ML20082L862
| ML20082L862 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/30/1991 |
| From: | William Cahill, Kay D, Wood A TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-91311, NUDOCS 9109040420 | |
| Download: ML20082L862 (45) | |
Text
_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _
""""" 9 Log # TXX 91311
{-
~~.
File # 911 (clo) 10010 TUELECTRIC 10160 (clo) 953 (clo) 954 (clo)
Ref. # 10CFR50 30a(a)(2)
M illiarm 3. Cahill, Jr.
Lucurns Vue hnUnnt August 29, 1991 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. D.C. 20555
SUBJECT:
C0 HANCE PEAK STEAM ELECTRIC STATION (CPSES)- UNIT 1 DOCKET NO. 50 445 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASL REPORT Gentlemen:
In rccordance with Section 6.9.1.4 of the CPSES Unit 1 Technical Specifications (Appendix A to License No. NPF 87) and the CPSES Offsite Dose Calculation Manual (ODCH), enclosed is the Semiannual Radioactive Ef flent Release Report which covers the six month reporting period from January 1, 1991 through June 30, 1991.
The tabular summaries of radioacive liquid and gaseous releases are provided in the format defined in Appendix D of Regulatory Guide 1.21, Rev. 1, dated June, 1974 During this six month reporting period there were no changes to the CPSES ODCH.
Sincerely, u d h ,,, 2 s k N b William J. Cahill, Jr.
/
By: _ k ,_ _
U Roget . Walter tionager of tioclear Licensing CLW/clw Enclosure c - Mr. R. D. Martin. Region IV Hr. T.A. Bergman. NRP,(clo) 2 Resident inspectors, CPSES (2) (clo) fa109040420 ^ =cx osom 910630 us . x. .. s.,.., uoi n
PDR n.i1.a... ,m,
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Enclosure to TXX-91311
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tulle (:1RIC comanche Peak Steam Electric Station Unit 1 Semiannual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 Prepared By: _fstnerpD?/0rr/ Date: 8/ 6ffl A.R. Woo,d, Summer Ertf3 1ncer Reviewed By: MMb1 'l Zz P Date: 8 '7 't I D.C. Senior Eligineer
/ ,)
Approved By:
Kay]C['Jkd] [r' n r.no .
Date: ? 71/
R.J. Prince, Radiation Protection Panager l
en su,, um own ame Tem wuuae
TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the Process control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 New Locations for Dose Calculations or Environmental Monitoring 6.5 Liquid Holdup and Gas Storage Tanks 6.6 Tritium Discharged Due to Turbine Generator Primary Water Cooling System Leakage 6.7 Noncompliance with Radiological Effluent Control Requirements 6.8 Batch Releases to the Evaporation Pond
l TABLE OF CONTENTS (CONTINUED) 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary 7.2 Abnormal Batch Liquid and Gasenus Release Summary 7.3 Gaseous Effluents--Summation of All Releases 7.4 Gaseous Effluents--Ground Level Releases 7.5 Liquid Effluents--Summation of All Releases 7.6 Liquid Effluents 7.7 Solid Waste and Irradiated Fuel Shipments 11 l l
l ACRONYMS AND ADDREVIATIOND CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station LHMT Laundry Holdup and Monitor Tanks MPC Maximum Permissible Concentration ODCM Offsite Dose Calculation Manual PCP Process Control Program REC Radiological Effluent Control TGPWCS Turbine Generator Primary Water Cooling System WWHT Waste Water Holdup Tank WMT Waste Monitor Tanks lii
CPSES Unit 1 Semiannual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991
1.0 INTRODUCTION
This semiannual Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station Unit 1, is submitted as required by Technical Specification 6.9.1.4 and Offsite Dose Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 1991 through June 30, 1991.
The information contained in this report includes:
(1) A summary of the quantities of radioactive liquid and gaseous effluents released from Unit 1 during the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June, 1974.
(2) A summary of solid waste shipped from Unit 1 in the format shown in Appendix B of Regulatory Guide 1.21, Revision 1, June, 1974, supplemented with three additional categories:
class _of waste (per 10CFR61), type of container (LSA, Type A, Type B, Large Quantity), and solidification agent or absorbent.
(3) A list and description of abnormal releases of radioactive material from the site to unrestricted areas.
