PLA-3253, Semiannual Effluent & Waste Disposal Rept for Jan-June 1989
| ML18040B255 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/30/1989 |
| From: | Carson B, Keiser H, Shank K PENNSYLVANIA POWER & LIGHT CO. |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PLA-3253, NUDOCS 8909080254 | |
| Download: ML18040B255 (64) | |
Text
'CELEBRATED 33 BUTlON DEMONSTR ON SYSTEM
~l, REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSXON NBR:8909080254 DOC.DATE: 697'66f3W NOTARIZED: NO DOCKET I FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH.NAME AUTHOR AFFILIATION CARSON,B.H.
Pennsylvania Power
& Light Co.
SHANK,K.E.
Pennsylvania Power
& Light Co.
DOTY,R.L.
Pennsylvania Power
& Light Co.
RECXP.NAME RECIPIENT AFFXLIATION R
SUBJECT:
"Semiannu fluent
& Waste Disposal Rept for Jan-June 1989.<<
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1tr.
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TITLE: 50.36a(a)(2)
Semiannual Effluent Release Reports NOTES:LPDR 1
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LPDR 1 cy Transcripts.
j 05000387 g
- 05000388, D
RECXPIENT XD CODE/NAME PD1-2 LA THADANI,M INTERNAL: ACRS IRM TECH ADV NUDOCS-ABSTRACT RGN1 DRSS/RPB EXTERNAL: BNL TICHLER,J03 LPDR NOTES COPIES LTTR ENCL 3
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Pennsylvania Power & Light Company Two North Ninth Street ~ Allentown, PA 18101-1179 ~ 215l770-5151 Harold W. Keiser Senior Vice President-Nuclear 21 5l770.4194 AUG 30
$989 Mr. William T. Russell Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT PLA-3253 FILE R41-2A Docket Nos.
50-387/NPF-14 and 50-388/NPF-22
Dear Mr. Russell:
In accordance with 10CRF50.36a(a)
(2) and the Susquehanna SES Unit 1 and 2
Technical Specifications, attached is the Semi-Annual Radioactive Effluent Release Report for SSES Units 1 and 2 covering the period January 1 through June 30, 1989.
Very truly yours, Wn. H.
W. Keiser Attachment cc:
NRC Document Control Desk.(original)
NRC Region I Mr. G. S. Barber, NRC Resident Inspector Mr. M. C. Thadani, NRC Project Manager 8909080254 890630 PDR ADOCK 05000387 R
J4,
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~ 8909080254 SEm NUALEFFLUENT ck WASTE DISPOSAL REPORT FOR JANUARY-JUNE 1989 Pennsylvania Power 5 Light Company Two North Ninth Street Allentown, Pennsylvania 18101-1179 August 1989
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SUSQUEHANNA SXFAM EUKTflIC STATION SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 01/Ol/89 06/30/89 Prepared by:
BUM
. H. Carson Health Physicist Reviewed:
K. E. Shank Env onmental and Chemistry Group Supervisor Nuclear Approved:
R.
. Doty Supervisor Radiologi al 5 Environmental Services Pennsylvania Power & Light Canpany Two North Ninth Street Allentown, Pennsylvania 18101
TABLE OF CONIKNIS SECTION PAGE
- l. Introduction and Supplemental Information.........
I
- 2. Effluent and Waste Disposal Data.................
9
- 3. Changes to the Offsite Dose Calculation h@nual and the Solid Waste Process Control Program......
27
- 4. Reports of Exception to the SSES Effluent Monitoring Program.
37
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LIST OF TABLES PAGE Table 1:
Supplemental Information..
6 Table 2:
Airborne Effluents-Sunmation of All Releases........
10 Table 3:
Airborne Effluents..
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~
~
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11 Table 4:
Waterborne Effluents-Suranation of All Releases......
12 Table 5:
Waterborne Effluents.
13 Table 6:
Waste Disposition.
14 Table 7:
Solid Radioactive Waste Class A..
15 Solid Radioactive Waste Class B..
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~
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15 Solid Radioactive Waste Class C.
15 Table 8:
Principal Radionuclides and Percent Composition:
Condensate Demineralizer Liner (Dewatered).........
16 Table S:
Principal Radionuclides and Percent Composition:
Condensate Demineralizer Liner (Portland Cement)...
17 Table 10: Principal Radionuclides and Percent Composition:
Condensate Demineralizer HIC (Dewatered)...........
18 Table ll: Principal Radionuclides and Percent Composition:
Reactor 'Water Fuel Pool Clean-Up HIC (Dewatered)...
19 Table 12: Principal Radionuclides and Percent Composition:
Condensate Demineralizer Regeneration (Evaporator Concentrates)
Liner (Portland Cement)....
~.........
20 Table 13: Principal Radionuclides and Percent Composition:
Liquid Radwaste Filter Media, Sludge and Evaporator Concentrates Liner (Portland Cement)...............
21 Table 14: Principal Radionuclides and Percent Composition:
Liquid Radwaste Filter Media, Sludge and Evaporator Concentrates HIC (Portland Cement).................
22 Table 15: Principal Radionuclides and Percent Composition:
Non-Compactable Trash Strong Tight Container.......
23 Table 16: Principal Radionuclides and Percent Composition:
Compacted Trash Strong Tight Container.............
24 I
Table 17: Estimated Total Errors Associated with Effluent Measurements........
25 Table 18: Effluent Data Not Available for Previous Semiannual Report........
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LIST OF FIGURES PAGE Airborne Effluent Release Points; Location and Detail.
SSES Waterborne Effluents; Release Pathway.
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SECTION 1 INTRODUCTION AND SUPPIZMENTAL INFORMATION
~
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INTRODUCTION The Susquehanna Steam Electric Station (SSES) is located in Salem Township, Mzerne County, Pennsylvania. It is on the west bank of the Susquehanna River, 8 km northeast of Berwick. The Station consists of two boiling water reactor generating units, each with 1,050 MW net electrical capacity.
The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.
Construction of the Station began in the early 1970s.
Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit 1 reactor on September 10, 1982.
The reactor reached 100K power for the first time on February 4, 1983.
Commercial operation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred on May 8, 1984. Unit 2 was declared caanercial on February 12, 1985.
Airborne effluents are released from the Susquehanna Station via five rooftop vents on the reactor building (see Figure 1). Each vent is continuously monitored, and a program of periodic sampling and analysis is conducted as specified in the plant Technical Specifications.
All waterborne effluents are released in batch mode and are sampled and analyzed prior to release.
Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (See Figure 2). Blowdown line flow rates are at least 5,000 gpm during periods of liquid radwaste release.
