ML18054B076

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Forwards Corrected Semiannual Effluent Release & Waste Disposal Rept for Period Jan-June 1988,including LER 88-002 Inadvertently Omitted from Original 880831 Submittal & Supplemental Jul-Dec 1987 Rept
ML18054B076
Person / Time
Site: Palisades Entergy icon.png
Issue date: 10/30/1989
From: Johnson B
Consumers Energy Co, (Formerly Consumers Power Co)
To:
NRC/IRM
Shared Package
ML18054B077 List:
References
NUDOCS 8911080515
Download: ML18054B076 (21)


Text

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  • ~

consumers Power POWERiNii

/llllCHlliAN'S PRDliRESS General Offices: 1945 West Parnall Road, Jackson,° Ml 49201 * (517) 788-0550 October 30, 1989 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 1988 *~ CORRECTION Attached is the corrected Semiannual Radioactive Effluent Release and Waste Disposal Report for the Palisades Plant covering the period from January through June 1988.

  • This submitt~l is.made in accordance with 10 CFR 50.36a and Technical Specifications 6.9.3.la. This correction includes Palisades LER 88-002 which was inadvertently omitted from the original August 31, 1988 submittal.

Also included with this report is supplemental information to the July through December 1987 Semiannual Radioactive Effluent Release Report.

Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment

( 8911080515 891030 I I PDR ADOCK 05000255\

R PNU OC1089-0214-NL04 A CM5 ENERGY COMPANY

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUGH JUNE 1988 Revised l0/5/89

. I S911080516 891030 kDR , ADOCK- 05000255 PNU IC0888-0179A-HP01 1

\,,

REVISED Palisades Nuclear *Plant Semiannual Radioactive Effluent Release Report January - June 1988 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 1988. The report format is detailed in Plant Technical Spe~ification 6.9.3.la. Palisades has been on-line during this*

reporting period since being returned to service Jan~ary 27, 1988.

1. Supplemental Information "A. Batch Releases Information relating to batch releases of gaseous and liquid effluents is provided in Table HP 10.S-l.

B. Abnormal Releases LER-PA1.88-002

. On February 9, 1988 at 1630 an Auxiliary Operator (AO) identified

.that the in-service waste gas decay tank (WCDT) T-68C [WE;TK] had lost approximately 26 psi. The gas from the WCDT was released ini;o I

I the Auxiliary Building [NF] and ultimately to the atmosphere via. the I monitored Plan~ 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 HPC fraction of 8.0E-3 at the site boundary. Thrs value is a small portion of the one maximum P.ermiss.ible concentration fraction allowed at the site boundary.

I I

The release was monitored by Plant stack radiation monitoring equipment. No alarms or annuni::iations were received in the Control I

Room due to the highest count rate seen being a factor of I approximately five below the alert alarm setpoint. Therefore, due to the insignificant dose consequence, no adverse effects were presented to the general public.

IC0888-0179A-HP01 2

2. Gaseous Effluents Table HP 10.5-2 lists and surrmarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was l.13E-06% of the total release.
3. Liguid Effluents Table HP 10.5-3 lists and summarizes all liquid radioactive effluents released during the reporting period. There was no unidentified beta released.
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. Surmiary 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 summarized as_

follows:

A. The maximum offsite air dose at the site boundary due to noble gases was 3.30E-02 millirad beta and l.llE-02 millirad ganma for the first quarter; and 4.72E-02 millirad beta and l.59E-02 millirad gamma for the second quarter.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulates and iodine) was the infant thyroid. Doses were 9.0lE-03 and 8.24E-03 millirem for the first and second quarters, respectively.

C. Integrated total body doses to the general population and average doses to individual~ (adults) within the population from gaseous effluent releases within a distance of 50 miles from the site boundary were: l.73E-02 manRem and l.65E-05 millirem for the first quarter; 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 millirem (teenage bone) for the first quarter and 4.42E-03 millirem (teenage liver) for the second quarter~_

IC0888-0179A-HP01 3

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: l.63E-02 manRem and l.55E-05 millirem for the first quarter; and 1.02E-02 manRem and 9.71E-06 millirem for the second quarter.