(4) A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use census.
(5) An explanatien of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.
(6) A description of the events leading to liquid holdup tanks or gas storage tanks exceeding Technical Specification limits.
(7) Changes made to the ODCM during the reporting period.
(8) The total amount of tritium discharged due to Turbine Generator Primary Water Cooling System (TGPWCS) leakage as required by ODCM Supplemental Guidance Number 3.
1
l CFSES Unit 1 Semiannual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 I
2.O MJEEliKNIAk_INFORMAILQ1{
2.1 Recul a t_qry Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
2.1.1 Fission and Activation Gases (Noble cases)
The dose rate due to radioactive materials released in gaseous effluents from the site boundary shall be limited to less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
a) During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b) During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.2 Iodine-131, Iodine-133. Tritium and Radioactive Material in Particulate Form.
The dose rate due to Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half lives greater than 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 1500 mrem /yr to any organ.
The dose to a member of the public from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
a) During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and b) During any calendar year: Less than or equal to 15 mrems to any organ.
1 2
CPSES Unit 1 i S:miennual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 l I
1 2.1.3 Liauld Effluents t i
The concentration of radioactive material released in i liquid effluents to unrestricted areas shall be limited [
to the concentrations specified in 10CFR Part 20, ;
Appendix B, Tablo II, Column 2 for radionuclides other l than dissolved or entrained noble gases. For dissolved '
or entrained noble gases, the total concentration shall i be limited to P.0E-04 #Ci/ml.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall ;
be limited:-
l a) During any calendar quarter to less than or f
equal to 1.5 mr3ms to the whole body and to :
less than 5 mroms to any organ, and I r
b) During any calendar year to less than or !
equal to 3 mroms to the whole body and to l less than or equal to 10 mroms to any organ.
[
2.1.4 Evaooration Pond i The quantity of radioactive material contained its the [
evaporation pond shall be limited by the following !
expression: ;
i l 264/V
- Z Aj/CJ < i.0 ,
b I
where*
- AJ= pond inventory limit for a single radionuclide j b l (Curies). ;
CJ= 10CFR20, Appendix D, Table II, Column 2, l
, concentration for a single radionuclide j '
i (pC1/cc), !
l V = design volume of liquid and slurry in the pond i (gallons), and '
264 = conversion unit (pCi/Ci per ml/ gal) i e
2.1.5 12_tal Dose ,
The annual (calendar year) dose or dose commitment to !
any member.of the public due to releases of l radioactivity and to radiation from uranium fuel cycle !
I sources shall be limited to less than or equal to 25 ;
mrems to the whole body or to any organ, except the ;
l 3
L I L :
CPSES Unit 1 Semiannual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 thyroid, which shall be limited to less than or equal to 75 mrnms.
2.2 Maximum Permissible Cnncontrationn 2.2.1 giqcous EffluqatE For gaseous effluents, maximum permissible concentration (MPC) values are not directly used in release rate calculations since the applicabic limits are expressed in terms of dose rate at the site boundary. The dose rate limits are given in Sections 2.1.1 and 2.1.2.
2.2.2 Liauid EU ly_qnts The values specified in 10CTR Part 20, Appendix B, Table II, Column 2 are used as the maximum permissible concentrations of liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 pC4/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
2.3 byerage Enercy This section is not applicable to the Radiological Effluent Controls of Part I of the ODCM for Comanche Peak, Unit 1.
2.4 licasureIp_ents and Annroximations of Total Radinanti.ylty Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tabic 4.11-1 and 4.11-2, respectively, of the CPSES ODCM.
2.4.1 Liauld Radioactive Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite sampics were analyzed monthly and quarterly for the Waste Monitor Tanks, Laundry Holdup and Monitor Tanks, and Wantewater Holdup Tanks.
Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the on-site laboratory using liquid scintillation and gas flow proportional counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90, and Fe-55 by a contract laboratory (Teledyne Isotopes). The results of the composite sampic analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in ,
l 4
1 - , , , . . . ,
CPSES Unit 1 Semiannual Ra.dioactive Effluent Release Report January 1, 1991 - June 30, 1991 l
liquid effluent relt ..es was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.
For releases of tritium via the TGPWCS, samples were analyzed for tritium, using liquid scintillation counting techniques. Leakage of tritium from the system was also tracked by comparing system tritium inventory at the beginning of the month to the end of the month.
