ML20235T167

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Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jul-Dec 1988
ML20235T167
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/31/1988
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20235S902 List:
References
NUDOCS 8903080176
Download: ML20235T167 (16)
v • d • e


Text

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' ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155-N*

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S IANNUAL RADIOACTIVE EFFLUENT RELEASC' AND WASTE DISPOSAL REPORT JULY THORUGH DECEMBER 1988 February 28, 1989 i

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Big R*ck Paint Semir nnu,1 R-diectiva Effluent Release Report July - December 1988 This report provides information relating to the radioactive effluent releases and solid radioactive waste disposal operations of Big Rock Point during the period of July - December 1988. Format for this report is contained in Technical Specification 6.9.2.2. Big Rock Point was off-line for 7 days during the third quarter and 4 days during the fourth quarter.

1. Supplemental Information A. Batch Releases Information relating to continuous and batch releases of gaseous and liquid effluents is provided in Table HP 10.3-1.

B. Abnormal Releases None.

2. Caseous Effluents Table HP 10.3-2 lists and sununarizes all gaseous radioactive ef fluents released during the reporting period. The unidentified beta was 12.3% of *.

s' the total (particulate) release.- The maximum noble' gas release rate for -.

thethirdandfourthquarterswas:3.80E+02and3.40p02pCi/second, respectively. '

3. Liquid Effluents Table HP 10.3-3 lists and sununarizes all liquid radioactive ef fluents released during the reporting period. The unidentified beta was 14.2% of the total release. The maximum liquid effluent release concentration for the third and fourth quarters was 2.45E-07 and 4.09E-07 pCi/ml, respec-tively.
4. Solid Radioactive Waste Solid radwaste classification sources, volume shipped, curie and nuclide content are detailed in Table HP 10.3-4. Radwaste shipments were processed and sent either to Barnwell, South Carolina or Richland, Washington for burial.
5. Summary of Radiological Impact on Han Potential doses tn 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 of f site air doses due to fioble gases was during the  ;

fourth quarter. Doses at the site boundary (.57 mi E) were 1.28E-02 millirad beta and 2.29E-02 millirad gamma. Doses at the nearest residence / garden (1.40 mi E) were 1.53E-02 millirad beta and 2.72E-02 millirad gamma.

IC0289-0034A-HP01 1

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B. The most restrictive organ dose to an individual in an " unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulate, and iodines) was_the child bone for both the third and fourth quarters. Doses were 3.13E-03 millirem'and 4.18E-03 millirem, respectively.

, C. The maximum total body dose to individuals (adult) in unrestricted water-related exposure pathways was"1.48E-02 millirem for the third quarter and 1.68E-02 millirem for the fourth quarter. The maximum -

organ doseLwas the child bone for both the third and fourth quar-ters. Doses were 3.33E-02 millirem and 2.77E-02 millirem, respec-tively.

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

8.72E-03 manRem and 5.66E-05 millirem for the third quarter; and 7.58E-03 manRem'and 4.92E-05 millirem for the fourth quarter.

E. Integrated total body dose to the general population and average  ;;

dose to individuals within the population from gaseous effluent 7 releases within a distance of 50 miles from the site boundary were 1.55E-02 manRem and 1.01E-04 millires for the third quarter; and 1.63E-02 manRem and 1.06E-04 millirem for the: fourth quarter.

F. There was no entrained noble gas present in e'ither the third or fourth quarter liquid releases. -

4

6. Process Control Program (PCP)

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

7. Of fsite Dose Calculation Manual (ODCM)

There were no changes to the ODCH during this reporting period, however the ODCM is currently undergoing technical revision as per NRC Corres-pondence, dated June 10, 1988, Docket No: 50-155.

8. Supplemental Information to the BRP January-June 1988 Semiannual Radioactive Effluent Release Report Revisions for the Big Rock Point Semiannual Radioactive Effluent Release Report, January - June 1988, are being submitted as follows:

A. Table HP 10.3-2; Caseous Effluents - Summation of Releases, item C.1 thru 3, 2nd Quarter only

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' Change the Particulate Total Release (1-lives >8 days) from 9.69E-04 Ci to 8.90E-04 Ci.

