Text

Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1984
	ML20099M438
Person / Time
Site:	Susquehanna
Issue date:	12/31/1984
From:	Doty R, Shank K, Widner T; PENNSYLVANIA POWER & LIGHT CO.
To:	Murley T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	PLA-2420, NUDOCS 8503250216
	Download: ML20099M438 (139)
	v • d • e

i SUSQUEllANNA SIEAM ELECTRIC STATION SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT REPORT PERIOD: 07/01/84 - 12/31/84 Prepared by: . -

Jf/s7 T.E. Widner licalth Physicist Reviowed: b, dt7 .2h6k5' K.E. Shank' / '

Envi ntal Group Supervisor- Nuclear Approved: 10 /d,( ! -a 66 RlL. Doty' ~'

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Radiological & Envifehmental Services Supervisor Pennsylvania Power & Light Company Two North Ninth Street Allentown, Pennsylvania 18101 h(@h '

B503250216 841231 PDR ADOCK 05000387 R PDR

TABLE OF CON'IDTTS SECTION PAGE

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

2. Effluent and Waste Disposal Data.................. 9

3. Meteorological Data and Dispersion Estimates...... 24

4. Dose Measurements and Assessments................. 56

'5. Qianges to the Offsite Dose Calculation Manual and the Solid Waste Process Control Pr @ a...... 64

6. Reports of Exception to the SSES Effluent '

Monitoring Program.............................. 137 e

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LIST OF TABLES PAGE

. Table 1: Supplemental Information.......................... 6 Table 2: Airborne Effluents- Summation of All Releases..... 10 Table 3: Airborne Effluents................................ 11 Table 4: Waterborne Effluents- Sm mation of All Releases... 12 Table 5: Waterborne Effluents.............................. 13 Table 6: 16

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Solid Waste and Irradiated Fuel Shipments.........

Table 7: Solid Radioactive Waste- Class A.................. 17 Table 8: Solid Radioactive Waste- Class B.................. 20 Table 9: Solid Radioactive Waste- Class C.................. 21 Table 10: Estimated Total Errors Associated with Effluent Measurements..................................... 22 Table 11: EffluentDatahotAvailableforPrevious Semiannual Report........./...................... 23

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Table 12: Meteorological Data Availab111ty.................. 26 Table 13: Joint Wind Frequency Distributions by Stability Class.................................. 30 Table 14: Average Annual Relative Concentrations............ 48 Table 15: Maximum Off-Site Doses and Dose Commitments to Members of the Pub 11c............................ 57 Table 16: Collective Doses to Members of the Public Within the Riverlands/Infomation Center Complex. 62

. Table 17: Calculated Doses at the Residences in the Southeast Sector Within the Site Boundary........ 63 e

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LIST OF FIGURES PAGE Figure 1: Airborne Effluent Rolcaso Point Locations....... 4 Figure 2: Waterborne Effluent Pathway..................... 5 Figure 3: Susuehanna River Monthly Average Flow Rates.....~14 Figure 4: Monthly Liquid Radwaste Discharge Totals....... 15 Figure 5: SSES Winct Rose: 10-meter Sensors . . . . . . . . . . . . . . . 27 Figure 6:' SSE3 Wind Rose; 60-meter Sensors. . . . . . . . . . . . . . . 28 Figure 7: Pasquill Stability Class Prevalences........... 29 Figure 8: Areas Within the SSES Site Boundary Open to Members of the Public...................... 61 e

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6 SECTION 1 INIRODUCTION AND SUPPLBENTAL IhTORh% TION M

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INIRODUCTION h e 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. h e Station consists of two boiling water reactor generating units, each with 1,050 MW net electrical capacity. h e 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 i' in Unit 1 in July of 1982. Initial criticality was achieved in the Unit I reactor on September 10, 1982. H e reactor reached 100% power for the first time on February 4 ,1983. Consnercial operation of Unit 1 was declared on June 8, 1983. Initial criticality of Unit 2 occurred on May 8.-1984. Unit 2 was declared commercial 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 Specificntions.

