ML18040B255

Semiannual Effluent & Waste Disposal Rept for Jan-June 1989. W/890830 Ltr

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. R DOTY,R.L. Pennsylvania Power & Light Co.

RECXP.NAME RECIPIENT AFFXLIATION

SUBJECT:

"Semiannu fluent & Waste Disposal Rept for Jan-June 1989.<< 890 3 1tr.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

NOTES:LPDR 1 COPIES RECEIVED:LTR Semiannual cy Transcripts.

'ENCL Effluent Release Reports SIZE:

05000387 g j

LPDR 1 cy Transcripts. 05000388, D

RECXPIENT COPIES RECIPIENT COPIES XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 LA 3 3 PD1-2 PD 1 1 THADANI,M 1 1 INTERNAL: ACRS 1 1 AEOD/DS P/TPAB 1 1 IRM TECH ADV 1 1 NRR DREP/RPB 10 2 2 NUDOCS-ABSTRACT 1 1 I 01 1 1 RGN1 DRSS/RPB 2 2 02 1 1 EXTERNAL: BNL TICHLER, J03 1 1 EG&G SXMPSON I F 2 2 LPDR 1 1 NRC PDR 1 1 NOTES 2 2

/

h TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

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 Docket Nos. 50-387/NPF-14 PLA-3253 FILE R41-2A 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 PDC

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8909080254 SEm NUAL EFFLUENT 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.. ~ ~ ~ ~ ~ ~ ~ ~ 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.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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'Water Radionuclides and Percent Composition:

Reactor 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........ ~ ~ ~ ~ 26

LIST OF FIGURES PAGE Airborne Effluent Release Points; Location and Detail.

SSES Waterborne Effluents; Release Pathway. 5

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SECTION 1 INTRODUCTION AND SUPPIZMENTAL INFORMATION

~ I INTRODUCTION i 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.

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 e 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 NIT H REACTOR REACTOR BUILDING BUILDING EXHAUST EXHAUST VENT VENT

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158,250 CFM 158.250 CF M ATBO F-110 F ATIXF F 110 F 355.000 CFM 7500 CFM 2iO.IXXICF M AT IIXF'F-12F AT 120 f AT IIXF'F-12' OUTSIDE AIR INTAKE REACTOR BUILDING UNIT I UNIT II EXHAUST STACKS TURBINE TURBINE BUILDING BUILDING DIESEL EXHAUST PLENUM EXHAUST EXHAUST DIESEL GENERATOR BUILDING VENT VENT EL.

MPp EL 525'4" >

CONTROL BUILDING

~s' IMEl Bli'-I 81i'.~11'ADhtASTE

~ r BUILDING

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TURBINE BUILDING UNIT I EL. 676'4" UNIT H

> <<s FIGURE 2: SSES WATERBORNE EFFlUENTS; REf EASE PATHWAY OIFFLISE A SUSQUEHANNA RIVER INTAHE 89, lt I GPM CL ParASLE SE WAGE TREATMENT lqtOOGPMgg RAINFALL FLOw WICKER PLANT I4% GPM (lb) 0 EOOGPM RLRONE R ADI OACTIVL 'RAD'wASTE LOT'OND AREA TREATMENT WATER USES CPM c"b AR6 CPM RAW WATER TREATMENT CRURAL WASTE I4SGPM PLANT TREATMENT PLANT LISEb X lf 45CPM OEMINKRAUZER WASTES RAIN CAL 50 CPM GENERATLO FIOWog EVAPORATION EVAPORA'T ION CHEM ICAl I+, SSO6PM I+,S50 Gal WASTE TREATMENT RAW WATER TREATMEHT WASTES 47d.OOO OPM 4Td.OOO OPM 50 CPM . WATER RECOvLRy FILTER CONDENSER CI CL IAICELLAI+)LE HEAT EXCHAHOERS CI GPg POND 45GPM MAKE u EMtr<EHCy I ~ I HEAT

~BCHAHOEqS 4 I tCAT

~~N6EREj. A-- SPRY E VAPORATI ON L I I

CkCAgEHCy~ P-- POND +S aPM L OIESELS I

~ KMEAOEHCy e

L COOLING TO IO.OOO GPM CE*)

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

'f noble gases). This number is calculated based on the expected mix 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).

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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 MPC (uCi/ml) 85Kr m 2 E-4 85Kr 5 E-4 87Kr 4 E-5 88Kr 9 E-5 4 1Ar 7 E-5

>>3Xe m 5 E-4 1 3 3)(e 6 E-4 135Xe m 2 E-4 1 3 5)(e 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

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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.

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 0 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.