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nt deminnruat Change the Particulate Average Release RatetToViPeriod from 1.23E-04 pCi/see to 1.13E-04 pCi/sec.

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g-r, Change the Particulate Percent of Annual Averags MPC from.3.37E-06. m to.3.48E-06.

Fo item F.i thru 2, 2nd quarter only:

Change the Maaimum Organ Dose to Public Based on Critical' Receptors from 2.83E-03 millires to 6.67E-04 millires.

Change'the-Percent-of Limit from 3.77E-02 to 8.89E-03.

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7 B.' . Table HP'10.3-2; Caseous' Effluent Isotopi c Particulate, item 3,.2nd Quarter only:

Change.Sr-f9 from 1.0E-04 Ci to 8.9E-06 Ci; change Sr-90 from u 1.2E-06.Ci to 7.7E-07 Ci and change the net unidentified beta from' none to 1.26E-05 Ci. Total Particulate Released also changes.from:

9.69E-04 Ci to 8.90E-04 Ci.

C. Table HP 10.3-3; Liquid Effluents - Summation of Releases, item A.3,.

2nd Quarter only. .

r Change the Total Release Percent of MPC from 1.76 to 1.79. ,

D. Table HP 10.3-3; Liquid Effluent Isotopes, item 1, 2nd Quarter only:

Change Sr-89 from 1.1E-03 Ci to 3.6E-04 Ci; change Sr-90 from-l'.6E-03 to 3.4E-03 Ci and change the net unidentified beta from-3.49E-02 Ci to 3.38E-02 Ci.

L' E. In the BRP. January-- June 1988 Semiannua1' Radioactive Effluent Release Report narrative the'following changes are also noted:

Item 2 - Caseous Effluents: change from "no unidentified beta released" to "the unidentified beta was 7.54E-01% of the total (particulate)' release".

Item 3 - Liquid Effluents:- change from "the unidentified beta was L. 25.0% of the total release" to "the unidentified beta was 9.2% of E

the total release".

Item 5 - Summary of Radiological Impact:on Man:

B. Change 2nd Quarter Organ Dose (child bone) from 2'.83E-3 millirem to 6.67E-04 millirem.

E. Change 2nd Quarter Integrated Total Body Dose to Ceneral Popula-tion from 1.84E-03 manRem and 1.19E-05 millires to 1.66E-03 manRem

i. and 1.08E-05 millirem, respectively.

p Reasons for the above data revisions.to the Big Rock Point Semiannual b Radioactive Ef fluent Release Report, January - June 1988 was that the calculated Sr-89 and Sre90 release quantities (gaseous and liquid ICO289-0034A-HP01 3

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I effluents, 2nd Quarter only) were based on estimated values for the

. months of April - 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. Oth r than what has been indicated, there were no

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significant dose changes to the public.

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., , TABLE HP 10.3-1 BIC ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JULY 1988'to December 1988

. A. Caseous - Continuous Release B. LIQUID 3rd Quarter- 4th Quarter Number of Releases 7 4

' Total Relesoe Time Minutes' 1.36E+0,3 6.54E+02 Maximum Release Time Minutes 3.85E+02 2.01E+02 Averste Release Time Minutes 1.95E+02 1.64E+02 Minimus' Release Time Minuteu 7.20E+01 1.43E+02 5

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-, , TABLE HP _10.3 BIC ROCK POINT SEMIANNUAL RADI0 ACTIVE u ,

- EFFLUENT RELEASE REPORT 4

CASEOUS EFFLUENTS - SUM ATION OF RELEASES JULY 1988 to DECEMBER 1988

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Est Total n 9 ' A. FISSION AND ACTIVATION CASES UNITS 3rd QUARTER 4th QUARTER' ' Error %-