The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed.
The diffuser serves to rapidly and uniformly mix the the station discharge with the main flow of the river.
This report presents a sunmary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from January 1,
1989 to June 30, 1989. In addition, 'this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to PP&L's Offsite Dose Calculation Manual (ODCM) and Solid Waste Process Control Program (PCP) and documentation of any exceptions to the SSES effluent monitoring program which must be reported per Technical Specifications 3.3.7.10 and 3.3.7.11.
Table 1 contains supplemental information pertaining to effluents from the Susquehanna plant. Included are regulatory limits, sampling and analysis
- methods, and characterization of the number and duration of batch and abnormal releases, if any.
e Table 2 contains a suaxnation of all airborne releases, grouped into the radionuclide categories of gases, particulates, iodine-131 and tritium.
Average release rates are presented and compared to the applicable limits. Table 3 presents the totals of specific radionuclides in airborne effluents.
Waterborne effluents are sunmarized in Table 4. Average diluted
, ~
, concentrations are presented and compared to the applicable limits.
Table 5 presents the release quantities of specific radionuclides in waterborne effluents over the report period.
Tables 6 through 16 present a characterization of the solid radioactive waste shipped off site during the report period.
Included are the volumes and curie contents associated with each type of solid waste.
An estimate of major nuclide composition is presented for each waste type.
as well as the number of waste shipments from the site, how they were transported, and their final destination.
Table 17 contains estimates of the errors associated with the measurements involved in quantifying effluents. Errors associated with sampling,
- counting, flow rate and volume determination all contribute to the total error of the effluent measurements.
Error estimates are presented for each category of radionuclides detected in airborne and waterborne effluents and solid wastes during the report period.
Table 18 presents effluent data from previous report periods which was not available at preparation time for the associated semiannual report.
Section 3 of this report is reserved for documentation of changes (if any) to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program.
Section 4 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within the time period specified in Technical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.
UNIT I REACTOR BUILDING EXHAUST VENT 158,250 CFM ATBO F-110 F NIT H REACTOR BUILDING EXHAUST VENT 158.250 CF M ATIXFF 110 F
~ ~
OUTSIDE AIR INTAKE REACTOR BUILDING EXHAUSTSTACKS DIESEL EXHAUSTPLENUM DIESEL GENERATOR BUILDING UNIT I TURBINE BUILDING EXHAUST VENT UNIT II TURBINE BUILDING EXHAUST VENT 355.000 CFM 7500 CFM 2iO.IXXICF M AT IIXF'F-12F AT 120 f AT IIXF'F-12' EL 525'4" CONTROL BUILDING MPp
~s'
~ r IMEl Bli'-I EL.
81i'.~11'ADhtASTE BUILDING
~o4.
1p<
TURBINE BUILDING UNIT I EL. 676'4" UNIT H
> <<s FIGURE 2:
SSES WATERBORNE EFFlUENTS; REf EASE PATHWAY SUSQUEHANNA RIVER OIFFLISEA INTAHE 89, ltI GPM CL ParASLE WICKER SE WAGE TREATMENT PLANT 0 EOOGPM lqtOOGPMgg RAINFALL FLOw I4% GPM (lb) c"b R ADIOACTIVL AREA WATER USES
'RAD'wASTE TREATMENT CPM RLRONE LOT'OND AR6 CPM RAW WATER TREATMENT PLANT CRURAL PLANT LISEb WASTE TREATMENT I4SGPM EVAPORATION I+,SSO6PM 47d.OOO OPM 45CPM 50 CPM EVAPORA'T ION I+,S50 Gal 4Td.OOO OPM OEMINKRAUZERWASTES CHEMICAl WASTE TREATMENT RAW WATER TREATMEHT WASTES X lf RAIN CAL GENERATLO FIOWog 50 CPM WATER RECOvLRy FILTER IAICELLAI+)LE HEAT EXCHAHOERS CI CL CONDENSER e
I EMtr<EHCy HEAT I
~~BCHAHOEqS4 L
tCAT I ~~N6EREj.
I COOLING TO POND 45GPM MAKEu I CkCAgEHCy~
OIESELS L
I IO.OOO GPM CE*)
A--
P--~
KMEAOEHCy L
SPRY POND CI GPg EVAPORATION
+S aPM
TABLE 1 SEMIANNUAL EFFLUENT 5 MASTK DISPOSAL REPORT DATA PERIOD:
JANUARY JUNE 1989 SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits
- a. Fission and Activation Gases:
0.851 Ci/minute (Release rate limit based on Technical Specification dose rate limit of 500 mrem/yr from noble gases).
This number is calculated based on the expected mix
'f noble gas radionuclides presented in Table 4.4 of the SSES Final Environmental Statement, NUIKG-0564.
- b. Iodine-131:
141 microcuries/minute (Release rate limit based on Technical Specification dose rate limit of 1500 mrem/yr from iodine-131, tritium, and particulates with half-lives greater than eight days).
I
- c. Particulates:
772.microcuries/minute (Release rate limit based on Technical Specification dose rate limit of 1500 mrem/yr from iodine-131, tritium, and particulates with half-lives greater than eight days).
This number is calculated based on the expected mix of particulate radionuclides presented in Table 4.4 of the SSES Final Environmental Statement, NUREG-0564.
- 2. hhximum Permissible Concentrations The concentrations of radioactive materials in waterborne effluents are limited to the concentrations specified in 10 CFR Part 20 Appendix B Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentrations are limited to the following values, as stated in the applicable Technical Specification:
Nuclide 85Kr m 85Kr 87Kr 88Kr 4 1Ar
>>3Xe m 1 3 3)(e 135Xe m 1 3 5)(e MPC (uCi/ml) 2 E-4 5 E-4 4 E-5 9 E-5 7 E-5 5 E-4 6 E-4 2 E-4 2 E-4 l
These values are calculated using Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water.
- 3. Methods of Quantifying Effluents
- a. Fission and Activation Gases:
Gas samples are routinely collected monthly and analyzed with a Ge(Li) detector syst'm which incorporates a data reduction program to determine radionuclide composition in
t7 t ~
terms of specific activity. Data tapes from the continuous vent monitors are used to determine the average concentration of noble gases.
The Ge(Li) isotopic scan is used to convert the continuous vent monitor activity to actual activity based on the determined nuclide mixture. The vent and sample flow rates are continuously monitored, and the average flow rates for each vent are used to calculate the total activity released in a given time period.
When the continuous monitors are out of service, manual grab samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).