For batch releases of powdex resin to the Evaporation Pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly for Sr-89 and Sr-90 by an offsite laboratory (Teledyne Isotopes).
2.4.2 Gaseous Radioactive E111ggntn Each gaseous batch was sampled and analyzed for radioactivity prior to release. For releases from Waste Gas Storage Tanks, noble gas grab samples were analyzed for gamma emitting radionuclids using gamma spectroscopy. For releases from the Containment Building, samples were taken using charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release with the exception of Containment vents made as a precursor to a containment purgo. In these cases, samples collected and analyzed as a prerequisite to the vent were used to estimate total radioactivity released during subsequent purge. The results of the analyses and the total volume of effluent released were used to determine the total amount of radioactivity released in the batch mode.
For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways were continuously sampled using radiciodine adsorbers and particulate filters. The filters were analyzed weekly for I-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radiciodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross alpha activity, in the 5
CPSES Unit 1 ;
S:miennual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 t
on-site laboratory using the gas flow proportional :
counting techniquo. Quarterly compositos of particulate filters were analyzed for Sr-89 and Sr-90 by an off- >
site laboratory (Tolodyno Isotopes). !
l 2.5 Ratch Releases A summary of information for gaseous and liquid batch [
releases is included in Table 7.1. !
2.6 Abnormal Relongga l Abnormal releases are defined as unplanned or uncontrolled releases of radioactive material from the sito boundary. ;
There was one abnormal liquid offluent releaso mado during l the period covered by this report. This event is discussed j in Section 6.7.2 of this report. ;
A summary of information for gaseous and liquid abnormal f releases is included in Table 7.2. '
i 3.0 9AGEQVp EFFLUXHIR The quantitles of radioactive material released in gaseous affluents are summarized in Tables 7.3 and 7.4. All releases of .
radioactive material in gaseous form are considered to be ground i level releases. t A total release of 4.60E-05 Curies of alpha emitting radioactive material in gaseous offluents is reported. This material is assumed to be radon daughter products since the filters used to collect samples were not allowed sufficient time to decay. Thus the analysis could not distinguish between the relatively short ,
lived radon progeny and the long lived alpha emitting nuclidos ;
found in irradiated nuclear fuel. In March, 1991, the procedure ;
for performing composito gross alpha analysis was revised to !
allow for decay of radon daughters prior to analysis. :
Subsequently, no gross alpha was measured. A composite gross ;
alpha activity was reported for the second quarter duo to the use i of the composite value from March as an estimate for the month of r April.
[
4.0 1,1 QUID _EFFLUEliTA The quantities of radioactive matorial rolcased in liquid effluents are summarized in Tables 7.5 and 7.6.
- 5. 0 - BOLID WABTER The quantities of radioactive material released as solid ,
effluents are summarized in Table 7.7.
6
CPSES Unit. 1 Semiannual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 6.0 RELhTED INFORMATION 6.1 Operability .of Liqujd and Gaseous Monitorina Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require an explanation of why designated inoperable liquid and gaseous monitoring instrumentation were not restored to operable status within thirty days. During the period covered by this report, there were no instances where this instrumentation was inoperable for more than thirty days.
6.2 Chances to the Process Control Procram There were no changes to the Process Control Program for the period covered by this report.
6.3 Chances to the O U Dite Dose Calc.ul,ation Manu_al There were no changes to the Offsite Dose Calculation Manual for the period covered by this report.
6.4 New Locatigns for Dose Calculations or Envirpunental Monitpr1DS ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations or environmental monitorjng, identified by the Land Use Census, to be included in the Semiannual Radioactive Effluent Release Report. No such locations were identified during this report period.
6.5 Liauld Holdun and Gas Storace Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to a liquid holdup or gas storage tank exceeding the Technical Specification limits. Technical Specification 3.11.1 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten Curies, excluding tritium and dissolved or entrained noble gases. Technical Specification 3.11.2.2 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 Curies of noble gases (considered as Xe-133 equivalent).
These limits were not exceeded during the period covered by '
this report.