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1. Total release Ci 2.63E+03- 2.76E+03-
2. Averaae release rate for period uCi/sec 3.31E+02 3.48E+02- 5.48'
3. Percent of annual ava MPC  % 9.15E-02 9.63E-02 L B. IODINES ^

Total Iodine

1. Ci 3.66E-03 2.62E-02
2. Averste release rate for period
  • uCi/sec 4.60E-04 1.19E-03 5.42*
3. Percent of annual ava MPC
  • 1 1.41E-05 3.26E-05 g .A C. PARTICULATE 3

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'eepjr235ml. Particulate with half-life > ,

'8 days Ci 4.98E-04 8.42E-04 H 7320*)'O-2. Averate release rate for period uCi/sec -6.27E-05 1.06E-04

3. Percent of annual ava MPC - 1 3.72E-06 4.51E-08 14.3
4. Cross alpha radioactivity Ci- .7.90E-04 5.80E-07
5. Cross alpha release rate f or period uCi/sec 9.94E-05 7.30E D. ' TRITIUM
1. Total release 'Ci 1.4E+00- 1.4E+00
2. Average release rate for period uCi/sec 1.8E-01 1.8E-01 3.- Percent of annual ava MPC  % 8.2E-06 8.2E-06 E.

1.. Beta air dose at cite boundary due

' to Noble Cases (TS 13.1.4'.2a) mRads -1.22E-02 1.28E-02 p 2. Percent limit- 1 1.22E-01 1.28E-01 3.- Camma air dose at site boundary due to Noble Cases (TS 13.1'.4.2a) mRads 2.20E-02 2.29E-02

4. Percent limit 1 4.40E-01 4.58E-01 F.

-1. Maximum organ dose to public based based on critical receptors

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<' (TSL13.1.4.3a) mrem 3.13E-03 4.18E-03

2. ' Percent of limit  % 4.17E-02 5.57E-02 O Note: . Data is. reported for I-131 and I-133 only IC0289-0034 A-HP01 6 l.

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, TABLE HP 10.3-2 BIG ROCK-POINT SEMIANNUAL RADIOACTIVE-EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS  !

JULY 1988 to DECEMBER 1988

1. FISSION CASES Units 3rd QUARTER 4th QUARTER Krypton-85m Ci 3.55E+01 3.79E+01 Krypton-87 Ci 1.77E+02 1.91E+02 Krypton-88 Ci 1.14E+02 1.18E+02 Kenon-133 Ci 1.30E+01 1.46E+01

' Xenon-133m Ci None None

- Xenon-135 ,

ci 1.65E+02 1,74 E+ 0$

Xenon-135m Ci 3.20E+02 3.30E+02-4 Xenon-138 Ci 1.33E+03 1.38E+03 p .-

Nitrogen-13 Ci 4.76E+02 5.20E+02 Total for Period Ci 2.63E+03 2.76E+03

2. IODINES'

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Iodine-131 Ci 4.20E-04 6.50E-04 Iodine-132 Ci None None Iodine-133 Ci- 3.24E-03 8.80E-03 Iodine-134 Ci None None E Iodine-135 Ci None 1.67E-02 l-Total for Period Ci 3.66E-03 2.62E-02

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TABLE HP 10.3-2

., . .BIC ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS t

JULY 1988 to DECEMBER 1988

3. PARTICULATE
  • Units 3rd QUARTER 4th QUARTER Chromium-51 Ci 2.00E-05 2.85E-04 Manamnese-54 Ci 5.06E-05 2.80E-05 Cobalt-58 Ci None 1.91E-06 Barium-140 Ci 1.13E-04 1.45E-04 Cobalt-60 Ci 5.70E-05 6.40E-05 OZine-65 Ci 1.96E-05 5.26E-05 Niobium-95 Ci 5.34E-06 None h

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CE'sid 3'4' " Ci- 1.84E-05 1. 72 E ' " desi'us2 IY7 "

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Ci 7.10E-05 5.80E-05 a _._.u . 3