- b. Iodines:
Iodine is continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a Ge(Li) system.
The daily average flow rates for the vents and,sample pumps are averaged for the duration of the sampling period, and a ratio of vent flow rate to sample flow rate is determined.
The ratio is used to determine the total activity of each isotope released during the time period in question.
When the continuous monitors are out'of service, iodine is continuously collected on charcoal cartridges attached to air samplers which draw directly from the affected rooftop vent(s) or from alternate sampling ports available on the sample lines.
0 C. Particulates:
Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a Ge(Li) system.
Flow rate corrections are performed as for iodines.
When the continuous vent monitors are out of service, particulates are continuously sampled directly from the affected rooftop vent(s) or from alternate sampling ports available on the sample lines.
- d. Waterborne Effluents: Each tank of liquid radwaste is sampled and analyzed for principal garana emitters prior to release, Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained.
Samples are analyzed on a Ge(Li) system and release permits are generated based on the values obtained from the isotopic analysis and the most recent values for tritium. gross alpha, iron-55, and strontium-89 and -90.
An aliquot based on release volume is saved and added to monthly and quarterly composite containers.
The monthly tritium analysis is done in-house.
The quarterly composite is sent to a vendor laboratory for iron-55, strontium-89 and -90. and gross alpha analyses.
The concentration of each radionuclide in each batch is decayed from the time of counting'to the midpoint of the release period, and is then multiplied by the volume of the batch to determine the total quantity of each nuclide released in each batch.
The isotopic totals for each are suraned to determine the total source term for the report period.
I
- 4. Batch Releases
- a. Waterborne
- 1. Number of Batch Releases:
- 2. Total Time Period for Batch Releases:
- 3. Maximum Time Period for a Batch Release:
- 4. Average Time Period for a Batch Release:
- 5. Minimum Time Period for a Batch Release:
- 6. Average Stream Flow During Period of Release of Effluent into a Flowing Stream:
103 1.94E+04 minutes 3.20E+02 minutes 1.89E+02 minutes 2.50E+Ol minutes
>5.82E+03 7.62E+06 gpm (cooling tower bio wdown) gpm (Susq. River)
- b. Airborne
- 1. Number of Batch Releases:
- 2. Total Time Period for Batch Releases:
3.
Maximum Time Period for a Batch Release:
- 4. Aver'age Time Period for a Batch Release:
- 5. Minimum Time Period for a Batch Release:
0 NA NA NA NA
- 5. Abnormal Releases
- a. Waterborne
- 1. Number of Releases:
- 2. Volume Released:
- 3. Total Activity Released:
0 NA NA
- b. Airborne
- 1. Number of Releases:
- 2. Total Activity Released:
0 NA
SECTION 2 EFFLUENT AND MASTE DISPOSAL DATA
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TABLE 2 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1989 AIRBORNE EFFLUENTS SUhSSTION OF ALL RELEASES Nuclide Category Unit First Quarter Second Quarter A. Fission and Activation Gases
- 1. Total Release~
- 2. Average Release Rate for Period Ci 5.35E+01 uCi/sec 6.88E+00 4.10E+01 5.21E+00
- 3. Percent of Applicable Limit~
4.85E-02 3.67E-02 B. Iodine-131
- 1. Total Release
- 2. Average Release Rate for Period
- 3. Percent of Applicable limit~
Ci
>3.55E-04
<5.15E-04
>1.94E-03
<2 '2E-03 uCi/sec
>4.57E-05
<6.62E-05
>9.09E-05
<2.40E-04
>1.16E-05
<3.05E-05
>4.92E-04
<1.30E-03 C. Particulates
- 1. Particulates with Half-lives >8 Days Released
- 2. Average Release Rate for Period
- 3. Percent of Applicable Limits
- 4. Gross Alpha Activity Released Ci
>2.09E-04
<1.29E-03 Ci
>2.08E-04
<1.29E-03
>1.33E-06
<1.34E-06 uCi/sec
>2.69E-05
<1.66E-04
>1.27E-04
<1.05E-03
>1 ~ 62E-05
<1.34E-04
>1.25E-04
<1.04E-03
<1.07E-06 D. Tritium
- 1. Total Release
- 2. Average Release Rate for Period
- 3. Percent of Applicable Limits Ci
>1.44E+Ol
<2.53E+01 uCi/sec
>1.85E+00
<3.25E+00
>3.79E-02
<6.67E-02
>1.75E+01
<2.06E+01
>2.23E+00
<2.62E+00 I
>4.56E-02
<5.37E-02
~Notation: The first value presented
(>) includes only activity positively detected at the 95X confidence level. The second value
(<) includes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95X CL.
~Based on release rate limit derived from dose rate Technical Specification.
sBased on a release rate (4.88E+03 uCi/sec) corresponding to the sH Maximum Permissible Concentration (2.0E-07 uCi/cc) in unrestricted areas.
A relative concentration of 4.1E-05 sec/ms is assumed.
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Nuclide A. Gases TABLE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1989 AIRBORNE EFFI UENTS (Curies)1 First Quarter Second Quarter
>>3Xe Total 5.35E+01 5.35E+01 4.10E+01 4.10E+01 B. Iodines 131I
>3.55E-04
<5.15E-04
>9.09E-05
<2.40E-04 C. Particulates with Half-lives > 8 d 51Cr 54Mn 59Fe 58Co 60Co 65Zn 89Sr 90$r 1 34Cs 1 37Cs 141Ce 1 44Ce Total
>7.38E-OS
>8.57E-07
>1.28E-06
>1.32E-04
>1.37E-06
>2.09E-04
<1.66E-04
<1.58E-04
<6.89E-05
<2.56E-04
<1.83E-04
<1.83E-06
<6.01E-07
<6.32E-05
<1.40E-04
<5.11E-OS
<2.04E-04
<1.29E-03
>6.54E-OS
>1.38E-05
>3.43E-05
>1.37E-05
>1.27E-04
<1.51E-04
<1.49E-04
<7.48E-OS
<1.55E-04
<1.78E-04
<4.95E-06
<5.35E-07
<5.73E-05
<6.11E-05
<4.31E-05
<1.79E-04
<1.05E-03 1Notation:
The first value presented
(>) includes only activity positively detected at'he 95X confidence level. The second value
(<) includes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95X CL.
