ML20217M012
| ML20217M012 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1997 |
| From: | Bergeron A, Hood G, Ramzy S ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20217L968 | List: |
| References | |
| NUDOCS 9805040383 | |
| Download: ML20217M012 (54) | |
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Annual R:dio:ctive 1997 Efflu:nt Rel:ase Report Waterford 3 Steam Electric Station i
l Originator:
., i Gregory L. Hood Che'mistry Supervisor Date Waterford 3 SES Reviewed By:
f,,,,.,,p, Samir Ramzy Radiation Protection,
(
' Date Sr. Lead Engineer, Waterford 3 SES Approved By:
p g,g e, ~...
Aaron S. Bergeron Chemistry Supenntsndent Date Waterford 3 SES
)
Annual Radioactive 1997 Efflu:nt Release Report Waterford 3 Steam Electric Station Table of Contents i
i
- 1. 0 I n tro d u c ti o n......................................................................................................
l 2.0 S u p p ie m e n ta l I n fo rm a ti o n.................................................................................................. 2 l
2.1RegulatonLimits.......................................................................................................................................2 2.1.1 Fission and Activation Gases (Noble Gases).
.2 2.1.2 lodines; Particulates with Half Lives > 8 Days; and Tritium.
.3 2.1.3 Liquid Effluents.
.3 2.1.4 tiipium Fuel Cycle Sources.
.4 2.2 Maximum Permissible Concentrations..................
....................................................................4 2.2.1 Fission and Activation Gases; lodines; and Particulates, Half Lives > 8 Days
.4 2.2.2 Liquid Effluents.
.4
- 2. 3 A y e ra g e E n e rg y ( E-B a r).........................................................................................................
... 4 2.4 Measu rements and Approximations of Total Radioactivity................................................................... 5 i
l 2.4.1 Fission and Activation Gases (Noble Gases).
.5 l
2.4.2 lodines and Particulates.
.5 i
2.4.3 Liquid Effluents.
.6 2.5BatehReleases...............................................................................................................................................6 2.6 U n p l a n n e d/A b n o rm a I R e l e a s es................................................................................................................. 7 2.6.1 Unplanned / Abnormal Gaseous Releases...
.7 2.6.2 Unplanned / Abnormal Liquid Releases.
.7 2.6.2.a Spent Fuel Pool Spill..
.7 2.6.2.a.1 Description of Event:
.7 2.6.2.a.2 Doses Calculated and Radioactivity Released..
.8 2.6.2.b Temporary Containment Air Conditioning System Spill.
.10 2.6.2.b.1 Description of Event:
.10 2.6.2.b.2 Doses Calculated and Radioactivity Released..
.11 j
- 3. 0 G a s e o u s Effl u e n ts............................................................................................................ 13
- 4. 0 Li q u i d E ffl u e n ts................................................................................................................. 1 3
- 5. 0 S o l i d Wa a te s....................................................................................................................
0.0 Mete o ro l o g i c a i Da ta.......................................................................................................... 14 i
i 1
Annual Radioactiva 1997 Efflu nt Rele:se Report Waterford 3 Steam Electric Station Table of Contents 7.0 A s s e s s m e n t of D o s e s.......................................................................................
7.1 Dos e D u e to G a s e o u s E ffI u e n ts...........................,..............................................................
.... 15 7.1.1 Air Doses at the Site Boundary..
.15 7.1.2 Maximum Organ Dose to the Critical Receptor.
.16 7.2 Doses Due to Liquid Effluenis-
.......................................................17 7.3 40 CFR Part 190 Dose Evaluation.......................
........................................17 7.4 Doses to Pu blic Inside the Site Bou n d a ry............................................................................
......... 18
- 8. 0 R e l a te d I n fo rm a ti o n....................................................................................................
8.1 C ha nges to the Process Control Prog ram......................................................................................... 19 8.2 C ha n ges to the Offsite Dos e CaIculatio n Ma n u al................................................................................... 19 8.3 Unavailability of REMP Milk Sampies....................
..................................................................19 8.4 Report of Required Effluent Instrument inoperability......................................................
............ 2 0 8.4.1 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-IRE-0648).
.20 8,4.2 Condenser Vacuum Pump (MCES) Wide Range Gas Monitor (PRM-IRE-0002).
.21 1
8.4.3 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-lRE-0648).
.21 8.4.4 Fuel Handling Building PIG Monitor A (PRM-IRE-5107A).
.22 8.4.5 Boron Waste Management (BWM) System Radiation Monitor (PRM-IRE-0627)..
.23 8.4.6 Liquid Waste Management (LWM) System Radiation Monitor (PRM-IRE-0647).
.23 8.4.7 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-IRE-0648).
.24 8.4.8 Fuel Handling Building pig Monitor A (PRM-IRE-5107A).
.25 8.5 A clivity Released Via Secon d a ry Pathways........................................................................................... 26 8.6 Miss ed E ffIu e nt Sa m ples:................................................................
.....................................26 8.6.1 CWD-SGBDHX Sample.,
,26 8.7 Maj or C ha nges to Ra d loa ctive Waste Syste ms....................................................................................... 27 8.8 B i-A n n u a I La n d U s e C e n s u s.................................................................
....................27 8.9 Gaseous Storage Tann Total Radioactivity Limit.....................................................................
27 i
l 8.10 U nproteeted Outside Tank Total Radioaetivity Limit........................................................................... 27 l
i 8.10.1 Outside Temporary Tank Exceeded Limit.
.27 l
l
- 9. 0 A d d i ti o n a I i n fo rm a ti o n...................................................................................................... 2 8 9.1 Reaetor Coolant System Average Energy (E-Bar)............
.. 28 10.0 Tables...............................................................................................................................29 ii i
)
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Annual Radioactivs 1997 Efflu:nt Release Report Waterford 3 Steam Electric Station Table of Contents i
1 1. 0 A tta c h m e n ts............................
................................ 2 9 1
1 1
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Annut! Radioactiva 1997 Efflu:nt Raltase Report Waterford 3 Steam Electric Station 1.0 Introduction This Annual Radioactive Effluent Release Report is submitted as required by Waterford 3's Technical Specification S.9.1.8. It covers the period from January 1,1997 through December 31,1997. Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21 and in section 5.9.1 of the Offsite Dose Calculation Manual (UNT-005-014).
The information contained in this report includes:
A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period A summary of the meteorological data collected during 1997.
Assessment of radiation doses due to liquid and gaseous radioactive effluents released during 1997.
A discussion of Unplanned / Abnormal releases that occurred during the reporting period.
l A submittal of changes to the Offsite Dose Calculation Manual and Process Control Program during this l
reporting period.
l
(
A discussion of why required radioactive effluent monitoring instrumentation was not returned to service e
within the time specified.
A discussion of an instance in which an effluent sample was not collected within the required frequency, i
Page 1 of 49
Annual Radio:ctiva 1997 Efflurnt Rtlinsa Report Wa'erford 3 Stram Electric Station 2.0 SupplementalInformation 2.1 Regulatory Limits The Limits applicable to the release of radioactive materialin liquid and gaseous effluents are described in the following sections. These limits are addressed in UNT-005-014, Offsite Dose Calculation Manual, and also in the Technical Requirements Manual (TRM).
2.1.1 Fission and Activation Gases (Noble G ses)
Toe dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to:
500 mrem /yr to the total body; and 3000 mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
During any calendar quarter: Less than or equal to:
5 mrad for gamma radiation; and 10 mrad for beta radiation During any calendar year: Less than or equal to:
10 mrad for gamma radiation; and 20 mrad for beta radiation.
Page 2 of 49
Annu:1 Radioictiva 1997
' Effluznt Raluss Rrport Watsrford 3 Stram Electric Station j
2.1.2 lodines; Particulates with Half Lives > 8 Days; and Tritium The dose rate due to iodine-131 and 133, tntium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to:
i 1500 mrem /yr to any organ.
l The dose to a member of the public from iodine-131 and 133, tritium, and all radionuclides in
(.
particulate form with half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
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During any calendar quarter: Less than or equal to:
7.5 mrem to any organ; and i
During any calendar year: Less than or equal to:
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15 mrem to any organ.
i 2.1.3 Liquid Effluents l
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 1
for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml (Total Activity).
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The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
During any calendar quarter to less than or equal to:
1.5 mrem to the total body; and 5 mrem to any organ, and Page 3 of 49
Annu:1 R:dioictiva 1997 i
j Efflusnt RIleass Report Watarford 3 Stsam Electric Station During any calendar year to less than or equal to 3 mrem to the whole body; and 10 mrem to any organ.
2.1.4 Uranium Fuel Cycle Sources The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources over 12 consecutive months shall be limited to less than or equal to:
l 25 mrem to the Total Body or any organ (except thyroid organ); and 75 mrem to the Thyroid 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases; lodines; and Particulates, Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.
