ML20206F559

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Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997
ML20206F559
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/31/1997
From: Ezzell P
FLORIDA POWER CORP.
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ML20206F550 List:
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NUDOCS 9905060168
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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACHMENT B-RADIOACTIVE EFFLUENT RELEASE REPORT - 1997 (REVISED) I L

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RADIOACTIVE EFFLUENT RELEASE REPORT 1997 FLORIDA POWER CORPORATION i

CRYSTAL RIVER - UNIT 3 1

Facility Operating License No. DPR-72 Docket No. 50-302 t

Prepared By: *I S bdC Chemrad Specialist II Approved By: d ,Md Manager, Nuclear Chemistry Date: 9/M/i T

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CONTENTS i 1

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Introduction .....,,.................... ,. ,... 1

- Tabular Data Summaries

. Gaseous Effluents - Quarters 1 & 2 ................... 2 Gaseous Effluents - Quarters 3 & 4 ............ ...... 4.

Liquid Effluents - Quarters 1 & 2 ................... 6 Liquid Effluents - Quarters 3 & 4 ................... 9 Radwaste Shipments ............................. .. 12 Unplanned Releases ................ ............... 13 Radioactive Waste Treatment Systems . . . . . . . . . . . . . . . . . . . . . . . 13 Environmental Radiological Monitoring Program . ......-........... 13 Effluent Monitor Instrument Operability . . . . ................. 13

- 000M & PCP Changes ............................... 13 Appendix I Dose Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 5

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INTRODUCTION

The following information is included:

A summary of the quantities of radioactive liquid and gaseous ef fluents and solid waste released from the plant.

Quarterly and annual dose summaries.

. A list and description of unplanned releases to unrestricted areas. l' A description of any changes to the:

Process' Control Program (PCP), and Offsite Dose Calculation Manual (00CM).

Significant changes to any radioactive waste treatment system.

A list of new dose calculation location changes identified by the annual land-usa census.

' Information relating to effluent monitors or required supporting instrumentation being inoperable for 30 or more days.

This reprt was revised to include dose summaries for liquid and gaseous effluents released during 1997. In addition further evaluation lead to the deletion of cadmium-113m and barium-139 from Yable 4 krypton-87 from Table 6, and xenon-135m fom

- Table 8.

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TABLE 1 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and activation gases

1. Total release Ci 5.65E-01 3.19E-02 30 l
2. Average release rate for period pC1/sec 7.26E-02 4.06E-03
3. Percent of technical specification limit  % 5.82E-04 7.52E-05
8. Iodines 1.' Total Iodine-131 Ci 0.00%00 0.00E+00 l
2. Average release rate for period pCi/sec 0.00E400 0.00E+00
3. Percent of technical specification limit  % 0.00E+00 0.00E+00 C. Particulates*
1. Particulates with half-lives > 8 days Ci 0.00E+00 1.35E-07 30 l
2. Average release rate for period pC1/sec 0.00E+00 1.71E-08 i
3. Percent of technical specification limit  % 0.00E+00 9.62E-03
4. Cross alpha radioactivity Ci 0.00E+00 0.00E+00 D. Tritium
1. Total release Ci 2.60E+00 3.01E+00 30 l
2. Average release rate for period pCi/sec 3.35E-01 3.82E-01
3. Percent of technical specification limit  % 8.33E-03 9.61E-03
  • The sum of the particulates reported on this paae may be less than the sum from Table 2 as Table 2 includes all llves greater than 8 days.particulates, while thls table includes only those with half-1 1

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TABLE 2 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 GASE0US EFFLUENTS - GROUND LEVEL RELEASE.S CONTINUOUS MODE BATCH MODE I Nuclides Released l Unit Quarter 1 l Quarter 2 Quarter 1 l Quarter 2

1. Fission gases Argon-41 C1 Krypton-55 C1 Krypton-55m C1 5.Olt-UZ 2.00E-UZ Krypton-57 C1 Kryptort-55 C1 Kenon-131m C1 3.53E-06 Kenon-;.33 C1 4.37E-01 Kenon-'. 3 3m C1 Kenon~;.35 Cl 4.77E-UZ l.19E-UZ xenon-; 35m C1 xenon-;55 C1 Total for period . Ci 5.64E-01 3.19E-02 0.00E+00 0.00E+00.
2. Iodines
odine- L31 C1