r J0
'TABLE 4 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1989 WATERBORNE EFFIUENTS SUMMATION OF ALL REHMSES Nuclide Category Unit First Quarter Second Quarter A. Fission 5 Activation Products
- 1. Total Release~
- 2. Average Diluted Concentration
- 3. Percent of Applicable Limit~
B. Tritium
- 1. Total Release
- 2. Average Diluted Concentration
- 3. Percent of Applicable limits C. Dissolved and Entrained Gases
- 1. Total Release
- 2. Average Diluted Concentration
- 3. Percent of Applicable Limit4 Ci uCi/ml Ci uCi/ml Ci uCi/ml 1.41E-02 4.72E-03 5.91E+00 3.07E-05 1.02E+00 6.92E+00 2.86E-OS 9.52E-01
>3.38E-04
<6.02E-02
>5.20E-04
<5.86E-02
>1.76E-09
<3.13E-07
>2 '5E-09
<2.42E-07
>4.39E-03
<7.81E-Ol
>5.36E-03
<6.04E-01
>4.23E-02
<5.05E-02
>1.48E-02
<2.08E-02
>2.20E-07
<2.62E-07
>6.11E-08
<8.58E-08 D. Gross Alpha Radioactivity Released E. Volume of Waste Released (Prior to Dilution)
Ci gal.
liters
<8.53E-05 6.86E+05 2.59E+06
<1.10E-04 8.85E+05 3.35E+06 F. Volume of Dilution Water Used
- 1. During Periods of Release gal.
liters
>5. 02E+07
>1.90E+08
>6.32E+07
>2.39E+08
- 2. Over Entire Period gal.
liters'7.78E+08
>2.94E+09
>7.48E+08
>2.83E+09
~Notation:
The first value presented
(>) includes only activity positively detected at the 95X confidence level. The second value
(<) includes detected activity plus the Lower Limit of Detection values of any samples in which activity was, not detected at the 95X CL.
~Based on quarterly dose limits from liquid effluents.
sBased on the Maximum Permissible Concentration for sH in effluents to unrestricted areas (3.0 E-03 uCi/ml).
~Based on the most restrictive Maximum Permissible Concentration for a noble
- gas, 4.0 E-05 uCi/ml (0'7Kr) from SSES Tech Spec Table 3.11.1.1-1.
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TABLE 5 SEMIANNUAL EFFLUENZ AND WASTE DISPOSAL REPORT - 1989 WATERBORNE EFFI,UENTS (Curies) 1 Nuclide A. Tritium First Quarter 5.91E+00 Second Quarter 6.92E+00 B. Fission and Activation Products 3~Na 51Cr 5~Mn 55Fe 59Fe 58Co 60Co 65Zn 76As 89Sr 90Sr
>>Mo
>>Tc m
>>0Ag m 131 I 134Cs 1 37Cs 141Ce 144Ce Total C. Dissolved and Entrained Gases 41Ar 85Kr m 85Kr 87Kr 88Kr
>>3Xe m
>>3Xe
>>5Xe m
>>5Xe Total 1.42E-03 2.91E-02
>5.74E-03
>1.47E-04
>6.77E-04
>3.54E-03
>1.12E-03
" 4. 15E-05 7.09E-05 5.57E-OS
>2.31E-04
>1.70E-04
>4. 23E-02
>2.54E-04
>8 '8E-05
>3.38E-04
<5.80E-03
<2.59E-03
<7.08E-04
<8.64E-04
<3.73E-03
<1.72E-03
<1.30E-04
<1 ~ 68E-03
<1.87E-04
<4.72E-04
<4.56E-04
<2.65E-04
<1.17E-03
<5.05E-02
<2.70E-05
<5.95E-05
<5.78E-02
<1.41E-05
<9.94E-05
<1.31E-03
<7.18E-04
<1.57E-08
<1.78E-04
<6.02E-02 2.13E-03
>2.53E-03 8.70E-03
>6.45E-06
>1.25E-04
>1.27E-03 4.08E-05 1.37E-05
>1. 48E-02
>3.51E-04
>1.69E-04
>5.20E-04
<2.67E-03
<6.52E-04
<4.07E-04
<1.59E-03
<7.33E-04
<1.34E-04
<2.34E-05
<1.59E-03
<2.01E-04
<2.70E-04
<3.16E-04
<2.42E-04
<1.06E-03
<2.08E-02
<2.11E-05
<3.29E-03
<5.30E-02
<9 '8E-06
<7.12E-05
<1.23E-03
<7.82E-04
<9.67E-09
<2.29E-04
<5.86E-02 1Notation: The first value presented
(>) includes only activity positively detected at the 95X confidence level. The second value
(<) includes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95X CL.
13
TABLE 6 SEMIANNUAL EFFLUENZ AND WASTE DISPOSAL REPORT WASTE DISPOSITION Data Period:
January 1, 1989 - June 30, 1989 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL Number of Shi ents Mode of Trans rtation Destination 25 Truck
- Barnwell, SC B.
IRRADIATED FUEL SHIPMENTS Number of Shi ents Mode of Trans rtation NONE Destination NOT APPLICABLE O.
14
0 TABLE 7 SKHLAHHUAL EFFLUENT AND SPDSN.
@PORT SOLID RADIOACTIVE CLASS A Date Period 4
Jen 1989 - June 30 1989 SOURCE DF MASTEt SOLIDIFICATION AOEHTt TYPE OF COHTAIHERa IsotoPes in units of uCi An-211 Ag lion C 11 Co-58 Co-60 Cr-51 Cs-1M Cs-137 Fe 55 Fe-59 H-3 I-129 Hn-5'I Kr 85 Hi-63 Sr-85 Sr-90 Tc-99 2n-65 I 131 Co-57 Sb-121 Zr-95 TOTAL ACTIVITY CCL>
CQHTAIHER VOLUHE Cft&
0%00Etoo 9%7?Et03 1%93Et05
~
le52Et05 1%32Et OS L%16Et 05 3 SDEtM L%05E401 L%10D06 9 LREtM 2%03Kt 01 1 LSK401 L.R3Kt06 0%0OEt 00 8.?3D01 0eooEt M 1%39Et 02 1%39Kt03 3%72Et 05
?eSSKtol 7%76Kt 0L 0%ODD OO 0 OOEtoo 5%0?5 1063 ~80 CQCGISATE DEHIRERNJ2ER PORTLACI CEIKHT CARBON STEEL LIHER 0%IIM 0eoOEt 00 3%2SKt01 1%5?KtIH 1%8SDOS 1%50Et OS 2%38EtM 2eBSEt03 L%1BK405
= 1 3W401 9%~4 M 3 23KtM 1 BBEt05 0 OOEtoo 2 OLKt01 0eoOEtoo 2%61Et 02 7%99D 02 1 50E401 2%61Et 02 0%00E400 0%00Etoo 0%00Etoo 0 822 531%90 CONDENSATE DEHIHKRALI2KR DEHATKRKD HIC 0 OOEtoo 0%0OKt 00 3 56Kt05 1 79DQS 3 2?Kt06 9%81Et01 7 SSK401 5 ?3Kt0'I 1 73DOS 6%'32Et 03 1 RBD01 1 35Kt01 1%8SEt 06 0 OOKtoo 3 ?3D01 0 ODEtoo 7%RSKt02
?e57D OR 1%26Kt 06 2%21Et03 0%00DOO 0 OOKtoo 0 OOKtoo 1R%RS7 8$3 30 REACTOR IIITKR FUG. POOL CLEWS-II
'BIATERED HIC 0%00Ktoo 3.51E405 2 62D02 1%01KIOS 1%05D 0?