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4. Batch Releases

a. Waterborne

1. Number of Batch Releases: 103

2. Total Time Period for Batch Releases: 1.94E+04 minutes

3. Maximum Time Period for a Batch Release: 3.20E+02 minutes

4. Average Time Period for a Batch Release: 1.89E+02 minutes

5. Minimum Time Period for a Batch Release: 2.50E+Ol minutes

6. Average Stream Flow During Period of Release of Effluent into a Flowing Stream: >5.82E+03 gpm (cooling tower bio wdown) 7.62E+06 gpm (Susq. River)

b. Airborne

1. Number of Batch Releases: 0

2. Total Time Period for Batch Releases: NA

3. Maximum Time Period for a Batch Release: NA

4. Aver'age Time Period for a Batch Release: NA

5. Minimum Time Period for a Batch Release: NA

5. Abnormal Releases

a. Waterborne

1. Number of Releases: 0

2. Volume Released: NA

3. Total Activity Released: NA

b. Airborne

1. Number of Releases: 0

2. Total Activity Released: 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 Nucl ide Category Uni t First Quarter Second Quarter A. Fission and Activation Gases

1. Total Release~ Ci 5.35E+01 4.10E+01

2. Average Release Rate for Period uCi/sec 6.88E+00 5.21E+00

3. Percent of Applicable Limit~ 4.85E-02 3.67E-02 B. Iodine-131

1. Total Release Ci >3.55E-04 <5.15E-04 >9.09E-05 <2.40E-04

2. Average Release Rate for Period uCi/sec >4.57E-05 <6.62E-05 >1.16E-05 <3.05E-05

3. Percent of Applicable limit~ >1.94E-03 <2 '2E-03 >4.92E-04 <1.30E-03 C. Particulates

1. Particulates with Half-lives >8 Days Released Ci >2.09E-04 <1.29E-03 >1.27E-04 <1.05E-03

2. Average Release Rate for Period uCi/sec >2.69E-05 <1.66E-04 >1 62E-05

~ <1.34E-04

3. Percent of Applicable Limits >2.08E-04 <1.29E-03 >1.25E-04 <1.04E-03

4. Gross Alpha Activity Released Ci >1.33E-06 <1.34E-06 <1.07E-06 D. Tritium

1. Total Release Ci >1.44E+Ol <2.53E+01 >1.75E+01 <2.06E+01

2. Average Release Rate for Period uCi/sec >1.85E+00 <3.25E+00 >2.23E+00 <2.62E+00

3. Percent of I Applicable Limits >3.79E-02 <6.67E-02 >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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TABLE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1989 AIRBORNE EFFI UENTS (Curies)1 Nuclide First Quarter Second Quarter A. Gases

>>3Xe 5.35E+01 4.10E+01 Total 5.35E+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 >7.38E-OS <1.66E-04 >6.54E-OS <1.51E-04 59Fe >8.57E-07 <1.58E-04 <1.49E-04 58Co >1.28E-06 <6.89E-05 >1.38E-05 <7.48E-OS 60Co >1.32E-04 <2.56E-04 >3.43E-05 <1.55E-04 65Zn >1.37E-06 <1.83E-04 >1.37E-05 <1.78E-04 89Sr <1.83E-06 <4.95E-06 90$ r <6.01E-07 <5.35E-07 1 34Cs <6.32E-05 <5.73E-05 1 37Cs <1.40E-04 <6.11E-05 141Ce <5.11E-OS <4.31E-05 1 44Ce <2.04E-04 <1.79E-04 Total >2.09E-04 <1.29E-03 >1.27E-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.

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'TABLE 4 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1989 WATERBORNE EFFIUENTS SUMMATION OF ALL REHMSES Nucl ide Category Unit First Quarter Second Quarter A. Fission 5 Activation Products

1. Total Release~ Ci >4.23E-02 <5.05E-02 >1.48E-02 <2.08E-02

2. Average Diluted Concentration uCi/ml >2.20E-07 <2.62E-07 >6.11E-08 <8.58E-08

3. Percent of Applicable Limit~ 1.41E-02 4.72E-03 B. Tritium

1. Total Release Ci 5.91E+00 6.92E+00

2. Average Diluted Concentration uCi/ml 3.07E-05 2.86E-OS

3. Percent of Applicable limits 1.02E+00 9.52E-01 C. Dissolved and Entrained Gases

1. Total Release Ci >3.38E-04 <6.02E-02 >5.20E-04 <5.86E-02

2. Average Diluted Concentration uCi/ml >1.76E-09 <3.13E-07 >2 '5E-09 <2.42E-07

3. Percent of Applicable Limit4 >4.39E-03 <7.81E-Ol >5.36E-03 <6.04E-01 D. Gross Alpha Radioactivity Released Ci <8.53E-05 <1.10E-04 E. Volume of Waste Released gal. 6.86E+05 8.85E+05 (Prior to Dilution) liters 2.59E+06 3.35E+06 F. Volume of Dilution Water Used

