ML18026A236

Semiannual Effluent & Waste Disposal Rept for Jan-June 1990 for Susquehanna Steam Electric Station. W/900829 Ltr

ML18026A236
Person / Time
Site:	Susquehanna
Issue date:	06/30/1990
From:	Carson B, Doty R, Shank K PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
PLA-3433, NUDOCS 9009070136
Download: ML18026A236 (119)

Text

ACCELERATED DISTIUBUTION DEMONST$&TION SYSTEM REGULATOR INFORMATION DISTRIBUTION STEM (RIDE)

ACCESSION NBR:9009070136 DOC.DATE: 90/06/30 NOTARIZED: NO DOCKET 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 a Light Co.

SHANK,K.E. Pennsylvania Power & Light Co.

DOTYFR.L. Pennsylvania Power -& Light Co.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

"Semiannual Effluent & Waste Disposal Rept for Jan-June 1990 for Susquehanna Steam Electric Station." W/900829 ltr. D DISTRIBUTION CODE: ZE4SD TITLE: 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual I ENCL Effluent Release Reports 2 SIZE:

/

NOTES:LPDR 1 cy Transcripts. 05000387 LPDR 1 cy Transcripts. 05000388 D

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D D

NOTE TO ALL "RIDS" RECIPIENTS:

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0,,

Pennsylvania Power Two North Ninth Street ~

8 Allentown, PA 18101

~

Light Company

~ 215/7706151 Harold W. Keiser Senior Vice President-Nuclear 215l770.4194 AU6 2 9 3990 Mr. Thomas T. Martin 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-3433 FILE R41-2A and 50-388/NPF-22

Dear Mr. Martin:

In accordance with 10CFR50.36a(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, 1990.

Very truly yours, H. W. Keiser Attachment cc:~NRC Document Control Desk (ongxna1)3 NRC Region I Mr. G. S. Barber, NRC Resident Inspector Mr. M. C. Thadani, NRC Project Manager AQ ep ~p)C 9009070i36 q00630I PDR ADOCK 05000387 R PNU

~O'5009070136

@A.Ning

~sic S~~

SEMIANNUAL EFFLUENT 5 WASTE DISPOSAL REPORT FOR JANUARY - JUNE 1990

s~~~g~6~e+4'.

PENNSYLVANIA POWER Et LIGHT COMPANY TWO NORTH NINTH STREET ALLENTOWNt PENNSYLVANIA 18101-1179 AuGusT 1990

SUSQUEHANNA STEAM ELECTRIC STATION SEMIANNUAL EFFLUENT AND MASTE DISPOSAL REPORT REPORT PERIOD: 01/01/90 06/30/90 Prepared by:

B. H. Carson Health Physicist Reviewed:

K. E. Shank Env ental and Chemistry Group Supervisor Nuclear Approved:

R. L. Doty Supervisor Radiologic & Environmental Services Pennsylvania Power k Light Company Two North Ninth Street

'Allentown, Pennsylvania 18101

TABI E OF CONTENTS SECTION PAGE

1. Introduction and Supplemental Information......... 1

2. Effluent'nd Waste Disposal Data.................. 9

3. Changes to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program...... 26

4. Reports of Exception to the SSES Effluent Monitoring Program... ~ ~ ~ ~ ~ ~ o 86

LIST OF TABLES PAGE Table 1: Supplemental Information. 6 Table 2: Airborne Effluents- Surrmation of All Releases........ 10 Table 3: Airborne Effluents.

Table 4: Waterborne Effluents- Sunmation of All Releases...... 12 Table 5: Waterborne Effluents............. 13 Table 6: Waste Disposition.. 14 Table 7: Principal Radionuclides and Percent Composition:

liquid Radwaste Filter Media HIC (Dewatered)....... 16 Table 8: Principal Radionuclides and Percent Composition:

Condensate Demineralizer/Radwaste Demineralizer-HIC (Dewatered). 17 Table 9: Principal Radionuclides and Percent Composition:

Condensate Demineralizer/Radwaste Demineralizer-Carbon Steel Liner (Dewatered).................. 18 Table 10: Principal Radionuclides and Percent Composition:

Sump Sludge Carbon Steel Liner (Solidification Portland Cement)................ .. .... ... 19 Table ll: Principal Radionuclides and Percent Composition:

Cartridge Filters HIC....,.. 20 Table 12: Principal Radionuclides and Percent Composition:

Compacted DAW Strong Tight Container 21 Table 13: Principal Radionuclides and Percent Composition:

Non-Compactable DAW Strong Tight Container......... 22 Table 14: Previous Report Correction. 23 Table 15; Estimated Total Errors Associated with Effluent Measurements 24 Table 16: Effluent Data Not Available for Previous Semiannual Report.................................... 25

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

SSES Materborne Effluents; Release Pathway..

SECTION 1 INTRODUCTION AND SUPPLEt KNTAt INFORMATION

I INTRODUCTION The Susquehanna Steam Electric Station (SSES) is located in Salem Township, Luzerne 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 hR 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 conmercial 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, 1990 to June 30, 1990. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Conmission staff of changes to PPM,'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 sunmation 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 13 present a characterization of the solid radioactive waste shipped offsite.during the report period. Included are the volumes and millicurie 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 14 contains a correction for the July 1 to December 31, 1989 report period. This correction reflects the manifest change submitted to Chem-Nuclear for the Dewatered RWCU Filter Media shipment made August 28, 1989 (Reference SOOR 1-90-172).

Table 15 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 16 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 UNIT H REACTOR REACTOR BUILDING BUILDING EXHAUST EXHAUST VENT VENT 15&250 CAI 16&260 CFM AT 00-110 DEG F -AT 00-110 MG F

~~

385.000 CFH 2411000 CAJ 0 OUTSIDE AIR INTAKE AT 100-120 DEG F AT 100-120 DEG F REACTOR BUILDING EXHAUST SfACKS EXHAUSf PLENUll UNM I TURBINE UNIT II 0

I DE1SEL BUILIXNG 7~ CFM TURBINE W

DHSEL GENERATOR BUILDING EXHAUST AT l20 DEG F BUILDING Q, ~

~

~

~

%r r r

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VENT EXHAUSl VENT ec I tD

'h r '

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f rr Q CONTROL BUILDING I

I ID RADNASrE BUILDING 0

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TURENE BL1LDING UNIT H

Figure 2: SSES Waterborne Effluents:

Release Pathway INTAKE 39.I2) CPM SUSQUEHANNA RIVER ~ jl PM D IFFUSKR 3I CPM POTABLE SEWAGE RA I V FALL TREA TNEN T FLOW WATER I0.200 0 PM )28)

PLANT a IIj G 8 IIB) 0 200 CPM RADIOACTIVE PARKING RADWASTK 0-200 AREA LOT AL TREATNEVT WATKl USES POND C P 126 CPM lAW WAtER TREATMENT GQI ERAL PLANT WASI'K I63 GPM PLANT 'flEAtMENT USES lj CPM OEMINKRALITERWASTES 30 CPM DENINKRAL)2Kl RAIVFALL EVAPORATION X CQI KRA TYI)

EVAPORATION FLOW IIB)

I 6.3 30 CPM j

I 6. 3 0 CPM CHEMICAL WASTE

'TREA TN EN T

<57,000 CPM F07.000 GPM lAW WAtKR TREATMENT WASTES S S A 0 CPM WATER Q, RECOVERY FILTKl 410.000 CONDQISBR IS C.

HEAT KZQIANGERS 30.000 0 GPM I I AI POVD < CPM QIKRGQ) CY MARK UP EMKRCQIGY HEAT HEAT SPRAT EICHANGERS &I A POND KMKRCQICY DE) SKLS P~

A EMERGENCY EVAPORATION INTAKE COOLINC TOWER BLOWDOWN 63 GPM l0.000 GPM IIA)

TABLE 1 SEMIANNUAL EFFIUENT k, WASTE DISPOSAL REPORT DATA PERIOD: JANUARY JUNE 1990 SUPPLHKNTAL 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 of noble gas radionuclides presented in Table 4.4 of the SSES Final Environmental Statement, NMM-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).

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. Maximum 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 41Ar 7 E-5 133Xe m 5 E-4 133Xe 6 E-4

>>5Xe m 2 E-4 1 3 5)(e 2 E-4 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 system which incorporates a data reduction program to determine radionuclide composition in

terms of specific activity. Data tapes from the continuous vent monitors are used to determine the average concentration of noble gases. The Ge(I i) 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(I i) 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(I i) system. Flow rate corrections are performed as for iodines. When the continuous vent monitors are out of,service, particulates are continuously I

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 gaama 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(I i) 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.

4. Batch Releases

a. Waterborne

1. Number of Batch Releases: 91

2. Total Time Period for Batch Releases: 1.66E+04 minutes

3. Maximum Time Period for a Batch Release: 3.00E+02 minutes

4. Average Time Period for a Batch Release: 1.74E+02 minutes

5. Minimum Time 'Period for a Batch Release: 2.00E+01 minutes

6. Average Stream Flow During Period of Release of Effluent into a Flowing Stream: >7.45E+03 gpm (cooling lowdown) tower b

9.86E+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. Average 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 EFFI VENT AND WASTE DISPOSAt'ATA

TABLE 2 SEMIANNUAL EFFIUENT AND WASTE DISPOSAL REPORT 1990 AIRBORNE EFFLUEVXS SUMMATION OF AU RELEASES Nuclide Category Unit First Quarter Second Quarter A. Fission and Activation Gases

1. Total Releasei Ci >3.85E+00 <4.22E+02 <4.50K+02

2. Average Release Rate for Period uCi/sec >4.95E-01 <5.43E+01 <5.72E+01

3. Percent of Applicable Limit~ >3.49E-03 <3.83E-01 <4.04E-01 B. Iodine-131

1. Total Release Ci <1.34E-04 <1.73E-04

2. Average Release Rate for Period uCi/sec <1.72E-05 <2.20E-05

3. Percent of Applicable limit2 <7.33E-04 <9.36E ~ -04 C. Particulates

1. Particulates with Half-lives >8 Days Released Ci >3.07E-06 <8.90E-04 <1.14E-03

2. Average Release Rate for Period uCi/sec >3.95E-07 <1.14E-04 <1 46E-04

~

3. Percent of Applicable Limit~ >3.06E-06 <8.87E-04 <1.13E-03

4. Gross Alpha Activity Released Ci >4.73E-07 <9.66E-07 <5.74E-07 D. Tri tium

1. Total Release Ci >1.16E+Ol <1.35E+01 >1.24E+Ol <1.40E+01

2. Average Release Rate for Period uCi/sec >1.49E+00 <1.74E+00 >1.58E+00 <1.78E+00

3. Percent of Applicable I imits >3 '6E-02 <3.56E-02 >3.23E-02 <3.65E-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 (4878 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.

10

TABlE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 19SO AIRBORNE EFFl,UENTS (Cur i es) 1 Nuclide First Quarter Second Quarter A. Gases 1 33)(e >3.85E+00 <4.22E+02 <4.50E+02 B. Iodines 131I <1.34E-04 <1.73E-04 C. Particulates with Half-lives > 8 d 64Mn >3.07E-06 <9.76E-05 <1.20E-04 69Fe <1.32E-04 <1.63E-04 90Co <5.60E-05 <7 '5E-05 60Co <1.21E-04 <1.52E-04 65Zn <1.49E-04 <1.S4E-04 89Sr <3.01E-06 <2.55E-06 90$ r <4.96E-07 <4.22E-07 134Cs <5.26E-05 ,

<7.40E-05 137Cs <5.98E-05 <7.26E-05 141Ce <4.36E-05 <5.82E-05 1 44Ce <1.75E-04 <2.34E-04 Total >3.07E-06 <8.90E-04 <1.14E-03 1Notation: The first value presented (>) includes only activity positively detected at the SSX 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 95K CL.