1 OBE40?
2% LTEt05 leSBEt05 2 62DOV 1 28D06 3%1?Kt 01 1 OSEt02 1%5BD 07 0%OOEt 00 3 26E405 0%0OEt 00 1%21D 01
. 2%98Et02 2% 15D 06 0%ODD OO 0%00Ktoo 0 OODOO 0 OQDOD 68,878 135,80 0%00Etoo 0 OODOO ~
6%?DEt 01 9 SDEtM 9%RSKt01 5 DSE401 0%00E400 0 OOEtoo 1 LSKt06 leRLEt01 1%61KtM 0 OODOO Le'%Et 05 0%OOEt 00 8%36Et01 0%00Etoo 1%31Et02 0%0OKtoo 2%LSEtM D%00E400 0%00Etoo 0%00Etoo 0%ME400 L%6937 11%60 CND% DENs.REBEN%
CKVAPORATDR CQHC%)
PORTLNO CERN?
CARSON STEEL LIER LIQUID RH FILTERS CF,H,S3 PORTLIBID CEIKKT CARBON STEEL LXI%R 0%0OEtoo 2%92Et 01 L%3LE401 1%5SKt05
. 2%20E406-5 7'K406'%00K400
=0 OOEtoo 3.06E407 5%75DOS
~I~LSDM 0 OOE400 3%35KtOS 0%0OKtoo 7%65Kt01 0%00Etoo 1%3'%402 5 16E402 1%S1D 05 0%ODD OO 0 OOEtoo 0 OOEtoo 0 OODOO
~I2%861 533%70 SOURCE OF MASTEt SOLIDIFICATION AOEHTt TYPE OF CONTAINER!
LIQUID RM FILTERS oafeham STROH8 TIBHT CDHT.
OILV HASTE An-201 Ag-lion C-11 Co-58 Co-60 Cr-51 Cs-LM Cs-13?
Fo-55 Fe-59 H-3 I-129 Hn-51 Kr-85 Hi-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57
~ Sb-121 Zr-.95 TOTAL ACTIVITY COHTAIHER VOLIRI CCD E Cft3>
0%00Etoo 0%0OE400 1%89D01 1%22EtoS 1%'tBEf0?
1%2LK406 0%00Etoo 0%0OEtoo
'%11E408 3%5?EtoS
~ 3%36Et03 0%ODD 00 2 12Eto?
5%56E406 1%36K405 2%29D 01 2 2'IKt02
~ 9%1?Kt02 1%9?Kt 06 0 OODOO 0%0DKtoo 6%82Et03 R%20D 01 161%298 684%70 0%00Etoo 0%00EtM
?%00K 01 R%69Et 02 le26KtM 6%29EI 02.
OeoOEtoo 0%00Et M 8%12E403 0%0OE400
'eOOEt 00 0 OODOO.
Le~iD3 0%00Et 00 7 ?9Ktol..
0%00Etoo 0%00Kt 00 7 SREt02.
'Ie91Kt02 0%ODD OO 0 OOE400 0 OOEtoo 0%00K400 0%011 ll?%00
~
0 OOEtM 0%00Et00 0%00Ktoo 0 OODOO 0%00Etoo 0%00DOO 0%0OEtOO 0%00KtDO 0%0ODOO 0%00E400 0%OOKtoo 0 ODDOO O.OODOO 0%00DOO 0%00DOO 0 OODOO 0%00Ktoo 0%00E400 0%ODD 00 0 OOEt00 0 OOKtoo 0%00DOO 0 OODDO 0%000 0'00 0 OOEtoo 0%ODD OO 0%0OE400 0 OOEtoo 0 OODOO 0%00Et 00 0 OODOO 0 OODOO 0%00Et 00 0 OODOO 0%00Et00 0%ODD 00 OeOOKtoo 0 OODOO 0%ODD 00 0 OOE400 0%ODD 00 0%ODD 00 0 OODOO 0 OOKtoo 0%00E400 0%0ODOD 0%ODD 00 0 QOO 0%00 0%00Etoo 0%00E400 1% L3EtM 1%09K405 8%0TEt05 Re35Et 05 0%0DEtoo 0%00Et 00 6%60D OS Le?3K%01 1% 12Et02 0%00Et M 1%15Et06 0%00Kt 00 2%9LE401 0%00Kt 00.