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- Me reury-203 Ci None 2.81E-06 Silver-110m Ci 3.23E-05 3.87E-05 Barium-139** Ci None 9.76E-04 Lanthanum-140** Ci 3.57E-04 4.20E-04 Strontium-91** Ci 2.70E-04 1.40E-04 I

Bromine-82** Ci 4.20F.-04 '3.90E-04 Sodium-24** Ci None 4.30E-05 Moly bd en um-99** Ci 1.76E-05 4.90E-05 Neptunium-239** Ci None 4.44E-05 Strontium-89*** - Ci 3.6E-05 5.8E-05

. g '~ Strentium-90*** -

Ci 7.0E-07 7.0E-07 2- ~- - =1 Netzunidentified - -

'e r e era 'W '

a :be t's - ' E - -- - - Ci '7.43E-05 9.03E-05

} Total Ci 4.98E-04 8.42E-04 l 0 Particulate with hal f-lives >8 days.

I CO- Particulate with half-lives <8 days; not reflected in overall isotopic totals.

O** Calculated from vendor analysis of monthly stack gas filters. Reported vendor analyzed Sr 89/90 results were input to CASPAR code as Sr90 to yield conservative dose j estimates.

IC0289-0034A-HP01 8 l-I I

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TABLE HP 10.3-3 l BIC ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES JULY 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 3.28E-02 1.52E-02
2. Average diluted concentration durina period uci/ml 1.31E-09 6.06E-10 6.98
3. Percent of MPC  % 1.76E-01 4.78E-02 B. TRITIUM
1. Total release ci 3.77E-02 2.95E-02
2. Average diluted concentration durina period uC1/mi 1.51E-09 1.18E-09 8.55
3. Percent of MPC  % 5.03E-05 3.92E-05 h.

C. DISSOLVED AND ENTRAINED CASES .

1. Total Release Ci None None

'2. Average diluted concentration durina period uCi/mi None None None

3. Percent of MPC I None None D. CROSS ALPHA RADIOACTIVITY (Total Release) Ci 4.50E-07 2.46E-06
1. Average diluted concentration during period uCi/mi 1.80E-14 9.80E-14 E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 1.02E+05 6.93E+04 F. VOLUME OF DILUTION WATER USED DURINC PERIOD Liters 2.50E+10 2.51E+10 C. MAXIMUM DOSE COMMI'INENT - WHOLEBODY mrem 1.48E-02 1.68E-02 Percent of TS 13.1.4.la limit I 9.87E-01 1.12E00 H. MAXIMUM DOSE COMMITMENT - ORGAN mrem 3.33E-02 2.77E-02 Percent of TS 13.1.4.la limit  % 6.66E-01 5.54E-01 IC0289-0034A-HP01 9

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TABLE HP 10.3-3 BIC ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS'-

JULY 1988 to DECEMBER 1988

1. NUCLIDES RELEASED Units 3rd QUARTER 4th QUARTER-Cesiam-137 Ci 3.10E-03 6.70E-03 Cobalt-58 Ci 6.50E-05 None Manganese-54 '

Ci 7.30E-03 1.20E-03 Cobalt-60 Ci 7.50E-03 3.50E-03 Cesium-134 Ci 5.30E-04' 3.10E-04 Iron-59 Ci 4.50E-04 None Zine-65 C1 3.50E-04 None  :

Chromium-51 Ci 3.31E-04 None Silver-110m Ci 8.40E-05 None Strontium-89** Ci 3.8E-05 3.4E-05 Strontium-90** Ci 2.3E-05 6.8E-05 Net Unidentified Beta Ci 1.30E-02 3.40E-03 Fission & Activation Product Total (Above) Ci 3.28E-02 1.52E-02 Xenon-133 Ci None None Tritium Ci 3.77E-02 2.95E-02 Crand Total Ci 7.05E-02 4.47E-02

(* Calculated from vendor analysis of monthly radwaste composite samples.