11

TABLE 4 SEh/IANNUAL EFHUENT AND WASTE DISPOSAL REPORT 1990 WATERBORNE EFFLUENIS SUCTION OF ALL RELEASES Nuclide Category Uni t First Quarter Second Quarter A. Fission Ec Act ivation Products

1. Total Release~ Ci >1.61E-02 <1.75E-02 >3.07E-04 <7.99E-03

2. Average Diluted Concentration uCi/ml >9.53E-08 <1.04E-07 >8.03E-10 <2.09E-08

3. Percent of Applicable Limit~ 3.46E-04 5.90E-05 B. Tritium

1. Total Release Ci 6.53E+00 2.58E+01

2. Average Diluted Concentration uCi/ml 3.86E-05 6.80E-05

3. Percent of Applicable limit> 1.29E+00 2.27E+00 C. Dissolved and Entrained Gases

1. Total Release Ci >7.72E-05 <1.23E-02 >5.91E-04 <3.46E-02

2. Average Diluted Concentration uCi/ml >4.57E-10 <7.28E-08 >1.56E-09 <9.12E-08

3. Percent of Applicable Limit4 >1.14E-03 <1.82E-01 >3.89E-03 <2.28E-01 D. Gross Alpha Radioactivity Released Ci <3.94E-05 <1.42E-04 E. Volume of Waste Released gal. 3.47E+05 1.02E+06 (Prior to Dilution) liters 1.31E+06 3.86E+06 F. Volume of Dilution Mater Used 1~ During Periods of gal. >4.43E+07 >1.00E+08 Release liters >1.68E+08 >3.79E+08

2. Over Entire Period gal. >9.14E+08 >1.03E+09 liters >3.46K+09 >3.89E+09

~Notation: The first value presented (>) includes only activity positively detected at the 95K 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 95/ CL.

~Based on quarterly dose limits from liquid effluents.

38ased on the hlaximum Permissible Concentration for 3H in effluents to unrestricted areas (3.0 E-03 uCi/ml).

4Based on the most restrictive hfaximum Permissible Concentration for a noble gas, 4.0 E-05 uCi/ml (S~Kr) from SSES Tech Spec Table 3.11.1.1-1.

12

TABLE 5 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1990 WATERBORNE EFFLUENTS (Curies)1 Nuclide First Quarter Second Quarter A. Tritium 6.53E+00 2.58E+01 B. Fission and Activation Products 51Cz 6.77E-05 54Mn >1.49E-04 <2 '4K-04 >2.66E-04 <4.98E-04 55Fe 1.58E-02 <3.87E-03 59Fe <1.23E-04 <3.33E-04 58Co <5.74E-OS <1.51E-04 60Co >7.97E-05 <1.93E-04 >4.12E-05 <3.74E-04 6 5Zn <1.36E-04 <3.42E-04 8 9Sz <5.25E-05 <1.55E-04 9 0Sz <7.88E-06 <2.71E-05 99Mo <3.47E-04 <9.43E-04 1311 <3.81E-05 <1.08E-04 1 34Cs <5.67E-05 <1.48E-04 1 37Cs <6.12E-05 <1 '4E-04 1 41Ce <5.95E-05 <1.66E-04 1 44Ce <2.61E-04 <7.24E-04 Total >1.61E-02 <1.75E-02 >3.07E-04 <7.99E-03 C. Dissolved and Entrained Gases 41Ar <6.79E-06 <1.18E-05 85Kr m <1.18E-05 <3.19E-05 85Kr <1 '7E-02 <3.27E-02 87Kr <2.41E-06 <5.71E-06 88Kr <2.90E-05 <5.28E-05

>>3Xe m <2.97E-04 <8.43E-04

>>3Xe >2,62E-OS <1.53E-04 >4. 20E-04 <7.24E-04

>>5Xe m <1.73E-09 <4.18E-09

>>5Xe >5 '0E-05 <9.43E-05 >1.71E-04 <2.27E-04 Total >7.72E-05 <1.23E-02 >5.91E-04 <3.46E-02 1Notation: The first value presented (>) includes only activity positively detected at the 95K 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 95/ CL.

13

TABLE 6 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT WASTE DISPOSITION Data Period: January 1, 1990 June 30, 1990 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL t

Number of Shi ents Mode of Trans ortation Destination 20 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS Number of Shi ents Mode of Trans ortation Destination NONE NOT APPLICABLE NOT APPLICABLE 14

REPORT NOTES

1. All activities reported in millicuries ~

(mCi) unless otherwise noted. ~

2. Reported activities, as indicated by ((), are comprised in whole or part of the lower limit of detection values. ~

3. No Class B or Class C Waste disposed of during this report period.

4. No waste disposed of in the following waste streams during the report period:

Condensate demineralizer/radwaste demineralizer solidified using Portland Cement Dewatered RWCU filter media Evaporator concentrates solidified using Portland Cement Liquid radwaste filter media solidified using Portland Cement Dewatered ultrasonic resin cleaning waste Incinerated DAW Absorbed oi 1 Liquid oily waste 15

TABLE 7 SOURCE OF WASTE: LIQUID RADWASTE FILTER MEDIA TYPE OF CONTAZHER: HIC METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) 4 OF TOTAL Ag-110m O.OOE+00 0.004 Am-241 2 '5E-03 0.004 C-14 1.15E+01 0.014 Cm-242 1.73E-03 0.004 Cm-244 1.53E-02 0.004 Co-58 1.34E+03 0.

Co-60 9.57E+03 604'.274 Cr-51 1.50E+04 6.674 CB-134 O.OOE+00 0.004 CG-137 O.OOE+00 0.004 Fe-55 1.62E+05 72.314 Fe-59 4.69E+03 2.094 H-3 2.21E+01 0.014 I-129 Z 2.24E-01 0.004 I-131 O.OOE+00 0.00%

Mn-54 2.98E+04 13.304'.024 Ni-63 5.52E+01 Pu-238 3.61E-03 0.004 Pu-239 2.29E-03 0.00%

Pu-241 1.57E+00 0.004 Sb-124 1.46E+02 0.074 Sr-89 O.OOE+00 0.004 Sr-90 O.OOE+00 0.

Tc-99 %6.95E-01 004'.004 Zn-65 1.46E+03 0.654 TOTAL ACTIVITY (Ci) 224.150 100.00%'0.264 CONTAINER VOLUME 715.600 f03 m3 16

TABLE 8 SOURCE OF WASTE CONDENSATE DEMINERALIZER/

RADWASTE DEMINEKQ IZER TYPE OF CONTAINER: HIC

.METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-110m O.OOE+00 O.OO%

Am-241 7.10E-04 0.00%

C-14 3.32E+02 3.97I Cm-242 O.OOE+00 0.00%

Cm-244 4.86E-04 0.00%

Co-58 9.47E+01 1.13%

Co-60 1.66E+03 19.92%

Cr-51 3.79E+02 '.54%

Cs-134 4.68E+01 0.56%

Cs-137 3.91E+01 0.47%

Fe-55 4.29E+03 51.39%

Fe-59 3.22E+01 0.39%

H-3 6.31E+Ol 0.76%

I-129 K 1.01E+00 0.01%

I-131 2.15E+00 0.03%

Mn-54 1.09E+03 13-01%

Ni-63 1.23E+00 0. 01%

Pu-238 6.89E-04 0. 00%

Pu-239 O.OOE+00 0.00%

Pu-241 5.80E-02 0.00%

Sb-124 O.OOE+00 0.00%

Sr-89 O.OOE+00 0.00%

Sr-90 5.65E-01 0.01%

Tc-99 A 1.53E+00 0.02%

Zn-65 3.17E+02 F 80%

TOTAL ACTIVITY (Ci) 8.350 1OO.OO%

CONTAINER VOLUME 2147.200 f53 60.803 m3 17

TABLE 9 SOURCE OF WASTE: CONDENSATE DEMINERALIZER/

RADWASTE DEMINERALIZER TYPE OF CONTAINER: CARBON STEEL LINER METHOD OF PROCESS: DEWATERED ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-110m O.OOE+00 0. 004 Am-241 O.OOE+00 0. 004'.974 C-14 9.08E+01 Cm-242 O.OOE+00 0. 004'.004 Cm-244 O.OOE+00 Co-58 3.51E+01 1.15%

Co-60 7.33E+02 23.954 Cr-51 3.98E+01 1.30$

Cs-134 O.OOE+00 0.004 Cs-137 3.58E+00 0. 12li Fe-55 1.33E+03 43.

Fe-59 1.13E+01 314'.374 H-3 1.70E+01 0.564 I-129 4,1.84E-01 0.01<

I-131 O.OOE+00 0.004 Mn-54 6.50E+02 21.234 Ni-63 1.71E+00 0.06<

Pu-238 O.OOE+00 0.00<

Pu-239 O.OOE+00 0.004 Pu-241 3 '4E-02 0.004 Sb-124 O.OOE+00 0.004 Sr-89 O.OOE+00 0.004 Sr-90 4 '2E-02

'~ 5 '0E-01 0.004 Tc-99 0.

Zn-65 1.52E+02 024'.974 TOTAL ACTIVITY (Ci) 3.061 100.004 CONTAINER VOLUME 531.900 ft3 15.062 m3 18

TABLE 10 SOURCE OF WASTE: SUMP SLUDGE TYPE OF CONTAINER: CARBON STEEL LINER METHOD OF PROCESS: SOLIDIFICATION- PORTLAND CEMENT ISOTOPES ACTIVITY (mCi) 0 OF TOTAL Ag-110m O.OOE+00 0.004 Am-241 O.OOE+00 0.004 C-14 7.29E+00 0.244 Cm-242 O.OOE+00 0.00%

Cm-244 O.OOE+00 0.00%

Co-58 O.OOE+00 0.004 Co-60 2 '3E+02 7.064 Cr-51 O.OOE+00 0.004 Cs-134 O.OOE+00 0.004 Cs-137 O.OOE+00 0.00%

Fe-55 2.69E+03 89.104'.

Fe-59 O.OOE+00 H-3 2.71E+00 00%'.

094 I-129 K 2.78E-02 0. 004 I-131 O.OOE+00 0.004 Mn-54 1.06E+02 3.514 Ni-63 O.OOE+00 0.004 Pu-238 O.OOE+00 0.00<

Pu-239 O.OOE+00 0.

Pu-241 O.OOE+00 004'.

Sb-124 O.OOE+00 004'.

00%

Sr-89 O.OOE+00 0. 00%

Sr-90 O.OOE+00 0.

Tc-99 &1.48E-02 004'.004 Zn-65 O.OOE+00 0.

.TOTAL ACTIVITY (Ci) 3 '19 004'00.004 CONTAINER VOLUME 177.900 ft3 5.038 m3 19

TABLE 11 SOURCE OF WASTE: CARTRIDGE FILTERS TYPE OF CONTAINER: HIC METHOD OF PROCESS: N/A ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-110m O.OOE+00 0.004 Am-241 1.74E-02 0.00<

C-14 6 '7E-02 0. 004' Cm-242 6.35E-04 ~ 004 Cm-244 1.07E-03 0.004 Co-58 7.53E+00 0.

Co-60 6.01E+03 03%'1.774'.00%

Cr-51 O.OOE+00 Cs-134 O.OOE+00 0. 004'.

Cs-137 O.OOE+00 Fe-55 1.79E+04 00%'4.644 Fe-59 1.58E+01 0.06%

H-3 6.09E-01 0.004 I-129 K 7.61E-03 0.004 I-131 O.OOE+00 0.004 Mn-54 3.46E+03 12.514 Ni-63 1.40E+02 0.514 Pu-238 6.29E-03 0.004 Pu-239 2.18E-03 0.004 Pu-241 1.02E+00 0. 00>o Sb-124 1.49E+00 0. 014 Sr-89 O.OOE+00 0.

Sr-90 004'.

O.OOE+00 Tc-99 X 1.78E-01 004'.

Zn-65 004'.

1.31E+02 TOTAL ACTIVITY (Ci) 27.615 484'00.004 CONTAINER VOLUME 114.000 ft3 3.228 m3 20

TABLE 12 SOURCE OF WASTE: COMPACTED DAW TYPE OF CONTAINER: STRONG TIGHT CONTAINER METHOD OF PROCESS: N/A ISOTOPES ACTIVITY (mCi) 4 OF TOTAL Ag-110m O.OOE+00 0.004 Am-241 O.OOE+00 0.004 C-14 6.44E-01 0. 02%'.004 Cm-242 O.OOE+00 Cm-244 O.OOE+00 0. 004'.