2.2.2 Liquid Effluents Ten times the effluent concentration (EC) values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/mlis used as the concentration limit for dissolved and entrained noble gases in liquid effluents.
2.3 Average Energy (E-Bar)
This is not applimble to Waterford 3's Effluent Specifications. E-Bars are not required to be j
calculated from effluent release data. The average energy (E-Bar) for the Reactor Coolant System l
(RCS) is supplied as additional information in the report further below.
Page 4 of 49
Annual Radioactive 1997 Efflu:nt Ral::s3 R port Waterford 3 St:am El ctric Station 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 5.3-1 and 5.4-1 of UNT-005-014, Offsite Dose Calculation Manual.
2.4.1 Fission and Activation Gases (Noble Gases)
I For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each woek a Gas Ratio (GR) was cc!culated according to the following equation:
Average Weekly Noble Gas Monitor Reading GR ~ Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch. In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.
2.4.2 lodines and Particulates lodines and particulates discharged were sampled using a continuous sampler which contained a charcoal cartridge and a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volumes discharged were used to calculate the previous vreek's activity released. The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Brown Engineering). Particulate gross alpha activity was measured weekly using alpha scintillation counting techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was performed.
Grab samples of continuous and batch releases were analyzed monthly for tritium. The determined concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.
Page 5 of 49
Annu:1 Radio:ctive 1997 Efflu:nt Ril:ase Report Waterford 3 Steam Electric Station j
2.4.3 Liquid Effluents l
l For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy.
The measured concentrations were used to determine radionuclide concentrations in the following week's releases. For batch releases, gamma analysis was performer 1 on the sample prior to release.
For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Teledyne Brown Engineering) for Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting techniques, respectively. For radionuclides measured in the composite samples, the measured concentrations in the composite sarrses from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter.
The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuctide present and the total volume of the effluent discharged.
2.5 Batch Releases 1
A summary of information for gaseous and liquid batch releases is included in Table 1.
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Annuil Radioactiva 1997 Efflutnt Rdeass Rzport Waterford 3 Steam Electric Station 2.6 Unplanned / Abnormal Releases
' 2.6.1 Unplanned / Abnormal Gaseous Releases There were no unplanned, Ibnormal gaseous releases during the reporting period.
2.6.2 Unplanned / Abnormal Liquid Releases There were two unplanned /abnormalliquid releases during this reporting period. A discussion of each occurrence follows.
2.6.2.a Spent Fuel Pool Spill 2.6.2.a.1 Description of Event:
On 5/21/97 at 0241, a spill of radioactive water occurred at the Waterford-3 site. The Spent j
Fuel Pool (SFP) was overflowed into the Fuel Handling Building (FHB) ventilation system and over the top of the Cask Washdown Pit. Water subsequently spilled over the top of the gate from the Cask Washdown Pit into the FHB Train Bay. The FHB Train Bay is at the same elevation as the asphalt surface in the Protected area. Water continued to fill the FHB Train Bay until the level was sufficient to cause water to flow from under the large metal exterior access doors end out onto the parking lot within the protected area. Some of the radioactive water entered the storm drain system which conveys runoff to drainage j
ditches and eventually, offsite.
The affected portions of the storm drain system were blocked off to prevent the release of radioactive water offsite. Plant personnelimmediately began to recover radioactive water from the affected portion of the storm drain system by pumping to temporary outside tanks Flushing was also commenced to reduce the concentrations of radioactivity in the storm drain system. Chemistry began periodic monitoring of storm water ditches downstream from the spill area in order to ensure that concentrations of radioactive liquids in the unrestricted area were below limits. This monitoring was maintained throughout the cleanup evolution until the storm drain system was cleared on 5/24/97.
Page 7 of 49
l Annu 1 Radioactive 1997 Effluent Releasa Report Waterford 3 Steam Electric Station 1
l On the day of the spill, a large thunderstorm occurred causing a breach of the dam that was preventing water from going offsite. By the time the storm had occurred, the total l
amount of radioactivity available for release had been significantly reduced by flushing and pumping operations. A continuous composite sampler had been set up and monitored the release. Other samples taken at locations further downstream also revealed that effluent 1
concentrations remained below their limits.
k 2.6.2.a.2 Doses Calculated and Radioactivity Released Data collected during remediation of the spill was used to construct a radioactivity balance in order to estimate the effluent radioactivity released. The estimates are further verified by comparing calculated concentrations to actual field data and measurements. The total amount of undiluted Spent Fuel Pool water released as effluent was determined to be 158.1 gallons from a total of approximately 800 gallons spilled cutside the FHB.
This SFP water was further diluted by rainfall prior to reaching the unrestricted area. The dilution provided by rainfall, as measured by on-site meteorologicalinstrumentation, was determined to be 6.89E+06 gallons during the release on 5/21/97. The release duration coincides with the preclpitation event and was determined to be approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Thus, using the data from the radioactivity balance, the radioactivity released to the unrestricted area is 3.59E-02 curies (including tritium). See table below:
- Released!
RCUries Cr-51~ ~ ^ 2.32E-05l j
I-131 - -3.85E-06i j
4
. Cs-134 ~ ~~ ~ 5.03E-05
!Cs-137 '
"4.18E~ 05!
!N b-95 '
~1.19E-06!
lCo-58' ~ ' 1.'13E-03l
! M n-54 "
~ 8.44E-07!
lCo-60 ~~ ~ 5.49E-06l lSbT124 T2.19E-06l
[! Li~3:59pp2j H-3 ~
[3.46E-02l The radioactivity released due to this event is also included in summary table 2B for liquid effluents.
Page 8 of 49
Annual Radioactiva 1997 Efflutnt Rel:ase Report Waterford 3 Steam Electric Station Thus, using the methodology and parameters proved in the ODCM, the doses calculated result in a maximum organ dose of 6.87E-02 mrem to the adult liver (1.37% of the quarterly limit) and 5.23E-02 m:em to the total body (3.49% of the quarterly limit). The sum of the effluent concentrations at the unrestricted area boundary divided by their limits (Ten times the values listed in 10CFR20, Appendix B, Table 2, Column 2) yielded a value of 7.48E-04 which is much less than the maximum value of 1.0. See table below:
, jQtr Lirnit 4 _Qtr limitf Annual Limit j%_Annuallimit mrem Bone, j 3.67E 02L 5p _0.73%[
10j
. 0.37%
Liver j 6.87E-02l 5!
^3.49%I" 3!'
' 1.74%
~
1.37%;
10!
0.69%
T. Body T5.23E 02[ ~
[5f Thyroid ~ I TiOE-03i
~5
~~ ~ '.~03'II~
~10)
^ 0.01 %
~
0 2.28E-02)
[5[03@5}
~
_ _ _ _23@o Kidney, _ _
_7.82E _03 I
, _ _5(_0_.16% [_
10, 0.08 %
__ 0 1
0.
Lung _
GI-LLI_.., -_5_.73E-03.! __
._S. i 0._1_1. %_
10;
. _. 0.06%
~
The liquid effluent release doses calculated are weil within the ODCM limits. Effluent concentrations at the unrestricted area boundary also remained well within the limits.
Since a spill of this type could have significant adverse consequences if allowed to recur, the plant is making efforts to reduce the chances that it will occur in the future. A Condition Report was written (CR-97-1284) documenting the occurrence of the spill. A root cause analysis was performed to determine the cause(s) ewi Mentify areas for improvement.
Some of the actions to prevent recurrence as a result of the root cause investigation included: procedure changes, valve line-up reviews, r-equipment adjustments.
Additionalinformation is available upon request.
Since the magnitude of the effluent release, as listed above, was small and within limits set forth in the ODCM, there was no adverse effect on the health and safety of the public.
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Page 9 of 49 l
Annu11 Rtdioactiva 1997 Effluznt R:13:s3 Rrport Waterford 3 Steam Electric Station I
2.6.2.b Temporary Containment Air Conditioning System Spill 2.6.2.b.1 Description of Event:
On 6/17/97 at 1130, a spill of radioactive water occurred at the Waterford-3 site. The Temporary Containment Air Conditioning System Catch Tank was overflowed onto the parking lot on the east side of the plant inside the protected area.
[
A portion of the Component Cooling Water (CCW) System is used to deliver chilled water i
to cool the air inside the Containment Building. Since the CCW system is contaminated with radioactive materials, a heat exchanger is utilized to prevent the contaminated water from entering the temporary chillers. A catch tank is used to collect overpressure relief I
water as well as venting and drain water from the system. The area where the temporary hoses and heat exchanger are located consisted of a diked area approximately one foot high to contain leakage or spillage from the contaminated side of the system. The catch tank was not located inside of this area at the time of the spill.
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The cause of the spill was due to simultaneous opening of the fill water valve and drain valve on the contaminated side of the Temporary Containment Air Conditioning System.
Water w is purg6d from the system into the catch tank which completely filled with water and overflowed. It was determined that approximately 75 gallons of water spilled from the ra n syste onvey his t he ch on th east side e plant he e t flo t
the south of the plant ultimately ending up in the 40 Arpent Canal.