5.6 Iritium Qischar.ged Due to Turbine Generator Primary Water Coolina System Leakane ODCM Supplemental Guidance Number 3 requires the total amount of tritium A.ischarged due to TGPWCS leakage to be reported in the Semiannual Radioactive Effluent Report. This activity is determined as described in section 2.4.1. The 7
.- -- .- . - ._ . = _ . - _ - - . - - - . - _ . _ _ _ . _ - _ - . -
i l
CPSES Uni't1 l S:miennual Radioactive Effluent Release Report January 1, 1991 - June 30, 1991 l 1
total amount of tritium discharged due to TGPWCS leakage was !
5.42E-01 Curies. This is in addition to the values reported [
in Tables 7.3 through 7.7. !
6.7 Noncomollance with Radioloaical Effluent Control Recuirements This section provides a listing of events that did not comply with the applicable requirements of the Radiological !
Efflu6nt Controls given in Part I of the CPSES ODCM. !
Detdiled documentation concerning evaluations of these i-events and corrective actions is maintained on site. 1 6.7.1 Use qf Nonconservative Setnoint !
During the Unit 1 Midcycle Outage, depressurization of '
the reactor coolant system required venting of the Pressurizer Relief Tank (PRT). To establish positive ,
controls over the venting evolution, the release was ,
treated as a batch gaseous release. The PRT discharge l was routed through the Auxiliary Building Vent via the !
Waste Gas Processing System discharge line so that a setpoint could Le established for the Auxiliary !'
Building Vent Duct Monitor. In the event of a high alarm on this monitor, the release would be !
automatically terminated by closure of the Waste Gas l Processing System discharge valve. During the post [
release review of the release data, it was discovered l that an error was made in the setpoint calculations, ;
-resulting in the use of a nonconservative setpoint. The
- error resulted from use of a nonconservative input into ;
setpoint calculation.
)
I The requirements for gaseous radioactive effluent monitoring instrumentation given in ODCM Radiological Effluent Control 3/4.3.3.5 were reviewed for l applicability to the PRT venting evolution. Item 1.a of I ODCM Table 3.3-8 establishes the monitoring requirements for-releases from the Waste Gas Holdup System (e.g., Gas Decay Tanks). The applicanility for this monitoring requirement is during batch radioactive !
releases via this pathway. Although the PRT venting ;
evolution is not a batch release from the waste gas '
holdup system, the monitoring requirements of Table i 3.3-8, Item 1.a were administratively imposed as a '
conservative approach to establish more positive .
controls over the effluent release. Because the i requirements of Table 3.3-8, Item 1.a were followed to i establish a setpoint for the Auxiliary Building Vent l Monitor (X-RE-5701), the use of the non-conservative setpoint did not comply with the requirements of Radiological Effluent Control 3.3.3.5. "
l 8
o :
CPSES Unit 1
- Semiannual Radioactive Effluent Release Report January 1. 1991 - June 30, 1991 l
Action (a) of Control 3.3.3.5 requires that with a radioactive gaseous offluent monitoring instrume-tation setpoint less conservative than required by Control 3.3.3.5, the release of the effluents monitored by the affected channel should be immediately suspended, or the channel declared inoperable, or the setpoint changed so that it is acceptably conservative. Upon completion of the release, the alarm setpoint was returned to the normal data base values. Trond data for the Auxiliary Building Vent Monitor shows that a significant radiological release did not occur during the period when the setpoint was adjusted to a non-conservative value. The concentration at the monitor did not exceed the proper alarm setpoint value corresponding to the limits of Control 3.11.2.1.
As a result of this event, procedural requirements for performing pre-release calculations and establishing monitor setpoints for routine releases were reviewed to see if a similar problem existed. It was determined that, for gaseous releases, appropriate precautions were not included to assure that non-conservative inputs were not used in setpoint calculations. However, procedures did allow for the use of conservative, pre-estsblished setpoints in lieu of the setpoint calculated based on actual release data. Review of all previous batch gaseous release permits revealed that the conservative, default setpoints had been used '-
all cases.
As an immediate response to this problem, a training session was conducted to review the event and to review ODCM setpoint calculational methodologies to emphasize those parameters which affect alarm setpoints and what changes in those parameters can result in non-conservative setpoints. To prevent a recurrence of the use of non-conservative setpoints, the following actions were also taken: a) procedures were revised to require use of maximum design stack flow rates for all pre-release calculations; and b) procedures were revised to include precautions specifically aimed at verifying data used in pre-release calculations to identify changes in any parameters which would cause pre-release calculations to become non-conservative.