Co-58 1.65E+01 39%'.

Co-60 3.09E+02 404 Cr-51 2.86E+01 0. 694 Cs-134 O.OOE+00 0. 004 Cs-137 O.OOE+00 0.

Fe-55 3.31E+03 004'9.184 Fe-59 4.34E+01 1.

2.02E-01 044'.

H-3 I-129 004'.

4 1.09E+00 034 I-131 O.OOE+00 0. 004'.944 Mn-54 4.16E+02 Ni-63 O.OOE+00 0.004 Pu-238 O.OOE+00 0.

Pu-239 O.OOE+00 004'.00<

Pu-241 O.OOE+00 0.00%

Sb-124 O.OOE+00 0.

Sr-89 O.OOE+00 004'.004 Sr-90 O.OOE+00 0.004 Tc-99 A 4.04E+00 0.104 Zn-65 5.08E+01 1 214

~

TOTAL ACTIVITY (Ci) 4 ~ 179 100.004 CONTAINER VOLUME 1128.400 ft3 31.953 m3 21

TA6LE 13 SOURCE OF WASTE: NON-COMPACTABLE DAW TYPE OF CONTAINER: STRONG TIGHT CONTAINER METHOD OF PROCESS: N/A ISOTOPES ACTIVITY (mCi) OF TOTAL Ag-110m O.OOE+00 0.004 Am-241 O.OOE+00 0.004 C-14 6.08E-02 0.024 Cm-242 O.OOE+00 0.004 Cm-244 O.OOE+00 0.004 Co-58 6.01E-01 0.19%

Co-60 2.34E+01 7.554 Cr-51 O.OOE+00 0.004 Cs-134 O.OOE+00 0.004 Cs-137 O.OOE+00 0.004 Fe-55 2.47E+02 79.744'.39%

Fe-59 1.20E+00 H-3 7.74E-02 0.024 I-129 Z 5.18E-01 0.174 I-131 O.OOE+00 0.004 Mn-54 3.24E+01 10.464 Ni-63 O.OOE+00 0.004 Pu-238 O.OOE+00 0.00%

Pu-239 O.OOE+00 0.004 Pu-241 O.OOE+00 0.004 Sb-124 O.OOE+00 0, Sr-89 004'.

O.OOE+00 004 Sr-90 O.OOE+00 0.004 Tc-99 Q 2.09E+00 0.674 Zn-65 2.40E+00 0.774 TOTAL ACTIVITY (Ci) 0.310 CONTAINER VOLUME 134.200 ft3 100.004'.800 m3 22

TABLE 14 PREVIOUS REPORT CORRECTXON SOURCE OF WASTE: Reactor Water/Fuel Pool Clean-up (Powdex)

TYPE OF CONTAINER: HIC METHOD OF PROCESS: Dewatered AS REPORTED IN JUL 1 TO DEC 31, 1989 1 '1 REPORT g~C' CORRECTED DATA SOTOPES ACTIVITY ~o OF TOTAL ACTIVITY 4 OF TOTAL AG-110M 4.42E2 0.21 7.93E2 0.21 CO-58 2.86E3 1.38 5.49E3 1 '8 CO-60 2.66E4 12.80 4.79E4 12.88 CR-51 1.77E3 0.85 3.77E3 1.01 CS-134 1.33E3 0.64 2.55E3 0.69 CS-137 1. 02E3 0.50 1.71E3 0 '6 FE-59 1.61E3 0.77 3.23E3 0.87 MN-54 3.85E4 18.51 6.54E4 17.58 ZN-65 1.25E4 6.01 2.34E4 6.29 H-3 1.87EO 0.00 1.87EO 0.00 C-14 2.74E-1 0.00 4.93E-1 0.00 FE-55 1.20E5 57.70 2.16E5 58.07 NI-63 8.86E2 0 '3 1.59E3 0.43 SR-90 2.40EO 0 F 00 4.02EO 0.00 TOTAL ACTXVITY (Ci) 208.0 372.0 CONTAINER VOLUME 135 CuFt 3.82 M3 REASON FOR CORRECTION: ONE SHIPMENT OF THIS WASTE STREAM WAS MADE DURXNG THE REFERENCED REPORT PERIOD. THE ORIGINAL SAMPLE USED TO CHARACTERIZE THIS SHIPMENT OF DEWATERED POWDEX RESIN WAS NOT DEWATERED PRXOR TO ANALYSXS. A SAMPLE FROM THIS SHIP-MENT WAS RETRIEVED AND RE-ANALYZED BY SAI. THE ABOVE NUMBERS REFLECT THE DEWATERED ISOTOPIC RESULTS AND USE THE SCALING FACTORS WHICH WERE IN EFFECT AT THE TIME OF THE ORXGINAL SHIPMENT. CHEM-NUCLEAR SYSTEMS (BARNWELL) HAS BEEN NOTIFIED OF THE MANXFEST CHANGE.

23

TABLE 15 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT ESTIMATED TOTAL ERRORS ASSOCIATED WITH EFFLUENT MEASUMMENTS Data Period: January 1, 1990 June 30, 1990 Measurement Estimated Total Error

1. Airborne Effluents

a. Fission and Activiation Gases 15.9 X

b. I-131 13.3 X

c. Particulates 15.8 X

d. Tritium 5.7 X

2. Waterborne Effluents

a. Fission and Activation Products 5.0 X

b. Tritium 3.3 X

c. Dissolved and Entrained Gases 8.4 X

d. Gross Alpha Radioactivity None Dectected

e. Volume of Waste Released (Prior to Dilution) 5.0 X

f. Volume of Dilution Water Used During Period 15.0 X

3. Solid Wastes

a. Liquid Radwaste Filter Media HIC (Dewatered) 15.1 X

b. Condensate Demineralizer/Radwaste Demineralizer HIC (Dewatered) 15.1 X

c. Condensate Demineralizer/Radwaste Demineralizer Carbon Steel Liner (Dewatered) 15.1 X

d. Sump Sludge Carbon Steel I incr (Solidification Portland Cement) 15 ' X

e. Cartridge Filters HIC 15 ' X

f. Compacted DAW Strong Tight Container 25.0 X

g. Non-Compactable DAW Strong Tight Container 25.0 X 24

TABLE 16 SEMIANNUAL EFFIUENT AND WASTE DISPOSAL REPORT 1990 EFFLUENT DATA NOT AVAILABLEFOR PREVIOUS SEMIANNUAL REPORT NUCLIDE CATEGORY UNIT FOURTH QUARTER 1989 A. Airborne Effluents

1. Sr-89 Ci >6.69E-07 <2.19E-06

2. S1-90 Ci <4.95E-07

3. Gross Alpha Ci >2.92E-07 <9.49E-07 B. Waterborne Effluents

1. Sr-89 Ci <1.59E-04

2. Sr-90 Ci <2.87E-05 25

SECTION 3 CHANGES TO THE OFFSITE DOSE CAlCULATION hVSUAK AND THE SOlID WASTE PROCESS COiVXROl PROGRAM 26

CHANGES TO THE OFFSITE DOSE CALCKATION hIANUM There were no revisions to the SSES Offsite Dose Calculation Manual during the report period.

CHANGES TO THE SOLID WASTE PROCESS CONTROL PROGRAM Revision 9 of the SSES plant procedure AD-QA-311, Solid Waste Process Control Program, was prepared and approved during the report period.

Copies of the affected pages are included following this page. The specific changes made to the procedure are sunmarized on page 2 of the procedure.

The changes were made to enhance the Process Control Program from an administrative standpoint and do not affect the final waste product acceptability.

28

PROCEDURE COVER SHEET PENNSYLVANIA POWER 8L LIGHT CO.

SUSQUEHANNA STEAM ELECTRIC STATION AO-QA-311 SOLID RADIOACTIVE WASTE PROCESS CONTROL PROGRAM Revision 9 Page 1 of 57 EFFECTIVE DATE PERIODIC REVIEW FREQUENCY ANO EXPIRATION DATE (check one):

( ) Procedure exempt from periodic review. Procedure will not expire.

(+) Periodic Review Frequency is:

Expiration Date:

Revised Expiration Dates:

PROCEDURE TYPE (check one): (Q) PORC ( ) NON-PORC REVIEW TYPE (check one):

( ) Expedited Review. PORC Review not required.

( ) Alternate Review. PORC Review not required.

(~) PORC Review. PORC Meeting No.

lo-os5'repared by Reviewed by Res o ible S er isor Recommended ,Date 5 -/- /c'-

Se tio d/Manager Approved by Date WORM AO-QA-101-1, Rev. 5, Page 1 of 1 fIlflfjIfIflfjiflIIfllIillillllfIlllIlllliflllll FYi->BR" sl l ItlElIfgfifIffilfIIfllIIIN lIlllllIfilllllll~]IllfJfll!

fll!fIilll

AD-QA-311 Revision 9 Page 2 of 57 PROCEDURE REVISION

SUMMARY

TITLE: SOLID RADIOACTIVE WASTE PROCESS CO~OL PROGRAM

1. Revise Section 6. 1.2.a.3 per PCAF 1-90-0059, de ating the word "sludge" and replacing it with the word "waste".

2. Add phrase "Sump sludges may not be dewatered" to section 6. 1.2.c, per PCAF 1-90-0059.

3. Amend Section 6.3.4 to include item "h. Cement and additives to be used in actual solidification shall be used in preparation of test solidification" per PCAF 1-88-0402.

4. Adding items, per PCAF 1-89-0327, to section 6.4.4:

"(m) Radlok 179 loaded weight: 14000 lb", and e 5.

"(n) Radlok 195 loaded weight: 15500 lb" Amending Attachment C, Item 9 89-0050 to include "-100 = per PCAF 1-

6. Add references to include WHNI Topical Reports, PCP and Certificate of Compliance.

7. Changed title of Radwaste Operations Engineer to Power Production Engineer" Radwaste.

8. Changed nomonclature throughout procedure for consistency to other procedures and burial site requirements.

9. Added changes to PCP need PORC approval prior to implementation of section 6.7.2 in accordance with Technical Specification 6.8.2.

10. Incorporated PCAF 1-90-0059 for NQA Audit 89-027 recommendations dealing with HIC UV tracking and Powdered Resin Solidification Tech Spec. Action Statement.

AD-QA"311

( Revision Page 3 of 9

57 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 2.0 SCOPE

3.0 REFERENCES

4.0 RESPONSIBILITIES

4. 1 Power Production Engineer-Radwaste 4.2 Shift Supervision 4.3 Radwaste Supervisor 4.4 Chemistry Group 4.5 Health Physics Foreman-Radwaste 4.6 Quality Control 10 4.7 I & C Supervisor 10 4.8 Auxilary System Operator 10 4.9 Solidification/Dewatering Services Vendor 10

4. 10 Nuclear Quality Assurance

4. 11 Materials Section 5.0 DEFINITIONS 6.0 PROCEDURE 13

6. 1 Waste Types 13 6.2 Sampling Analysis Requirements 16 6.3 Radioactive Waste Solidification 17 6.4 Radioactive Waste Dewatering 24 6.5 Container Inspection 30 6.6 Waste Container Utilization 30

AD-gA-311 Revision 9 Page 4 of 57 TABLE OF CONTENTS (Continued)

SECTION PAGE 6.7 Changes to the Solid Radioactive Waste Process 30 Control Program 6.8 Equipment Calibration 31 7.0 RECORDS 31 ATTACHMENTS ATTACHMENT PAGE A Solidification Record Sheet 32 B Dewatering Record Sheet C Susquehanna Guaranteed Waste Volume Record 57

AO-QA-311 Revision 9 Page 5 of 57 1.0 PURPOSE Provide administra'tive control, guidance and records for the solidification and dewatering of applicable forms of Radwaste for ultimate disposal. This procedure is the Process Control Program required by SSES Technical Specifications.

2.0 SCOPE This procedure is applicable to SSES installed systems, temporary systems and equipment provided by vendors for solidification, dewatering and packaging of applicable waste forms. Ory Active Waste is not within the scope of this procedure.