.:odine-;,32 C1 i

odi ne-;.33 I C1
odine- L 35 C1 C1 Total for period 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
3. Particulates Zinc-72 Ci 4.55E-05 Cobalt-55 C1 1.35E-07 Coba1t-50 C1 5trontium-59 C1 5trontium-90 C1 Yttrium-93 C1 T1n-113 C1 Tellurium-13Z C1 1.33E-05 1.95E-05 Ce s t um-;.34 C1 Cesi um-;.37 C1 Cesium- .35 C1 la ri um-; 39 C1

.anthanum-142 C1 Ce ri um-;.43 C1 1.55E-07 Cerium- .44 C1 Rhenium-155 C1 Total for period C1 1.81E-07 2.00E-07 0.00E+00 0.00E+00 l

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E TABLE 3 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation gases

1. Total release Ci 4.88E-01 ~ 0.00E+00 30 l
2. Average release' rate for period pCi/sec 6.14E-02 0.00E+00
3. Percent of technical specification limit  % 5.15E-04 0.00E+00 B. Iodines-
1. Total Iodine-131 Ci ' O.00E+00 0.00E+00 l
2. Average release rate for period pCi/sec 0.00E+00 0.00E+00
3. Percent'of technical specification limit  % 0.00E+00 0.00E+00 C. Particulates*
1. Particulates with half-lives > 8 days Ci 0.00E+00 0.00E+00 l
2. Average release rate for period pCi/sec 0.00E+00 0.00E+00
3. Percent of technical specification limit  % 0.00E+00 0.00E+00
4. Cross alpha radioactivity Ci 0.00E+00 0.00E+00 D .' Tritium
1. Total release C1 4.47E+00 6.50E-01 30 l
2. Average release rate for period pC1/sec 5.62E-01 8.17E-02
3. Percent of technical specification limit  % 1.43E-02 2.08E-03 1
  • The sum of the particulates remrted on this pace may be less than the sum from Table '

4 as Table 4 includes all llves greater than 8 days.particulates, while this table includes only those with half-I l

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F TABLE 4 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 CASE 005 EFFLUENTS - GROUND LEVEL RELEASES l CONTINUOUS MODE BATCH MODE

[ Nuclides Released l Unit Quarter 3 l Quarter 4 Quarter 3 [ Quarter 4

1. Fission gases )

Argon-41 C1 ,

Krypton-55 C1 1.29E-01 i Krypton-55m (1 Krypton-57 C1 Krypton-55 C1 xenon-;.31m C1 3.59E-Ul 9.62E-07 xenon-;.33 C1 xenon-; 53m C1 xenon-; 55 u menon-;.35m Ci xenon-;.35 C1 Total for period Ci 3.59E-01 0.00E+00 1.29E-01 0.00E+00

2. Iodines
odine-131 C1 a

..odine-13Z C1

..odine-135 C1

.;odine-155 u Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.- Particulates 21nc-72 C1 l Cobalt-55 C1 Cobalt-60 C1 5trontium-59 C1 Strontium-90 C1 Yttrium-93 C1 Tin-ll3 C1 Indtum-;.13m C1 C es i um-; 34 C1 Les t um-; 37 01 Cesium-; 35 C1 Bartum-; 39 01 Lanthanum-14Z C1 Certum-; 43 C1 Ce ri um-;.44 C1 unenium-155 C1 Total for period ' Ci 0.00E*00 0.00E+00 0.00E+00 0.00E+00 5

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TABLE 5 EFFLUENT MS WASTE DISPOSAL REPORT - 1997 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 2 Error %

A. Fission and activation products

1. ^ Total release (not including tritium, Ci 8.61E-02 6.48E-02 25 cases, alpha)
2. Average diluted concentration during pCi/ml 3.31E-10 2.11E-10 perid
3. Percent of applicable Limit  % 4.51E-03 4.71E-02 8 .' Tritium -