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.

h e diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. H e diffuser serves to rapidly and uniformly mix the the station discharge with the main flow of the river. Figure 3 presents monthly average flow rates for the Susquehanna River at-the SSES Biological Laboratory.

his report presents a sununary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during

- the period from July 1,' 1984 to December 31, 1984, his report also includes meteorological data and dispersion estimates for the calendar year 1984, and assessments of the doses to members of the public both within the site boundary and in unrestricted areas. In addition, this report serves as a medium for notifying the US Nuclear Regulatory Commission staff of changes to PP&L's Off-Site Dose Calculation Manual (ODCM) and Solid Waste Process Control Program (PCP) and doctanentation 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 Susquehanna. 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 summation of all airborne releases, grouped into the radionuclide categories of gases, particulates, lodines, and tritium.

. Average release rates are presented and compared to the applicable limits. Table 3 presents the totals of specific radionuclides in airborne effluents.

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Watcrborna effluents era numarized in Taolo 4. Averaga diluted concentrations era prtsented and compared to the applicablo limits.

Table 5 presents the release quantities of specific radionuclides in waterborne effluents over the report period. Figure 4 presents the monthly discharge totals of 11guld waste from SSES during 1984.

Tables 6 through 9 present a characterization of the solid radioactive waste shipped off site during the report period. Included are the i volumes and curie contents associated with each type of solid waste.

An estimate of major nuclide composition is presented for each waste type, as well as the number of waste shipments from the site, how they

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were transported, and,their final destination.-

Table 10 contains estimates of the errors associated with the measurements involved in quantifying effluents. Sampling errors, counting errors, and errors associated with detemining effluent flow rates and volumes all

! contribute to the total error of effluent measurements. Error estimates I

are presented for each category of radionuclide detected in airborne and watteborne effluents and solid wastes during the report period.

Table 11 presents effluent data from previous report periods which was not available at' preparation time for the associated semiannual report.

}- Section 3 of this report contains the meteorological data associated with the year 1984. Availability statistics for the SSES me.teorological data are shown in Table 12. Meteorological data for the calendar year 1984 is presented in the form of joint wind frequency distributions by atmospheric stability class. These distributions are. presented as Table 13.

Figures 5 and 6 are wind rose plots for the SSES primary meteorological tower 10 m and 60 m sensors, respectively. Figure 7 presents the relative

__ _ prevalences of the Pasquill stability classes for 1984. In addition, the meteorological data from the report year were used to generate annual average relative concentrations (X/Qs) and deposition rates (D/Qs). '

n ese values are presented in Table 14, and are required input for use of the GASPAR code for calculation of the doses resulting from airborne releases.

Section 4 of this report contains an assessment of the calculated doses attributed to the reported radiological effluents, he LADIAP II code was used for calculation of doses from waterborne effluents. h e GASPAR code was used for calculation of doses from airborne effluents. ,

l h ese calculated doses and direct radiation estimates can be used to estimate the doses to maximally exposed members of the public. Table 15 summarizes maximum calculated doses and dose comitments to members of l the public from waterborne and airborne effluents and direct radiation.

Section 5 of this report is reserved for documentation of changes to the Off-Site Dose Calculation Manual and the Solid Waste Process Control Program. H e July 9, 1984 revised pages of the ODCM are presented with changes noted. A revised copy of the administrative procedure which l

describes the Process Control Program is included along with a statement of the purpose and nature of the changes.

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Section 6 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrumentation was declared inoperable i and was not restored to operability within the time period specified in Techt.ical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

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RADIOACTIVE RADWASTE S' AREAS ,4 TREATMENT _ap. [

WATER SYGTEM 9 USES t RAW /

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- FIGURE 2 WATERBORNE EFFLUENT PATHWAY' i-l l .