1. During Periods of gal. >5. 02E+07 >6.32E+07 Release liters >1.90E+08 >2.39E+08

2. Over Entire Period liters'7.78E+08 gal. >7.48E+08

>2.94E+09 >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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I TABLE 5 SEMIANNUAL EFFLUENZ AND WASTE DISPOSAL REPORT - 1989 WATERBORNE EFFI,UENTS (Curi es) 1 Nuclide First Quarter Second Quarter A. Tritium 5.91E+00 6.92E+00 B. Fission and Activation Products 3~Na 1.42E-03 51Cr 2.91E-02 2.13E-03 5~Mn >5.74E-03 <5.80E-03 >2.53E-03 <2.67E-03 55Fe <2.59E-03 8.70E-03 59Fe >1.47E-04 <7.08E-04 >6.45E-06 <6.52E-04 58Co >6.77E-04 <8.64E-04 >1.25E-04 <4.07E-04 60Co >3.54E-03 <3.73E-03 >1.27E-03 <1.59E-03 65Zn >1.12E-03 <1.72E-03 <7.33E-04 76As 4.08E-05 89Sr <1.30E-04 <1.34E-04 90Sr "

4. 15E-05 <2.34E-05

>>Mo <1 68E-03

~ <1.59E-03

>>Tc m 7.09E-05 1.37E-05

>>0Ag m 5.57E-OS 131 I <1.87E-04 <2.01E-04 134Cs >2.31E-04 <4.72E-04 <2.70E-04 1 37Cs >1.70E-04 <4.56E-04 <3.16E-04 141Ce <2.65E-04 <2.42E-04 144Ce <1.17E-03 <1.06E-03 Total >4. 23E-02 <5.05E-02 >1. 48E-02 <2.08E-02 C. Dissolved and Entrained Gases 41Ar <2.70E-05 <2.11E-05 85Kr m <5.95E-05 <3.29E-03 85Kr <5.78E-02 <5.30E-02 87Kr <1.41E-05 <9 '8E-06 88Kr <9.94E-05 <7.12E-05

>>3Xe m <1.31E-03 <1.23E-03

>>3Xe >2.54E-04 <7.18E-04 >3.51E-04 <7.82E-04

>>5Xe m <1.57E-08 <9.67E-09

>>5Xe >8 '8E-05 <1.78E-04 >1.69E-04 <2.29E-04 Total >3.38E-04 <6.02E-02 >5.20E-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.

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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 Destination NONE NOT APPLICABLE O.

14

0 SKHLAHHUAL EFFLUENT AND Date Period 4 TABLE 7 SOLID RADIOACTIVE Jen SPDSN. @PORT CLASS A 1989 - June 30 1989 SOURCE DF MASTEt CQCGISATE CONDENSATE REACTOR IIITKR CND% DENs .REBEN% LIQUID RH FILTERS DEHIRERNJ2ER DEHIHKRALI2KR FUG. POOL CLEWS-II CKVAPORATDR CQHC%) CF,H,S3 SOLIDIFICATION AOEHTt PORTLACI CEIKHT DEHATKRKD 'BIATERED PORTLNO CERN? PORTLIBID CEIKKT TYPE OF COHTAIHERa CARBON STEEL LIHER HIC HIC CARSON STEEL LIER CARBON STEEL LXI%R IsotoPes in units of uCi An-211 lion 0%00Etoo 9%7?Et03 0%IIM 0 OOEtoo 0%00Ktoo 0%00Etoo 0%0OEtoo Ag 0eoOEt 00 0%0OKt 00 3.51E405 0 OODOO ~ 2%92Et 01 C 11 1%93Et05 ~ 3%2SKt01 3 56Kt05 2 62D02 6%?DEt 01 L%3LE401 Co-58 le52Et05 1%5?KtIH 1 79DQS 1%01KIOS 9 SDEtM 1%5SKt05 Co-60 1%32Et OS 1%8SDOS 3 2?Kt06 1%05D 0? 9%RSKt01 . 2%20E406-Cr-51 L%16Et 05 1%50Et OS 9%81Et01 1 OBE40? 5 DSE401 5 Cs-1M 3 SDEtM 2%38EtM 7 SSK401 2% LTEt05 0%00E400 7'K406'%00K400 Cs-137 L%05E401 2eBSEt03 5 ?3Kt0'I leSBEt05 0 OOEtoo =0 OOEtoo Fe 55 L%10D06 L%1BK405 1 73DOS 2 62DOV 1 LSKt06 3.06E407 Fe-59 9 LREtM = 1 3W401 6%'32Et 03 1 28D06 leRLEt01 5%75DOS H-3 2%03Kt 01 9%~4 M 1 RBD01 3%1?Kt 01 1%61Kt M ~