3.0 REFERENCES

3. 1 49 CFR 173 General Requirements for Shipments and Packaging 3.2 10 CFR 20 Standards for Protection Against Radiation 3.3 10 CFR 61 Licensing Requ'irements for Land Oisposal of Radioactive Waste 3.4 10 CFR 71 Packaging and Transportation of Radioactive Material 3.5 SSES Technical Specifications. Section 3/4. 11.3 Solid Radwaste System 3.6 Standard review plan 11.4 3.7 WHNI Mobile Incontainer Oewatering and Solidification System (MOSS),

Typical Report No. STO-R-05-011P-A 3.8 WHNI Report on Dewatering of Bead Ion Exchange Resin and Activated Carbon, Report No. STO-R-03-001 3.9 WHNI Process Control Program for Oewatering Ion-Exchange Resin and Activated Charcoal filter media to 1/2/o drainable liquid, Report No.

STO-P-03-048

3. 10 WHNI Report on Dewatering of Bead Ion Exchange Resin and activated Carbon in Hittman RAOLQK High Integrity containers, Report No. STO-R-03"002

3. 11 WHNI Report on Powdered Resin Oewatering in Radlok Containers, Report No. STO-R-03-005

3. 12'HNI Topical Report Cement Solidified Wastes to Meet Stability Requirements of 10 CFR61, Report No. STO"R-05-007

AD-QA-311 Revision 9 Page 6 of 57

3. 13 WHNI Mobile Incontainer Dewatering and Solidification System Process Control Program (PCP), Report No. STD-PCP"03"003

3. 14 Burial Site Criteria for Barnwell S.C.

3. 15 Burial Site Criteria for Richland, Washington.

3. 16 AD-QA-765, Solid Radwaste Program 3.17 AO-QA-605, Calibration of Installed Plant Instrumentation 3.18 CNSI Topical Report "Mobile Cement Solidification System" 4313-01354-01P-A

~

3.19 CNSI Topical Report "Polyethylene High Integrity Containers" CNSI-HIC-14571-01-P 3.20 CNSI Topical Report "CNSI Oewatering Control Process Container s Topical Report" CNS I-DW-11118-01-P 3.21 DHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers 3.22 OHEC-HIC-PO-006 South Carolina Certificate of Compliance for CNSI Overpak High Integrity Containers 3.23 DHEC-HIC-FRP-003 South Carolina Certificate of Compliance for CNSI Fiberglass Reinforced Polyester 24 Inch Pressure Vessel as a High Integrity Container 3.24 CNSI FO-AO-002 Operating Guidelines for use of Polyethylene High Integrity Containers 3.25 CNSI FO-AS-004 Operating Guidelines for use of Fiberglass Reinforced Plastic High Integrity Containers 3.26 CNSI FO-OP-019 Polyethylene High Integrity Container Overpak Handling Procedure 3.27 WHNI STD-0-03-009 USERS MANUAL for HNDC RAOLOK-Z00, RADLOK-500,'RAOLOK 100, RAOLOK-179 and RADLOK-195 3.28 WHNI STD-0-03"008 USERS MANUAL for HNOC RADLOK-55 3.Z9 DHEC-HIC-PL-005 South Carolina Certificate of Compliance for WHNI RAOLOK-100, -179 and -195 Containers 3.30 DHEC-HIC-PL-004 South Carolina Certificate of Compliance for WHNI RAOLOK-55 Container

AO"QA-311 Revision 9 Page 7 of 57 3.31 OHEC-HIC-PL-0014 South Carolina Certificate of Compliance for WHNI RAOLOK-500 Container 3.32 OHEC-HIC-PL-007 South Carolina Certificate of Compliance for WHNI RAOLOK-200 3.33 NOI-QA-6.5. 1 Radwaste Program 3.34 AO-QA-210, Procurement Control Activities 3.35 NTP-QA-42.3, Radwaste Worker Training 3.36 NTP-QA-41.2, Chemistry Technician Certification Training 3.37 HP-TP-800, Shipment of Radioactive Material 4.0 RESPONSIBILITIES

4. 1 Power Production Engineer-Radwaste responsibilities:

4. 1. 1 Ensure procedures a'e adequate to provide for proper solidification and dewatering of waste.

4.1.2 Ensure test data or rationale is available to justify applicable solidification and dewatering functions of each waste type or any combination to address burial and regulatory agencies requirements.

4.1.3 Evaluate services provided by various vendors to ensure contracted solidification and dewatering operations are performed in the most efficient and economical method as required by applicable regulatory agencies.

4. 1.4 Perform the duties of Radwaste Supervisor as specified in this procedure in his absence.

4' Shift Supervision shall assume the responsibility of the Radwaste Supervisor and Power Production Engineer-Radwaste in their absence.

4.3 Radwaste Supervisor responsibilities:

4.3.1 Ensure Solidification/Oewatering Equipment is operated in accordance with approved operating procedures including vendor supplied equipment.

4.3.2 Ensure appropriate waste solidification and dewatering records are generated.

AO-QA-311 Revision 9 Page 8 of 57 4.3.3 Interface with station support groups to ensure proper implementation of process control programs.

4.3.4 Interface with contractor personnel involved in solid waste processing activities including:

a. Ensure test data is available to justify specific functions.

b. Ensure applicable vendor procedures and revisions are incorporated into applicable plant procedure and approved by PORC.

4.3.5 Ensure Solidification and Oewatering operations are carried out in an ALARA manner.

4.3.6 Interface with HP Supervision-Radwaste for liner and cask selection for solid waste shipping activities.

4 3 7

~ ~ Ensure proper marking of containers prior to filling.

4.3 ' Maintain a log of batch processes for test solidification requirements.

4.3.9 Ensure Radwaste solidification personnel are adequately trained per NTP-QA-42.3.

4.3. 10 Oetermine classification of waste to be processed.

4.3.11 Ensure that waste streams loaded into High Integrity Containers are sampled for radionuclide and evaluated for chemical compatability applicable to the use of High Integrity Containers.

4.3.12 Ensure proper selection of High Integrity Containers for the waste stream being processed and packaged.

I 4.3.13 Ensure proper inspections and documentation are complete prior to use of a High Integrity Container and container is properly used up to the point of transfer to Health Physi.cs.

4.3.14 Complete and process High Integrity Container User Certification Statement to ensure the container is used properly.

AO-gA-311 Revision 9 Page 9 of 57 4.4 Chemistry Group responsibilities:

4.4.1 Perform required sampling analysis in accordance with approved chemistry procedures.

4.4.2 Perform test solidification if required. Store test solidification billet until associated liner is buried.

4.4.3 Provide the Isotopic mix and concentration of isotopes detected in the material sampled for solidification or dewatering.

4.4.4 Complete Chemistry portion of the Solidification Record Sheet.

(Attachment A)'and Oewatering Record Sheet (Attachment 8).

4.4.5 Ensure personnel are adequately trained per NTP-gA-41.2.

4.4.6 Provide radionuclide sampling and chemical analysis support as necessary for use of High Integrity Containers.

4.4.7 Implement a program in accordance with 10CFR61 to establish correlation factors from isotopic analysis to determine required radionuclide concentrations in each waste stream.

4.5 Health Physics Supervision-Radwaste responsibilities:

4.5. 1 Oetermine type and specification of casks which may be required.

4.5.2 Completing applicable portions of the Solidification or Oewatering Record Sheet.

4.5.3 Process the Solidification and Oewatering Record Sheets.

4.5.4 Storage of packaged solidified and dewatered material outside the Radwaste facility.

4.5.5 Oetermine curie content of solidified and dewatered material.

4.5.6 Final disposition of solidified and dewatered material.

4.5.7 Ensures SSES is a registered user of applicable High Integrity Containers.

4.5.8 Ensures personnel involved with radioactive waste handling have received Radwaste Worker training per AO-gA-765.

4.5.9 Radioactive material evaluation of product acceptability for disposal at specific burial sites.

AO-QA-311 Revision 9 Page 10 of 57 4.5. 10 Assure specific approval is requested and obtained for disposal of High Integrity Containers as required by applicable regulatory agencies.

4.6 Quality Control Group responsibilities:

4.6. 1 Review of Solidification and Oewatering Record Sheets.

4.6.2 Inspection of Liners and High Integrity Containers as required by applicable procedures.

4.6.3 Ensure process controls are adhered to by verification of test solidifications, waste volumes, solidification agent additions, product acceptability checks, processing sequence and acceptance criteria.

4.7 I&C Supervisor is responsible for ensuring periodic calibrations and inspections are performed as required.

4.8 Auxiliary Systems Operator is responsible for operating the plant solid and liquid radwaste equipment in accordance with approved operating procedures as directed by the Radwaste Supervisor and Assistant Unit Supervisor.

I 4.9 Solidification/Oewatering Services Vendor responsibilities:

Provide solidification and/or dewatering services in accordance with a valid contract for said services and provide test data or make same available for PP&L review during vendor audits to demonstrate that their services and equipment meet the applicable regulatory and burial site limitations for the function they are providing.

4.9.2 Provide training documentation to demonstrate that the personnel being provided, to conduct the applicable service, are in fact trained and knowledgeable in the applicable functions.

4.9.3 Provide procedures that are or can be placed into the SSES procedure format for the functions being provided.

4.9.4 Ensure an appro'ved Quality Assurance Program exists that covers the services being provided. The vendor shall work within the SSES Quality Assurance Program when applicable.

4.9.5 Complete applicable sections of Attachments A,B and C as required for each liner processed.

AD-'0A"311 Revision 9 Page 11 of 57 4.9.6 Ensure prequalification test data for each waste form shall be submitted to the Nuclear Regulatory Commission.

4.9.7 Provide an equipment/process description that is used in processing waste.

4. 10 Nuclear guality Assurance responsibilities:

4.10.1 Receipt inspection of High Integrity Containers and document review to ensure conformance.

4.10.2 Ensure Certificate of Compliance (C of C) is received with High Integrity Container.

4. 10. 3 Perform periodic audit on implementation of this program and review of Solidification/Dewatering Services Vendor gA program.

4.11 Materials Section responsibilities:

4.11.1 Ensure High Integrity Containers are not exposed to ultra violet light (sunlight).

4.11.2 Ensure proper material certification is complete prior to issuance of High Integrity Containers to plant for use.

5.0 DEFINITIONS

5. 1 Batch " The total volume of waste contained in a liner, waste mixing tank, spent resin tank concentrates tank or phase separator that has been sampled for solidification.

5.2 Solidification- A conversion of radioactive materials from liquid and solid systems to a monolithic immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides ( free standing), with a free standing liquid content of less than 0.55 by waste volume.

5.3 Waste Type- A category of waste from one or several waste streams which may be Evaporator Concentrates, Powdered Resin, Filter Sludges, Bead Resins, etc. or a combination of each.

5.4 Waste Pre-Conditioning- The physical or chemical adjustment of the waste to bring it within an established envelope to assure solidification.

AO-QA-311 Revision 9 Page 12 of 57 n

5.5 Curing Time - The time allowed for the solidified product to set prior to transporting or capping the liner.

5.6 Mixing Ratio- The ratio of waste to cement and additives required for satisfactory solidification.

5.7 Test Solidification - The mixing of waste(s) and solidification agents in the labratory to support selection of mixing ratios and provide insurance ',or final product acceptability.

5.8 Oewatered- The removal of free standing liquid from solid material to a point where less than 1% for HIC's and 0.5% for steel liners by waste volume remains as required by the burial site license.

5.9 Liner - The physical container in which dewatered or solidification product is deposited.

5. 10 High Integrity Container (HIC) - A burial site licensing department approved container that has an expected life of 300 years and provides the stability to meet burial requirements.

5 ~ 11 Low Specific Activity - Material in which the activity is essentially uniformly distributed and in which the estimated average concentration per gram of contents does not exceed the specification as stated in 49 CFR 173.403 (N).

5. 12 Stable and Unstable Waste Forms - Shall be defined as stated in 10CFR Part 61.

5. 13 Mixed Waste - A mixture of radioactive and hazardous waste.