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TABLE 1 SEMIANNUAL EFFLUENT f WASTE DISPOSAL REPORT- 1984

- SUPPM M NIAL INFORMATION j

1. Regulatory Limits

a. Fission and Activation Gases: 0.851 C1/ minute (Release rate limit

' based on Technical Specification dose rate limit of 500 mrem /yr from noble gases).

b. Iodine-131: 141 microcurfes/ minute (Release rate limit based on.

Technical Specification dose rate limit of 3.30C mrem /yr from iodine-131,ctritium, and particulates with half-lives greater than eight days).

c..Particulates: 772 microcuries/ minute (Release rate limit based om Technical Specification dose rate limit of 1500 mrem /yr from iodine-131, trititse, 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 S3ES Final Environmental Statement, NUREXI-0564).

2. Maxinnan Permissible Concentrations The concentrations of radioactive mater 4als in waterborne effluents are limited to the concentrations specified in 10CFR 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) asKr m 2 E-4 esKr 5 E-4 e7Kr 4 E-5 l 88Kr 9 E-5 41Ar 7 E-5 1ssXe m 5 E-4 issXe 6 E-4 tasXe m 2 E-4 1ssXe 2 E-4 These values are calculated using Equation 20 of ICRP Publication 2 (1959), adjusted for IN inite 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(L1) detector system which incorporates

'a data reduction program to determine radionuclide composition in ter1ns of specific activity. Data tapes from the continuous vent monitors are used to determine the average concentration of noble I

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gases. Ihn Ge(L1) isotopic acan in u:ed to conysrt thn continuous vent moniter ectivity to actual cctivity based on thn datermined nuclide mixture. H e 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.

W en the continuous monitors are out of service, manual grab samples are taken from each vent once each eight hours.

- b. Iodines: Iodine is continuously collected via an isokinctic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a Ge(L1) system. h e 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. He 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, lodine is continuously collected on charcoal cartridges attached to air samplers which draw directly frein the rooftop vent (s).

-c. Particulates: Particulates are continuously collected via an isokinetic sampling ass _embly in each vent. Filters are normally exchanged once per week and analyzed on a Ge(L1) system. Flow rate corrections are performed as for iodines. Wen the continuous vent monitors are out of service, particulates are continuously sampled directly from the affected rooftop vent (s).

d. Waterborne Effluents: Each tank of 11guld radwaste is sampled and analyzed for principle ganna emittges prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative saaple is obtained.

Samples are analyzed on a Ge(L1) 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.

h e monthly tritium analysis is done in-house. H e quarterly conposite 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 multiplied by the volume of the batch to detemine the total quantity of each nuclide released in each batch. The isotopic totals for each are summed to determine the total source tem for the report period.

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4. Batch R21ea::es

a. Waterborne

1. Ntanber of Batch Releases: 150

2. Total Time Period for Batch Releases: 3.46E+4 minutes

3. Maximum Time Period for a Batch Release: 305 minutes

4. Average Time Period for a Batch Release: 193 minutes

5. Minimum Time Period for a Batch Release: 20 minutes

6. Average Stream Flow During Period of -

Release of Effluent into a Flowing Stream: >5000 gpm (cooling tower blowdown)'

3.47E+6 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. Ntanber of Releases: O

2. Voltane Released: NA

3. Total Activity Released: NA

b. Airborne 0

1. Number of Releases:

2. Total Activity Released: NA Q

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9 SECIION 2 EFFLUENT AND WASTE DISPOSAL DATA M

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TABLE 2 SEMIANNUAL EFFLUENI AND WASIE DISPOSAL REPORT- 1984 AIRBORNE EFFLUEN13- SUMMATION OF ALL RELEASES j Nuclide Category Unit Ihlrd Quarter Fourth Quarter A. Fission and Activation Gases