6.7.2 Liauid Waste Discharg.e without Samnlina/ Analysis A waste discharge tank (Laundry Holdup Monitor Tank-02) was released to Squaw Creek Reservoir without prior sampling and analysis as required by ODCM Radiclogical Effluent Control 3/4.11.1.1, Table 4.11-1, " Radioactive Liquid Waste Sampling and Analysis Program." The event 9
t CPSES Uni't 1 f Saniennual Radioactive Effluent Aelease Report January 1, 1991 - June 30, 1991 !
i L
resulted from the inadvertent marking of the incorrect I source tank on the Batch Liquid Radioactive Effluent l Release Permit. The error was not detected in ;
subsequent reviews of the release permit by chemistry, j Radiation Protection, and Operations due to poor self- i checking and inadequate ~ommunications. The ev(nt was i discovered after the Lau ry Holdup Monitor Tank-02 !
(LHMT-02) release had beers completed. The analyris fram the LHMT-02 heel volume was used for nuclide I concentration and distribution of the LHMT. Results of {
this analysis indicated that the release was (
substantially below 10CFR50 Appendix I limits.
l' Upon discovery, the event was documented in accordance with site procedures and radwaste processing procedures i were revised to restrict the number of tanks allowed to be in recirculation or discharged simultaneously to :
one. The final evaluation of the event, to determine !
Its root cause and additional corrective actions, has ;
not yet been completed. [,
6.8 Batch Releases to the Evaporatisn Pond .
t A total of 2.20E+03 ft 3 of resin was transferred to the !
Evaporation Pond in 17 batch releases during the period '
covered by this report. The results of the sample analyses indicate no radioactive material was transferred to the "
Evaporation Pond. i 7.0 TARLRs !
i 7.1 Batch Liquid and Gaseous Release Summary f 7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents--Summation of All Releases I 7.4 Gaseous Effluents--Ground Level Releases l
7.5 Liquid Effluents--Summation of All Releases [
\
7.6 Liquid Effluents ;
7.7 Solid Waste and Irradiated Fuel Shipments ;
l f
l t
?
i 10 )
t b
i
' [
Table 7.1 ;
DATCH LIOUID AND GASEOUS RELEASE SUMMM Y Quarter 1 Quarter 2 A. Liquid Releases All Sources j Number of Batch Releases 1.21E+02 1.85E+02 !
Total Time Period For Batch Releases (Min) 6.95E+03 1.10E+04 Maximum Time Period For A Batch Release (Min) 8.40E+01 1.87E+02 Average Time Period For A Batch Release (Min) 5.70E+01 5.90E+01 !
i l
Minimum Time Period For A Batch Release (Min) 4.00E+00 3.10E+01 ow During Periods of l AverageStreamFg/s)
Release (Ft N/A N/A ;
i
-1 i B.- Gaseous Releases All Sources '
l Number of Batch Releases 1.80E+01 7.00E+00 l f Total rime Period For Batch Releases (Min) 5.61E+03 2.07E+03 I i
I Maximum Time Period For A Batch Release (Min) 1.44E+03 3.59E+02 i Average Time Period For A Batch Release (Min) 3.12E+02 2.96E+02 :
1 Minimum Time Period For A Batch Release (Min) 2.00E+00 1.86E+02 I
t Table 7.2 !
ADHQRMAL BATCH LIQUID AND GASEOUS RELElS_E_S_QMMARY t
I A. Liquids i
! Number of Releases 0.00E+00 1.00E+00 >
L !