5. 14 Waste Stream - A defined byproduct of a process system or component.

5. 15 Mixing Recipe - The amount of waste, cement and additives mixed to solidify waste.

6.0 PROCEOURE

6. 1 Waste Types - The following waste types shall be processed in accordance with this procedure or in combinations as defined. The waste should be dewatered whenever possible to minimize burial volume or solidified.

AO-QA"311 Revision 9 Page 13 of 57 Evaporator Concentrates

a. The following process waste streams are concentrated with the Radwaste Evaporators and are considered Evaporator Concentrates:

( 1) Condensate Oemineralizer regeneration effluent (2) Oecon Shop drains (3) Chemistry Laboratory sink drains (4) Auxiliary 8oiler blowdown effluent

b. The constituents of these waste streams may include the following:

( 1) Tri-Sodium Phosphate (2) Sodium Sulfate (3) Phosphoric Acid (4) Sulfuric Acid (5) Sodium Hydroxide (6) Oecontamination solutions (7) Negligible amounts of reagent chemicals used for chemistry analysis

c. Evaporator Concentrates in the range of 0-25 weight percent sodium sulfate (equivalent) shall be solidified in steel liner for final disposal.

d. Evaporator Concentrates shall not be mixed with any other waste type in final processing.

Mixed Solids The following process waste streams are collected either in Waste Mix Tanks, Waste Sludge Phase Separator or transferred directly to a liner and are considered Mixed Solids:

(1) LRW Filter material'and drain liquid (2) Sump Sludge

AO-QA-311 Revision 9 Page 14 of 57 (3) Ultrasonic Resin Cleaner Waste The constituents of these waste streams may include the following:

( 1) Diatomaceous Earth (2) Powdered Resins (3) Fibrous material (4) Carbon material (5) Corrosion products (6) Various solids and dirt in small concentrations Mixed Solids may be solidified in steel liners or dewatered in High Integrity Containers for final disposal. Sump sludges may not be dewatered.

Each waste stream shall be processed separately.

Powdered Resin The Reactor Water Cleanup System and Fuel Pool Cooling and Cleanup System filter/demineralizer waste are collected in the RWCU Phase Separator and should be allowed to decay for 60 days. This waste stream is considered Powdered Resin.

The constituents of this waste stream may include anion and cation powdered resin, corrosion and dirt removed from the primary coolant.

C. Powdered Resin shall be dewatered in High Integrity Containers. If this waste must be solidified, Technical Specification 3/4. 11.3 action statement must be performed.

Bead Resin Resins from the Condensate Oemineralizers and Liquid Radwaste Oemineralizer are collected in the Spent Resin Tank which is considered to be Bead Resin.

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

AD-gA-311 Revision 9 Page 15 of 57

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

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

6.1.5 Cartridge Filter s

a. Cartridge Filters from various plant systems are collected and may be disposed of by emplacement in a cement matrix in a steel drum/liner or in a High Integrity Container.

b. Cartridge Filters to be solidified for final disposal shall not be mixed with any other waste type.

c. Cartridge Filters to be placed in High Integrity Containers shall be dried. Absorbant material may be included to absorb unintentional and incidental amounts of liquids.

6. 1.6 Liquid Oily Waste or Petroleum Based Materials

a. Contaminated Liquid Oily Waste generated at the facility should initially be processed by a decontamination system. If oil cannot be decontaminated then the oil should be solidified for final disposal.

b. Liquid Oily Waste at concentrations 1% and greater may be solidified provided the following are adhered to:

( I) An emulsification agent is added at required concentrations.

(2) The Liner is NOT SHIPPED TO Barnwell, S.C. Disposal Facility.

c. Liquid Oily Waste less than lio by waste volume of unintentional oil or petroleum based materials may be shipped to Barnwell Disposal Facility.

A Waste Type that is combined with a known amount of Hazardous Waste or "Mixed Waste" shall not be processed for final disposal unless concurrence is obtained from the burial sites, Environmental Protection Agency and U.S. Nuclear Regulatory Commission.

AO-gA-311 Revision 9 Page 16 of 57

6. 1.8 Various other materials not specifically identified as waste types will be evaluated for solidification or dewatering on a case by case basis.

6.2 Sampling/Analysis Requirements 6.2. 1 Samples shall be obtained and analyzed for each batch of waste if possible and, at a minimum, contain two sample volumes.

6.2.2 Samples of the waste shall be taken in its state :rior to processing for final disposal. Bead Resin used ror chemical demineralization shall be sampled after the resin has been used in the process.

6.2.3 Oeviations from the sampling requirement shall be approved by Radwaste Supervisor.

6.2.4 The tank to be sampled shall be recirculated for a minimum of one hour prior to sampling.

6.2.5 A Chemistry Technician or another qualified individual shall obtain the required samples after specified recirculation time is complete.

6.2.6 Material to be processed may also be recirculated and sampled from mobile processing equipment.

6.2.7 Bead Resin processed in liners shall be mixed for a minimum of 30 minutes prior to sampling.

6.2.8 Radionuclide concentration will be determined by gamma spectromentry and correlation factors.

6.3 Radioactive Waste Solidification 6..3. 1 General Requirements a ~ Solidification processing shall be conducted by qualified SSES or vendor personnel.

b. The solidification process shall be operated in accordance with approved operating procedures.

Procedures shall specify waste type, amounts of solidification agent and additives or method for determination.

AO"0A-311 Revision 9 Page 17 of 57 Waste Preconditioning

a. Waste preconditioning will be determined by chemistry analysis during batch sampling.

b. Preconditioning of waste prior to determining will be performed if required mix ratios.

c. Waste preconditioning is required when any of the following conditions exist:

( 1) A high or low pH condition, as determined by chemical analysis procedure.

(2) Liquid content of the batch is too low or too high, out of the acceptable envelope for solidification.

(3) Solids content of the batch is too low or too high, out of the acceptable envelope for solidification.

d. Waste preconditioning will be performed in accordance with approved procedures as recommended by Chemistry Group.

e. Upon completion of waste preconditioning, additional samples as required to determine mixing ratios will be obtained in accordance with Section 6.2 of this procedure.

Oetermination of Mixing Ratios

a. Oetermination of mixing ratios shall be performed for each waste batch to be processed.

b. Oeviation from the recommended mixing ratios shall be approved by Radwaste Supervisor.

c. Chemistry Group determines the following:

( 1) Oensity of the waste samples.

(2) Specific gravity of Sodium Sulfate Solution.

(3) Percent settled solids.

d. Chemistry Group shall perform test solidification of waste as required in section 6.3.4 of this procedure.

0 AO-QA-311 Revision 9 Page 18 of 57 Chemisty Group determines mixing ratios to ensure proper solidification.

Chemistry Group shall provide an isotopic analysis which will be attached to the Solidification Record Sheet.

( Form AO-QA"311-1)

Chemistry Group shall provide the projected curie concentration to the Radwaste Supervisor.

Test Solidification Test solidification shall be performed to support waste mixing ratios as follows:

(1) At least every tenth (10th) Batch of the same waste type.

(2) When sample analysi s fal l outside the establ i shed range and criteria indicating a change in waste type.

(3) When it is believed that some unexpected or abnormal contaminant may be present.

(4) When requested by Radwaste Supervisor.

b. Upon failure of a test solidification, additional samples will be obtained, alternative solidification parameters are determ'-ed and a subsequent test verifies solidification. Test solidifications shall be performed on each subsequent batch of the same waste type until at least three (3) consecutive initial test solidifications demonstrate acceptability in accordance with Technical Specification 3/4. 11.3.

Quality Control shall verify test solidification acceptability and indicate the acceptability on the survei lance documentation. The acceptabi i ty 1 1 requirements shall be defined in an established procedures d ~ Extra sample volume for backup test which may be required shall be disposed-of after liner burial.

Test solidification billets should be disposed after the liner is buried.

AO-QA-311 Revision 9 Page 19 of 57

f. Test solidifications may be performed with waste from samples obtained as follows:

( 1) Oirect sampling of the liner after mixing.

(2) Sampling of the tank to be transferred.

(3) Sampling of the solids in the liner and the liquid for hydration, then mixed to the ratios that exist in the liner.

g. Test Solidification Procedures shall be developed'for each specific waste type.

h. Cement, water type and additives to be used in actual

'olidification shall be used in preparation of test solidification.

Curing Time

a. A minimum of 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> shall be allowed for curing prior to capping or transporting container. If liner contains an unstable waste form, this requirement may be wavied by Radwaste Supervisor.

b. The liner may be moved during the first hour after solidification but must remain undisturoed fo'r the remaining 29 hours.

C. Oeviations from minimum required curing time shall be approved by Radwaste Supervisor and justifications documented in remarks section of Solidification Data Sheet. (Form AO-QA-311-1)

d. A temperature indicator should be used to monitor exothermic reaction. The temperature profiles will be used for information only.

Sol.idification Product Quality a 0 Solidification product quality is assured by use of predetermined mixing ratios of waste, cement and additive.

Liquid to be used for solidification may be demineralized water or liquid radwaste.

Mixing ratios are based on laboratory testi'ng non-radioactive waste materials.

AO-gA-311 Revision'9 Page 20 of 57

c. Mixing ratios are re-enforced by the following:

(1) Test solidifications performed periodically as stated in 6.3.4.

(2) Visually and physically checking at least every fifth (Sth) container of the same waste type.

d. Container checks shall consist of:

( 1) A visual check of solidified product for liquid on surface of product.

(2) Physically poking the surface of solidified product with a rigid unyielding device prior to capping (Nominal surface denting may occur and is acceptable).

e. guality Control shall verify acceptability of solidified product when containers are checked.

f.. Oeviation from the container checking requirement shall be approved by the Power Production Engineer-Radwaste.

6.3.7 Handling of Unacceptable Solidified Waste Containers;

a. If a solidified waste container does not meet acceptability requirements (except for freestanding water) a Non-Conformance Report (NCR) shall be issued.

b. If the reason for unacceptability is free standing water:

( 1) The free standing liquid will be removed or (2) Extra cement/additive will be added to solidify free liquid.

If portions or all of the product did not solidify after three days for'unstable waste:

( 1) The waste container will be capped and placed in a storage location in the Radwaste facility and periodically checked until such a time product is acceptable or (2) Additional solidification agents may be added to achieve satisfactory solidification, as determined by the Radwaste Supervisor.

AD-gA-311 Revision 9 Page 21 of 57

d. Specific instructions shall be established for handling unacceptable solidified waste container on a case by case basis.

e. guali ty Control shall verify acceptability of solidified product in accordance with 6.3.6.d.

f. If the product solidifies prematurely prior to completing the addition of required amount of cement and additive as calculated on the solidification calculation sheet for the specific procedure used,'he following is required:

( 1) Chemistry Group shall perform a test solidification at actual ratio of cement and waste in the liner, provided sufficient sample volume remaining to complete this item.

(2) guality Control shall check the product for acceptability in accordance with 6.3.6.d of this procedure.

(3) The liner may be shipped provided the subsequent test solidification and/or product quality checks are acceptable to equality Control and concurrence of the Radwaste Supervisor.

(4) The above apply only if the Radwaste Supervisor and the HP Supervision-Radwaste agree that waste can be re-classified as "Class A unstable" in accordance with 10CFR61 and the burial site criteria.

g. If the product is a class which requires stability as defined in 10CFR Part 61 and does not solidify properly in accordance with the specific operating proceaure, the following are required.

( 1) An evaluation of 'the liner shall be made by the following personnel.

(a) Radwaste Supervisor (b) HP'Supervision-Radwaste (c) Solidification Vendor - Operations (d) Solidification Vendor - Engineering

AO"QA-311 Revision 9 Page 22 of 57 (2) Burial sites shall be contacted and requirements for receipt of the liner in question shall be defined.

(3) Alternative packaging/processing shall be evaluated.

(4) Recommendations for final disposition shall be made to the Power Production Engineer"Radwaste.

(5) Records shall be kept and documentation supportive of final disposition attached to the liner document package.

(6) The liner may be shipped after Q AC. review of documen-tation is complete and burial site concurrence is received in letter form.