1 Radiation Protection and Chemistry personnelimmediately responded to the area upon l
notification that water was flowing from the catch tank. The fill and drain valves were immediately closed, stopping the spill. Liquid samples were collected and analyzed for radioactivity. Samples were also collected in the ditch downstream of the storm drain connection to the ditch. The analyses for radioactivity indicated that the concentrations of j-radionuclides in the catch tank were below 10CFR20 limits (10 times the values listed in
(
10CFR20, Appendix B, table 2, column 2).
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Page 10 of 49
Annual Radioactiva 1997 Effluent Raltass Report Waterford 3 Steam Electric Station The catch tank was immediately transported to the RAB and drained to the Liquid radioactive waste system. A platform was constructed inside of the diked area surrounding the heat exchanger and temporary hoses, and the catch tank was placed inside of this diked area.
2.6.2.b.2 Doses Calculated and Radioactivity Released The radioactivity used in the effluent release calculations was determined using the l
estimated volume of water released (75 gallons). No additional dilution was used in the calculations. During the spill, a precipitation event (rain) was ongoing. However, due to the insignificant amount of radioactivity released and the resulting low doses, calculation of l
additional dilution was not warranted. The release duration was one minute.
Thus, the radioactivity released to the unrestricted area is 6.69E-06 Curies (including tritium). See table below:
I l
Released Nuclide NCuriss ~ ~
H-3 6.48E-06 Cs-1k[7 j 1.39E-07[6.73E{08
~
Csij3 _
[
l total
._6.69E-06 l
The radioactivity released due to this event is also included in the summary table 2B for f-l liquid effluents.
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Page 11 of 49
Annual Radioactive 1997 Efflusnt Ratsase Report Waterford 3 Steam Electric Station The calculated doses from this spill resulted in a maximum organ dose of 7.20E-03 mrem to the adult liver (0.14% of the quarterly limit) and 5.18E-03 mrem to the total body (0.35%
of the quarterly limit). The sum of the effluent concentrations at the unrestricted area boundary divided by their limits (Ten times the values listed in 10CFR20, Appendix B, Table 2, Column 2) yielded a value of 7.77E-02 which is much less than the maximum value of 1.0. The liquid effluent release doses calculated are well within the ODCM limits.
See table below:
hind M'EMd lid
! Bone ~--i~4.37E-03H-^~ 5i~~~0.09%
'- ~10!
0.04% '
! wr ~ ~ # 7.20E 03I'~~ ~5f~ 0.14% ~ ~~ ~ '10l ~- ~ 0.07%1 Li T. Body ~
5.18E-03) 1.5! ~ ~ 0.35% ^
3
~ 0.17%l
[ 2.~40E-03p ~ 5{E O.05%]-~ ^ ~ 5 ~^ ' O.00%I-~~
~ 10[ ~
~ 0.00% !
~ 3.41E-06I l Thyroid ~
lKidriey
~107- ~~~ ~ 0.02%1 (Lung ~~~t 8.00E-04 p ~ -~ 57~0.02%~~
'10b ~ 0.01%
$N_
- ?.l?0$
}0Q 10 0.00*/o t Even though a spill of this type will probably have a low adverse impact if allowed to recur, there is a possibility that effluent limits could be challenged during future operation of the Temporary Containment Air Condition System. The plant is making efforts to reduce the chances that it will occur in the future by ensuring that the Catch Tank will be placed inside of the diked area to contain incidental overflow. Procedures for set-up of the the system will also be modified. A Condition Report was written (CR-97-1534) documenting the occurance of the spill. Additionalinformation is available upon request.
Since the magnitude of the effluent release, as listed above, was very small and within limits set forth in the ODCM, there was no adverse effect on the health and safety of the public.
Page 12 of 49
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I Annu:1 Radioactiva 1997 Efflu:nt Raleasa Report Waterford 3 Steam Electric Station i
3.0 Gaseous Effluents The quantities of radioactive material released in gaseous effluents are summarized in Tables 1 A,1B, and
- 10. Note that there were no elevated mieases, since all Waterford 3 releases are considered to be at ground level. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc, l
i 4.0 Liquid Effluents The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 28. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
5.0 Solid Wastes The summary of radioactive solid wastes shipped offsite for disposalis listed in Table 3. For certain waste l
forms Waterford 3 is now using volume reduction services provided by Scientific Ecology Group, Inc.
l (SEG). These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal volumes. Final disposal volumes for wastes compacted offsite are available upon request. The estimated total error in % is based upon several statistical uncertainties due to L
sample courding, efficiency, volume, etc.
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Annual Radio ctiva 1997 Effluent Reisase Report Waterford 3 Steam Electric Station G.0 Meteorological Data in Table 4, the hourly meteorological data from January 1,1997 through December 31,1997, is presented in the form of a joint frequency distribution of wind speed, wind direction, and atmospheric stability. The standard Pasquill classification scheme as presented in Regulatory Guide 1.23 is used to determine stability class from differential temperature measurements The Waterford-3 data recovery results by parameter are as follows: Hourly data is also available upon request.
Parameter Monitored Annual Data Recovery Rate Diffenential Temp.
99.77 %
Wind Speed 99.77 %
Wind Direction 99.77 %_
Overall*
99.77 %
- Simultaneous occurrence of valid dite for all three parameters.
Dispersion and deposition values were determined from the 1997 data and used in the assessment of doses due to gaseous effluents released from site during the 1997 period.
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1 Annuil Radio:ctiva 1997 Efflutnt Rel ass Report Waterford 3 Steam Electric Station l
7.0 Assessment of Doses 7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary Air doses from gaseous effluents were evaluated at the closest offsite location that could be occupied continuously during the term of plant operation and that would result in the highest dose.
This location was determined by examining the atmospheric dispersion parameters (x/Q's) at the closest offsite locations that could be continuously occupied during plant operation in each of the meteorological sectors surrounding the plant. The location that would have the highest dose would be that location having the most restrictive (largest) x/O value.
Based on actual meteorological data collected during 1997, this location was determined to be in the NE sector at a distance of 966 meters (0.6 miles) from the plant. Doses were assessed at this location in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and gamma exposures in air due to noble gas. The results of these assessments for the year 1997 are summarized as follows:
Beta air dose:
0.31 mrad Gamma air dose:
0.12 mrad The above Beta and Gamma air doses represent the following percentage of the Annual Dose limits:
1.55% of the Beta air dose limit (20 mrad).
1.20% of the Gamma air dose limit (10 mrad).
Dose calculation results are summarized by quarters in Table 5. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.
Page 15 of 49
Annual Rrdioactive 1997 Efflurnt Reisase Raport Waterford 3 Steam Electric Station 7.1.2 Maximum Organ Dose to the Critical Receptor The maximum organ dose to a MEMBER OF THE PUBLIC from I-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary was determined for 1997.
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An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was assumed to be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (X/Q) and deposition (D/Q) parameters. Furthermore, it was assumed that the receptor living at this residence consumed food products that were either raised l
or produced at this residence.
Using land use census and meteorological data for 1997, the residence with the highest x/O and D/O values was determined to be in the NE sector at a distance of 1448 meters (0.9 miles) from the plant. The dose calculation was performed in accordance with the methodology described in the l
Waterford 3 Offsite Dose Calculation Manual considering the inhalation, ground plane exposure, l
and ingestion pathways. The maximum organ dose to the critical receptor was determined to be:
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l 0.48 mrem to an infant thyroid.
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This represents 3.20 % of the Annual Organ Dose limit (15 mrem).
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Dose calculation results are summarized by quarters in Table 5. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual..
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r Annual Radio:ctiva 1997 Effluznt Ral:ase Report Watsrford 3 Steam Elsctric Station l
_7.2 Doses Due to Liquid Effluents The annual doses to the maximum exposed individual resulting from exposure to liquid effluents released during 1997 from Waterford 3 were:
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0.19 mrem to the Total Body.
0.27 mrem to the maximum exposed organ (Liver).
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The above doses represent the following percentage of the Annual Dose limits:
6.33% of the Total Body Dose Limit (3 mrem), and l
2.70% of the Organ Dose Limit (10 mrem).
Dose calculation results are summarized by quarter in Table 5. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.
7.3 40 CFR Part 190 Dose Evaluation L
in accSrdance with Waterford 3 Offsite Dose Calculation Manual, Section 5.5.2, dose evaluations to l
demonstrate compliance with Surveillance Requirements 5.5.'..a and 5.5.1.b of the ODCM, dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases),10 mrem to any organ (liquid releases),10 mrad gamma air dose,20 mrad beta air dose, or 15 mrem to any organ from radioiodines and particulates.
At no time during 1997 were any of these limits exceeded; therefore, the evaluation was not required.