1. Total Release 1 C1 24.78E+01 <8.66E+02 28.56E+00 <8.40E+02

2. Average Release Rate for Period uC1/sec 26.01E+00 <1.09E+02 21.08E+00 <1.06E+02

3. Percent-of Applicable Limita % 24.24E-02 <7 69E 01 27.59E-03 <7.45E-01 B. Iodine-131

1. Total Release C1- 28.94E-03 <9.26E-03 <5 00E-04 .

2. Average Release Rate for Period uC1/sec 21.12E-03 <1.16E-03 <6.29E-05

- 3. Percent of Applicable limita 2 24.77E-02 <4.96E-02 <2.68E-03 C. Particulates

1. Particulates with Half-lives >8 Days Released C1 21.62E-05 <2.10E-03 22.24E-03* <4.67E-03*

2. Average Release Rate for Period uC1/sec 22.04E=O6 <2.64E-04 22.82E-04* <5.88E-04*

3. Percent of .

Applicable Limita % 21.59E-05 <2.05E-03 22.19E-03 <4.57E-03

4. Gross Alpha Activity Released Ci <1.26E-06 <1 07E-06*

l D. Tritium

' 1. Total Release C1 26.46E+00 <1.39E+01 21.72E+01 <6.41E+01

2. Average Release Rate for Period uC1/sec 28.13E-01 <2.16E+00 22.16E+00 <8.06E+00

3. Percent of Applicable Limits % 21.67E-02 <4.43E-02 24.43E-02 <1.65E-01 l

1 Notation: Ihe first value presented (2) includes only activity positively detected at the 95% 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.

abased on release rate limit derived from dose rate Technical Specification.

j 3 Based on release rate corresponding to aH Maximum Pennissible Concentration in unrestricted areas (Relative concentration 4.1E-5 sec/m3 assumed).

Strontium and gross alpha values are estimated based on third quarter 1984 sample analyses and fourth quarter ventilation exhaust rates.

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TABLE 3 SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT- 1984 AIRBORNE EFFLUENIS (Curles)1 Nuclida Third Quarter Fourth Quarter 1

A. Gases esKr m 1.04E+01 2.60E+00 e7Kr < 6.44E+01 <7.52E+01 esKr 21.23E+01 < 6.49E+01 23.08E+00 <6.80E+01 tasXe m < 2.16E+02 <2.52E+02 tasXe 22.51E+01. < 1.10E+02 22.88E+00 <9.18E+01 tasXe a < 1.50E+02 <1.25E+02 tasXe < 2.34E+01 <2.58E+01 tseXe < 2.27E+02 .

<2.00E+02 Total 24.78E+01 < 8.66E+02 28.56E+00 <8.40E+02 B. Iodines-1st I. 28.94E-03 < 9.26E-03 <5.00E-04

'issI 7.23E-03 1.11E-04 C. Particulates with Half-lives > 8 d s1Cr 22.21E-03 <2.26E-03 s4Mn 29.00E-06 < 2.14E-04 <2.20E-04 BSFe < 2.96E-04 <3.26E-04

<1.86E-04

< 1.51E-04 seCo 22.71E-05 seCo < 2.34E-04 <2.53E-04 s5Zn < 3.21E-04 <3.69E-04 8SSr 27.20E-06 < 8.0DR-06 25.79E-06* <6.56E-06*

seSr 21.41E-08 < 7.39E-07 21.34E-08* <6.23E-07*

1:4Cs - < 1.22E-04 <1.43E-04 137Cs < 1.34E-04 - <1.56E , .141Ce < 1.21E-04 <1.62E-04 144Ce < 4.99E-04 e <5.86E-04 Total 21.625-05 < 2.10E-03 22.24E-03 <4.67E-03 1 Notation: The first value presented (2) includes only activity i

positively detected at the 95% confidence level. The second value

(<> incluoes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95% CL.

Estimated based on third quarter 1984 sample analyses and fourth quarter 1984 ventilation exhe;ust rates.