I ~ LSD M I-129 1 LSK401 3 23KtM 1 35Kt01 1 OSEt02 0 OODOO 0 OOE400 Hn-5'I L.R3Kt06 1 BBEt05 1%8SEt 06 1%5BD 07 Le'%Et 05 3%35KtOS Kr 85 0%0OEt 00 0 OOEtoo 0 OOKtoo 0%OOEt 00 0%OOEt 00 0%0OKtoo Hi-63 8.?3D01 2 OLKt01 3 ?3D01 3 26E405 8%36Et01 7%65Kt01 Sr-85 0eooEt M 0eoOEtoo 0 ODEtoo 0%0OEt 00 0%00Etoo 0%00Etoo Sr-90 1%39Et 02 2%61Et 02 7%RSKt02 1%21D 01 1%31Et02 1%3'%402 Tc-99 1%39Kt03 7%99D 02 ?e57D OR . 2%98Et02 0%0OKtoo 5 16E402 2n-65 3%72Et 05 1 50E401 1%26Kt 06 2% 15D 06 2%LSEtM 1%S1D 05 I 131 ?eSSKtol 7%76Kt 0L 2%61Et 02 0%00E400 2%21Et03 0%00DOO 0%ODD OO 0%00Ktoo D%00E400 0%ODD OO Co-57 0%00Etoo 0 OOEtoo Sb-121 0%ODD OO 0%00Etoo 0 OOKtoo 0 OODOO 0%00Etoo 0 OOEtoo Zr-95 0 OOEtoo 0%00Etoo 0 OOKtoo 0 OQDOD 0%ME400 0 OODOO TOTAL ACTIVITY CCL> 5%0?5 0 822 1R%RS7 68,878 L%693 ~

I2% 861 CQHTAIHER VOLUHE Cf t& 1063 ~ 80 531%90 8$ 3 30 135,80 7 11%60 533%70 SOURCE OF MASTEt LIQUID RM FILTERS OILV HASTE SOLIDIFICATION AOEHTt oafeham TYPE OF CONTAINER! STROH8 TIBHT CDHT.

An-201 0%00Etoo 0%00Etoo 0 OOEtM 0 OOEtoo 0%00Etoo 'O.OOEt 00 Ag-lion 0%0OE400 0%00EtM 0%00Et00 0%ODD OO 0%00E400 0%00KI 00 C-11 1%89D01  ?%00K 01 0%00Ktoo 0%0OE400 1% L3Et M O.ODD OO Co-58 1%22EtoS R%69Et 02 0 OODOO 0 OOEtoo 1%09K405 0%0OK400 Co-60 1%'tBEf 0? le26Kt M 0%00Etoo 0 OODOO 8%0TEt05 0 OOEtoo Cr-51 1%2LK406 6%29EI 02. 0%00DOO 0%00Et 00 Re35Et 05 0 OOKtoo Cs-LM 0%00Etoo OeoOEtoo 0%0OEtOO 0 OODOO 0%0DEtoo 0 OODOO Cs-13? 0%0OEtoo 0%00Et M 0%00KtDO 0 OODOO 0%00Et 00 0%ODD 00 Fo-55 '%11E408 8%12E403 0%0ODOO 0%00Et 00 6%60D OS 0%ODD 00 Fe-59 3%5?EtoS 0%0OE400 0%00E400 0 OODOO Le?3K%01 OeOOEt 00 H-3 ~ 3%36Et03 00 'eOOEt 0%OOKtoo 0%00Et00 1% 12Et02 D OOEtoo I-129 0%ODD 00 0 OODOO. 0 ODDOO 0%ODD 00 0%00Et M 0%00Etoo Hn-51 2 12Eto? Le~i D3 O.OODOO OeOOKtoo 1%15Et06 0 OOE400 Kr-85 5%56E406 0%00Et 00 0%00DOO 0 OODOO 0%00Kt 00 O.OOE400 Hi-63 1%36K405 7 ?9Ktol.. 0%00DOO 0%ODD 00 2%9LE401 0 OOEtoo Sr-85 2%29D 01 0%00Etoo 0 OODOO 0 OOE400 0%00Kt 00. 0 OODOO Sr-90 2 2'IKt02 0%00Kt 00 0%00Ktoo 0%ODD 00 0%00Ktoo 0%00DOO Tc-99

~

9%1?Kt02 7 SREt02. 0%00E400 0%ODD 00 8126D M 0%00DOO Zn-65 1%9?Kt 06 'Ie91Kt02 0%ODD 00 0 OODOO 2%19Et05 0 OOE400 I-131 0 OODOO 0%ODD OO 0 OOEt00 0 OOKtoo 0%0OEI 00 0 OOE400 Co-57 0%0DKtoo 0 OOE400 0 OOKtoo 0%00E400 0%00DOO 0 OOKtoo