F'. Both 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 wholebody*or organ doses.

6. Process Control Program (PCP).

There were no chang.es to the PCP during the reporting period.

7. Offsite Dose Calculation Manual (ODCM)

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

8. Supplemental Information for the July-December 1987 Semiannual Radioactive Effluent Release Report The Palisades Nuclear Plant Semiannual Radioactive Effluent Release .

Report; July - December 1987, Tables HP 10.5-2 Gaseous Effluents and Tables HP 10 *. 5-3 Liquid Effluents are being submitted .as an attachment with the following revisions:

A. Table.HP 10.5-2,. Gaseous Effluents - Su1J111ation of Releases, items C.l. 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/s~~ to 5.58E~05 uCi/sec.

B. Table HP 10.5-2, Gaseou~ Effluents (isotopic Ci li~tings),_it~m 3,

  • Particulates~ 4th Quarter only:

Change Sr-89 from 4.SE-06 Ci to 2.6E-06 Ci Change Sr-90 from l.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 - Swnma~ion of All Releases, items A.3. and D., 4th Quarter only:

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

Change the Gross Alpha ~adioactivity (Total Release) from 2.7E-05 to 8.2E-06.

IC0888-0179A-HP01 4

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

D. Table HP 10.5-3, Liquid Effluents (isotopic Ci listings), item 1.,

Nuclides Released, 4th Q~arter only:

Change Sr-89 from S.6E-06 Ci to 3.3E-P4 Ci Change Sr-90 from 6.lE-04 Ci to 4.3E-04 Ci Change Net Unidentified Beta fro~ 3.73E-03 Ci to 3.59E-03 ti E. In the Palisades July - December 1987 Semi-Annual Radioactive Effluent Release Repo~t Narrative, the following changes are also noted:

Item 2 - Gaseous Effluents: change from "the unidentified beta was 4.09E-OS%*of the total release" to "the unidentified beta was 4.lOE-05%" of the total release'~.

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

Reasons fbr the above data revisions to the, Palisades Semi-Annual RaJio-acti ve Effluent Release Report, July - December* 1987 was that the calcu-lated Sr-89 and S~-90 reJease quantities (gaseous and liquid ~ffluents, 4th Quarter only) were based on estimated values for the months of .

November and December. Teledyne Isotopes Midwest Laboratory had not yet completed the actual sample analyses prior to the Technical Specification Semi-Annual Report due date. All data changes are indicated by "#" in the right-hand margins. There were no significant dose change~ to the public.

IC0888-0179A-HP01 5

\

TABLE HP 10. 5-1 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JANUARY 1988 to JUNE 1988 A. GASEOUS Units I lst Quarter 2nd Quarter Number of Releases* I 14 18 I

Total Release Time i Minutes I 2.72E+03* 7.54E+03

! I Maximum Release Time* i Minutes I 3.41E+02 l.77E+03 Avera2e Release Time Minutes l. 94E+02 4.19E+02 Minimum Release Time I1 Minutes

. l.13E+02 9.00E+Ol B. LIQUID  ! Units

  • lst Quarter 2nd Quarter Number of Releases 20 16 I Total Release Time Minutes 4.37E+03 6. 71E+03 I Maximum Release Time Minutes 5.67E+02 I I 6.95E+02 I

I Avera2e Release Time Minutes 2.19E+02 4.20E+02 Minimum Release Time Minutes 4.90E+Ol 6.lOE+Ol IC0888-0179A-HPOi 5

TABLE HP 10. 5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACT[VE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JANUARY 1988 to JUNE 1988 I Est Tot al :

A. FISSION AND ACTIVATION GASES UNITS lst QUARTER 2nd QUARTER;

  • Er"r"Or" ?

l

  • Total r"elease Ci 6.93E+02 9.91E+02 ii
2. Aver"a2e release rate for period uCi/ sec 8.81E+Ol l. 26E+02 I 7. 20
3. Percent of annual ava MPC  % 4.20E-02 I 6.0lE-02 !

I B. IODINES '

l. Total Iodine i Ci 3.81E-03 2. 75E-03
2. Averaae release rate for period
  • I uCi/sec 4.21E-04 3.SOE-04 4.37* '
3. Percent of annual avg MPC *  !