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TABLE 4 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT- 1984 WATERBORNE EFFLUENIS- SUhNATION OF ALL RELEASES Nuclide Category Unit Third Quarter Fourth Quarter A,. Fisalon & Activation Prcducts

1. Total Release 1 C1 27.34E-02 <1.01E-01 21.74E-02 <2.46E-02

2. Average Diluted Concentration uC1/ml 21.40E-07 <1.93E-07 21.21E-07 <1.72E-07

3. P(rcent of Applicable Limit 2 % 25.20E-03 <1.37E-01 22.27E-03 <4.16E-02 B. Tritium

1. Total Release C1 3.91E+00 1.33E+00*

2. Average Diluted Concentration uC1/ml 7.48E-06 9.28E-06

3. Percent of Applicable limit 3 % 2.49E-01 3.09E-01

. C. Dissolved and Entrained Gases

1. Total Release C1 25.03E-03 <2.17E-01 28.72E-04 <6.58E-02

2. Average Diluted Concentration uC1/ml 29.62E-09 <4.15E-07 26.08E-09 <4.59E-07

3. Percent of .

Applicable Limit 4 % 22.41E,,02 <1.04E+00 21.52E-02 <1.15E+00 D. Gross Alpha Radioactivity

. Released C1 <2.20E-04** <5.78E-05**

E. Voltane of Waste Released gal. 2.33E+06 6.11E+05 liters 8.81E+06 2.31E+06 F. Volume of Dilution Water Used gal. >1.36E+08 >3.72E+07 l liters >5.15E+08 >1.41E+08 i

2 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. The second value

(<> includes detected activity plus the Lower Limit of Detection l

values of any samples in which activity was not detected at the 95% CL.

abased on quarterly dose limits from liquid effluents, abased on the Maximum Pemissible Concentration for 3H in effluents to unrestricted areas.

4 Based on the most restrictive Maximum Pemissible Concentration i for a noble gas (87Kr) from SSES Tech Spec Table 3.11.1.1-1.

December tritium based on November sample due to loss of December sample.

- Based on sample analyses from August and September 1985 and release volumes from the applicable time period due to inavailability of July and 4th quarter gross alpha results at time of report preparation.

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TABLE 5 SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT- 1984 WATERBORNE EFFLUENIS (Curies)1 ;

Nuclide Third Quarter Fourth Quarter A. Tritium 3.91E+00 1.33E+00*

B. Fission and Activation Products a4Na 6.08E-02 1.2SE-03 s1Cr 9.21E-03 1.09E-02 s4Mn 21.57E-03 < 2.22E-03 21.49E-03 <1.64E-03 ssFe ,

< 7.06E <1.85E-03**

s9Fe < 2.50E 25.80E-04 <8.58E-04 seCo 21.42E-03 < 1.90E-03 21.53E-03 <1.60E-03 seCo 21.88E-04 < 1.73E-03 21.17E-03 <1.32E-03 ssZn < 2.80E-03 <5.66E-04 esSr < 3.53E-04 <9.24E-05**

seSr < 5.29E-05 <1.39E-05**

saSr 1.28E-04 j- s7Nb 5.69E-05 ssMo < 4.28E-03 <1.64E-03 11eAg a 8.61E-05 23.37E-04 <3.37E-04 11eAg 6.32E-05 1:1I 23.16E-06 < 7.23E 21.45E-05 <2.00E-04 134Cs < 8.59E-04 ~