1.' Total release C1 2.27E+01 3.11E+01 30 l

2. Average diluted concentration during pCi/ml 8.71E-08 1.01E-07 peri M
3. Percent of applicable limit  % 2.10E-02 3.05E-02 C. Dissolved and entrained gases
1. Total release Ci 0.00E+00 0.00E+00 l
2. Averaae diluted concentration during pC1/m1 0.00E+00 0.00E+00 peri d
3. Percent of applicable limit '% 0.00E+00 0.00E+00~

D. Gross alpha radioactivity

'!1.'Totalrelease l Ci  !'0.00E+00 l0.00E+00 l- l

'E. Volume of waste released (prior to dilution)

'l1. Batch and continuous modes l Liters "l4.07E+05 l9.05E+05 l 10 l F. Volume of dilution water used during period '

l 1.' Batch and continuous modes  ! Liters l2.61E+11 l3.07E+11 l 10 -l 6

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j- _ TABLE 6 e o EFFLUENT A m WASTE DISPOSAL REPORT - 1997 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE muclides Released unit Quarter 1 Quarter Z Quarter 1 Quarter z bodlum-24 C6 Chromium-51 C1 planganese-54 C1 .3dE-03 1.43E-03 planganeSe-56 01 i.59E-U6

..ron-55 C1 P.95E-03 7.90E-03

..ron-59 C1 Cobalt-57 C1 2.5DE-04 Cobalt-55 C1 2.35t-U3 4.4bE-03 Cobalt-60 C1 1.34t-UZ l.5DE-02

< Copper-64 C1 1.90E-04 l

Zinc-72 C1 5trontium-55 C1 5trontium-59 C1 5trontium-90 C1 5trontium-9Z C1 Yttrium-92 01 Yttrium-93 C1 grom1ne-52 C1 N10bl um-95 C1 6.13E-05 N1obium-97 Cl Zirconium-95 C1 1.63E-04 Zi rcon t um-97 C1 2.51E-03 9.52E-04 plo l ybdi num-9') C1 Technetium-9'IM C1 Technetium-101 C1 Ruthenium-:.03 C1 Ruthenium- .06 C1 1 . 5 91i-03 4.24E-03 511ver-110m 01 5.70:;-02 1.94E-U2 Tin-113 C1 9.141[-05 9.90E-06 Indium-llHe C1 1.31;-04 1.39E-05 Antimony-'.i7 C1 Ant 1 mony-:.i4 C1 1.95'E -04 4.53E-05 Antimony- < '5 C1 3.16'i-03 7.30E-03 Teilurium-;.29 C1 1.97E-06 Te i I u r t um-'.,32 C1 1.67E-07

. 0(li ne-;. I;. 01

.ot 1ne- ,;h' 01

04 Ine- .i C1 odline- . 5 C1 Ce 51 um-;,H4 C1 4.44E-05 Cesium-:.37 C1 4.56E-05 3.53E-04 CeStur ..35 C1 2.20E-C5 Bartum-;.39 C1 Barlum .JIU C1

.anthanum-140 C1 Ce r t um-;.43 C1 Ce r l um-;.44 C1 5.17E-04 9 . 5 91E-05 Rhenium-155 C1 3.09'E -0 7

__mept un t um-2 39 C1 Total for period Ci 0.00E+00 0.00F+00 8.61E-02 6.48E-02 I  !

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TABLE 6 (CONTINUED)

EFFLUENT AND WASTE DISPOSAL REPORT - 1997 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE U1ssolved a

Entrained Cases Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Argon-41 ct Krypton-55 c1 Kr ton-55m ct ryp on~57 c1 Krypton-55 c1 xenon-15;m c1 xenon-13n ct xenon-u ne ci xenon-155 ci xenon-135m ct ,

i Total for Period Ci 'O.00E+00 0.'00E+00 0.00E+00 0.00E+00 l- T r i t t um I c1 1 0.00E+00 1 0.00E+00 l 2.27E+01 1 3.11E+01 ]

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TABLE 7 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error %

A. Fission and activation products

1. Total release (not including tritium, C1 1.08-01 5.80E-02 25 gases, alpha)
2. Average diluted concentration during pC1/ml 2.62E-10 1.27E-10 period