6.3.8 Capping of Solidified Waste Containers

a. At a minimum the requirements of 6.3.6 of this procedure shall be met prior to capping the container.

b. If the container contents are within the requirements of Low Specific Activity (LSA) ensure one of the following:

(I) The container must be shipped within (10) ten days after sealing.

(2) If a container has been sealed for longer than ( 10) days, it shall be opened, vented, and then closed and shipped within (10) ten days.

c ~ If the container exceeds the limits for Low Specific Activity and contains water and/or organic substances which could radiolytically generate combustible gases, determination must be made by test and measurements of a representative package such that the following criteria are met over a period of time that is twice the expected shipment time:

(I) The hydrogen generated must be limited to a molar quantity that would be no more than 5.> by volume of the container gas void; or (2) The container and shipping cask cavity must be inerted with a dilutent to assure that oxygen is limited to less than 5X by volume in those portions of the package which could have hydrogen greater than SX.

AD-QA"311 Revision 9 Page 23 of 57 Solidification Agent Control

a. Portland Cement - ASTM C-150 Type I shall be used for the mobile st idification process.

b. Other solidification agents may be used only after acceptable testing of the agent has been completed that demonstrates acceptable solidification.

C. Documented Certification is not required for materials received in bags provided material verifica ion can be obtained as follows:

( 1) Cement is acceptable provided the bag containing the cement indicates that cement is Portland Type I.

(2) Sodium Silicate is acceptable provided the bag containing the additive indicates Anhydrous Sodium Metasilicate and is a product of PQ Corporation.

(3) Other additives are acceptable provided the bag containing the additive is clearly marked indicating the type of additive.

d. Other additives may be used for enhancement of solidification process as specified in the operating procedure and documented on the solidification record sheet.

Radioactive Waste Solidification Records A Solidification Record Sheet ( Form AD-QA-311-1) shall be completed for each liner filled with solidification products.

Guidelines for complet'ing the Solidification Record Sheet are attached to each part of the form. Parts of the form shall be completed by the following responsible individuals or groups:

a. The Radwaste Supervisor is responsible for initiating this form.

b. Part I, Solidification Record Sheet cover page, shall be completed by the Radwaste Supervisor.

Part II, Sampling and Pre-Solidification Analysis shall be completed by Chemistry Group.

AO-gA-311 Revision 9 Page 24 of 57 Part III, Container Selection shall be completed by the Radwaste Supervisor.

Part IV, System Preparation and Processing shall be completed by vendor personnel and Radwaste Supervisor.

Part V, Solidified Liner Data shall be completed by Health Physics Supervision-Radwaste.

c. guality Control shall provide verification as required in the Solidification Record Sheet.

6.4 Radioactive Waste Oewatering 6.4. 1 General Requirements

a. Oewatering of Radioactive Waste shall be performed by qualified SSES or vendor personnel.

b. Oewatering of Radioactive Waste shall be performed in accordance with approved operating procedures.

C. Oewatering procedures shall be based on documented test data that has demonstrated the ability to achieve drainable water limits as specified by burial sites and applicable regulatory agencies.

d. High Integrity Containers must be used for, the disposal of unsolidified solid waste when the concentration of radionuclides with half-lives greater than 5 years exceeds I pCi/cc.

6.4.2 Oewatered Product Control a ~ The final dewatered product shall contain less than lFo free standing liquid for High Integrity Containers and 0.55 for steel liners. guality Control checks will be performed on process steps.

b. Deviation from the container checking requirement shall be approved by the Power Production Engineer-Radwaste.

AO-QA"311 Revision 9 Page 25 of 57 6.4.3 Radioactive Waste Oewatering Records A Oewatering Record Sheet (Attachment B, Form AO-QA-311-2) shall be completed for each container filled with dewatered resins. Guides for completing the Oewatering Record Sheet are attached to each part of the form. Parts of the form shall be completed by the following responsible individuals or groups:

a. The Radwaste Supervisor is responsible for initia ing this form and completing Part I.

b. Part II Sampling and Pre Oewatering Analysis shall be completed by Chemistry Group

c. Part III Container Selection shall be completed by Radwaste Supervisor.

d. Part IV Dewatering operation documentation shall be completed by qualified person. completing various operations.

e. Part V Oewatered container data shall be completed by HP technicians, and HP Foreman-Radwaste as applicable.

f. Quality Control personnel shall provide verification as required by the Dewatering Record Sheet.

6.4.4 High Integrity Containers (HIC)

a. Storage of High Integrity Containers (I) Radlok and CNSI High Integrity Containers (HIC) stored in direct sunlight or in areas where there is a strong source of ultraviolet radiation must be filled within one year of manufacturing date.

(2) Radlok High Integrity Containers stored away from any sources of ultraviolet radiation must be filled within two years of manufacturing date, or specific guidance from the vendor must be obtained.

(3) Once filled a Radlok High Integrity Container may be stored in an approved storage facility for up to (5) five years prior to burial.

(4) Once filled a CNSI High Integrity Container may be stored for a period until one (I) year of ultraviolet radiation is received.

AO-QA-311 Revision 9 Page 26 of 57 (5) Short exposures (i.e., several hours) to sunlight, such as occur ring during shipment and on site transfer need not be counted when determining total ultraviolet exposure.

b. Uses of High Integrity Containers

( I) High Integrity Containers may-be used to package the following waste materials for burial at Barnwell, South Carolina low level waste burial site:

- Oewatered bead ion exchange resin

- Oewatered powdered ion exchange resin

- Activated carbon, powdered carbon, diatamaceous earth and other granular or fiberous filter material

- Cartridge filter elements

- Filter sludge

- Sand blasting grit 'and crud

" Stabilized incinerator ash

- Other dewatered and dry material provided concurrence is received by container vendor and burial site.

(2) Prior to using a High Integrity Container for a specific waste material, procedures shall be established to define the specific requirement that shall be met during use of the container.

The procedure shall contain:

- Documentation requirements that specific conditions have been met such as inspection and exposure to degrading'conditions.

- Instructions as to how to handle and properly close the container.

- Instructions for on-site storage of loaded containers for ultimate shipment for disposal.

AD-QA-311 Revision 9 Page 27 of 57 (3) The procedures shall provide a method for documenting required information relevant to the container from initial receipt to shipping for disposal.

Required information shall be based upon the container certificate of compliance and disposal site requirements.

Retention and utilization of the documentation shall be defined in the procedures.

The procedures shall establish specific Quality Control inspection requirements.

(4) The Radwaste Supervisor shall assure that SSES is an authorized user of High Integrity Containers (HIC) used at SSES for the purpose of Radwaste disposal prior to use of a specific type HIC.

(5) Prior to the first shipment of a specific type of High Integrity Container, authorization shall be.

requested and received from the applicable regulatory agency governing use of the container in question at the disposal site of concern.

High Integrity Container Limitations High Integrity Containers are approved for use provided the following physical limitations of the waste are met:

(a) Bulk density 0.7 to 2.5 gms/cc (b) pH 4 to 11 (c) Loading temperature <140 F (d) Radlok 100 loaded weight: <10500 lb (e) Radlok 200 loaded weight: <5500 lb (f) Radlok 55 loaded weight <950 lb (g) CNSI 14-195 loaded weight  : <12200 lb (h) CNSI 14-170 loaded weight: <10800 lb (i) CNSI 8-120 loaded weight: <17500 lb

AO-QA-311 Revision 9 Page 28 of 57 (i) CNS I 6-80 loaded weight ". <5000 lb (k) CNSI 24-INCH FRP loaded weight <1600 lb (l) Radlok 500 loaded weight  : <9500 lb (m) Radlok 179 loaded weight  : <14000 lb (n) Radlok 195 loaded weight  : <15500 lb 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 uCi/cc.

The following chemicals are prohibited and may not be disposed of in High Integrity Containers.

(a) Aqua Regia (b) Bromine (c) Chromi c/Su 1 i fur c Acid (d) Fuming Sulfuric Acid (e) Nitric Acid >50% concentration (f) Organic peroxides (g) Phenol-concentrated (h) Acetone (i) Butane (S) Carbon Oisulphide (k) Chloroform (l ) Ethyl Ether (m) Ethylene Dichloride (n) Methylene Chloride (o) Methyl Ethyl Ketone

AO-QA-311 Revision 9 Page 29 of 57 (p) Propane (q) Pentane

d. Closure of High Integrity Containers

( 1) Closure of High Integrity Containers shall be completed in accordance with approved procedures.

(2) If the container contents are within the limits of Low Specific Activity ensure the following:

(a) The container is shipped within ( 10) ten days after sealing; or (b) If the container has been sealed for longer than (10) ten days, it shall be opened, vented, and then closed and shipped within (10) days.

(3) If the container exceeds the limits for Low Specific Activity or contains water and/or organic substances which could radiolytically generate combustible gases, determination must be made by test and measurements of a representative package such that the following criteria are met over a period of time that is twice the expected shipment time:

(a) The hydrogen generated must be limited to a molar quantity that would be no more than 5<<

by volume of the container gas void; or (b) The container and shipping cask cavity must be inerted with a di lutent to assure that oxygen is limited to <5% by volume in those portions of the package which could have hydrogen greater than 5'.

6.5 Container Inspections Quality Control shall inspect containers to be used for solidification and dewatering.

6.5. 1 This inspection shall assure High Integrity Containers are acceptable for use in accordance with the Certificate of Compliance.

AO-QA-311 Revision 9 Page 30 of 57 6.5.2 This inspection shall assure that prior to use, the containers to be used for solidification or dewatering are intact and their internals are free of any visual damage that would prevent them from performing their intended function.

6.6 Waste Container Space Utilization 6.6.1 Waste volume shall be maximized within the guidelines of specific operating procedures to minimize potential void space at the top of waste container after solidification or dewatering is complete.

6.6.2 Specific waste volumes committed to by the vendor shall be met or otherwise-justified as to why waste volumes were not achieved.

6.6.3 Susquehanna Guaranteed Waste Volume Record, Attachment C, will be completed by vendor personnel and shall be used to track waste volumes achieved in each individual container.

6.7 Changes to the Solid Radioactive Waste Process Control Program 6.7. 1 Any changes to Solid Radioactive Waste Process Control Program shall be provided in the semiannual Radioactive Effluent Release Report filed with the NRC.

6.7.2 Any changes to the Solid Radioactive Waste Process Control Program shall be approved by Plant Operations Review Committee (PORC) prior to implementation.

6.8 Equipment calibrations shall be in accordance with AD-QA-605, Calibration of Installed Plant Instrumentation.

7.0 RECORDS

7. 1 The Solidification Record Sheet or Dewatering Record Sheet and the attached Isotopic Analysis shall be forwarded to the HP Supervision-Radwaste for retention until such time as the liner/container identified on Record Sheet is shipped for final disposition.

7.2 When the identified liner /container is shipped the Solidification Record Sheet or Dewatering Record Sheet and other documents concerning the Shipment shall be forwarded to DCC for retention.

Attachment A AO-QA-311 Revision 9 Page 31 of 57 SOLIOIF ICATION RECORO SHEET Part I: Cover Page Liner Identification Number Z. Waste Type (Powdered Resin cannot be ente. ed)

3. Batch No ~

4. Waste Volume Test Solidification required? YES NO (circle one)

6. Approval for use Radwaste Supervisor FORM AO-QA-311"1, Rev. 9, (OUPLEX) Page 1 of 14, (File R24-1)

Attachment A AD-QA-311 Revision 9 Page 32 of 57 Part I; Cover Page Instructions

a. Step 1

- Enter PP&L liner identification number from Radwaste Supervisor Log Book.

b. Step 2 - Enter waste type to be processed. Powdered Resin cannot be entered. Technical Specification 3/4. 11.3 must be performed.

c. Step 3 - Enter the batch number associated with this process from Radwaste Supervisor Log Book for this waste type.

d. Step 4 - Enter volume of waste in container to be solidified.

e. Step 5 - Identify if a test solidification is required based on information contained in Radwaste Supervisor Log Book for this waste type.

f. Step 6 - Radwaste Supervisor signature indicates approval for sampling and test solidification if required.