I  % 4.llE-04 3.63E-04

c. PARTICULATES  !
1. Particulates with half-life > l 8 davs Ci l.27E-04 l.78E-05 i I
2. Averaae release rate for oeriod uCi/ sec l.62E-05 2.26E-06
3. Percent of annual ava limit MPC  % l .09E-05 1. 90E-06 75 .1 **

i 4. Gross alpha radioactivity  ! Ci 3.86E-06 5. 36E-06

s. Gross alpha average release rate I I for period I uCi/Sec ; 4.91E-07 6.82E-07 j

I D. TRITIUM

! L Total release Ci 9.l8E-Ol 8.98E-Ol I 2. Averaae release rate for period I uCi I sec

  • l.17E-Ol l.14E-Ol I 3. Percent of annual ava MPC I  %*  : 8. 36E-05 8 .14E-05

! E.

1. Beta air dose at site boundary due* I to Noble Gases (TS 3.24.5.2a)- mRads 3. 30E-02 4.72E-02
2. Percent limit  % 3.30E-Ol 4.72E-Ol
3. Ganma air dose at site boundary due to Noble Ga*es (TS 3.24.5.21) mRads i l. llE-02  ! l.59E-02 I

I 4. .Percent li11i t I  % i 2.22E-Ol I 3.18E-Ol F.

1. Maximum organ dose to public based I based on critical receptors (TS 3.24.5.3) mRem 9.0LE:-03 ! 8.24E-03
2. Percent of limit  % l.20E-Ol I 1. lOE-01
  • Note: Data is reported for I-131 and I-133 only.
    • Note: Large error factor due to very small amount of particulates present in gaseous effluents.

IC0888-0l79A-HP01 6

TABLE HP 10.5-2.

PALISADES NUCLEAR PLANT SEMIANNUAL RADLOACTIVE

. EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS*

JANUARY 1988 to JUNE 1988 l* FI SS ION GASES ' Units I 1st QUARTER I 2nd QUARTER I I i Krvoton-85 Ci 7.90E-Ol i 4.24E-Ol '

I  : i

! Krvoton-85m Ci l.16E-02 I S.79E-03 I

I i

i Krypton-87 Ci l.42E-02 2. 39E-03 * ,.

I Krvoton-88 Ci l.71E-02 5.96E-03 I! I j

Xenon-13lm Ci 2.13E-Ol 7.37E-02

! Xenon-133 Ci 6.92E+02 9.91E+02 .i j i Xenon-133m Ci l.91E-02 1. 92E-02 i

! I I i I Xenon-135 I. Ci 6.JOE-02 5. 95 E-02 i

I Xenon-135m I Ci 3.84E-02 8.49E-03 i Xenon-138 ' Ci 2.62E-02 3.olE-03 Argon-41  ; Ci 9.20E*04 I None Total for Period Ci 6.93E+02 9.92E+02

2. IODINES Iodine-131 Ci l.9 lE-03 l.7SE-03

- *. 1- --

Iodine-132 Ci None None Iodine 133 Ci l .40E-03 9. 96E-04 Iodine-135 Ci 5.04E-04 None I.  !

Total for Period Ci I J.81E-03 I 2.75E-03 IC0888-0179A-HP01 7

TAB LE HP l 0 . 5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE

'EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JANUARY 1988 to JUNE 1988

3. PARTICULATES
  • Units l st QUARTER I 2nd QUARTER Chromiwn-51 i Ci None. None I

Man~anese-54 i Ci None I None Cobal t-58 Ci l.32E-05 None i

Cobalt-60 Ci 2.55E-06 4.64E-07 I Seleniwn-75 Ci 9.32E-05 1. 34E-05 I I

I I

Cesium-134 Ci  ! None None  !

I Cesiwn-137  ! Ci i l.08E-06 5.98E-07

! I Strontium-89 ** Ci I 6.3E-07 4. 5E-07 Stl"ontium-90 ** I Ci 3 .4E-07 2.4E-07 Net Unidentified  !