0%00Ktoo 8126D M 2%19Et05 0%0OEI 00 0%00DOO 0 OQKtoo
~
0%0OEtoo 9%251 2888%'IO
'O.OOEt 00 0%00KI00 O.ODD OO 0%0OK400 0 OOEtoo 0 OOKtoo 0 OODOO 0%ODD 00 0%ODD 00 OeOOEt 00 D OOEtoo 0%00Etoo 0 OOE400 O.OOE400 0 OOEtoo 0 OODOO 0%00DOO 0%00DOO 0 OOE400 0 OOE400 0 OOKtoo O.OOK40O O.ODD OO 0 000 "No Class B or Class C Waste Generated
TABLE 8 Source of Waste:
Condensate Demineralizer Type of Container:
Liner Method of Process:
Dewatered
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Nn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 2n-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit (uCi)
O.OOE+00 9.77E+03 1.93E+05 1.52E+05 1.32E+06 1.46E+05 3.50E+04 1.05E+04 1.40E+06 9.12E+04 2.03E+04 1.15E+04 1.23E+06 O.OOE+00 8.73E+04 O.OOE+00 4.39E+02 1.39E+03 3.72E+05 7.96E+01 7.76E+01 O.OOE+00 O.OOE+00 5.08E+06 X of Total O.OOX Oe195 3.81$
2.995 25.96%
2.885 0.695 0.21%
27.56K 1.80%
0.40$
0.234 24.21$
0.00$
1.72K 0.005 0.01$
0.035 7.33%
0.005 O.OOX
- 0. 00'A 0.00%
100.00K 16
TABLE 9 Source of Maste:
Condensate Demineralizer Type of Container:
Liner Method of Process:
Solidification Portland Cement
~Isoto es Activit (uCi)
X of Total Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 2n-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY O.OOE+00 O.OOE+00 3.29E+04 1.57E+04 1.89E+05 1.50E+05 2.38E+03 2.85E+03 1.48E+05 1.34E+04 9.44E+03 3.23E+03 1.88E-05 O.OOE+00
- 2. 01E+04 O.OOE+00 2.64E+02 7.99E+02 4.50E+04 2.64E+02 O.OOE+00 O.OOE+00 O.OOE+00 8.22E+05 O.OOX O.OOX 4.01%
1.91%
23.05Ã 18.24%
0.29%
0.35%
18.01%
1.63$
le15X 0.39%
22.89%
0.00Ã 2.44K 0.005 0.03%
0.10%
'.48%
- 0. 03'4 O.OOX 0.00%
0.00$
100.00'X 17
TABLE 10 Sour ce of Waste:
Condensate Demineralizer Type of Container:
HIC Method of Process:
Dewatered
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit (uCi)
O.OOE+00 O.OOE+00 3.56E+05 4.79E+05 3.27E+06
- 9. 81E+04 7.69E+04 5.73E+04 4.73E+06 6.32E+03 1.28E+04 1.35E+04 1.86E+06 O.OOE+00 3.73E+04 O.OOE+00 7.29E+02 7.57E+02 1.26E+06 2.24E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.23E+07 X of Total O.OOX O.OOX 2.90K 3.90$
26.67K 0.805 0.63%
0.47%
- 38. 59'A 0.05$
0.10K 0.11%
15.20%
0.00%
0.30K 0.00Ã
- 0. 01'X
- 0. 01'X 10.24%
0.02%
- 0. 00'X
- 0. 00'X 0.00%
100.00K 18
TABLE 11 Source of Waste:
Reactor Water Fuel Pool Clean-up Type of Container:
HIC Method of Process:
Dewatered
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit (uCi)
O.OOE+00 3.54E+05 2.62E+02 1.04E+06 1.05E+07 1.08E+07 2.17E+05 1.98E+05 2.62E+07 1.28E+06
- 3. 47E+01 1.05E+02 1.58E+07 O.OOE+00 3.26E+05 O.OOE+00
- 1. 21E+04 2.98E+02
- 2. 15E+06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 6.89E+07 X of Total O.OOX 0.51%
O.OOX 1.51%
15.24%
15.68%
0.32%%d 0.29%%d 38.04%%d 1.86%
0.00%%d 0.00%%d 22.94K O.OOK 0.47%%d 0.00%%d 0.02%%d O.OOX 3.12K 0.00%%d 0.00%%d 0.00%%d O.OOX 100.00%
19
5 P0
TABLE 12 Source of Maste:
Condensate Demineralizer Regeneration (Evaporator Concentrates)
Type of Container:
Liner Method of Process:
Solidification Portland Cement
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129
, Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit (uCi)
O.OOE+00 O.OOE+00 6.70E+04 9.50E+03 9.29E+04 5.06E+04 O.OOE+00 O.OOE+00
- 1. 19E+06
'1. 61E+04
- 1. 61E+04 O.OOE+00 1.46E+05 O.OOE+00 8.36E+04 O.OOE+00 1.31E+02 O.OOE+00
- 2. 15E+04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.69E+06 X of Total 0.00Ã O.OOX 3.96K 0.56%
5.49%
- 2. 99'5 0.00%
O.OOX 70.52%
0.71%
0.95%
O.OOX 8.605 O.OOX 4.94K 0.00%
0.01%
0.00K 1.27%
0.00K 0.00Ã 0.00%
0.00%
100.00K 20
l I
e
TABLE 13 Source of Waste:
Liquid Radwaste Filter Media, Sludge, and Evaporator Concentrates Type of Container:
Liner Method of Process:
Solidifcation - Portland Cement
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Nn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit uCi)
O.OOE+00 2.92E+04 1.31E+04
- 1. 56E+05 2.20E+06 5.74E+06 O.OOE+00 O.OOE+00 3.06E+07 5.75E+05
- 4. 18E+03 O.OOE+00 3.35E+06 O.OOE+00 7.65E+04 O.OOE+00 1.34E+02 5.46E+02
- 1. 61E+05 O.OOE+00 O.OOE+00 O.OOE+00 0:OOE-00 4.29E+07 X of Total 0.00%
- 0. 07'I 0.03%
0.36%
Se13%
13.40%
O.OOX O.OOX
- 71. 29'A 1.34%
0.01%
0.00%
7.81%
0.00%
Oe18%
0.00%
O.OOX O.OOX
- 0. 37'5 O.OOX O.OOX O.OOX O.OOX 100.00K 21
TABLE 14 Source of Waste:
Liquid Radwaste Filter Media, Sludge, and Evaporator Concentrates Type of Container:
HIC Method of Process:
Solidification Portland Cement
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 Zn-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit uCi)
O.OOE+00 O.OOE+00 1.89E+04 1.22E+06 1.48E+07
- 4. 21E+06 O.OOE+00 O.OOE+00 1.11E+08 3.57E+06 3.36E+03 O.OOE+00
- 2. 12E+07 5.56E+06 4.36E+05 2.29E+04 2.24E+02
- 9. 17E+02 1.97E+06 O.OOE+00 O.OOE+00 6.82E+03 2.20E+04 1.64E+08 X of Total O.OOX 0.00$
0.01$
0.74%
- 9. 02'5 2.56K O.OOX O.OOX 67.71%
2.18Ã O.OOX 0.00Ã 12.90%
3.38%
0.27%
0.01Ã 0.00%
O.OOX 1.20%
O.OOX 0.00%
- 0. 00'X 0.015 100.00'X 22
t I
~
4
TABLE 15 Source of Waste:
Non-Compactable Trash Type of Container:
Strong Tight Container
~Isoto es
.Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59
"'-3 I-129 Nn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 2n-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit (uCi)
O.OOE+00 O.OOE+00
- 7. OOE+01 2.69E+02 1.26E+03 6.29E+02 O.OOE+00 O.OOE+00 8.42E+03 O.OOE+00 2.00E+00 O.OOE+00 1.84E+03 O.OOE+00 7.79E+01 O.OOE+00 O.OOE+00 7.62E+02 4.94E+02
'O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.38E+04 X of Total O.OOX O.OOX
- 0. 01'5 1.96K 9e16%
4.57K O.OOX O.OOX 61.22Ã O.OOX 0.01K
- 0. 00'X 13.38%
O.OOX,
- 0. 57%
O.OOX 0.00%
5.54K 3.59%
O.OOX
- 0. 00'X O.OOX 0.00$
100.00'X 23
I
TABLE 16 Source of Waste:
Compacted Trash Type of Container:
Strong Tight Container
~Isoto es Am-241 Ag-110m C-14 Co-58 Co-60 Cr-51 Cs-134 Cs-137 Fe-55 Fe-59 H-3 I-129 Mn-54 Kr-85 Ni-63 Sr-85 Sr-90 Tc-99 2n-65 I-131 Co-57 Sb-124 Zr-95 TOTAL ACTIVITY Activit uCi)
O.OOE+00 O.OOE+00
- 1. 13E+03 1.09E+05 8.07E+05 2.35E+05 O.OOE+00 O.OOE+00 6.60E+06 1.73E+04 4.12E+02 O.OOE+00
- 1. 15E+06 O.OOE+00 2.91E+04 O.OOE+00 O.OOE+00 8.26E+04
- 2. 19E+05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.25E+06 X of Total 0.00%
O.OOX
- 0. 01'X
- l. 18'5
- 8. 73'5 2.54K O.OOX 0.00%
71.30K
- 0. 19'5 O.OOX O.OOX
- 12. 48'5 O.OOX'.31%
O.OOX O.OOX 0.89Ã 2.36K O.OOX O.OOX O.OOX O.OOX 100.00K mts/tbh1773c(26)
TABLE 17 SEMIANNUAL EFFLUENT AND MASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED MITH EFFIUENT hKASUREhKNXS Data Period:
January 1, 1989 June 30, 1989 Measurement
- 1. Airborne Effluents Estimated Total Error,
- a. Fission and Activiation Gases
- b. I-131
- c. Particulates
- d. Tritium 15.9 r.