~ Sb-121 6%82Et03 0 OOEtoo 0%00DOO 0%0ODOD 0 OQKtoo ~

O.OOK40O Zr-.95 R%20D 01 0%00K400 0 OODDO 0%ODD 00 0%0OEtoo O.ODD OO TOTAL ACTIVITY CCD 161%298 0%011 0%000 0 QOO 9%251 0'00 0 000 COHTAIHER VOLIRIE Cft3> 684%70 ll?%00 ~

0%00 2888%'IO "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 Activit (uCi) X of Total Am-241 O.OOE+00 O.OOX Ag-110m 9.77E+03 Oe195 C-14 1.93E+05 3.81$

Co-58 1.52E+05 2.995 Co-60 1.32E+06 25.96%

Cr-51 1.46E+05 2.885 Cs-134 3.50E+04 0.695 Cs-137 1.05E+04 0.21%

Fe-55 1.40E+06 27.56K Fe-59 9.12E+04 1.80%

H-3 2.03E+04 0.40$

I-129 1.15E+04 0.234 Nn-54 1.23E+06 24.21$

Kr-85 O.OOE+00 0.00$

Ni-63 8.73E+04 1.72K Sr-85 O.OOE+00 0.005 Sr-90 4.39E+02 0.01$

Tc-99 1.39E+03 0.035 2n-65 3.72E+05 7.33%

I-131 7.96E+01 0.005 Co-57 7.76E+01 O.OOX Sb-124 O.OOE+00 0. 00'A Zr-95 O.OOE+00 0.00%

TOTAL ACTIVITY 5.08E+06 100.00K 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 O.OOE+00 O.OOX Ag-110m O.OOE+00 O.OOX C-14 3.29E+04 4.01%

Co-58 1.57E+04 1.91%

Co-60 1.89E+05 23.05Ã Cr-51 1.50E+05 18.24%

Cs-134 2.38E+03 0.29%

Cs-137 2.85E+03 0.35%

Fe-55 1.48E+05 18.01%

Fe-59 1.34E+04 1.63$

H-3 9.44E+03 le15X I-129 3.23E+03 0.39%

Mn-54 1.88E-05 22.89%

Kr-85 O.OOE+00 0.00Ã Ni-63 2. 01E+04 2.44K Sr-85 O.OOE+00 0.005 Sr-90 2.64E+02 0.03%

Tc-99 7.99E+02 0.10%

2n-65 4.50E+04 '.48%

I-131 2.64E+02 0. 03'4 Co-57 O.OOE+00 O.OOX Sb-124 O.OOE+00 0.00%

Zr-95 O.OOE+00 0.00$

TOTAL ACTIVITY 8.22E+05 100.00'X 17

TABLE 10 Sour ce of Waste: Condensate Demineralizer Type of Container: HIC Method of Process: Dewatered

~Isoto es Activit (uCi) X of Total Am-241 O.OOE+00 O.OOX Ag-110m O.OOE+00 O.OOX C-14 3.56E+05 2.90K Co-58 4.79E+05 3.90$

Co-60 3.27E+06 26.67K Cr-51 9. 81E+04 0.805 Cs-134 7.69E+04 0.63%

Cs-137 5.73E+04 0.47%

Fe-55 4.73E+06 38. 59'A Fe-59 6.32E+03 0.05$

H-3 1.28E+04 0.10K I-129 1.35E+04 0.11%

Mn-54 1.86E+06 15.20%

Kr-85 O.OOE+00 0.00%

Ni-63 3.73E+04 0.30K Sr-85 O.OOE+00 0.00Ã Sr-90 7.29E+02 0. 01'X Tc-99 7.57E+02 0. 01'X Zn-65 1.26E+06 10.24%

I-131 2.24E+03 0.02%

Co-57 O.OOE+00 0. 00'X Sb-124 O.OOE+00 0. 00'X Zr-95 O.OOE+00 0.00%

TOTAL ACTIVITY 1.23E+07 100.00K 18

TABLE 11 Source of Waste: Reactor Water Fuel Pool Clean-up Type of Container: HIC Method of Process: Dewatered

~Isoto es Activit (uCi) X of Total Am-241 O.OOE+00 O.OOX Ag-110m 3.54E+05 0.51%

C-14 2.62E+02 O.OOX Co-58 1.04E+06 1.51%

Co-60 1.05E+07 15.24%

Cr-51 1.08E+07 15.68%

Cs-134 2.17E+05 0.32%%d Cs-137 1.98E+05 0.29%%d Fe-55 2.62E+07 38.04%%d Fe-59 1.28E+06 1.86%