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Annutt Rrdioactiva -
1997 Efflurnt Reistse Report Watsrford 3 Steam Electric Station l
7.4 Doses to Public Inside the Site Boundary
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The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at Waterford 1 and 2 fossil fuel plants, located in the WNW sector at a distance of approximately 670 meters (0.42 miles) from the plant.
The doses for such an individual was determined by scaling the full-time occupancy doses due to airborne effluents by the occupancy time due to a normal working year. Based on an assumed occupancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week) and the fact that all employees are adults, the calculated doses were determined to be less than:
1.16E-02 mrem to the maximum exposed organ (Thyroid) 2.02E-02 mrem to the Total body 2.09E-02 mrem to the skin Doses were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only the inhalation and ground plane exposure pathways.
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AnnualRadio ctiva 1997 Efflu:nt Rebass Rtport Waterford 3 Steam El:ctric Station
'8.0 Related information i
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8.1 Changes to the Process Control Program Changes were made to the Process Control Program (PCP), procedure RW-001-210, during the reporting period. Revision 8 was done to remove unnecessary information and make editorial changes. A copy of the PCP is included in attachment 11.1 of this report.
8.2 Changes to the Offsite Dose Calculation Manual Changes were made to the Offsite Dose Calculation Manual (ODCM), procedure UNT-005-014, during the reporting period. Change 1 was dorie to clarify ACTION and source check requirements for effluent monitoring instrumentation and to implement REMP sampling reductions. Change 2 was done to further clarify effluent monitoring instrumentation channel check requirements. A copy of the ODCM is included in 1.2 of this report.
8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with ODCM Table 5.8-1. Milk is collected, when available, from the control location and two identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation l
Manual, Attachment 6.14.
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f Annu:1 Rcdio ctiva 1997 Efflu nt Reb:s3 R:: port Watsrford 3 Steam Electric Station 8.4 Report of Required Effluent instrurnent inoperability ODCM Specification 5.6.1.b and 5.6.2.b require reporting in the Annual Radioactive Effluent Release Report of why designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the Action Statement.
During the reporting period, there were eight cases when instrumentation was not restored to operability within the time specified. These cases are described in the following sections.
8.4.1 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-IRE-0648)
Time Required by Specifications to Restore Operability: 30 Days Period of inoperability: 0903 on 1/7/97 to 1339 on 4/10/97 (93.15 Days)
Number of Batch Releases performed during period: None.
Cause ofinoperability: The GWM radiation monitor was declared inoperable at 0903 on 1/7/97 due to detector problems noted during functional test. Insufficient count rate was obtained during the functional test. A new detector was installed.
Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returned to service within 30 days was due to delays in procurement of the calibration gases needed in order to perform the primary calibration, l&C also inadvertently ordered a non-standard container configuration (breakable glass ampoules instead of lecture bottles) which delayed the supplier in producing the source materials. The source manufacturer specifies at least a 30 day lead time for delivery from the time of reciept of an order. After the source materials were received on-site, the primary calibration was performed and the monitor returned to service as soon as possible at 1339 on 4/10/97.
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Annual R:dioictive 1997 Efflu:nt Ral: ass Report Waterford 3 Steam Electric Station 8.4.2 Condenser Vacuum Pump (MCES) Wide Range Gas Monitor (PRM-IRE-0002)
Time Required by Specifications to Restore Operability: 30 Days Period of inoperability: 1000 on 5/2/97 to 0233 on 7/13/97 (71.69 Days)
Release period with monitor out of sentice: 7/9/971235 to 7/13/97 0233 (3.58 days).
Cause of Inoperability: The MCES radiction monitor was declared inoperable at 1000 on 5/2/97 due to problems in completing the calibration due to a temporary alteration. The temporary alteration prevented the automatic diversion of exhaust to the plant stack. Since this feature could not be tested, the entire calibration procedure could not be enmpleted.
Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returryed to service within 30 days was due to delays in performing a deviation to the I&C calibration procedure. Note that there was no vacuum in the system until 1235 on 7/9/97. The plant was shut down in a refueling outage for the majority of the period of inoperability. During the period for which there was a vacuum (3.58 days), the monitor was actually online and, additionally, the ACTION requirements were being performed. The deviat;on to the I&C calibration procedure was performed and the monitor was officially placed back in service at 0233 on 7/13/97.
8.4.3 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-IRE-0648)
Time Required by Specifications to Restore Operability: 30 Days Period of inoperability: 0200 on 5/16/97 to 1545 on 7/10/97 (55.57 Days)
Number of Batch Releases performed during period: One.
Cause of Inoperability: The GWM radiation monitor was declared inoperable at 0200 on 5/'i6/97 due to monitor process flow rate problems noted during functional test. Insufficient i
process flow rate was obtained during the functional test.
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i Annual Radioactiva 1997 tiffluent R:l ase Report Waterford 3 Stecm Electric Station Reason Operability Not Restored With;n Allotted Time: The reasoa that the monitor was not returned to service within 30 days was due to problems in reparing the flow instrument I&C repaired the flow instrument, completed the functional test, and returned the monitor to service at 1545 on 7/10/97. For the batch release performed during this period of inoperability, the ACTION requirements were followed.
G.4.4 Fuel Handling Building PIG Monitor A (PRM-IRE 5107A)
Time Required by Specifications to Restore Operability: 30 Days Period of Inoperability: 1545 on 6/11/97 to 1346 on 8/5/97 (54.97 Days)
Release period with mor.itor out of service: 7/31/971406 to 7/31/971416 (10 min.) and 8/5/91 1343 to 015/971346 (3 min.).
Cause of Inoperab;lity: The functional test could not be performed due to a spill of Spent Fuel Pool water into the ventuation system. The FHB PlG A radiation monitor was flooded with water and had to be disassembled, dried, oecontaminated, and repaired. The A train ef FHB ventilation was also tagged out at this time to open it up, remove the water, and decontaminate accessible areas inside the exhaust ventilation system.
Reason O erability Not Restored Within Allotted Time: The reason that the monitor was J
not returned to service within 30 days was due to length of time required to clear the FHB A train exhaust ventilation system and restore proper radiation monitor operation. After the Spent Fuel Pool spill, the FHB B train of ventilation was used after it had been cleared of water. The FHB B PIG radiation monitor was not significantly affected by the spilled water.
The FHB A train ventilation was only used after proper operation of the monitor was restored. When the FHB A train ventiiation system was initially run, some residual moisture that could not be accessed wetted the filters installed in the moniter. Portat'le sampling equipment was stationed at the exit plenum and used as additional monitoring during the initial runs. Therefore, all of the time that the FHB ventilation system was running, with the exception of the periods listed above, a PlG radiation monitor was on-line monitoring the release. The proper operation of the FHB A PlG radiation monitor was restored at 1346 on 8/5/97.
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Annual Rrdioactive 1997 Efflu:nt R:lrass Report Waterford 3 Steam El:ctric Station 8.4.5 Boron Waste Management (DWM) System Radiation Monitor (PRM-lRE-0627)
Time Required by Specifications to Restore Operability: 30 Days Period of inoperability: 1650 on 8/13/97 to 1307 on 10/2/97 (49.85 Days)
Number of Batch Releases performed during period: None.
Cause of Inoperability: This monitor was declared out of service due to a potential problem identified in a Condition Report (CR-97 2075). It was believed by Operations personnel that upon a power loss to the monitor it might not secure a release and that a CPU lockup or freeze condition (computer program halt) could cause the same condition.
Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returned to service within 30 days was due to the time required to investigate and prepare an engineering evaluation, plus the amount of time required by Operations to review the engineering evaluation and clear the paperwork. The problem did not affect this monitor and after an engineering evaluation, the monitor was returned to service at 1307 on 10/2/97.
8.4.6 Liquid Waste Management (LWM' System Radiation Monitor (PRM-IRE 0647)
Time Required by Specifications to Restore Operability: 30 Days Period of inoperability: 1650 on 8/13/97 to 1307 on 10/2/97 (49.85 Days)
Number of Batch Releases perfoimed during period: Twelve.
Cause of inoperability: This monitor was declared out of service due to a potential problem identified in a Condition Report (CR-97-2075). It was believed by Operations personnel that upon a power loss to the monitor it might not secure a release and that a CPU lockup or freeze condition (computer program halt) could cause the same condition.
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i Annual Radioactive 1997 l
Efflu:nt Rel:ase Report Waterford 3 Steam Electric Station Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returned to service within 30 days was due to the time required to investigate and prepare art engineering evaluation, plus the amount of time required by Operations to review the engineering evaluation and clear the paperwork. The problem did not affect this
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monitor and after an engineering evaluation, the monitor was returned to service at 1307 on 10/2/97. Even though the monitor was declared out of service, eight of the twelve release permits contain trend plots from the radiation monitoring system that demonstrate that the alarm setpoint for each release was entered into the monitor. Printer problems with the radiation monitoring system prevented printing trend plots for the other four release j
permits, however, the practice of utilizing the setpoint during the release was the same.