<2.49E-04 tasCs 3.3 E-05 1a7Cg <.1.06E-03 <3.50E-04 141Ce < 9.90E-04 <2.80E-04 144Ce < 4.67E-03 <1.27E-03 Total 27.34E-02 < 1.01E-01 21.74E-02 <2.46E-02 C. Dissolved and Entrained Gases 41Ar < 1.17E-03 <3.12E-04 esKr m < 6.57E-04 <1.88E-04 e sKr - < 1.98E-01 <6.12E-02 e7Kr < 1.34E-03 <3.84E-04 eeKr < 1.44E-03 <4.12E-04 183Xe m < 5.33E-03 <1.42E-03 taaXe 23.31E-03 < 4,97E-03 23.76E-04 <7.44E-04 tasXe m < 1.66E-03 <4.66E-04 tasXe 21.72E-03 < 2.27E-03 24.96E-04 <6.41E-04 4

Total 25.03E-03 < 2.17E-01 28.72E-04 <6.58E-02 1 Notation: ihe first value presented (2) includes only activity 5 positively detected at the 95% 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.

December trititan based on November sample due to loss of December sample.

- Based on third quarter 1984 sample analyses and fourth quarter discharge volumes.

13

FIGURE 3 Susquehanna River ,

Monthly Average Flow Rates Data Period: 1984 cubic hieters per second 1600 k

. 1400 - i-+---- - + -- - -- - - - - +

i . .

1200 - - - - -- :- - -

i 1000- + +- ' +- - -

800 - - - - - - ;- - -

600 - -

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+

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i 400 - - - -

l i < -<- - - >- >-

200 g j - -

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FIGURE 4 Susquehanna Steam Electric Station MONTHLY LIQUID RADWASTE DISCHARGE TOTALS Data Period: 1984 gallons 1400000 b

-=- -=- =-

1200000- - - -- - -

1

-- =-

1000000-- - - - - - - - -- - - -

-l-800000- -

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600000- - -- - -- - -

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TABW 6 SD4IANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l SOLID WASTE AND IRRADIATED FUEL SHIPMENIS

. Data Period: July 1, 1984 - December 31, 1984 1

-A. SOLID WASIE SHIPPED OFF SITE FOR BURIAL OR DISPOSAL y Number of Shloments- . Mode of Tri-scortation Destination 43 Truck Barnwell, SC 12 Truck '

R1chland, WA-

'B. IRRADIATED FUEL SHIPE NIS Ntsnber of Shloments Mode of Transoortation Destination none- not applicable not applicable 16

TABW 7 Paga 1 of 3 SEMIANNUAL EFFLUENI AND WASTE DISPOSAL REPORT SOLID RADIACIIVE WASIE- CLASS A*

Data Period: July 1, 1984 - December 31, 1984 Source of Waste Condensate Reactor Water Reactor Water Liq. Radwaste and Processing Domineralizer Clean-up/ Fuel Clean-up/ Fuel Filters Fmployed (Bead Resin) Pool Clean-up Pool Clean-up (Filter Media.

(Waste Stream) (Powdex) (Powdex) Sludge, DE)

Container Volume (ft3) 3570 680 170 5950 Total Activity Content (Cl) 5.42 383.1 99.1 269.6 Above Deterssined By: ,

a) measurement b) estimation C 'C C C c) measurement and correlation factors Principle CR-51 36% FE-55 26% CR-51 46% FE-55 39%

Radionuclides E-54 15% W-54 .21% CO-60 17% CR-51 33%

(Identity and 00-60 14% C0-60 20% W-54 15% W-54 9%

Percent 00-58 12% CR-51 18% (X)-58 12% CO-60 8%

Ccepositlon) FE-55 12% C0-58 9% ZN-65 5% C0-58 6%

H-3 4% 2N-65 3% AG-110m 3% FE-59 5%

C-14 4% AG-110m 3% FE-59 2%

FE-59 3%

Above Detemined by:

a) measurement b) estimation C C C C c) measurement and

, correlation

, factors Type of Carbon Steel Carbon Steel High Integrity Carbon Steel Container Liners Liners Container Liners i

Solidification Agent or Portland Portland Dewatered Portland Absorbent Cement Cement Cement

As defined in 10CFR Part 61.