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

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IC0289-0034A-HP01 10

TABLE HP 10.3 q.

, BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE JULY'1988 to DECEMBER 1988 I

- Waste Source-of Solidification Container Volume Total'

  • Principal Class Weste Agent Type (cu ft)' Curies Radionuclides A DAW- N/A Boxes & 2.53E+03 0.84- Co-60,Mn-54,Cr-51 drums Zn-65,Zr.-95 C Dewatered N/A HIC 5.47E+02 7.64E+01 Cs-137,Co-60,Mn-54 Resi.ns Cs-134,Zn-65,Fe-55 C Dewatered N/A HIC 8.34E+01 6.86E+01 Fe-55,Co-60,Mn-54, Filters Fe-5 9,Zn-65, A;;-110m, Cs-137 5-
  • NOTE: Canuna isotopes are measured quantities; all' other isotopes are estimated. -

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t Big Rock Point Semiannual Radioactive Effluent Release Report E

January - June 1988 (Revised)

This report provides information relating to the radioactive ef fluent ' releases and solid radioactive waste disposal operations'of Big Rock Point during the period of January - June 1988. Format for this report is contained in Tech-nical Specification 6.9.2.2. Big Rock Point was off-line for the second quarter of 1988 due to a refueling outage.

1. Supplemental Information A. Batch Releases Information relating to continuous and batch releases of gaseous and liquid effluents is provided in Table HP 10.3-1; -

B. Abnormal Releases- * * + ' ' a.

7 None. ' ' >-" ,

2. Caseous Effluents "" " ener a vuou ai .m 4 r. a e.etam, m r- cuta: '

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Table HP 10.3-2 lists and' summarizes al1~ gaseous" radioactive effluents released during the reporting ~ period. The unidentified beta was #

7.54E-01% of the total (particulate) release. The maximum noble gas.

release rate-for the first and second quarters was 2.93E+02 and 2.15E+02 pCi/second, respectively.-

3. Liquid Effluents Table HP 10.3-3-lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 9.2% of f the total release. The maximum liquid effluent release concentration for the first and second quarters was 4.94E-07 and 1.48E-06 pCi/mi, respective-ly+

l

4. Solid Radioactive Waste Solid radwaste classification sources, volume shipped, curie and nuclide content are detailed in Table HP 10.3-4. Two radwaste shipments were l

processed and sent to Barnwell," South Carolina for burial.

5. Summary of Radiological Impact on Man m o. a. w n s t u, c ,

.m 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 swnmarized as follows:

MIO289-0032A-HP01 12

A. The maximum offsite air dose due to noble gases was 9.97E-03 millirad beta and 1.73E-02 millirad gamma for the first quarter at site boundary; and 1.3E-03 millirad beta and 1.96E-03 millirad gamma for the second quarter at 1.4 miles (neare'st residence).

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulate, and iodines) was the infant thyroid for the first quarter and child bone for the second quarter. - Doses were 2.96E-03 millirem and 6.67E-04 millires, respectively. #

C. The maximum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 4.40E-02 millirem for the first quarter'and 4.74E-02 millires for the second quarter. The maximum organ dose was the child bone for the first and second quarters.

Doses were 7.14E-02 millirem and 1.00E-01 millires, respectively.

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

1.92E-02 manRem and 1.2SE-04 millires for the first quarter; and '.

3.36E-02 manRem and 2.18E-04 millires for the second quarter. w  ;

E. Integrated total body dose to'the gene'ral population and average dose to individuals within the population f rom gaseous ef fluent releases within a distance of 50 miles from the site boundary were:

1.43E-02 manRem and 9.29E-05 millirem for the first quarter; and 1.66E-03 manRem and 1.08E-05 millirem for the second quarter. # l F. There was no entrained noble gas present in either the first or second quarter liquid releases.