8.4.7 Gaseous Waste System (GWM) Noble Gas Monitor (PRM-IRE-0648)
Time Required by Specifications to Restore Operability: 30 Days l
Period of Inoperability: 1650 on 8/13/97 to 1307 on 10/2/97 (49.85 Days) l l
Number of Batch Releases performed during period: None.
Cause of lnoperability: This monitor was declared out of service due to a potential problem identified in a Condition Report (CR 97-2075). It was believed by Operations personnel that upon a power loss to the monitor it might not secure a release and that a CPU lockup or freeze condition (computer program halt) could cause the same condition.
Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returned to service within 30 days was due to the time required to investigate and prepare an engineering evaluation, plus the amount of time required by Operations to review the engineering evaluation and clear the paperwork. The problem did not affect this monitor and after an engineering evaluation, the monitor was returned to service at 1307 on 10/2/97.
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Annu:1 Rrdiorctiv3 1997 Efflutnt Ralatsa Report Watsrford 3 Steam Electric Station l
8.4.8 Fuel Handling Building PIG Monitor A (PRM-IRE-5107A) l l
Time Required by Specificatioro to Restore Operability: 30 Days Period of inoperability: 0203 on 8/17/97 to 2030 on 9/16/97 (30.77 Days) l Release period with monitor out of service: None.
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j Cause of inoperability: The FHB A PIG radiation monitor was declared inoperable at 0203 on 8/17/97 due to failure of the check source mechanism. The check source for the iodine channel became stuck in the source exposed position and made the iodine channel stay in an alarm condition.
Reason Operability Not Restored Within Allotted Time: The reason that the monitor was not returned to service within 30 days was due to delays in restoring proper function of the source check mechanism. This monitor was the one that was significantly flooded during l
the Spent Fuel Pool spill. Proper operation of the check source mechanism was difficult to t
restore due to degradation due to corrosion. Proper function of the iodine source check mechanism was restored and the monitor returned to service at 2030 on 9/16/97. During the period that this monitor was out of service, the FHB B train exhaust system and its associated PIG radiation monitor was utilized, i
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Annu:1 Rrdioactiva 1997 l
Efflu:nt R bise Report Wat:rford 3 St:am El:ctric Station
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8.5 Activity Released Via Secondary Pathways l
The following secondary release paths were continuously monitored for radioactivity:
The Hot Machine Shop Exhaust (AH-35),
e Decontamination Shop Exhaust (AH-34),
The RAB H&V Equipment Room Ventilation system Exhaust (E-41 A and E-418); and The Switchgear/ Cable Vault Area Ventilation System (AH-25).
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Continuous sampling for these areas is maintained in order to demonstrate the operability of installed l
treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems.
l Sampling for these areas was limited to continuous particulate and iodine sampling and monthly noble gas grab sampling. The activity released via these secondary pathways resulted from routine operations and l
remained below significant levels.
l 8.6 Missed Effluent Samples:
l One liquid effluent sample was not collected within the requirements specified in the CDCM/TRM during j
this reporting period.
8.6.1 CWD-SGBDHX Sample The ODCM/TRM requires that the Circulating Water Discharge - Steam Generator Blowdown Heat Exchanger Discharge (CWD-SGBDHX) sample be collected weekly. On 12/26/97, the sample was l
obtained, yet the surveillance frequency of weekly + 25% was exceeded. The reason that the frequency was exceeded was due to personnel error. The technician that performed the previous weekly sample (collected at 12/17/97 09:22) incorrectly marked the task card which is used to schedule sampling for this task with 12/18/97 as the completion date. Subsequently, using the incorrect date to schedule the next weekly sample caused the required interval to be exceeded.
This incident is documented in condition report CR-98-0031. Corrective actions included:
A review of task cards used to schedule effluent sampling and analysis tasks, providing instructions to all Chemistry Technicians on the proper upkeep of task cards, and including ODCM/TRM effluent sample in a new computerized Chemistry Data Management software application used to schedule and document Chemistry sampling and analysis.
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Annu;l R dioactivs 1997 Efflu nt R:l::s3 Rrport Wat rford 3 St:am Electric Station 8.7 Major Changes to Radioactive Waste Systems During the reporting period, no Major Changes were made to any Radioactive Waste Systems.
8.8 Bi-Annual Land Use Census i
No Land Use Census was required in 1997. The latest Land Use Census performed in 1996 did not ide. y l
any new locations for effluent dose calculations.
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8.9 Gaseous Storage Tank Total Radioactivity Limit Technical Specification 3/4.11.2.6 specifies that the quantity of radioactivity contained in each gas storage tank be maintained less than or equal to 8.5E+04 Curies noble gas (considered as Xe-133 equivalent). At no time during the reporting period was this value exceeded.
8.10 Unprotected Outside Tank Total Radioactivity Limit i
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Technical Specification 3/4.11.1.4 specifies that the quantity of radioactive material contained in each unprotected outdoor tank be maintain less than or equal to 7.85E-04 Curies (excluding tritium and dissolved l
and entrained noble gases). During this reporting period, there was one instance in which this limit was l
exceeded. A discussion of the events leading to this condition is presented below.
8.10.1 Outside Temporary Tank Exceeded Limit l
On 5/21/97, a large radioactive liquid spill from the Spent Fuel Pool occurred. The plant was shut i
down and a refueling outage was in progress. During remediation of the spill, radioactive water was pumped from affected portion the site storm drain system to several temporary outside tanks brought on-site. These tanks are commonly referred to as " Baker Tanks" since they are usually leased from a supplier of the same name. On 5/23/97, while performing sampling of outside I
temporary storage tanks to meet the surveillance requirements of Technical Specification 4.11.2.6, l
W was discovered that Baker Tank #3059 contained 1.88E-03 Curies of radioactivity. The ACTION requirement was immediately entered and a Condition Report initiated. All additions of radioactive material to the tank were immediately suspended. Transfer of the contents of the tank to the in-plant Liquid Waste Management (LWM) System commenced on 5/23/97. The ACTION statement Page 27 of 49 l
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Annual Radioactive 1997 Effluent Rel: ass Report Waterford 3 Steam Electric Station requirements were completed on 5/24/97, after transferring the contents of the tank to the LWM system. Condition Report CR-97-1303 documents this event.
9.0 AdditionalInformation 9.1 Reactor Coolant System Average Energy (E-Bar)
The most recent Reactor Coolant System E-Bar calculation was 0.239 MeV/ Disintegration from a sample obtained on December 1,1997. Reactor Coolant System E-Bar is supplied for information l
only and is not used for effluent dose calculations.
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AnnualR dioictiva 1997 Effluint R:l: ass R: port Watsrford 3 St am El ctric Station 10.0 Tables Ta ble 1, B a tc h Rele as e S u m ma ry................................................................................................................... 3 0 Table 1 A, Annual Summation of All Releases By Quarter, All Airborne Effluents...................................... 31 Table 1B, Annual Airborne Continuous Elevated and Ground Level Releases, Totals for Each Nuclide Released...........................................................................................................................................................32 Table 1C, Annual Airborne Batch Elevated and Ground Level Releases, Totals for Each Nuclide Released
..........................................................33 Table 2A, Annual Summation of All Releases by Quarter, All Liquid Effluents.......................................... 34 Table 2B, Annual Liquid Continuot's and Batch Releases, Totals for Each Nuclide Released................. 35 Ta ble 3, Solid Waste Shlpped Offsite for B urial or Dis posal.................................................................. 36 Table 4, Joint Freq uency Distribution of Meteorological Data................................................................ 44 Table 5, Dose Calculation Results, Doses Due to Gaseous Radioactive Effluents...................
..... 48 Table 5, Dose Calculation Results, Doses Due to Liquid Radioactive Effluents...................................... 49 11.0 Attachments l 1.1. Copy of Process Control Program (PCP), Procedure RW-001-210, Revision 8 (9 sheets) 1.2, Copy of Offsite Dose Calculation Manual (ODCM) Procedure, UNT-005-014. Revision 5, Change 2 (311 sheets)
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- Annuil Radio ctive 1997 Efflu:nt Rsbise Report Watzrford 3 Steam Electric Station l
l Table 1 Batch Release Summary Batch Release Summary information for 1997 Report Period.
Report Catagory Batch Release Summary Release Point All Type of Release
- Batch liquid and Gaseous Period Start Time : 01-jan-1997 00:00:00 Period End Time
- 31-dec-1997 23:59:59 j
Liquid Releases i
Number of Releases 146 l
Total Time for All Releases :
39943.1 Minutes Maximum Time for a Release
+
373.0 Minutes Average Time for a Release 273.6 Minutes Minimum Time for a Release :
58.0 Minutes i
Average Stream riow 670306.1 GPM l
l Gaseous Releases Number of Releases 16 Total Time for All Releases :
2682.0 Minutes Maximum Time for a Release 600.0 Minutes Average Time for a Release 167.6 Minutes j
Minimum Time for a Release 3.0 Minutes j
s Batch Release Summary information for 1997 by Quarter.