FORM 'AD-QA-311-1, Rev. 9, (DUPLEX) Page 2 of 14, (File R24-1)

Attachment A AD-QA"311 Revision 9 Page 33 of 57 SOLIDIFICATION RECORD SHEET Part II: Sampling and Pre-Solidification Analysis

l. Tank/Liner sampled Waste Volume

2. Sample Number

3. Waste Type'.

Wet WT.  ; settled solids

b. WT.  % Sodium Sulfate

c. '~ Water by volume

d. 'H

4. Waste sample density gm/ml

5. Oil Content (check a or b, or enter,o by volume in c)

a. None I

Less than 1-c ~ xo ol 1

6. Isotopic Analysis Attached By

7. Specific activity of sample pCi/gm

8. Test Solidification density gm/cc Include nomenclature of type of Waste Type, i.e. bead resin, mixed solids, oil, or combination, etc, n

FORM AD"QA-311-1, Rev. 9, (DUPLEX) Page 3 of 14, ( File R24-1)

Attachment A AO-QA-311 Revision 9 Page 34 of 57 Part II: Sampling and Pre-Solidification Analysis Instructions NOTE: If any of these steps or part of a step is not required by the specific test 'solidification procedures mark it as N.A.

a. Step 1

- Identify which tank/liner that is to be processed and volume.

b. Step 2 - Enter sample number.

c. Step 3 - Enter waste type, wet weight percent settled solids, weight percent sodium sulfate, percent water by volume of sample, and pH of sample waste.

d. Step 4 - Enter density of the sample taken from tank/liner. Be sure to use density of whole sample not just of liquid phase.

e ~ Step 5 - Check off quantity of oil in the sample by noting either "none", less than one percent, or indicating percentage of oil.

Step 6 - Chemistry Technician initials indicating that a copy of the isotopic analysis is attached.

Step 7 - Based on isotopic analysis attached enter the specific activity.

h. Step 8 Oetermine test solidification density and enter results.

FORM AO-QA-311"1, Rev. 9, (OUPLEX) Page 4 of 14, (File R24-1)

Attachment A AD-QA-311 Revision 9 Page 35 of 57

9. Mixing Recipe Waste lbs/ft'f waste ft'ement Sodium Silicate 1bift of waste Water Type Other additive gals.

gals.

gals.

10. Test Solidification Completed Acceptable YES NO (circle one)

By ll. Cure time required hours.

12. The above tank/liner has been analyzed and is acceptable for solidification at the indicated mixing ratios.

Chemistry Supervision Date Time FORM AD"QA"311-1, Rev. 9, (DUPLEX) Page 5 of 14, (File R24-1)

Attachment A AD-QA"311 Revision 9 Page 36 of 57 PART II INSTRUCTIONS Cont'd

j. Step 9- Enter waste volume, cement volume, Sodium Silicate quantity and type, volume of other additives and water type (i.e., demin, LRW).

k. Step 10- Solidification Vendor initials indicating the test solidification is completed and Quality Control acceptability results.

l. Step 11- Enter number of hours the test solidification needed to cure.

m. Step 12" Chemistry Supervision reviews data and signs, with date and time, indicating waste or identi-fied tank/liner has been sampled and analyzed in accordance with approved procedures and is acceptable for solidification at indicated mixing recipe.

FORM AD-QA-311-1, Rev. 9, (DUPLEX) Page 6 of 14, (File R24-1)

Attachment A AD-QA-311 Revision 9 Page 37 of 57 SOLIDIFICATION RECORD SHEET PART III: Container Selection

1. Estimated Liner Dose rates mr!hr on contact mr/hr at 2 meters

2. Projected Curie Concentration uCi/gm

3. Waste Classification/Stability

4. Liner type used Type

5. Type cask to be used Type

6. PP&L Liner Identificiation Number

7. The above specified liner and cask have been determined appropriate for the solidified waste based on projected curie loading and dose rates Radwaste Supervisor Date Time FORM AD"QA-311-1, Rev. 9, (DUPLEX) Page 7 of 14, (File R24-1)

Attachment A AD-QA-311 Revision 9 Page 38 of 57 Part III: Container Selection Instructions

a. Step 1

- Based on isotopic analysis of waste to be solidified provide the estimated dose rates for the bare liner on contact and at a distance from the surface of 2 meters.

b. Step 2 - Enter projected curie concentration of solidified waste.

c. Step 3 - Enter expected waste classification and stability reauire-ment based on the isotopic analysis per 10CFR part 61 (i.e., A,B,C).

d. Step 4 - Identify type of liner to be used.

e. Step 5- Enter appropriate cask designation to be used for sh pment More than one designation may be entered.

f. Step 6 - Enter PP&L liner identification number.

g. Step 7 - The Radwaste Supervisor or his des'ignee shall sign, with date and time, that cask(s) and liner identified above are appropriate for waste to be solidified.

FORM AO-QA-311-1, Rev. 9, (OUPLEX) Page 8 of 14, (File R24-1)

Attachment A AD-QA-311 Revision 9 Page 39 of 57 SOLIDIFICATION RECORD SHEET Part IV: System Preparation and Processing

1. Liner Serial Number

2. PP&L Liner Identificat on Number stenciled on liner Liner ID. No. Confirm

3. Liner properly positioned and ALARA consideration made Confirm

4. Pretransfer requirements:

a. Operating procedure to be used OP-068- , Rev.

Confirm Verify be Liner apron installed Confirm Verify cd Fill Head Installed and Properly Secured Confirm Verify

d. The following checks are complete.

Confirm Verify (1) All transfer lines properly connected/secured.

(2) All transfer lines inspected for visible signs o'f wear'.

(3) Transfer line drain valves checked closed and capped.

(4) Proper transfer valve opened.

(5) Three way valve in "Fill" position.

(6) Communications established with Radwaste Operator.

Oewatering Hose Connected to Pump Skid Suction if required Confirm v'erify

f. High Level Alarm Probe Installed and Tested Confirm verify

g. Temperature monitoring ins rumentation installed Confirm Verify

5. Authorization to commence processing Raawaste Supervisor Cate Time FORM AD-QA-311-1, Rev. 9, (DUPLEX) Page 9 of 14, (File R24"1)

. Attachment A AD-QA"311 Revision 9 Page 40 of 57

6. Post Transfer requirements:

a. Transfer Lines Flushed and All Valves Secured Confirm Ve.ify

b. Fill Head Removed Confirm Ver i fy cd High Level Alarm'Probe Removed and Plug Replaced if required Confirm Veri;y

d. Inspection Plate Secured Conf rm Ver =y

7. Solidification parameters Calculated Actual Waste in liner Cement to be added to liner lbs lbs Bags Sodium Silicate to be added to liner lbs lbs Other additive added to liner Type lbs/ft /gallons Type lbs/ft'/gallons Calcium Hydroxide to be added to liner lbs lbs Vendor Technician Date Time QC Verification

8. Pre-Solidification requirements CAUTION FOR SOLIDIFICATION OF WASTE CONTAINERS WHICH WERE PREVIOUSLY USED, ANO EMPT.'"0 SY SLUCING SUCH AS SODIUM SULFATE, A SEPARATE BATCH NUMBER SHALL BE ASSIGNEC AND WILL REQUIRE SAMP'NG FOR TEST SOLiDIFICATION AND ISOTOPIC ANALYSIS.

a. Mixer Head Drive Assembly Installed and Secured Confirm

b. Flexcon Cement Feed Properly Installed "cnfirm

c. Hopper Installed and Slide Gate Opened Confirm

d. Cement Discharge Brushed Out Confirm

e. Cement Feed Ball Valve Opened Confirm FORM AD-QA-311"1, Rev. 9, (DUPI EX) Page 10 of 14, (File R24-1)

Attachment A AO-gA"311 Revision 9 Page 41 of 57

9. Authorization to commence solidification Radwaste Supervisor Date Time

10. Solidification Processing Data:

a. Time processing started Confirm

b. Time processing stopped Confirm

c. Hydraulic Pressure at pslg Conf irm

11. Post Solidification requirements:

a. Mixer Head Drive Assembly Removed from Liner and Installed in Stand Confirm

b. Vacuum Filter Cleaned and Emptied Confirm

12. Liner check for complete solidification and visible/drainable water.

a. Penetration check (6.3.6.d) gC Verification/Date/Time

b. Visible liquid (6.3.6.d) gC Verification/Date/Time

13. Curing time hrs. (A minimum of 30 hrs is required.)

14. Liner Volume Usage 100 x (Solidified Waste Vol. ft': Available Waste Vol ft') =

15. Supervisory review and Health Physics notification.

Liner 4 meets the following criteria:

a. TYPE: A, B, C (circle one)

b. ,Classification: STABLE/UNSTABLE (circle one)

c. >85/a Liner volume utilized: YES/NO (circle one)

Radwaste Supervisor Date Time FORM AD"gA-311-1, Rev. 9, (DUPLEX) Page 11 of 14, ( File R24-1)

Attachment A AD"gA-311 Revision 9 Page 42 of 57 Part IV: System Preparation and Processing Instruction NOTE: Processing vendor personnel shall complete all confirm and verify signoffs. If only one available, verification will be per Radwaste Supervisor direction.

Step 1

- Enter serial number of liner to be used.

b. Step 2 - Record PPKL liner identification number and confirm it is stenciled on liners Step 3 - Confirm liner is proper ly positioned and ALARA consideration has been made for shielding, spills and expected dose rates.

Step 4 - Confirm and verify pre-transfer requirements have been performed.

Step 5 - Radwaste Supervisor signs step indicating authorization to commence waste transfer.

Step 6 - Confirm and verify post transfer requirements have been performed.

g. Step 7 - Enter solidification parameters.

h. Step 8 - Confirm presolidification requirements have been performed Step 9 - Radwaste Supervisor signs step indicating authorization to commence solidification.

Step 10 - Enter Solidification Processing Data.

Step ll - Confirm Post Solidification requirements.

Step 12 - gC verification for hardness/solidification by manual penetra;ion tests and visual observation for liquid in liner.

Step 13 - The actual curing time prior to capping shall be entered here.

Step 14 - Calculate the Liner Volume Usage. If usage is less than B5'o',

the burial sites shall be notified.

o. Step 15 " Radwaste Supervisor will indicate the expected type o. waste classification based on the isotopic analysis, the waste classification process used and if 85.< or greater of the liner volume was utilized.

He then signs, indicating the release of liner to Health Physics.

FORM AD-gA-311-1, Rev. 9, (DUPLEX) Page 12 of 14, (File R24-1)

Attachment A AO-QA"311 Revision 9 Page 43 of 57 SOLIOIFICATION RECORO SHEET Part V: Solidified Liner Oata

1. Liner Identification No.

2. Liner Radiation Levels

a. Top mr/hr Bottom mr/hr 4 Quadrants 1 mr/hr 2 mr/hr 3 mr/hr 4 mr/hr

b. Smearabl e Acti vi ty dpm/100cm~

c. Container washdown / decon performed Yes/NR

d. Smearable activity after washdown/decon dpm/100cm~

(attach radiological survey form)

e. Liner ready for transfer to storage or shipment:

HP Technician Oate Time

3. Liner Capped Oate Time By

4. Shipment 0

5. Oestination HP Supervision-Radwaste Cate Time Quality Control Review Gate Time

6. REMARKS:

FORM AO-QA-311-1, Rev. 9, (OUPLEX) Page 13 of 14, (File R24-1)

Attachment A AO-QA"311 Revision 9 Page 44 of 57 Part V: Solidified Liner Oata Instructions

a. Step 1

- Enter PP&L liner identification number t'.

Step 2 - Complete radiological data and attach survey form to Solidification Record Sheet. If washdown is not required, enter "NR".

Step 2e - Health Physics shall verify and sign, with date and time, liner is ready for transfer to storage or for transfer directly to a shipping cask for transportation to a licensed burial site.

d. Step 3 - Enter date and time liner capped.

e. Step 4 - Enter transportation shipment number.

f. Step 5 - Enter the destination (e.g. burial site, LLRWHF, etc.) of liner. Health Physics and QC shall review and sign that procedure nas been properly followed.

g. Step 6 - Enter any remarks that may be related to this filled liner.