_3. Percent of applicable limit  % 1.04E-01 1.48E-02 B. Tritium

1. Total release C1 1.38E+01 9.57E+00 30 l
2. Average diluted concentration during pCi/ml 3.34E-08 4.27E-07 period
3. Percent of applicable limit  % 1.50E-02 1.24E-02 C. Dissolved and entrained gases
1. Total release C1 4.04E-05 0.00E+00 25 l
2. Average diluted concentration during pC1/ml 9.79E-14 0.00E+00 period
3. Percent of applicable limit  % 2.19E-06 0.00E+00 D. Gross alpha radioactivity l1. Total release l C1 l0.00E+00 l0.00E+00 l l E. Volume of waste released (prior to dilution) l1. Batch and continuous modes l Liters l8.98E+05 l4.13E+05 l 10 l F. Volume of dilution water used during period
1. Batch and continuous modes Liters 4.13E+11 4.51E+11 10 I

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ElFLUENT AND WASTE DISPOSAL REPORT - 1997 LIQUID EFFLUENTS COMTINUOUS MODE BATCH MODE Nucitdes Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Sodium-24 C1 Chromium-51 C1 1.35E-04 5.39E-04 Manganese-54 L1 3.01E-03 2.96t-04 Manganese-56 La Iron-55 L1 6.53E-03 2.0bE-03 Iron-59 Lt Cobalt-57 L1 1.bbE-04 5.bOE-05 Cobalt-58 L1 2.26E-03 3.14E-04 Lobalt-b0 01 3.47E-02 5.71E-03 linc-b5 C1 L1nc-72 C1 b.3bE-05 Strontium-55 Lt 1.45E-07 5trontium-59 C1 5trontium-90 01 1.91E-05 5trontium-92 C1 Yttrium-91 Ci 5.21E-04 Yttrium-93 L1 Hromine-52 L1 Niobium-95 L1 1.00E-05 1.14E-07 Niobium-95m (1 j Nioblum-97 Ci 2trcontum-95 C1 4.10E-04 Zircontum-97 C1 1.52E-03 9.37E-04 Molybdinum-99 L1 Technetium-99m Ci Technettum-101 Cl Ruthenium-103 C1 Ruthenium-10b Lt 1.02E-02 2.23t-03 51Iver-110m C1 3.72E-02 1.54E-02 Tin-ll3 L1 1.93E-04 Indium-ll3m C1 2.65E-04 Antimony-122 L1 Antimony-324 L1 Antimony-125 L1 8.47E-03 2.42E-02 Tellurtum-129 C1 Tellurium-132 Lt 9.99E-Ob Iodine-131 C1 Iodine-132 Lt Iodine-133 L1 Iodine-135 C1 Cestum-134 Ci b.72E-Ob 2.10E-07 Cestum-137 Ci 1.34E-04 1.71E-05 Barium-139 Cl Barium 140 Lt Lanthanum-140 (1 Certum-143 L1 1 Cerium-144 L1 1.10E-03 Rhen1um-155 C1

)

Total for period Ci 0.00E+00 0.00E+00 1.08E-01 5.80E-02 i

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TABLE 4 (CONTINUED)

EFFLUENT AfG WASTE DISPOSAL REPORT - 1H 7

' LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Dissolved &

' Entrained Cases Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Argon-41 c1 Kryizton-s5 c1 3.39E-05 Krypton-55m c1 Kry>t on- 57 c1 Kry'ston-55 c1 xenon a  :;1m c1 2.23E-06 xenon-:m3 c1 4.z5t-00 xenon-:.H3m c1 xenon-;.H5 c1 Kenon- .H5m c1 Total for period ,Ci .0.00E+00 0.00E+00 4.04E-05 -0.00E+00 1 Trittum I c1 l 0.00E+00 l 0.00E+00 ] 1.35E+01 l 9.57E+00 l 11

i TABLE 9 EFFLUENT AND WASTE DISPOSAL REPORT - 1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR PROCESSING OR BURIAL (Non-i* radiated fuel) l