Peport Catagory
- Batch Release Summary Release Point All
?
Type of Release Batch Liquid and Gaseous Period Start Time 01-jan-1997 00:00:00 Period End Time
- 31-dec-1997 23:59:59 Liquid Releases Otr 1 Otr 2 Otr 3 Otr 4 Number of Releases 27 69 31 19 Total Time for All Releases :
7519.0 18491.0 8789.8 5143.4 Minutes Maximum Time for a Release :
323.0 373.0 317.0 308.0 Minutes Average Time for a Release :
278.5 268.0 283.5 270.7 Minutes Minimum Time for a Release :
170.0 58.0 228.0 191.1 Minutes Average Stream riow 772785.0 528074.1 827516.8 763169.5 GPM 4
Gaseous Releases Otr 1 Otr 2 Otr 3 Otr 4 Number of Releases 5
4 2
5 Total Time for All Releases :
933.0 1135.0 446.0 168.0 Minutes Maximum Time for a delease :
350.0 600.0 266.0 150.0 Minutes Average Time for a Release 186.6 283.8 223.0 33.6 Minutes Minimum Time for a Release t
9.0 40.0 180.0 3.0 Minutes Page 30 of 49
Annual Radioactiva 1997 Efflurnt Rilus3 Report Waterford 3 St:am El:ctric Station
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l Table 1 A l
Annual Summation of All Releases by Quarter All Airborne Effluents Report Catagory Summation of All Releases Type of Activity : All Airborne Effluents j
Period Start Time 01-jan-1997 00:00:00 Period End Time 4 31-dec-1997 23:59:59 Est. Total Type of Effluent Units Qtr 1 Otr 2 Qtr 3 Otr 4 Error %
A.
Fission and Activation Cases i
- 1. Total Release Curies 8.72e+01 4.46e+02 4.20e+00 1.79e+01 1.50e+01 l
- 2. Average Release Rate for Period uC1/sec 1.12e+01 5.67e+01 5.29e-01 2.25e+00
- 3. Percent of Applicable Limit t
n/a n/a n/a n/a B. Radioj odine s
- 1. Total Iodine-131 Curies 0.00e+00 5.36e-04 6.17e-07 0.00e+00 1.50e+01
- 2. Average Release Rate for Period uCi/sec 0.00e+00 6.82e-05 7.76e-08 0.00e+00
- 3. Percent of Applicable Limit n/a n/a n/a n/a C.
Particulates
- 1. Particulates (Half-lives > 0 Days) Curies 2.01e-06 1.34e-05 3.43e-06 6.90e-06 1.50e+01
- 2. Average Release Rate for Period uCi/sec 2.58e-07 1.71e-06 4.31e-07 8.68e-07
- 3. Percent of Applicable Limit n/a n/a n/a n/a
- 1. Gross Alpha Radioactivity Curies 2.30e-06 5.82e-07 5.60e-07 4.30e-07 1.50e+01 i
D. Tritium
- 1. Total Release Curies 1.79e+01 2.05e+01 1.98e+01 1.39e+02 1.50e+01
- 2. Average Release Rate for Period uC1/sec 2.30e+00 2.61e+00 2.49e+00 1.75e+01
- 3. Percent of Applicable Limit n/a n/a n/a n/a l
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Annual Radioactive 1997 Effluent Rel ase Report Waterford 3 Steam El:ctric Station Table 18 Annual Airborne Continuous Elevated and Ground Level Releases Totals for Each Nuclide Released Report Catagory Airborne Continuous Elevated and Ground Level Releases.
Totals for Each Nuclide Released.
Type of Activity i Fission Gases, Iodines, and Particulates Period Start Time 01-jan-1997 00:00:00 Period End Time
- 31-dec-1997 23:59:59
)
Elevated Releases Ground Releases Nuclide Units Qtr 1 Qtr 2 Qtr 3 Otr 4 Otr 1 Qtr 2 Qtr 3 Qtr 4 l
Fission and Activation Gases Kr-85m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.70e-01 0.00e+00 0.00e+00 xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.15e+01 3.60e+02 3.99e-01 1.53e+01 xe-133m Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.34e+00 0.00e+00 0.00e+00 xe-135 Curies 0.00e+00 0.0a=+00 0.00e+00 0.00e+00 0.00e+00 1.90e+01 0.00e+00 0.00e+00 l
Total for Period Curies 0.00e+00 0.00e+00 0.0ue+00 0.00e+00 5.15e+01 3.83e+02 3.99e-01 1.53e+01 Radiolodines I-131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.36e-04 6.17e-07 0.00e+00 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.36e-04 6.17e-07 0.00e+00 Particulates l
H-3 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.75e+01 2.02e+01 1.97e+01 1.39e+02 l
Cr-51 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.24e-07 0.00e+00 0.00e+00 Co-58 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e-06 8.0Ee-07 5 77e-07 Co-60 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.24e-07 1.12e-06 3.97e-07 9.70e-07 Sn-113 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.09e-08 0.00e+00 Cs-134 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.02e-06 6.05e-07 1.31e-06 l
Cs-137 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.59e-06 2.10e-06 1.55e-06 4.04e-06 Os-191 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.29e-06 0.00e+00 0.00e+00 l
Gralpha Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.30e-06 5.82e-07 5.60e-07 4.30e-07 l
l Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.75e+01 2.02e+01 1.97e+01 1.39e+02 l
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Annu:1 R dio:ctiva 1997 Efflu:nt R lease R: port Watsrford 3 Steam Electric Station Table 1C i
Annual Airborne Batch Elevated and Ground Level Releases Totals for Each Nuclide Released Report Catagory
- Airborne Batch Elevated and Ground Level Releases.
Totals for Each Nuclide Released.
6 Type of Activity. Fission Gases, Iodines, and Particulates Period Start Time. 01-jan-1997 00:00:00 Period End Time 31-dec-1997 23:59:59 Elevated Releases Ground Releases Nuclide Units Qtr 1 Otr 2 Otr 3 Otr 4 Qtr 1 Qtr 2 Otr 3 Otr 4 Fission and Activation Gases Ar-41 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.21e-01 1.71e-01 4.26e-02 4.46e-02 Kr-85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.89e+00 3.24e-02 0.00e+00 Kr-85m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.72e-03 1.88e 0.00e+00 0.00e+00
'Xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.98e-01 1.29e+00 0.00e+00 6.10e-02 i
l Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e400 3.44e+01 5.95e+01 3 68e+00 2.52e+00.
Xe-133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.38e-01 2.32e-01 2.74e-02
- 1. 4 5e-02 l
Xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.42e-01 2.79e-01 2.24e-02 1.30e-02 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.58e+01 6.34e+01 3.80e+00 2.65e+00 l
Radiciodines None Particulates H-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.01e-01 3.34e-01 8.71e-02 1.04e-01 l
Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.01e-01 3.34e-01 8.71e-02 1.04e-01 i
i
)
l Page 33 of 49 i
r Annual Rrdioictiva 1997 Efflu nt Ral:ase R: port Watsrford 3 Steam El ctric Station i
Table 2A Annual Summation of All Releases by Quarter All Liquid Effluents l
Report Catagory 4 Summation of All Releases Type of Activity All Liquid Effluents i
l Period Start Time 01-jan-1997 00:00:00 l
Period End Time 31-oec-1997 23:59:59 Est. Total Type of Effluent Units Qtr 1 Otr 2 Ctr 3 Otr 4 Error %
A.
Fission and Activation Products l
- 1. Total Release (Not including l
Tritium, Gases, and Alpha Curies 2.96e-02 9.94e-01 3.07e-01 1.93e-02 1.50e+01
[
- 2. Average Diluted Concentration l
During Period uCi/sec 7.60e-11 3.79e-09 7.39e-10 5.05e-11
- 3. Percent of Applicable Limit t
n/a n/a n/a n/a B. Tritium
- 1. Total Release Curies 1.17e+02 1.81e+02 1.91e+01 2.03e+01 1.50e+01 l
l
- 2. Average Diluted Concentration During Period uCi/sec 3.08e-07 6.89e-07 4.59e-08 5.31e-08
- 3. Percent of Applicable Limit t
n/a n/a n/a n/a C. Dissolved and Entrained Gases
(
- 1. Total Release Curies 1.40e-01 1.11e+00 2.96e-04 3.74e-03 1.50e+01
- 2. Average Diluted Concentration During Period uC1/sec 3.69e-10 4.26e-09 7.14e-13 9.76e-12 i
- 3. Percent of Applicable Limit n/a n/a n/a n/a I
i l
D. Gross Alpha Radioactivity
- 1. Total Release Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.50e+01 l
l E. Waste Volume Released (Pre-Dilution) Liters 1.05e+07 1.10e+07 1.52e+07 1.06e+07 1.50e+01 F. Volume of Dilution Water Used Liters 3.79e+11 2.62e+11 4.15e+11 3.83e+11 1.50e+01 i
1 l
1 l
i l
h Page 34 of 49
Annual RIdiorctiva 1997 Efflu:nt Raltase Report Waterford 3 Steam Electric Station i
Table 28 Annual Liquid Continuous and Batch Releases Totals for Each Nuclide Released Liquid Continuous and Batch Releases.