FORM AO-QA-311-1, Rev. 9, (OUPLEX) Page 14 of 14, (File R24"1)

Attachment 8 AD"QA-311 Revision 9 Page 45 of 57 OEWATERING RECORD SHEET Part I: Cover Page

1. Liner identification Number

2. Waste Type

3. Waste Volume

4. For High integrity Containers, documentation package complete per section 6.4.4.b(3) of this procedure. (QC acceptance tag, QC Verification Date Time letter from storeroom, etc.)

5. Approval for use.

Radwaste Supervision FORM AO-QA-311-2, Rev. 9, (DUPLEX) Page 1 of ll, (File R24-1)

Attachment B AO-QA-311 Revision 9 Page 46 of 57 Part I: Cover Page Instructions

a. Step 1

- Enter PP&L liner identification number from Radwaste S pervisor Log Book.

b. Step 2 - Enter the waste type identification (e.g., Bead resin, Powdex, carbon, etc.).

c. Step 3 - Enter volume of waste in container to be dewatered ~

d. Step 4 - initial to ensure all documents are together. QC verifies acceptable documentation package.

e. Step 5 - Radwaste Supervisor signa ure indicates approval of High Integrity Container to be used and the dewatering process to continue.

FORM AO-QA"311-2, Rev. 9, (DUPLEX) Page 2 of 11, (File R24-1)

Attachment B AD-QA-311 Revision 9

'age 47 of 57 OEWATERING RECORD SHEET Part II: Sampling and Pre-Oewatering Analysis

1. Tank/Liner sampled Waste Volume

2. Sample Number

3. Waste Type a ~ pH of liquid contained within solids if a Carbon Steel liner is used pH

b. Oil Content (check one)

None less than 15

4. Isotopic Analysis at. ached By

5. Specific activity of Oewatered Sample pCi/gm

6. Sample density gm/cc

7. The above tank/liner containing solids has been sampled and found to contain the isotopes and specific activities as indicated on the attached data sheets.

Chemistry Supervision Date Time FORM AO-QA-311-2, Rev. 9, (DUPLEX) Page 3 of ll, (File R24-1)

Attachmen't B AO-QA-311 Revision 9 Page 48 of 57 Part II Sampling and Pre-Oewatering Analysis Instructions

a. Step 1 - Identify which tank/liner that is to be processed and volume.

b. Step 2 - Enter sample number.

c. Step 3 - Enter waste type, pH and oil determination results.

f. Step 4 - Chemistry Technician initials indicating isotopic analysis is attached.

g. Step 5 - Based on isotopic analysis attached, enter specific activity.

h. Step 6 - Determine sample density and enter results.

i. Step 7 - Chemistry Supervision shall sign with date and time indicating identified tank/liner has been sampled and analyzed in accordance with approved procedures.

FORM AO-QA-311-2, Rev. 9, (DUPLEX) Page 4 of 11, (File R24-1)

Attachment B AO"QA-311 Revision 9 Page 49 of 57 OEWATERING RECORO SHEET Part III: Container Selection

1. Estimated Liner Oose Rates mr/hr on contact mr/hr at 2 meters

2. Projected Curie Loading pCi/gm

3. Waste Classification/Stability

4. Liner type used Type

5. Type cask to be used Type

6. PP&L Liner Identification Number

7. The above specified container and cask have been determined appropriate for the dewatered waste based on projected curie loading and dose rates.

Radwaste Supervisor Oate Time FORM AO-QA"311-2. Rev. 9, (OUPLEX) Page 5 of 11, (File R24-1)

Attachment B AO"QA"311 Revision 9 Page 50 of 57 Part III Container Selection Instructions

a. Step 1 - Based on isotopic analysis of the material to be dewatered provide the estimated dose rates for the bare container on contact and at a distance of 2 meters from the surface.

b. Step 2 - .Enter projected curie concentration on dewatered waste.

c. Step 3 - Enter expected waste classification and stability requirements based on the isotopic analysis per 10CFR part 61 (i.e., A, B or C).

d. Step 4 - Identify type of container to be used.

e. Step 5 - Enter the appropriate cask designation to be used for shipment.

More than one designation may be entered.

f. Step 6 - Enter PP8L liner identification number.

g. Step 7 - The Radwaste Supervisor or his designee shall sign, with date and time, that cask(s) and container identified above are appropriate for, waste to be dewatered.

FORM AO-QA-311-2, Rev. 9, (OUPLEX) Page 6 of ll, (File R24-1)

Attachment B AD-QA-311 Revision 9 Page 51 of -57 OEWATERING RECORD SHEET Part IV: System Preparation and Processing

1. Liner Serial Number

2. PP&L Liner Identification Number stenciled on liner Liner IO. NO. Confirm

3. Liner Properly Positioned and ALARA considerations made.

Confirm

4. Pretransfer requirements

a. Operating procedure to be used OP-068- , Rev.

Confirm Verify

b. Liner apron installed Confirm Verify

c. Fill Head Installed and Properly Secured if required Confirm Verify

d. The following checks are complete.

Confirm Verify

( 1) All transfer lines properly connected/secured.

(2) All transfer lines inspected for visible signs of wear.

(3) Transfer line drain valves checked closed and capped.

(4) Proper transfer valve opened.

(5) Three way valve in "FILL" position.

(6) Communications established with Radwaste Operator.

Oewatering Hose Connected to Pump Skid Suction Confirm 'reri;y

f. High Level Alarm Probe Installed and Tested Confirm Verify

g. Temperature monitoring instrumentation installed Cor.firm ve,i;y

5. Authorization to commence'processing.

Radwaste Supervisor Gate Time FORM AO-QA"311-2, Rev. 9, (OUPLEX) Page 7 of 11, (File R24-1)

I Attachment B AO-QA-311 Revision 9 Page 52 of 57

6. Post Transfer Requirements

a. Transfer Lines Flushed and All Valves Secured Confirm Verify

b. Fill Head Removed if required Confirm Veri;y

c. High Level Alarm Probe Removed and Plug Replaced if required Confirm Veri fy

d. Inspection Plate Secured if required Con.i rm Verify

7. Authorization to commence dewatering.

j Radwaste Supervi sor Oate Time

8. Attach the complete specific operating procedure check off sheet for the specific'ewatering container being used. (QC verification is performed in accordance with the procedure.) By

9. Container Volume Usage 100 x (Oewatered Waste Vol. ft': Available Waste Vol. ft') =

10. Supervisory review and Health Physics notification.

Liner 0 meets the following criteria:

a. TYPE: A, B, C (circle one)

b. Classification: STABLE/UNSTABLE (circle one)

c. >85~ Container Volume Utilized: ". S/NO (ci.cle one)

Radwaste Supervisor Date Time FORM AO-QA-311"2, Rev. 9, (OUPLEX) Page 8 of 11, (File R24-1)

Attachment B AD"QA-311 Revision 9 Page 53 of 57 Part IV System Preparation and Processing Instruction r

NOTE: Processing vendor personnel shall complete all confirm and verify signoffs. If only one available, verification will be per Radwaste Supervisor direction.

a. Step 1

- Enter serial number of liner to be used.

b. -

Step 2 - Record PP&L liner identification number and confirm it is stenciled on container.'.

Step 3 - Confirm. container is properly positioned and ALARA considerat.on has been made for shielding, spills and expected dose rates.

d. Step 4 - Confirm and verify pre-transfer requirements have been performed.

e. Step 5 - Radwaste Supervisor signs step indicating authorization to commence transfer.

f. Step 6 - Confirm and verify Post-transfer requirements have been performed.

g. Step 7 - Radwaste Supe~visor signs step indicating authorization to commence dewatering.

h. Step 8 - Confirm any procedure checklist and data forms used are attached.

i. S.tep 9 - Calculate the Container Volume Usage. If usage is less than 855, burial site criteria shall be reviewed to determine appropriate actions

j. Step 10 - Radwaste Supervisor will indicate the expected type of waste classi-fication based on isotopic analysis, the waste classification process used and if 855 or greater of the container volume was utilized.

He then signs, indicating release of container to Health Physics.

FORM AD-QA"311"2, Rev. 9, (DUPLEX) Page 9 of 11, (File R24-1)

Attachment B AO-QA-311 Revision 9 Page 54 of 57 DB/ATERED RECORD SHEET Part V: Oewatered Container Data

1. Liner Identification No.

2. Container Radiation Levels

a. Top mr/hr Bottom mr/hr 4 Quadrants 1 mr/hr 2 mr/hr 3 mr/hr 4 mr/hr

b. Smearable Activity dpm/100cm~

c. Container washdown/decon performed Yes/NR

d. Smearable activity after washdown/decon dpm/100cm~

(attach radiological survey form)

e. Container ready for transfer to storage or shipment HP Technician Date Time

3. Container capped or sealed Date Time By

4. Shipment ¹

5. Destination HP Supervision-Radwaste Date Time Quality Control Review Date Time

6. REMARKS:

FORM AO-QA-311-2, Rev. 9, (DUPLEX) Page 10 of 11, (File R24-1)

IS Attachment B AD-QA-311 Revision 9 Page 55 of 57 Part V: Dewatered Container Data Instructions

a. Step 1 - Enter the PP&L liner identification number.

b. Step 2 - Complete radiological data and attach survey form to Oewatering Record Sheet. If washdown is not required, enter "NR".

c. Step 2E Health Physics shall verify and sign with date and time, con.ainer is ready for transfer directly to a shipping cask for transportation to a licensed burial site.

d. Step 3 - Enter date and ime container is capped or sealed.

e. Step 4 - Enter the transportation shipment number.

f. Step 5 " Enter the destination (e.g. burial site, LLRWHF, etc.) of liner.

Health Physics and QC shall review and sign that procedure has been properly followed.

g. Step 6 - Enter any comments of remarks that may be related to filled container.

FORM AD-QA-311"2, Rev. 9, (DUPLEX) Page 11 of 11, (File R24-1)

Attachment C AO-QA"311 Revision 9 Page 56 of 57 SUSQUEHANNA GUARANTEED WASTE VOLUME RECORD

l. Date Liner number,

2. Waste Type

3. Container Type 4 ~ Burial Volume

5. Useable Container Volume

6. Guaranteed Minimum Waste Volume

7. Waste Volume Attained inches x ft'/inch =

8. Waste Volume Container Usage 100 x (Waste Vol.

t ft': Guaranteed Min. Waste Vol. ft') -100 = 0/

10

9. Remarks:

10. Signature Solidification Vendor Representative 1

11. Signature Radwaste Supervisor FORM AO"QA"311-3, Rev. 2, (DUPLEX) Page .'f 2, (File R24-1)

l s

0 Attachment AD-QA"311 Revision Page 57 9

of C

57 INSTRUCTIONS SUSQUEHANNA GUARANTEED WASTE VOLUME RECORD

a. Step 1

- Enter date and PPBL Liner Identification number.

b. Step 2 - Enter type of waste processed, (e.g., Bead Resin, Powdered Resin, etc.).

]

c. Step 3 - Enter container type used.

d. Step 4 - Enter burial volume associated with this container.

e. Step 5 - Enter usable container volume for container specified in Step 3.

f. Step 6 - Enter Guaranteed Minimum Waste Volume in cubic feet.

g. Step 7 - Enter waste volume attained in inches (measured from bottom of container) and calculate cubic feet.

h. Step 8 - Calculate waste volume container usage.

i. Step 9 " Remarks " this section is used to explain all waste shortages or waivers to guarantee.

j. Step '10 - The solidification vendor representative signs indicating all the information contained on this document is correct.

k. Step 11 - The Radwaste Supervisor signs indicating agreement with the tnfor-mation contained on this documents 0 FORM AD-QA-311-3, Rev. 2, (DUPLEX) Page 2 of 2, (File R24-1)

SECTION 4 REPORTS OF EXCEPTIOiV TO THE SSES EFFLUENT MONITORING PROGRAM There were no instances during the report period in which airborne or waterborne effluent monitoring instrumentation was declared inoperable and was not restored to operability within the time period specified in Technical Specificaton Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

86

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