Beta Ci l.64E-05 I 2.65E-06 I

I Total Ci l.27E-04  ! l.78E-05

  • Note: Particulates with half-lives > 8 days.
    • Note: Calculated from vendor analysis of monthly stack gas filters; 2nd quarter result includes data estimates for Hay and June due to unavailability of completed sample analyses. Reported net beta and vendor analyzed Sr~89/90 were input to GASPAR code as Sr-90 to yield conservative dose estimates.

IC0888-0l79A-HPOl 8

TABLE HP 10. 5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY 1988 to JUNE 1988 I

Est Total '

A. FISSION AND ACTIVATION PRODUCTS UNITS . 1st QUARTER 2nd QUARTER Et"ro t" %

1. Total l"elease (not* including tl"itium. !lases. al nha) Ci 7.JlE-03 4.23E-03 I
2. Average diluted concentt"ation dut"ina oeriod uCi/ml 2.56E-l0 ,* l.29E-10 14.4
3. Percent of MPC  % 9.3SE-03 2.52E-03 B. TRITIUM
l. Total l"elease Ci 3.49E+Ol 1. 07E+02
2. Average diluted concentration durimr oeriod uCi/ml l.22E-06 3. 28E-06 22.3
3. Percent of MPC  % 4.07E-02 l. 09E-Ol
c. DISSOLVED AND ENTRAINED CASES
1. Total Release Ci l.93E-03 7.SSE-02 '

I

2. Average diluted concentt"ation I dut"ina oeriod uC i I ml 6.75E-ll 2.31E-09 4.0*
3. Percent of MPC  % 3.38E-OS l.16E-03 I D. CROSS ALPHA RADIOACTIVITY I (Total Release) ** Ci. 3.0E-06 2.SE-06
l. Ct"oss alpha average diluted I concentration durina oeriod uCi/ml l.OE-13 7.6E-l4 E. VOLUME OF WASTE RELEASED (Prior to Dilu~ion) Liters 8.27E+05 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.86E+l0 C. MAXIMUM DOSE COMMITMENT - WHOLEBODY mRem 4.S4E-03 2.67E-03 Percent of TS 3.24.4.la limit  % 3 .03E-Ol l.78E-Ol H. MAXIMUM DOSECOHHITMENT - ORGAN mRem 7.90£-03 4.42E-03 Percent of TS 3.24.4.la limit  % 1.58£-01 8.84E-02
  • ~ Data is t"ep(>rted for Xe-133, Xe-l33m, Xe-135 and Kr-8Sm
    • ~ Calculated from vendor analysis of monthly radwaste composite samples; 2nd quarter result includes data estimates for May and June due to unavailability of completed sample analyses.

IC0888-0179A-HP01 9

e.

TAB LE HP l 0

  • 5- 3
  • PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS JANUARY 1988 to JUNE 1988
1. NU CL IDES RELEASED Un its l st OUARTER 2nd QUARTER I

I Cesi um-137 Ci 1. 71E-03 9.80E-04  !

Cobalt-58 Ci* 1. 30E-03 5.&0E-05 i Manaanese-54 Ci l.14E-04 2.03E-04  !

Cobal t-60 Ci 1. 38E-03 2.13E-03 I I

I Cesi um-134 Ci 1. 62E-04 l.21E-04 i Iodine-131 Ci 2.37E-05 None  !

Strontium-89*** Ci 2.lE-03 5.9E-04  !

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

Net Unidentified Beta  ;

Ci None None Fission & Activation.

Product Total

  • Ci 7.llE-03 4.23E-03 Noble Gases ' Ci l 1. 93E-03 7.55E-02 I

I I 3.49E+Ol L07E+02 Tritium Ci I Grand Total ' Ci .. i 3.49E+Ol l.07E+02

      • NOTE: Calculated from vendor analysu of mont*hly radwaste composite samples; 2nd quarter result includes estimates for May and June due to unavailability of completed sample *analyses. Reported net beta and vendor analyzed Sr-89/90 were input to LADTAP code as Sr~90 to yield conservative dose estimates.