Report Cat - Jory.
t
- Totals for Each Nuclide Released.
Type'of Activity All Radionuclides Period Start Time : 01-jan-1997 00:00:00 Period End Time
- 31-dec-1997 23:59:59 L.
Continuous. Releases Batch Releases I-Nuclide Units Otr 1 Otr 2 Otr 3 Otr 4 Otr 1 Qtr 2 Otr 3 Otr 4 l
l All Nuclides H-3 Curies 5.21e-02 2.65e-02 2.86e-02 7.73e-02 1.17e+02 1.81e+02 1.90e+01 2.02e+01 Na-24 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.35e-04 1.07e-05 0.00e+00 Cr-51 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.70e-02 7.79e-04 0.00e+00 Mn-54 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.04e-03 2.54e-03 4.04e-03 1.84e-04 i
l Fe-55 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.82e-03 4.34e-02 3.73e-02 1.04e-02 l
re-59 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.06e-05 3.55e-04 1.49e-05 0.00e+00 i
Co-57 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.97e-05 6.43e-04 6.40e-04 5.84e-06
'Co-58 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.58e-03 8.10e-01 2.41e-01 3.97e-03 Co-60 Curies 0.00e+00 0.00e+00.0.00e+00 0.00e+00 3.81e-03 1.70e-02 8.16e-03 1.40e-03 j'
Br-82 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.52e-05 0.00e+00 0.00e+00 F.r-8 5 Curles 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.36e-03 2.86e-02 0.00e+00 0.00e+00 i
Sr-92 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.40e-06 0.00e+00 7.15e-06 0.00e+00 I
Y-91m Curies 0.00e+00 0.00e+00 0.00e+00 2.17e-07 0.00e+00 0.00e+00 0.00e+C0 0.00e+00 Zr-95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.19e-04 5.72e-03 1.52e-03 3.07e-04 J
Nb-95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.66e-04 8.86e-03 2.74e-03 6.49e-04 Nb-97 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.90e-05 9.90e-05 0.00e+00 0.00e+00 Mo-99 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.12e-05 0.00e+00 0.00e+00 Te-99m Curies 0.00e+00 0.00e+00 0.00e+00 0 00e+00 0.00e+00 2.85e-05 0.00e+00 0.00e+0C Ag-110m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.88e-04 9.43e-04 1.41e-04 9.52e-04 Sn-113 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.47e-05 0.00e+00 5.23e-06 0.00e+00 Sb-122 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.27e-03 0.00e+00 0.00e+00 Sb-124 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.37e-04 7.24e-03 3.28e-04 0.00e+00 Sb-125 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.80e-03 5.63e-02 8.60e-03 1.22e-03 Sb-126 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.43e-04 0.00e+00 0.00e+00 Te-132 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.58e-04 0.00e+00 0.00e+00 I-131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.24e-04 1.88e-02 1.02e-04 3.00e-06
-I-132 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.60e-04 0.00e+00 0.00e+00 1-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.05e-06 5.62e-06 4.74e-06 0.00e+00 Xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.59e-03 2.79e-02 0.00e+00 4.31e-05 Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.25e-01 1.06e+00 2.96e-04 3.66e-03
.Xe-133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.06e-05 2.99e-03 0.00e+00 1.89e-05 Xe-135.
Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.92e-05 1.54e-04 0.00e+00 1.85e-05 Cs-134 Curies 0.00e+00 1.32e-06 0.00e+00 0.00e+00 1.57e-03 4.48e-04 6.60e-04 1.02e-04 l
Cs-136 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.01e-06 0.00e+00 0.00e+00 i
Cs-137 Curies 1.37e-06.4.83e-06 1 10e-05 3.82e-06 1.85e-03 3.40e-04 7.61e-04 8.15e-05 l:
La-140 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.09e-06 9.18e-04 2.15e-05 0.00e+00 Ce-144 Curies 0.00e+00 0.00e+00 0 00e+00 0.00e400 0.00e+00 0.00e+00 0.00e+00 3.79e-05 W-187 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.31e-06 0.00e+00 Total for Period Curies 5.21e-02 2.65e-02 2.86e-02 7.73e-02 1.17e+02 1.83e+02 1.93e+01 2.02e+0)
L l
il.
i 1
l 1
Page 35 of 49 i
L..
...s..
I Annual Radioictiva 1997 Efflu nt Rst: ass Rtport Waterford 3 Stram Electric Station j
Table 3 Solid Waste Shipped Offsite for Burial or Disposal Individual Shipments n Weste.Typei. Source,M
.10CFR61; iType of M
! Contained ETotal Activityi WesteVolume!(
Q,
- Errorf
,:[
p p
y['h,
(7 'h[
.[.[
'A' I
m (B)
A-U 8x8x20 ft 1040 each, 58.9 1.42E-014 125%
Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SEG Corp for Volume Reduction.
(B)
A-U 8x8x20 ft 1040 each, 58.9 8.84E-02 4 125 %
Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SJG Corp for Volume Reduction.
(B)
A-U 8x8x20 ft 1040 each, 58.9 8.86E-02 4 125%
l.
Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SEG Corp for Volume Reduction.
(B)
A-U 8x8x20 ft 1040 each, 58.9 2.66E-01 a 125%
l Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SEG Corp for Volume Reduction.
(B)
A-U 8x8x20 ft 1040 each, 58.9 1.35E-01 A 125%
Non-Compacted Dry STP 2080 Total l
Activity Waste Shipped to SEG Corp for Volume Reduction.
A Activity determined by estimations
- Activity determined by measurements Page 36 of 49 j
l Annu:1 Radioactiva 1997 Efflu:nt R Isisa Report Watsrford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Individual Shipments (cont.)
.3Weste Type, Source 4 ', -
10CFR6C 0'; Type ofi
-! Container We,ste Volume O otal Activity?
) Errori T
rauyt, Pmeessingy Wests l
!;. Container}
Volume -(Pt')?
, E(M*)f m
2 3.
..<..q"..
u.
p l
f(Curies)1 4
Gw n ".a
.in,^-
' ~ :o 1 '
'~
'4 e*
w l
- jz
.(, 7
'J'
{ef &
~,
$$~1
,n g
n 8
(A)
B EL-190 174.3 4.936 2.26E+02 +
25%
Resin Waste Management Poly-HIC Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A)
A-U EL-210 202.1 5.723 1.09E+01 +
25%
Liquid Waste Management Poly-HIC l
Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A)
A-U EL-210 202.1 5.723 2.49E-01 e 25%
Liquid Waste Management Poly-HIC j
Resin Dewatered in a High integrity Container (Bead Resin) Shipped for I
Burial.
l 4 Activity determined by estimations j
e Activity determined by measurements l
Page 37 of 49
Annu 1 Radioactiva 1997 Efflu nt Rel:ase Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal
SUMMARY
BY MAJOR WASTE TYPES (A)
Spend resins, Filter Sludges, Evaporator Bottoms, etc.
(B)
Dry Compressit'!e Waste, Contaminated Equipment, etc.
(C)
Irradiated Components, Control Rods, etc.
(D)
Other.
w i
.. Waste Type - b Waste Volume (M') -
Total Activity'(Cl)'
- Error (A) 16.4 2.37E+02 25%
(S) 294.5 7.20E-01 125%
(C) 0.00 0.00E+00 125%
(D) 0.00 0.00E+00 i25%
i Page 38 of 49 l
Annuil Radioactivo 1997 Efflurnt R l:ase R: port Waterford 3 Steam El:ctric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal
SUMMARY
BY MAJOR WASTE TYPES (Cont'd)
Radionuclides by Major Waste Type 1
l j v.
i ype..