13.3 r.
15.8 r.
5.7 r.
- 2. Waterborne Effluents
- a. Fission and Activation Products
- b. Tritium
- c. Dissolved and Entrained Gases
- d. Gross Alpha Radioactivity e.
Volume of Waste Released (Prior to Dilution) 5.o r.
3.3 r.
8.4 r.
None Dectected
- f. Volume of Dilution Water Used During Period
- 3. Solid Wastes
- a. Condensate Demineralizers (Bead Resin Dewatered) 15.0 r.
15.1 r.
- b. Reactor Mater Clean-up (Fuel Pool Dewatered) 15.1 r.
- c. Condensate Demineralizer Regeneration (Evaporator Concentrates Solidified)
- d. Liquid RW Filters (Filter Media, Sludge and Evaporator Concentrates Solidified)
- e. Non-Compactable Trash
- f. Compacted Trash 15.1 r.
15.1 r.
25 r.
25 r.
25
TABLE 18 SEMIANNUAL EFFlUENT AND WAKE DISPOSAL REPORT DATA'NOT REPORTED IN PREVIOUS SEMIANNUAL REPORT All data needed for preparation of the previous report (July - December 1988) were recieved in time for incorporation into the tables.
No estimated values were used.
26
SECTION 3 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND THE SOLID WASTE PROCESS CONTROL PROGRAM 27
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL r
There were no revisions to the SSES Offsite Dose Calculation Manual during the report period.
28
I ~
~ (I0 CHANGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM The following changes to Revision 8 of the SSES plant procedure AD-QA-311, Solid Waste Process Control Program, were prepared and approved during the report period.
Copies of the affected pages are included following this page The changes made do not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.
29
PROCEDURE CHANGE APPROVAL FORM 1.
2.
PCAF NO.
"QOS0 PAGE 1
OF 3.
PROCEDURE NO.
4~ -
8 - 3f~
REV. 8 5.
PROCEDURE TITLE Sg geo/<<ra 4, Ciaeoso Cerrd~a f Pi-ogrrrroos i.
FORM NUlSER/ REVISION Rn-pa-'J]l J Ae. (
6.
PROCEDURE TYPE:
PORC ~
N-7.
REQUESTED CHANGE g //isa /ssc~
F~roi rrr0 - P8'-g//- g arri'+~~ )
+g 4'.
REASON FOR CHANGE F
Q f ~ -4 ycrFv": gHorrros 4c~~/
W~csas~7~M Mrooo~,f SCC~Hi~
H~~ ~
1 MioP
" r c7 9.
RECOMMENDED FOR PERMANENT STA S
NO, EZPIRATION DATE 10.
COMPLETE U 15 ON REVERSE SIDE Of THIS FORM.
16.
PER ITEM 15,IS A
fOR QMPLEMEbeTAT tgYR$
( lm 18.
A ORI VALID PCAFT 17-lQNAGEMENT REVIEW
- a. (Q giDl lOT RlgOIRN ll01-PORC) b.(~ giDl PRRPORIN
($bl RRYRR5l $IDll, l0 COMRT$
- c. (Q lgl giDR RlgOIRN PRIOR TO iPPROBL Pll bLOC! Il 19.
H{}A R
] lgi giDR lOT RlglHRN, b.(
j lgi giDR PlbtORm, l0 COONT$
c.(
j lgi glOR PbltORM, COINlT5 iTTlClN 20.
REVIEWS PORC lbbTIRO lUlHRR:
'lbPOlbIRLR $lCTIOl RRRDIM. IRITIlL$:
RRCOMNlD:
(
] Yl5
(
j l0 RRYISN:
(
)
YR5
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O 21.
SUPT. Of PLANT APPROVAL:
~
~
POQ hlHg~l, ha l, hgn. hy l st 2 30 OPS TRAINING INFO OTHER UNIT SA'K CHANGE HOT BOX PCI NONE CI C1 5B C1
k,'-g9 - 0050 PpME
~
Ot.
t~a~4+
+~
C AD-QA-311 Revision 8
Page 57 of 60 1.
Date Z.
Waste Type 3.
Liner Type 4.
Burial Volume 5.
Waste Volume SUSQUEHANNA GUARANTEED WASTE VOLUME RECORD Liner number irches in container 6.
Useable Liner,Volume 7.
Guaranteed Minimum Waste Volume 8.
Waste Volume Attained inches x
ft'/fnch "-
9.
Waste Volume Container Usage 100 x (Waste Vo'1.
ft' Guaranteed Mfn.
10.
Remarks:
Waste Vol.
ft )
/oo
- 11. Signature Solidification Vendor Representatfve
- 12. Sfgnature adwaste Supervisor FORM AO-QA-311-3, Rev.