Total Activity Released (C1) 0.00E+00 8.10E-01 [
L B. Gases E l Number of Releases 0.00E+00 0.00E+00 I Total Activity Released (Ci) 0.00Et00 0.00E+00 l i
l
{
. - - , - , . ~ . ~ . . ---..,,-..,,-n , , , - - - - ,
T&ble 7.3 GPRSOUS EFFLUENTS--SUMMATION OF ALL RELEASER Units Quarter Quarter Est. Total 1 2 Error %
A. Fiselon a:ad Activation Gases
- 1. Total release Ci 3.79E+03 1.39E+03 2.00E+01
- 2. Average release rate for period pCi/sec 4.88E+02 1.77E+02
-(Total Body)
B. Iodines
- 1. Total iodine-131 Ci 0.00E+00 0.00E+00 Note 1
- 2. Average relcase rate for period 4Ci/sec 0.00E+00 0.00E+00
1.Particulates with half lives Ci 0.00E+00 0.00E+00 Note 1
> 8 days
- 2. Average release rate for period pCi/sec 0.00E+00 0.00E+00 l
I (Organ)
- 4. Gross alpha radioactivity Ci 4.19E-05 4.13E-06 Note 2 l-D. Tritium
- 1. Total release Ci 9.13E-01 7.59E-01 2.28E+01
- 2. Average release rate for period pCi/sec 1.1/E-01 9.66E-02
Note 1. No iodine or particulate activity is reported f or gaseous ef fluents, therefore errors f or these values are not ,
re yrted.
[
Note 2. The gross alpha radioactivity reported is assumed to be redon daughters, as discussed in section 2.4.2. ,
. _ _ - _ _ _ .- _ _ .- - .- . - = _ . - - .
t i
, Table 7.4 i
GASEOJB EEF1EENTS--GROJHQ_LEYEL_}lELEAS_EH Continous Mode Batch Mode !
Nuclides Released Units Quarter Quarter Quarter Quarter ;
1 2 1 2 r
- 1. Fission and Activation Gases c
Ar-41 Ci 0.00E+00 0.00E+00 6.18E-02 2.08E-02 .
Xe-131M Ci 9.47E+01 0.00E+00 6.76E+00 1.11E-01 Xe-133M Ci 0.00E+00 0.00E+00 5.83E+00 1.36E-02 i
Xe-133 C1 2.84+03 1.38E+03 8.41E+02 8.93E+00 Xe-135 Ci 0.00E+00 0.00E+00 3.48E-03 8.34E-04 f Total for period Ci 2.94E+03 1.38E+03 8.54E+02 9.07E+00 f
r
- 2. Iodines f i
I-131 Ci 0.00E+00 0.00E+00 0.00E+00 0. 00E4 00
- I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 1-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates H-3 Ci 8.01E-01 7.58E-01 1.11E-01 1.27E-03 !
Na-24 (Note 1) Ci 0.00E+00 0.00E+00 0.00E+00 2.64E-06 ,
i G. Alpha Ci 4.19E-05 4.13E-06 0.00E+00 0.00E+00 t i
Br-82 (Note 1) Ci 0.00E+00 0.00E+00 2.21E-07 0.00E+00 ;
I Total for period Ci 8.01E-01 7.58E-01 1.11E-01 1.27E-03 r I
Note 1, since the half lives of ha+24 and Br 82 are less than eight days, the amount released in gaseous ef fluents is not ,
l reported in Table 7.3, item c. For the same reason, these isotopes are not considered in dose calculations. ;
a i
.-,e. -r -- . . _ . _ - - -
i Table 7.5 LIQUID _E EELU EliT B -- SMMM ATI O N_QL A LL_B E LEA D E D Units Quarter Quarter Est. Total 1 2 Error %
A. Fission and Activation Products
- 1. Total release (not including Ci 9.53E-03 3.02E-02 1.95E401 tritium, gases, alpha)
- 2. Average diluted concentration pCi/ml 5.39E-10 1.06E-09 during period
- 1. Total release C1 1. 2 5E4 02 1. 60E4 02 1.88E+01
- 2. Average diluted concentration pCi/ml 7.07E-06 5.62E-06 during period
- 1. Total release Ci 3.63E-01 4.33E-02 2.00E401
- 2. Average diluted concentration pCi/ml 2.05E-08 1.52E-09 during period
- 1. Total release Ci 0.00E+00 0.00E+00 Note 1 E. Volume of waste released Liters 1.86E+06 3.76E+07 2.20E+00 (prior to dilution)
F. Volume dilution water used Liters 1.77E+10 2.85E+10 1.00E+01 during period hote 1. No gross alpha activity is reported f or Liquid ef fluents, theref ore er rors f or these values are not ry orted.
