-HP0l 17 I

i I

I I

I I

I I

i

I TABLE HP 10.5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JULY 1987 to DECEMBER 1987 i A.

FISSION AND ACTIVATION PRODUCTS UNITS 3rd QUARTER i

I

~

1. Total release (not including tritium. 2ases. aloha)
2.

Average diluted concentration durin2 oeriod

3.

Percent of HPC

8.

TRITIUM

1. Total release
2.

Average diluted concentration durina D@riod

3. Percent of MPC
c.

DISSOLVED AND ENTRAINED CASES

1. Total Release
2. Average diluted concentration durina D@riod
3.

Percent of MPC D.

GROSS ALPHA RADIOACTIVITY (Total Release) '**

l. Gross alpha average diluted concentration durina neriod E.

VOLUME OF WASTE RELEASED (Prior to Dilution)

F.

VOLUME OF DILUTIOH WATER USED DURIHC PERIOD G.

MAXIMUM DOSE CllllITM!Vr -

WHOLEBODY Percent of TS 3.24.4.la limit H.

MAXIMUM DOSE COMMITMENT - ORCAM Percent of TS 3.24.4.la limit

  • ~

Data i1 reported for Xe-133 I

I Ci 8.80E-03 uCi /ml 2.62E-10 l.06E-02 Ci 5.73E+Ol uCi/ml

l. 71E-06 5.68E-02 Ci 7.97E-02 uCi/ml 2.37E-09 l.19E-03 Ci 2.6E-05 uCi/ml 7.7£-13 Liters 9.55!+05 Liters 3.36E+l0 mllem 4.38£-03 2.92£-01 mRem 7.83£-03 l.57E-Ol 4th QUARTER:

6.88E-02 I

I 2.27E-09 5.86E-02 I

4.47E+Ol l.47E-06 4.92E-02 3.76E-02 l.24E-09 6.20E-04 8.2E-06 2.7E-13 l.40E+06 3.03E+l0 5.86£-02 3.91EOO 9.72E-02 l.94EOO

    • Hote:

Calculated from vendor analysis of monthly radvaste compo1ite samples.

IC0288-0022A-HP01 18 Est Total Error %

15 16 5.6*

I I

1

  • NUCLIDES RELEASED Cesium-137 Cobalt-58 Manaanese-54 Cobalt-60 Cesium-134 Rubidium-88 Molvbdenum-99 Strontium-89**'*

Strontium-90**'*

Cobalt 57 Ant imonv-12 5 Iodine-131 Iodine-133 Chromium-51 Net Unidentified Beta TABLE HP 10. 5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

LIQUID EFFLUENTS JULY 1987 to DECEMBER 1987 I.

Units I

3rd QUARTER l

i I

I Ci I

l.65E-03 Ci 9.85E-05 I

I Ci I

5.62E-04 Ci 4.39E-03 Ci 2.46E-04 Ci 8.58E-04 Ci None Ci 7.2!-06 Ci I

8.5E-06 Ci I

None I

Ci None Ci i

5.51E-06 i

Ci 2.49E-06 er

~

None I.

Ci 9.72E-04 Fission & Activation I

4th QUARTER 2.20E-02

1. 77E-03 9.70E-03 2.42E-02 i

5.94E-03 I

None I

2.95E-05 I

I I 3.JE-04 i

I 4.3E-04 I I l.lJE-05 I

1. 90E-04 4.67E-04 None l.04E-04 i

3.59E-03

--- ----Product* -Tot-al -(Above-) -- -- - ---- -

~ -er- -- -

---a.;SOE*OJ- - -- -

-~ - - --- 6. 88E-02----*-------

Noble Cases Ci 7.97E-02 3.76E-02 I

Tritium Ci 5.73E+Ol i

4.47E+Ol Grand Total Ci 5.74£+01 j

4.48E+Ol NOTE: Calculated from vendor analy111 of monthly radvaste composite samples:

Reported net beta and vendor analyzed Sr89/90 results were input to LADTAP do1e as Sr-90 to yield conservative dose estimates.

IC0288-0022A-HP01 19

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