1. Type of Waste Unit 12 month period - Est. Total Error %
a. 5 pent resins, filter sludges, evaporator bottoms, etc. m3 1.4/E+04 45 Ci 3.08E+01
b. Dry compressible waste, contaminated equipment, etc. m3 5.95E+02 25 C1 1.25E+00
c. Irradtated components, control rods, etc. m3 0.00E+00 Ci 0.00E+00
d. Other (describe); Oli m3 1.30E+00 25 Ci 3.20E-01
2. Estimate of major nuclide composition (by type of waste in %)*

Fe-55 51.1 N1-b3 13.6

a. Co-60 20.8 Cs-137 5.5 Fe-55 30.0 Ag-110m lb.4
b. Ni-63 19.9 Cs-137 2.9 Co-60 19.2 c.

H-3 54.1 N1-b3 4.7

d. C-14 8.9 Co-60 1.6
3. Solid Waste disposition Number of Shipments Mode of Transportation Destination 2 Exclusive Use Casks BarrwA1. SC CNSI) 14 Exclusive Use Flatbeds (13) Oak A.dge. TN SEG)

Exclusive Use Casks 1) 6 Exclusive Use Flatbe s Clive. UT (Envirocare)

Type a wastes were shipped in liners. Type b and d wastes were shipped in strong tight containers.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A

  • Curie values and principle radionuclides are estimates based on a combination of direct and indirect methods.

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Unplanned Releases There,were no unplanned gaseous or liquid releases.

Radioactive Weste Treatment Systems There were no significant changes to the. radioactive waste treatment systems.

Radiological Environmental Monitoring Program

'The June,1997 land-use census did not identify any new dose calculation locations.

Effluent Monitor Instrument Operability Required effluent monitor instrumentation was not out of service for more than 30 days during 1997.

Special Reports 97-03 and 97-08 were submitted to the Nuclear Regulatory Commission because the Post Accident Sampling System Mid and High Range Noble Gas menitors for the Reactor Building and Auxiliary Building were inoperable for more than seven days.

00CM & PCP Changes The PCP was not revised during 1997.

The ODCM was revised three times during 1997.

ODCM Revision 21. Approved for issuance on 4/3/97. Revised to 1) clarify the term " degassing"

2) provide for separate fixed setpoints for as it applies laundry tank to and Waste Gas Decay Evaporator Tank samplingYank condensate Storace (ECST) releases, 3) delete an unnecessary definition for " and requirements, independent
5) clarifyverification". between requirements and considerations for sampling 4) broaden the scope of the pow the distinction

'the Reactor Building when the hatches (personnel and equipment) are open.

ODCM Revision 22. Approved for issuance on 7/28/97. Revised to clarify the requirements for making changes to the ODCM.

00CM Revision 23. Approved for issuance on 12/16/97. Revised to clarify the Surveillance Requirement for the Waste Gas Decay Tank Curie determination.

A complete copy of the 00CM was provided with the original submittal of this report.

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1997 Appendix I Dose Sunenary ,

Maximum Hypothetical Individual '

- Liquid Effluent Dose Limits Total Body: 1.5 mres/ quarter, 3 mrem / year

~Any Organ: 5 arem/ quarter,10 mrem / year Liquid Effluent Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Total Body Dose (ares) 7.92E-06 3.16E-05 4.71E-05 4.65E-06 9.13E-05 Maximum Organ Dose (arem) 2.25E-04 2.35E-03 5.19E-03 7.40E-04 8.51E-03 Maximum Organ was GI Gaseous Effluent Dose Limits '

Gamma Air Dose: 5 mrad / quarter, 10 mrad / year Beta Air Dose: 10 mrad / quarter, 20 mrad / year Any Organ: 7.5 mrem / quarter, 15 mrem / year Gaseous Effluent Dose Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Total Gamma Air Dese (arad) 2.73E-05 3.76E-06 4.61E-06 0.00E+00 3.57E-05 Beta Air Dose (mrad) 5.82E-05 5.44E-06 S.15E-05 0.00E+00 1.15E-04 Total Body Dose (mrem) . 6.25E-04 7.21E-04 1.07E 1.56E-04 2.57E-03 i Maximum Orgam Dose (arem) 6.25E-04 7.21E-04 1.07E-03 1.56E-04 2.57E-03 j All Organs were equal I 1

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