Table 7.6 MQ1 LID _EEFMERTE Continous Mode Itatch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 H-3 Ci 0.00E+00 0.00E+00 1.25E+02 1.60E+02 Cr-51 Ci 0.00E+00 0.00E+00 8.83E-05 1.06E-03 Mn-54 Ci 0. 00E4 00 0.00E+00 8.96L-05 3.94E-04 Fe-55 Ci 0.00E+00 0.00E+00 9.30E-04 4.25E-03 Fe-59 Ci 0.00E+00 0.00E+00 5.41E-05 1.56E-04 Co-58 Ci 0.00E+00 0.00E+00 7.12E-03 1.87E-02 Co-60 Ci 0. 00E4 00 0.00E+00 4.15E-04 1.33E-03 Zr-95 Ci 0.00E+00 0.00E+00 1.95E-04 3.72E-04 Nb-95 Ci 0.00E+00 0.00E+00 4.59E-04 8.03E-04 Mo-99 Ci 0.00E+00 0.00E+00 1.06E-05 5.00E-05 Tc-99M Ci 0.00E+00 0.00E+00 2.00E-06 1.01E-05 Sb-124 Ci 0.00E+00 0.00E+00 2.89E-06 6.75E-05 I-131 Ci 0.00E+00 0.00E+00 1.28E-04 6.82E-04 I-133 Ci 0.00E+00 0.00E+00 2.79E-05 2.68E-04 Cs-134 Ci 0.00E+00 0.00E+00 0.00E+00 2.44E-04 Cs-137 Ci 0.00E+00 0.00E+00 8.30E-06 1.81E-03 Sn-113 Ci 0.00E+00 0.00E+00 0.00E+00 3.53E-06 Co-57 Ci 0.00E+00 0.00E+00 1.02E-06 4.58E-07 As-76 Ci 0.00E+00 0.00E+00 1.00E-06 0.00E+00 Br-82 Ci 0.00E+00 0.00E+00 0.00E+00 1.36E-05 Total for period Ci 0.00E+00 0.00E+00 1.25E+02 1.60E+02
. .-. . _ . ~ - . . . _ . - . _ . . =- . . .= .- -. .~
4
- TCblo 7.6-- Continuod 4
Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 l
- Kr-85M Ci 0.00E+00 0.00E+00 6.50E-06 0.00E+00
. .r --
Xe-131M Ci 0.00E+00 0.00E+00 3.83E-03 2.66E-05 Xu 133M Ci 0.00E+00 0.00E+00 2.63E-03 1.55E-05 Xe-103 Ci 0.00E+00 0.00E+00 3.56E-01 4.32E-02
- i. Xe-135 Ci 0.00E+00 0.00E400 9.73E-04 4.89E-05 Total for period Ci 0.00E+00 0.00E+00 3.63E-01 4.33E-02 l
a l
4 d
i-a i
2 i
i e
, Tablo 7.7 SOLID WASTE AND IRRADIATED FUEL SHIPEE_ HTS A. Solid Waste Shipped Offsite For Burial or Disposal (Not Irradiated Fuel)
- 1. Type of Waste Unit 6-month Est. Total Period Error %
- a. Spent resins 1,2 m3 5.83E400
'i 1.22E-02 1.00E+01 b.Drycompress{blewaste, equip., etc. 'J contaminated v 5.73E+00 l
. 9.97E-02 1.00E+01
- c. Irradiated components, control m3 NONE rods, etc. Ci N/A N/A
- 1. There were no solidification agents or absorbents applied to tne solid waste.
- 2. Volume shipped to burial site
- 3. Volume shipped to burial sites via waste processors
- 2. Estimate of Major Nuclide Composition (by type of waste)
Type of Waste Nuclide % Abund. Activity
- a. Spent resins H-3 99.7% 1.22E .2
- b. Dry Compressible waste, Co-58 63.8% 6.36E-02 contaminated egiup., etc. Fe-55 8% 2.97E-02 Mn-54 .4% 6.38E-03
- 3. Solid Waste Disposition Waste Number of DOT Type of Transportation Shipped Burial Class Shipments Type Container Mode To Site AU 1.00E+00 LSA Type A Truck Barnwell Barnwell AU 1.00E+00 LSA Strong-tight Truck SEG Barnwell AU 1.00E+00 LSA Strong-tight Truck SEG Beatty B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transooration Destination 0 N/A N/A