- nuwiv ri ui.
yunes e acuriu. w W
Co-58 1.73E+02 72.91 Ni-63 1.87E+01 7.88 Fe-55 1.73E+01 7.29 Co-60 6.81E+00 2.87 Cs-137 5.97E+00 2.52 Cs-134 4.99E+00 2.10 l
~
Mn-54 4.86E+00 2.05 Sb-125 2.78E+00 1.17 Co-57 1.30E+00 0.55 Ag-110m 3.56E-01 0.15 Sb-124 2.11E-01 0.09 Fe-59 1.70E-01 0.07 H-3 1.70E-01 0.07 Ni-59 1.66E-01 0.07 l
Sn-113 1.64E-01 0.07 Zn45 8.37E-02 0.04 Nb-95 7.51 E-02 0.03 l
l-131 6.23E-02 0.03 Zr-95 3.78E-02 0.02 C-14 2.98E-02 0.01 St-90 2.40E-02 0.01 Ce-144 1.93E-02 0.01 Cr-51 1.16E-03 0.00 Ba/LA-140 3.28E-04 0.00 Cm-243/244 1.01 E-04 0.00 Am-241 3.19E-05 0.00 Cm-242 1.36E-05 0.00 iotal 2.37E+02 l
l l
{
i i
Page 39 of 49
Annu:1 Radio ctiva 1997 Efflu:nt Releass Report Watsrford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal
SUMMARY
BY MAJOR WASTE TYPES (Cont'd)
Radionuclides by Major Waste Type vvaste type -
mucnoe name,
,vunes To Aounaance.
tW Co-58 2.85E-01 39.61
{
Fe-55 1.63E-01 22.65 Ni-63 7.29E-02 10.13 Co-60 6.01 E-02 8.35 i
Cs-137 4.33E-02 6.02
)
Cs-134 3.43E-02 4.77 l
H-3 2.56E-02 3.56 Mn-54 1.98E-02 2.75 C-14 1.47E-02 2.04 Ni-59 6.50E-04 0.09 Sr-90 1.92E-04 0.03 iotai 7.20E-01 l
l I
l l
l Page 40 of 49
Annu 1R dioictiva 1997 Efflu:nt R:leiss R: port Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal
SUMMARY
BY MAJOR WASTE TYPES (Cont'd)
Radionuclides by Major Waste Type v:yvensw Iype.
NUwww swu s..
- UUnes,
,7o ADun05nCO.
(U)
N/A U.UUt+UU U.UUU i0181 U.UUt+UU Page 41 of 49
Annual Radioactiva 1997 Effluent R ls:se Report Waterford 3 Stram Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal
SUMMARY
BY MAJOR WASTE TYPES (Cont'd) l l
Radionuclides by Major Waste Type l
, Freeta 1 ype c
, NUwww Name,
,lyUDUs;<-p
. 7o ADunoance.,
j (U)
N/A U.UUt:+UU V.UUU iUiAL U.UUc+UU l
l l
l l
\\
l Page 42 of 49
Annual R:dioictivo 1997 Efflurnt Ral:2se R:pon Wat:rford 3 Stram Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Solid Waste Disposition NM 0F SHIPRAENTSie RADDE OF TRANSPORTATIONi 4f l
DESTINATION }
3 Truck Barnwell, SC 5
Truck Oak Ridge, TN Irradiated Fuel Shipments (Disposition)
- f
- NUSABER OF SHIPIAENTS.
- AAODE OF TRANSPORTATION 6S4fDESTINATlON NONE N/A N/A Page 43 of 49
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Annuil Radio:ctiva 1997 Efflu:nt Release Report Waterford 3 Steam Electric Station Table 5 Dose Calculation Results Doses Due to Gaseous Radioactive Effluents Doses due to Noble Gases (mrad or mrom)
Age Group e AH l
Organ otr 1 Otr 2 Otr 3 Qtr 4 Year Total Total-body 1.4524e-02 8.1688e-02 8.2386e-04 2.8666e-03 9.9902e-02 Skin 3.3189e-02 1.9220e-01 1.8024e-03 6.6066e-03 2.3380e-01 Air Beta 4.7074e-02 2.5335e-01 2.3242e-03 9.6000e-03 3.1235e-01 Air Gamma 1.7210e-02 9.5551e-02 9.5821e-04 3.4120e-03 1.1713e-01 Doses due to Radiolodines/Particulates/ Tritium (mrom)
Age Group t Adult organ Otr 1 Otr 2 Qtr 3 Otr 4 Year Total Bone 2.8838e-05 1 8659e-04 3.4389e-05 8.5372e-05 3.3519e-04 Liver 1.7554e-02 2.0336e-02 1.9369e-02 1.3575e-01 1.9301e-01 Total-body 1.7548e-02 2.0249e-02 1.9362e-02 1.3573e-01 1.9289e-01 Thyroid 1.7536e-02 7.8603e-02 1.9410e-02 1.3569e-01 2.5123e-01 Kidney 1.7542e-02 2.0437e-02 1.9352e-02 1.3571e-01 1.9304e-01 Lung 1.7538e-02 2.0125e-02 1.9346e-02 1.3569e-01 1.9270e-01 Gi-111 1.7537e-02 2.0169e-02 1.9344e-02 1.3569e-01 1.9274e-01 Skin 1,8120e-05 4.4574e-05 2.0411e-05 5.0542P-05 1.3365e-04 l
Age Group Teen l
Organ Qtr 1 Otr 2 Otr 3 Otr 4 Year Total l
Bone 3.8266e-05 2.8096e-04 4.6085e-05 1.1460e-04 4.7991e-04 Liver.
1.9900e-02 2.3141e-02 2.1961e-02 1.5386e-01 2.1886e-01 Total-body 1 9880e-02 2.2971e-02 2.1934e-02 1.5379e-01 2.1858e-01 Thyroid 1.9869e-02 1.0558e-01 2.2012e-02 1.5375e-01 3.0122e-01 Kidney 1.9880e-02 2.3302e-02 2.1932e-02 1.5379e-01 2.1890e-01 Lung 1.9874e-02 2.2804e-02 2.1923e-02 1.5377e-01 2.1837e-01 Gi-111 1.9871e-02 2.2853e-02 2.1918e-02 1.5376e-01 2.1840e-01 l
Skin 1.8120e-05 4.4574e-05 2.0411e-05 5.0542e-05 1.3365e-04 l
l Age Group Child Organ Otr 1 Otr 2 Otr 3 Otr 4 Year Total Bone 6.9556e-05 6.0584e-04 8.4874e-05 2.1154e-04 9.7181e-04 Liver 2.7486e-02 3.2047e-02 3.0335e-02 2.1250e-01 3.0237e-01 Total-body 2.7442e-02 3.1753e-02 3.0274e-02 2.1235e-01 3.0182e-01 l
Thyroid 2.7434e-02 1.8872e-01 3.0442e-02 2.1232e-01 4.5892e-01 Kidney 2.7451e-02 3.2278e-02 3.0285e-02 2.1238e-01 3.0240e-01 Lung 2.7441e-02 3.1478e-02 3.0270e-02 2.1235e-01 3.0153e-01 Gi-111 2.7435e-02 3.1508e-02 3.0262e-02 2.1232e-01 3.0153e-01 Skin 1.8120e-05 4.4574e-05 2.0411e-05 5.0542e-05 1.3365e-04 Age Group Infant Organ Qtr 1 Otr 2 Otr 3 Otr 4 Year Total Bone 6.4921e-05 1.0084e-03 8.0003e-05 1.9796e-04 1.3513e-03 Liver 1.2464e 1.5397e-02 1.3767e-02 9.6172e-02 1.3780e-01 Total-body 1.2410e-02 1.4706e-02 1.3691e-02 9.5987e-02 1.3679e-01 Thyroid 1.2406e-02 3.5610e-01 1.4078e-02 9.5971e-02 4.7855e-01 Kidney 1.2421e-02 1.5485e-02 1.3707e-02 9.6024e-02 1 3764e-01 Lung 1.2413e-02 1.4253e-02 1.7694e-02 9.5994e-02 1.3635e-01 G1-111 1.2406e-02 1.4277e-02 1.3685e-02 9.5972e-02 1.3634e-01 Skin 1.8120e-05 4.4574e-05 2.0411e-05 5.0542e-05 1.3365e-04 Page 48 of 49 I
l Annu:1 Radio:ctiva 1997 Efflurnt R:l; ass R: port Wat:rford 3 Steam El ctric Station Table S Dose Calculation Results j
Doses Due to Liquid Radioactive Effluents j
l 1
l Age Group Adult Organ Otr 1 Otr 2 Otr 3 Otr 4 Year Total Bone 1.3512e-02 7.1713e-02 5.6295e-02 1.9010e-02 1.6053e-01 Liver 2.5882e-02 1.2772e-01 8.1373e-02 3.2650e-02 2.6713e-01 Total-body 1.9597e-02 9.5298e-02 5.4952e-02 2.3687e-02 1.9353e-01 Thyroid 4.6954e-03 1.5772e-02 3.1823e-03 6.4982e-03 3.0148e-02 F.idney 1.1742e-02 4.3950e-02 2.9569e-02 1.5357e-02 1.0062e-01 Lung 7.0071e-03 1.6691e-02 1.1975e-02 9.4572e-03 4.5130e-02 Gi-111 5.3794e-03 2.4953e-02 8.7584e-03 7.1682e-03 4.6259e-02 I
1 l
l l
Page 49 of 49
Annual Rrdioactiv3 1997 Efflu:nt R:leasa R: port Wat rford 3 St::m El:ctric Station Attachments s
ATTACHMENT 11.1 Copy of PROCESS CONTROL PROGRAM (PCP)
PROCEDURE RW-001-210 Revision 8 (9 sheets)
_ _ _ _ _ _ _ _ _