17

TAB W 7 Paga 2 of 3

. SEMIANNUAL EFFLLTNI AND WASTE DISPOSAL REPORT

SOLID RADIACIIVE WASIE- CLASS A*

' Data Period: July 1, 1984 - December 31, 1984 Source of Waste Condensate Plant and Processing Demineralizer Equipment Non- Compacted

. Employed Regeneration (011 and Compactable Trash (Waste Stream) (Evaporator Evaporator Trash Concentrates) Concentrates) ,

a Container j Volume (ft3) 1020 2040 1280 3390 i Total Activity 0.18 0.97 0.90 6.78 Content (C1)

Above Determined By:

a) measurement ,

b) estimation C C B B c) measurement ,

and correlation factors Principle FE-55 57%. FE-55 47% FE-55 54% FE-55 55%

. -Radionuclides H-3 25% C0-60 _15% MN-54 17% MN-54 17%

(Identity and 00-60 7% W-54 14% CO-60 15% C0-60 15%

Percent W-54 5% H-3 10% FE-59 7% FE-59 8%

Compositlon) 00-58 3% NI-63 9% CO-58 7% CO-58 5%

- CR-51 3% CR-51 5%

Above Determined by:

a) measurement b) estimation C C B B c) measurement and correlation factors t

i Type of Carbon Steel Carbon Steel 128 ft3 55-gallon Container Liners Liners Metal Boxes 17H Drums

! Solidification Agent or Portland Portland Not Not 1 Absorbent Cement Cement Applicable Applicable l[

As defined in 10CFR Part 61.

1 1

i

18 ,

TABLE 7 Pago 3 of 3 SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT SOLID RADIACTIVE WASTE- CLASS A*

Data Period: July 1, 1984 - December 31, 1984 Source of Waste and Processing ,

Employed Olly Waste (Waste Stream)

Container Voltane (ft8) 1882.5 Total Activity Content (C1) ,0.77 Above Determined By:

a) measurement b) estimation B c) measurement and correlation factors Principle FE-55 33%

Radionuclides H-3 22%

~

(Identity and CR-51 13%

Percent lei-54 12%

Composition) 00-60 10% .

00-58 5%

i FE-59 5%

Above Determined by:

a) measurement b) estimation B c) measurement and correlation factors Type of 55-gallon Container 17H Drums Solidification

, Agent or Oil-Dri Absorbent

As defined in 10CFR Part 61.

I 19

I TABLE 8 Paga 1 of 1 SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT SOLID RADIACTIVE WASTE- CLASS B*

Data Period: July 1. 1984 - December 31, 1984 Source of Waste l l and Processing Employed

NO CLASS B WASTE GENERATED *

(Waste Stream)

Container Volume (ft3)

Total Activity Centent (C1)

Above Determined By:

a) measurement l - b) estimation ,

c) measurement and correlation factors Principle Radionuclides ~

i (Identity and Percent Composition) i

- Above Determined by:

a) measurement b) estimation c) measurement i and

< correip. tion factors Type of .

Container

,- Solidification Agent or Absorbent l

l

As detined in 10CFR Part 61.

! 20

. - ~. -- .

b TABLE 9 Paga 1 of 1 SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT SOLID RADIACTIVE WASIE- CLASS C*

Data Period: July 1, 1984 - December 31, 1984 Source of Waste l l and Processing 1

Fmployed

NO CLASS C WASTE GENERATED *

(Waste Stream)

Container Volume (fta)

Total Activ'ity -

Content (C1)

Atuwe Detemined By:

a) measurement b) estimation c) measurement and correlation factors Principle '

Radionuclides

! (Identity and Percent Composition)

Above Determined by:

, a) measurement b) estimation c) measurement 4 and i

correlation factors Type of Container Solidification Agent or i

Absorbent

As defined in 10CFR Part 61.

l 21

TABLE 10 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPCfd ESTIMATED 'IUIAL ERRORS ASSOCIATED WITH EFFLUENT MEASUREMENIS Data Period: July 1, 1984 - December 31, 1984 Measurement Estimated Total Error