H-3 3. 47E+01 0.00%%d I-129 1.05E+02 0.00%%d Mn-54 1.58E+07 22.94K Kr-85 O.OOE+00 O.OOK Ni-63 3.26E+05 0.47%%d Sr-85 O.OOE+00 0.00%%d Sr-90 1. 21E+04 0.02%%d Tc-99 2.98E+02 O.OOX Zn-65 2. 15E+06 3.12K I-131 0.00E+00 0.00%%d Co-57 O.OOE+00 0.00%%d Sb-124 O.OOE+00 0.00%%d Zr-95 O.OOE+00 O.OOX TOTAL ACTIVITY 6.89E+07 100.00%

19

5 P

0

TABLE 12 Source of Maste: Condensate Demineralizer Regeneration (Evaporator Concentrates)

Type of Container: Liner Method of Process: Solidification Portland Cement

~Isoto es Activit (uCi) X of Total Am-241 O.OOE+00 0.00Ã Ag-110m O.OOE+00 O.OOX C-14 6.70E+04 3.96K Co-58 9.50E+03 0.56%

Co-60 9.29E+04 5.49%

Cr-51 5.06E+04 2. 99'5 Cs-134 O.OOE+00 0.00%

Cs-137 O.OOE+00 O.OOX Fe-55 1. 19E+06 70.52%

Fe-59 '1. 61E+04 0.71%

H-3 1. 61E+04 0.95%

I-129 O.OOE+00 O.OOX Mn-54 1.46E+05 8.605 Kr-85 O.OOE+00 O.OOX Ni-63 8.36E+04 4.94K Sr-85 O.OOE+00 0.00%

Sr-90 1.31E+02 0.01%

Tc-99 O.OOE+00 0.00K Zn-65 2. 15E+04 1.27%

I-131 O.OOE+00 0.00K Co-57 O.OOE+00 0.00Ã Sb-124 O.OOE+00 0.00%

Zr-95 O.OOE+00 0.00%

TOTAL ACTIVITY 1.69E+06 100.00K 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 Activit uCi) X of Total Am-241 O.OOE+00 0.00%

Ag-110m 2.92E+04 0. 07'I C-14 1.31E+04 0.03%

Co-58 1. 56E+05 0.36%

Co-60 2.20E+06 Se13%

Cr-51 5.74E+06 13.40%

Cs-134 O.OOE+00 O.OOX Cs-137 O.OOE+00 O.OOX Fe-55 3.06E+07 71. 29'A Fe-59 5.75E+05 1.34%

H-3 4. 18E+03 0.01%

I-129 O.OOE+00 0.00%

Nn-54 3.35E+06 7.81%

Kr-85 O.OOE+00 0.00%

Ni-63 7.65E+04 Oe18%

Sr-85 O.OOE+00 0.00%

Sr-90 1.34E+02 O.OOX Tc-99 5.46E+02 O.OOX Zn-65 1. 61E+05 0. 37'5 I-131 O.OOE+00 O.OOX Co-57 O.OOE+00 O.OOX Sb-124 O.OOE+00 O.OOX Zr-95 0:OOE-00 O.OOX TOTAL ACTIVITY 4.29E+07 100.00K 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 Activit uCi) X of Total Am-241 O.OOE+00 O.OOX Ag-110m O.OOE+00 0.00$

C-14 1.89E+04 0.01$

Co-58 1.22E+06 0.74%

Co-60 1.48E+07 9. 02'5 Cr-51 4. 21E+06 2.56K Cs-134 O.OOE+00 O.OOX Cs-137 O.OOE+00 O.OOX Fe-55 1.11E+08 67.71%

Fe-59 3.57E+06 2.18Ã H-3 3.36E+03 O.OOX I-129 O.OOE+00 0.00Ã Mn-54 2. 12E+07 12.90%

Kr-85 5.56E+06 3.38%

Ni-63 4.36E+05 0.27%

Sr-85 2.29E+04 0.01Ã Sr-90 2.24E+02 0.00%

Tc-99 9. 17E+02 O.OOX Zn-65 1.97E+06 1.20%

I-131 O.OOE+00 O.OOX Co-57 O.OOE+00 0.00%

Sb-124 6.82E+03 0. 00'X Zr-95 2.20E+04 0.015 TOTAL ACTIVITY 1.64E+08 100.00'X 22

t I

~ 4

TABLE 15 Source of Waste: Non-Compactable Trash Type of Container: Strong Tight Container