IC0888-0l79A-HPOl 10

TAB LE HP l 0 . S-4 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE JANUARY 1988 to JUNE 1988 Waste Source of Solidification Container Volume Total Principal Class Waste Agent Type (Cu.ft. ) Curies Radionuclides..:.-

A DAW N/A B-25 Box-LSA 1174 .o 3.1 H3 ,Mn-S4,Fe-55,Co-57, Co-58,Co-60,Ni-63 Cs-134,Cs-137,Sr-90, Tc-99, C-14,* I-129 A Evaporator Asphalt Metal drum 661.S 7.9 H3 ,Mn-54,Fe-55,Co-57, Bottoms co~58,co-60,Ni-63 Cs-134,Cs-137,Sr-90, Tc-99, C-14, I-129 Sb-125 B Irradiated N/A Steel liner l4.6 149.0 Mn-54,Fe-55,Sb-125, 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

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

IC0888-0l79A-HP01 11

Palisades Nuclear Plant Semiannual Radioactive Effluent Release R~port (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 l - 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.

B. Abnormal Releases There were two (2) reportable incidents of abnormal gaseous r~leases from the Palisades Plant during the July - December 1987 reporting period. A brief description of each is provided:

1. *0n 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 Gas 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.l and resulted in an Event Report (E-PAL-87-029) to the NRC. Cause of the WCDT release was determined to be theperformance*of maintenance activity on the (then in-service) T-68A WGDT relief valve. Approximately 5.78 m3 of noble gas escaped from the WCDT into the Auxiliary Building. The noble gas was vented from the Auxiliary Building via the ventilation system and out the plant stack.. The release wa1 monitored by the stack. noble gas monitor (RIA 2326)
  • and occurred over an approximate thirty (30) minute time period. 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 Waste Gas Decay Tank. (WGDT) 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 unauthorized WCDT release was inattention to detail and procedure non-compliance. The activity of WCDT-1018 was known as it had been isolated and sampled prior to the release. No release limits were exceeded. A total of 7.20 IC0288-0022A-HP01 12

  • ~6Rl 1080'519 891030 R ADOCK 05000255 PNU .

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

2.
  • Gaseous Effluents Table HP 10.5-2 lists and su!Tlllarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 4.lOE-05% of the total release. 4
3. Liquid Effluents Table HP 10.5-3 lists and surm1arizes all liquid radioactive.effluents released during the reporting peri9d. 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. AU radwaste *shipments were made to either Barnwell, South Carolina*or Richland, Washington for burial.

5. Sunmary of Radiological Impact on Han
  • Potential doses to individua(~ and populations were calculated using GASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follo.ws:

A. The maximum offsite air dose at the site boundary due. to noble gases was 2.62E-02 millirad beta and 8.SOE-03 millirad ganma for the third quarter; and 2.73E-02 millirads beta and 9.21E-03 millirads gamma for the fourth quarter.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents

{tritium, particulate and iodine) was the child bone. Doses were 6.63!-02 and 1.14E-Ol millirem for the third and fourth quarters, re1pectively.

C. The mazimum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 4.38E-03 millirem for the third quarter and 5.86E-02 millirem for the fourth quarter. The maximum organ dose (teenage liver) was 7.83E-03 and 9.72E-02 millirem for the third and fourth quarters, respectively.

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

l.48E-02 manRem and l.41E-05 millirem for the third quarter; and l.91E-Ol manRem and l.82E-04 mi 11 ;rem 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 site boundary were: 3.34E-02 manRem and 3.18E-OS millirem for the third quarter; and 4.94E-02 manRem and 4.70E-OS millirem for the fourth quarter.

F. The.Selenium-75 in gaseous effluent releases (fourth quarter only) and* the entr~ined noble gases presen~ in both the third and fourth quarter liquid releases were not significant in either wholebody or organ doses.

6. Process Conti6l 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 - Su1J111ation of Releases, item C.3., 2nd Quarter only:

Change the Particulate P~rcent of Annuai Average Limit HPC from 2.62E-06 to 2.64E-O!.

B. Table HP 10.5-2, Gaseous Effluents (isotopic Ci listings), item 3, Particulates, 2nd Quart~r ~nly:

Change Sr-89 from J.2E-07 Ci to 5-.9E-07 ci-.---

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

Chana* Net Unidentified Beta from 4.31E-05 Ci to 4.26E-05 Ci.