6. Process Control Program (PCP)  ;

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

7. Of fsite Dose Calculation Manual (ODCM)

Changes to the Big Rock Point ODCM, Revision 2, are being submitted per the requirements of Technical Specifications 6.9.2.2.A(5) and 13.2.3. A complete revision 3 with PRC/ evaluation sheets is provided. The specific changes are itemized as follows:

A. Table of Contents, pages 1 and 2, ODCM, Revision 3: added to ODCM to indicate changes in text.

B. . Text of ODCM, pages 14-64, ODCM, Revision 3; the following numbered steps / items are clarified: '

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MIO289-0032A-HP01 13 i

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1)- I.B.1.3.

.2)' I.C.

3) I.C.1
4) .I.C.2 5)- I.C.4 '

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' 6 )' I.D.

7)- I.E.

8) II.A.3.
9) II.B.1.
10) II.B.2.
11) II.C.1.
12) II.C.2.  ?
13) II.C.2.3.
14) II.E.

C. Text of ODCM, pages 14-64, ODCM, Revision 3; the following data tables were revised:

1) Table 1.3, pages 28 meteorological data based on a three year composite of BRP on-site conditions from 1984 - 1986.
2) Tables 1.4 and 1.4A, pages 36 1987 Land Use Census Report with reverified critica1' receptor and. distance-locations of the' nearest residence, garden, dairy / beef-ca'ttle and goats to BRP.

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3) Table 1.9, .ges 51 1988 'BRP" Caseous ~ Design Objective ,

Annual Quantities. 7 ont L.

8. Supplemental Information to the BRP ~ July-December 1987 Semi-Annual Radioactive Effluent Release Report The Big Rock Point Semi-Annual Radioactive Effluent Release Report: July
l. - December:1987, the following revisions 'are being' submitted:

A. Table HP 10.3-21 Caseous Effluents - Summation of Releases, item  :

C.3, 4th Quarter only:

Change the Particulate Percent of Annual Average MPC from 1.67E-06 to 2.31E-06.

.B. Table HP 10.3-2; caseous Effluent Isotopic Particulate, item 3, 4th I

Quarter only:

Change Sr-89 from 1.0E-04 Ci to 8.1E-05 Ci; change Sr-90 from 1.4E-06 Ci to 1.3 E-06 Ci and change the net unidentified beta from 4.60E-06 Ci to 2.37E-05 Ci.

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l-C. Table HP 10.3-3; Liquid Effluents - Summation of Releases, item A.1

and A.3, 4th Quarter only
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I MIO289-0032A-HP01 14

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Change'the Fission and Activation Products Total Release from 6.53E-03 Ci to 6.48E-03 Ci and change the Total' Release Percent of MPC from 3.74E-03 to 4.77E-03.

D. Table HP 10.3-3; Liquid Effluent Isotopes, item 1, 4th Quarter only:

Change Sr-89'from 1.6E-04 Ci_to 2.3E-05 Ci; change Sr-90 from 1.9E-04 to 3.5E-05 Ci and change the net unidentified beta from none to 2.42E-04 Ci.

s.

E. In the BRP July - December 1987 Semi-Annual Radioactive Effluent Release Report narrative the following changes are also noted:

Item 2 - Caseous Effluents ' change from "the unidentified beta.was 3.10E-06% of- the total release" to "the unidentified beta was

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3.45E-06% of the total release".

Item 3 Liquid Effluents: change from "the unidentified beta was 15.6% of the total release" to "the unidentified beta was 15.7% of 1.; the total release". .

[$ Reasons for the above data revisions to the Big Rock Point Semi-Annual '

fi~i[' ' Radioactive Effluent' Release Report, July'- Decembeil19871was that the I?$i~. -calculated'Sr-89 and Sr-90' release quantiEles (gaseoustand~ liquid

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G lih- effluents, 4th Quarter only) were based oniestimatedivalues for the -

months of October - December. Teledyne Isotopes Midsesitaboratory had

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not yet completed the actual sample analyses prior to the Technical Specification Semi-Annual Report due date. All data changes are indi-cated by "#" in the right-hand margins. There were no significant dose

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