~Isoto es Activit (uCi) X of Total

.Am-241 O.OOE+00 O.OOX Ag-110m O.OOE+00 O.OOX C-14 7. OOE+01 0. 01'5 Co-58 2.69E+02 1.96K Co-60 1.26E+03 9e16%

Cr-51 6.29E+02 4.57K Cs-134 O.OOE+00 O.OOX Cs-137 O.OOE+00 O.OOX Fe-55 8.42E+03 61.22Ã Fe-59 O.OOE+00 O.OOX

"'-3 2.00E+00 0.01K I-129 O.OOE+00 0. 00'X Nn-54 1.84E+03 13.38%

Kr-85 O.OOE+00 O.OOX, Ni-63 7.79E+01 0. 57%

Sr-85 O.OOE+00 O.OOX Sr-90 O.OOE+00 0.00%

Tc-99 7.62E+02 5.54K 2n-65 4.94E+02 3.59%

I-131 'O.OOE+00 O.OOX Co-57 O.OOE+00 0. 00'X Sb-124 O.OOE+00 O.OOX Zr-95 O.OOE+00 0.00$

TOTAL ACTIVITY 1.38E+04 100.00'X 23

I TABLE 16 Source of Waste: Compacted Trash Type of Container: Strong Tight Container

~Isoto es Activit uCi) X of Total Am-241 O.OOE+00 0.00%

Ag-110m O.OOE+00 O.OOX C-14 1. 13E+03 0. 01'X Co-58 1.09E+05 l. 18'5 Co-60 8.07E+05 8. 73'5 Cr-51 2.35E+05 2.54K Cs-134 O.OOE+00 O.OOX Cs-137 O.OOE+00 0.00%

Fe-55 6.60E+06 71.30K Fe-59 1.73E+04 0. 19'5 H-3 4.12E+02 O.OOX I-129 O.OOE+00 O.OOX Mn-54 1. 15E+06 12. 48'5 Kr-85 O.OOE+00 O.OOX'.31%

Ni-63 2.91E+04 Sr-85 O.OOE+00 O.OOX Sr-90 O.OOE+00 O.OOX Tc-99 8.26E+04 0.89Ã 2n-65 2. 19E+05 2.36K I-131 O.OOE+00 O.OOX Co-57 O.OOE+00 O.OOX Sb-124 O.OOE+00 O.OOX Zr-95 O.OOE+00 O.OOX TOTAL ACTIVITY 9.25E+06 100.00K 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 Estimated Total Error,

1. Airborne Effluents

a. Fission and Activiation Gases 15.9 r.

b. I-131 13.3 r.

c. Particulates 15.8 r.

d. Tritium 5.7 r.

2. Waterborne Effluents

a. Fission and Activation Products 5.o r.

b. Tritium 3.3 r.

c. Dissolved and Entrained Gases 8.4 r.

d. Gross Alpha Radioactivity None Dectected

e. Volume of Waste Released (Prior to Dilution)

f. Volume of Dilution Water Used During Period 15.0 r.

3. Solid Wastes

a. Condensate Demineralizers (Bead Resin Dewatered) 15.1 r.

b. Reactor Mater Clean-up (Fuel Pool Dewatered) 15.1 r.

c. Condensate Demineralizer Regeneration (Evaporator Concentrates Solidified) 15.1 r.

d. Liquid RW Filters (Filter Media, Sludge and Evaporator Concentrates Solidified) 15.1 r.

e. Non-Compactable Trash 25 r.

f. Compacted Trash 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 ~

~ (I 0 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

1. 2.

PROCEDURE CHANGE APPROVAL FORM PCAF NO. - "QOS0 PAGE 1 OF 3.

4~ -

i. FORM NUlSER/ REVISION PROCEDURE NO. 8 - 3f~ REV. 8 Rn- pa-'J]l J Ae. (

5.

Sg PROCEDURE geo/<<ra TITLE 4, Ciaeoso Cerrd~a f Pi-ogrrrroos 6.

N-PORC ~

PROCEDURE TYPE:

7. REQUESTED CHANGE g //isa /ssc~ F~roi rrr0 - P8'-g//- g arri'+~~ )

f ~4

+g 4'.

REASON FOR CHANGE F Q - ycrFv": gHorrros 4c~~/

W~csas~7~M Mr ooo~,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 VALID 17- lQNAGEMENT REVIEW fOR QMPLEMEbeTAT PCAF T a. (Q giDl lOT RlgOIRN ll01-PORC) tgYR$ ( lm b. (~ giDl PRRPORIN ($ bl RRYRR5l $ IDll, l0 COMRT$

c. (Q lgl giDR RlgOIRN PRIOR TO iPPROBL Pll bLOC! Il

18. A ORI

19. H{}A R 20. REVIEWS

] lgi giDR lOT RlglHRN, PORC lbbTIRO lUlHRR:

b.( j lgi giDR PlbtORm, l0 COONT$ 'lbPOlbIRLR $ lCTIOl RRRDIM. IRITIlL$:

c.( j lgi glOR PbltORM, COINlT5 iTTlClN RRCOMNlD: ( ] Yl5 ( j l0 RRYISN: ( ) YR5 ( I RO I O 21.~ SUPT.~ Of PLANT APPROVAL:

OPS TRAINING INFO OTHER UNIT SA'K CHANGE CI HOT BOX C1 PCI 5B NONE C1 POQ hlHg~l, ha l, hgn. hy l st 2 30

k,'-g9 - 0050 t~a~4+ +~ C PpME ~ Ot. AD-QA-311 Revision 8 Page 57 of 60 SUSQUEHANNA GUARANTEED WASTE VOLUME RECORD

1. Date Liner number Z. Waste Type

3. Liner Type

4. Burial Volume

5. Waste Volume 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. Waste Vol. ft ) /oo

10. Remarks:

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

1. 2~

PROCEDURE CH1NGE 1PPROVlh FORN PC1F XO. -5 7- 01'47 PlGE 1 Or 3

3. 4. FORN ensERI REvxszox PROCEDURE XO. PD- GA,- K[I REV.

5. PROCEDUR TITLE 6.

4~ P~~~ C M'l ~p PROCEDURE

[~

TYPE'ORC

7. RZQUESTED CH1NGE gg.eAa

8. RE15ON fOR CHANGE

~ /~AS

/ p// jgggj 5'/ic/S v~ ~~'/p Ja 9'7

9. RECONNEXDED FOR PERMlNQfT 5 .YES

(~ No, EEPIR1TION D1TE

10. COMP 1 U 15 OR REVERSE SIDE OF THIS FORN.

16. PER ITEN 1S,IS VlhID 17. N1X1GEXEXT REVIEW tOR INP S PClt? lelm Se opal iim-wc'.t t~7N tQ tatmra t>N @Vent nial. N C0mmS lg QN HgIHQ HI tO ltHNLL HR lL0C! )I

~ -)7.W

18. 1UTHOR I a~A.

19. gg QUADR 20. REVIEWS l.t ).5Q QN Nt RgflHl MC lQfIS EMN:

s.t I mi Ne nueam. a coams 'NNNIlMAC210l HQ/IQ. ?lITIlL$:

4 t t Kl 310l HOON, CNSN5 1TtlNS mmmm: t I m t I N0 llTI5N: tQ TQ tQ N

21. SUPT. OF PhlNT 1PPROVlh:

OPS TRAINIAC Idio OTHE(. lPifIT SA.'K C.tAltCK Q HOT BOX CI PC? 8

'AoiE CI l0ll AIH}h~l.hv. I, Ilgwu!. hy I oI i 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 (7) Negligible amounts of reagent chemicals used for chemistry analysis c ~ 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 fol lowfng 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:

(1) LRW Filter material and drain liquid (2) Sump Sludge (3) Ultrasonic Resin Cleaner She~

b. 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 >>~~> ~ ~4 4~ <le~ 4~i~)

d. Each waste stream shall be processed separately.

Powdered Resin

a. 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.

~

b. The constituents of these waste streams may include anion and cation powdered resin, corrosion and from the primary coolant.

dirt'emoved c Powdered Resin shall be dewatered in High Integrity If

~

Containers. 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. The constituents of these waste streams may include various types of anion, cation and mixed bead resin.

c~ Bead Resin may be solidified or dewatered for final disposal in either steel liners or High Integrity Containers.

d. Bead Resin may be used to. demineralize Chemical Waste in expoxied steel liners. The Bead Resin may be solidified or dewatered for final disposal.

1. 2~

PROCEDURE CONGE 1PPROVlL tORM PCif NO. /- 9-0~>~ tiGE 1 Of

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-. ~ NO) EZPIR1TION DlTE 10 1 TSRU 15 OW MORSE SIDE OF TNIS FORM.

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OPS TRAI )I )G IHTO OTHER I%IT - SA'K CH)OCE HOT BOX PCI VASE tMN AHA~I, hr. I. hying@ hy I ot l 35

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nv qn v Revision 8 g- gP - 0357 Page 29 of 50 (i ) CNS I 8-120 loaded weight 7500 lb (j) CNSI 6-80 loaded weight 5000 lb

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(k) CNSI 24-INCH FRP loaaea weight: 1600 lb (1) Radl ok 500 loaded weight 9500 lb.

(gn) p~g),y. )1S fooc4,4 ~i~kt )+ciao l4.

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(2) The maximum concentration of radionuclides with half lives greater than (5) five years thatis may be disposed of in a High Integrity Container 350 pCi/cc.

and may not (3) The following chemicals are prohibited 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 or i de (o) Methyl Ethyl Ketone (p) Propane 36

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SECTION 4 REPORTS OF EXCEPTION TO THE SSES EFFLUEZT MONITORING PROGRAM Based on a review unrestored 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 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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