C. Table HP 10.5-3, Liquid Effluents

  • Summation of Releases, item A.3., 2nd Qaurter only:

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

IC0288-0022A-HP01 14

]1

  • D. Table HP 10.5-3, Liquid Effluents (isotopic Ci Listings)i icem L, Nuc1ides 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 ~as that the calculated Sr-89 and Sr-90 release quantities (for both gaseous and liquid effluents) were based on estimated values for the mon~h of June. Teledyne Isotopes Midwest* Laboratory had not yet completed the actual sample analyses prior to the Techniql Specific.ation Semiannual report due date. All data changes are indicated by "#" in the right-hand margins. There were no reportable changes in doses to the pubiic.

IC0288-0022A-HP01 15

TABLE HP 10.5-2 e

(~evised)

PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1987 to DECEMBER 1987

' Est Total i A. F'ISSION AND ACTIVATION GASES UNITS 3t'd QUARTER 4th QUARTER! En"OC' % i

1. total C"elease Ci 5.49E+02 5.70E+02 i I
2. Avet"aae release t'ate for period uCi/sec 6.89E+Ol 7.17E+Ol 24.0
3. Percent of annual av2 MPG  % 3.29E-02 3.43E-02 i I I B. IODINES
1. Total Iodine Ci  ! 5.49E-03 l .49E-02 I i

i

2. Averaae release rate for' Pet'iod
  • uCi/ sec I 6. 90E-04 l .88E-03 4. 66* i
3. Percent of annual av2 MPG *  % I 7.71E-04 2.59E-03 I
c. PAR TI CLTT .ATES
1. Particulates with half-life >

8 davs Ci l.80E-04 4.44E-04

2. Averaae release rate for Period uCi/sec 2.26E-05 5.58E-05
3. Percent of annual av2 1 imit MPC  % l.OJE-04 l. 76E-04 20.8**

. 4. Gross alpha radioactivity . Ci 6.lSE-06 6.40E-06

5. Gross alpha average release rate for period I uCi/Sec 7. 74E-07 8.0SE-07  :

iI D. TRITIUM l

  • Total C"elease Ci 8.25E-Ol 7.56E-Ol I
2. Averaae release rate for period uCi/sec l.04E-Ol 9.SlE-02 I
3. Percent of annual ava MPC  % 7.41E-05 6.79E-05 I i

E.

l. Beta *ai.r dose at site boundary due to Noble Gases (TS 3.24.5.2a) mRads 2.62E-02 2. 73E-02 .
2. -Percent limit  % 2.62E-Ol 2. 73E-Ol-
3. Gamma air doae at site boundary due to Noble Ga*** (TS 3.24.5.21) - mRads 8.SOE-03 9.21E-03 l.84E-Ol
4. Percent li*it I  % l.76E-Ol F.
1. Maximum organ dose to public based  :

based on critical receptors (TS 3.24.5.3) mRem 6.63E-02 l.14E-O 1-

2. Percent of limit  % 8.84E-Ol l.52EOO Data is reported for I~l31 and I-133 only.

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

IC0288-0022A-HP01 16

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

GASEOUS EFFLUENTS JULY 1987 to DECEMBER 1987

3. PARTICULATES**
  • I Units *  : 3rd QUARTER 4th QUARTER I

I Ch r-omi um-5 1 Ci I None None Han2anese-54 Ci I None None Cobalt-SB Ci None 6. 77E-OS Cabal t-60 Ci 7.44E-06 6.48E-06 Selenium-75 Ci None 6.56E-OS i

Niobium-95 Ci None 1. iOE-06 Cesium-134 Ci None None '

Cesium-137 Ci None 9.35E-06 I

Strontium-89****  ! Ci 1. 7E-06 2.6E-06 #

II i

St ront ium-90***'*

  • Ci 4. lE-07  ! 9.2E-07 Net unidentified I I

beta Ci 1. 70E-04 2. 90E-04 Total Ci I l.BOE-04  ! 4.44E-04 I

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

Reported net beta and vendor analyzed Sr89/90 results were input to CASPAR code as Sr~90 to yield conservative dose estimates.