1, (DUPLEX) Page 1 of 2 (File No.
R24-1).
31
4 ~
P
~
(h
PROCEDURE CH1NGE 1PPROVlh FORN 1.
PC1F XO. -5 7- 01'47 2 ~
PlGE 1
Or 3 3.
PROCEDURE XO. PD-GA,- K[I REV.
4.
FORN ensERI REvxszox 5.
PROCEDUR TITLE 4~
P~~~
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RZQUESTED CH1NGE 6.
PROCEDURE TYPE'ORC[~
gg.eAa 8.
RE15ON fOR CHANGE 9.
RECONNEXDED FOR PERMlNQfT 5
~ /~AS
/ p// jgggj 5'/ic/S v~
Ja ~~'/p 9'7
.YES
(~ No, EEPIR1TION D1TE 10.
COMP 1
U 15 OR REVERSE SIDE OF THIS FORN.
16.
PER ITEN 1S,IS tOR INP t~7N tQ 18.
1UTHOR I
VlhID S PClt?
~
-)7.W 17.
N1X1GEXEXT REVIEW lelm Se opal iim-wc'.t tatmra t>N @Vent nial. N C0mmS lg QN HgIHQ HI tO ltHNLLHR lL0C! )I a~A.
- 19. gg QUADR l.t
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SUPT.
OF PhlNT 1PPROVlh:
l0ll AIH}h~l.hv. I, Ilgwu!. hy I oI i 20.
REVIEWS MC lQfIS EMN:
'NNNIlMAC210l HQ/IQ. ?lITIlL$:
mmmm:
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8
'AoiE CI 32
V'f J
AO-qA-311 Revision 8
Page 14 of 60
{4) Auxiliary Sofler blowdown effluent b.
The constituents of these waste streams may include the following:
(I)
Tri-Sodium Phosphate (2)
Sodium Sulfate (3)
Phosphoric Acid
{4)
Sul furic Acid
. (5)
Sodfum Hydroxide (6)
Oecontamfnation. solutions c ~
(7)
Negligible amounts of reagent chemicals used for chemistry analysis Evaporator Concentrates in the range of 0-25 weight percent sod'ium sulfate (equivalent) shall be solidified in a liner for final di.sposal.
d.
Evaporator Concentrates sha3 1 not be mixed with any other waste type in final processing.
Mixed Solids a.
The followfng process waste streams are collected either in the Waste Mfx Tanks, Waste Sludge Phase Separator or transferred directly to a liner and are considered Mfxed Sol'fds:
b.
(1)
LRW Filter material and drain liquid (2)
Sump Sludge (3)
Ultrasonic Resin Cleaner She~
The constituents of these waste streams may include the following:
(1)
Ofatomaceous Earth (2)
Powdered Resins (3)
Fibrous material 33
)
AD-QA-311 Revision 8
P.age 15 of 60 (4)
Carbon material (5)
Corrosion products (6)
Various solids and dirt in small concentrations c.
Hixed Solids may be solidified or dewatered for final disposal in either steel liners or High Integrity Containers, (s~~e
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d.
Each waste stream shall be processed separately.
Powdered Resin a.
~ b.
c ~
The Reactor Water Cleanup System and Fuel Pool Cooling and Cleanup System filter/demineralizer waste are collected in the RWdU Phase Separator and should be allowed to decay for 60 days.
This waste type is considered Powdered Resin.
The constituents of these waste streams may include anion and cation powdered resin, corrosion and dirt'emoved from the primary coolant.
Powdered Resin shall be dewatered in High Integrity Containers.
If this waste must be solidified, a
LCO is in effect for this waste stream and the action statement must be performed.
(Note LCO entered in 1985).
Bead Resin a.
Resins from the Condensate Demineralizers and Liquid Radwaste Demineralizer are collected in the Spent Resin Tank which is considered to be Bead Resin.
b.
c ~
d.
The constituents of these waste streams may include various types of anion, cation and mixed bead resin.
Bead Resin may be solidified or dewatered for final disposal in either steel liners or High Integrity Containers.
Bead Resin may be used to. demineralize Chemical Waste in expoxied steel liners.
The Bead Resin may be solidified or dewatered for final disposal.
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Revision 8
Page 29 of 50 (i )
CNS I 8-120 loaded weight (j)
CNSI 6-80 loaded weight
~ (k)
CNSI 24-INCH FRP loaaea weight:
(1)
Radl ok 500 loaded weight (gn) p~g),y. )1S fooc4,4 ~i~kt
(~~
)QI,K, les lW<J ~i~H 7500 lb 5000 lb 1600 lb 9500 lb.
)+ciao l4.
ipecac lb.
(2)
The maximum concentration of radionuclides with half lives greater than (5) five years that may be disposed of in a High Integrity Container is 350 pCi/cc.
(3)
The following chemicals are prohibited and may not be disposed of in High Integrity Containers.
(a)
Aqua Regia (b)
Bromine (c)
Chromic/Sulfuric Acid (d)
Fuming Sulfuric-Acid (e)
Nitric Acid >50% concentration (f)
Organic peroxides (g)
Phenol-concentrated (h)
Acetone (i)
Butane (j)
Carbon Oisulphide (k)
Chloroform (1)
Ethyl Ether (m)
Ethylene Oichloride (n)
Methyl ene Chl oride (o)
Methyl Ethyl Ketone (p)
Propane 36
r r C
SECTION 4 REPORTS OF EXCEPTION TO THE SSES EFFLUEZT MONITORING PROGRAM Based on a review of the Significant Operating Occurence'Reports (SOORs) for SSES Units 1 and 2 for the report period, there was one case in which effluent monitoring instrumentation was not operable and was not unrestored to operability within the applicable time. period specified in Technical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.
The Unit I and Unit II Circulating Mater blowdown flow recorders were declared inoperable on 2/14/89 after failing their surveillances.
This was caused when mud/debris collected on the Mark VI element resulting in mechanical deformation and unacceptable hysteresis during calib-ration.
The Unit I and Unit II flow elements were replaced with other Mark VI and later, with Mark V type elements.
The Unit II blowdown flow recorder was returned to service 6/3/89.
The Unit I blowdown flow recorder was returned to service 8/24/89. In the interim, the cooling tower blowdown flow rates were estimated using Attachment G of AD-QA-310, Revision 9, for Unit 1, or Attachment H of AD-Qh-310 for Unit II.
These Tables were used to plot the cooling tower blowdown flow rate as a
function of the blowdown valve position.
37
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