IC0288-0022A-HP01 17

TABLE riP l0.5-J PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

LIQUID EFFLUENTS - SUHHAT ION OF ALL RELEASES JULY 1987 to DECEMBER 1987

  • I

! Est Total

. A. FISSION AND ACTIVATION PRODUCTS I UNITS 3rd QUARTER 4th QUARTER: Error %

l. Total release (not including i tritium. aases. aloha)  :

Ci 8.80E-03 6.88E-02

2. Average diluted concentration i durina oeriod uCi /ml 2.62E-10 I 2.27E-09  ; 15
3. Percent of MPC  % 1. 06E-02 5.86E-02 I
8. TRITIUM i
l. Total release i Ci S.73E+Ol 4.47E+Ol
2. Average.diluted concentration durinll oeriod uCi/ml 1. 71E-06 l .4 7E-06 . 16
3. Percent of MPC  % 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 oeriod uCi/ml 2.37E-09 l.24E-09 5.6*
3. Percent of MPC  % l.19E*03 6.20E-04 D. CROSS ALPHA RADIOACTIVITY I (Total Release) ** Ci 2.6E-05 8.2E-06 I 1
  • Gross alpha average diluted concentration durina oeriod uCi/ml 7.7E-13 2.7E-l3 I

. E. VOLUME OF WASTE RELEASED ..

(Prior to Dilution) Liters 9.55E+05 l.40E+06 F. VOLUME OF DILtrrION WAT!I USED DURING

. PERIOD Liters 3.36E+l0 3.03E+l0 G. MAXIMUM DOS! COtltITMIHT - WHOLEBODY mRem 4.38E-03 5 .86E-02

  • Percent of TS 3.24.4.la limit  % 2. 92E-Ol 3.91EOO H. MAXIMUM DOSE COMMITMENT - ORGAN miem 7 .83!-03 9.72E-02 Percent of TS 3.24.4.la limit  % l.57E-Ol l.94EOO
  • ~ Data is reported for Xe-133
    • ~ Calculated from vendor analysis of monthly radvaate composite samples.

IC0288-0022A-HP01 18

\

v, *

  • TABLE HP 10.5-3

.PALISADES NUC~EAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Revised)

LIQUID EFFLUENTS JULY 1987 to DECEMBER 1987 I l. NUCLIDES RELEASED I Units  ! 3rd QUARTER 4th QUARTER

I Ces ium-13 7  ;

Ci I l.6SE-03 I 2.20E-02 Cobalt-58 Ci I 9.85E-05 l. 77E-03

\

Manaanese-54 Ci I 5.62E-04 9. 70E-03 Cobalt-60 Ci 4<39E:..03 2.42E-02 Cesium-134 Ci 2.46E-04

Rubidium-88 Ci 8.58E-04 None i Molvbdenum-99 Ci None*  !

2.95E-05

~

Stronti um-89*** Ci 7 .2E-06 3.JE-04  :

I i

Strontium-90*** Ci I!

8 .SE-06

  • 4.3E-04.

I Cobalt 57 Ci I None l. l3E-05 I

Antimonv-125 Ci

!i None 1. 90E-04 Iodine-131 Ci I

  • S.SlE-06 4.67E-04 i .

I od ine-133 Ci 2.49E-06 None Chromium-51 Ci None 1. 04E-04 I1

  • Net Unidentified  !

Beta Ci 9.72E-04 3.59E-o3*

I Fission & Activa.tion Product Total (Above) Ci 8.80!-03 6.88E-.02 ...

I I Noble Gases Ci 7.97!-02 3.76E-02 I

I Tritium Ci 5.73E+Ol 4.47E+Ol Grand Total Ci

  • 5. 74E+Ol . I 4.48E+Ol
      • NOTE: Calculated from vendor analysis of mon~hly radwaste composite samples:

Reported net beta and vendor analyzed Sr89/90 results were input to

~TAP dose as Sr-90 to yield conservative dose estimates.

IC0288-0022A-HP0l 19