1. Airborne Etflut.nts

a. Fission and Acti.viation Gases 9.5 %

b. Iodines - 13 %

c. Partleulates 13 %

d. Trititan 11.4 %

2. Waterborne Effluents

s. Fission and Activation Products 7.5 %

b. Tritium 9.3 %

c. Dissolved and Entrained Gases 8.0 %

3. Solid Wastes -

s. Condensate Demineralizers 26 %

b. Reactor Water Clean-up and Fuel Pool Clean-up (Powdex, solidified) 26 %

c. Reactor Water Clean-up and Fuel Pool Clean-up (Powdex, dewatered) 26 %

d. Liquid Radwaste Filters 26 %

e. Condensate Demineralizer Regeneration 26 %

f. Solidified Oil 26 %

g. Non-Compactable Trash 30 %

h. Compacted Trash 30 %

1. Absorbed Olly Waste 30 %

2 22

TABLE 11 SEMIANNiiAL EFFLUENI AND WASTE DISPOSAL REPORT- 1981 EFFLUENT DATA NOT AVAILABLE FOR PREVIOUS SEMIANNUAL REPORT Nuclide Category Unit Second Quarter 1984 A. Airborne Effluents

1. *SSr Ci . 23.33E-06 <4.31E-06

2. seSr C1 <6.98E-07

3. Gross Alpha Radioactivity C1. 22.40E-07 <8.78E-07 B.~ Liquid Effluonts

1. s'Sr C1 <1.47E-04

2. seSr C1 <7.34E-05

3. ssFe C1 <5.87E-03

4. Gross Alpha Radioactivity C1 <2.55E-04 m

t e

p D 1

)

23 i

SECTION 3 MEIEOR000GY AND DISPERSION ESTIMATES O

m O

h 24

EIEOROLOGY AND DISPERSION DATA Meteorological data have been collected at the Susquehanna SES site since the early 1970s. At the present time, the meteorological system is based on a 300-foot high tower located approximately 1,000 feet to the southeast of the plant. Wind sensors are mounted at the 10-meter and 60-meter elevations on this tower. Vertical temperature differential is measured with redundant sensor pairs 'aetween the 10m and 60m levels. I Sigma theta (the standard deviation of horizontal wind direction) is i measured at both levels. Dewpoint and ambient temperature sensors are present at the 10m level. Precipitation is measured at ground level.

I A back-up meteorological tower was erected in 1982. It'is a 10-meter tower providing alternate measurements of wind speed, wind direction, and sigma theta.

SSES meteorological data is transmitted to the plant control room, Technical Support Center, and Emergency Operat' ions Facility for emergency response availability. The data is also transmitted via telephone line data-link to the Pl%L corporate computer in Allentown.

On the corporate computer, the data is available for preparation of stannary reports, wind rose plots, and dispersion estimates.

Dispersion modeling for effluents from nomal operation of SSES is done using ADSSES, a straight-line sector averaged Gaussian plume model designed to estimate average relative con _centrations. The model was developed in accordance with Regulatory Guide 1.111. Wind directions for calm periods are distributed in accordance with the directional I

distribution by stability class of the lowest wind speed class.

ADSSES uses terrain correction factors to account for the temporal and spatial variations in the airflow in the region, since a straight-line trajectory model assumes that a constant mean wind transports and diffuses effluents (in the wind direction at the release point) within the entire region of interest. The SSES terrain correction factors presented on the seventh page of Table 14 were determined as the ratio between puff-advection dispersion estimates and straight-line' dispersion estimates based on 1973-1976 meteorological data. The terrain correction factors are multiplied by the Intermediate results of the straight-line-

model to approximate puff-advection model results.

I

\

25

TAB [E 12 SEMIANNUAL EFFLUENT AND WASIE DISPOSAL REPORT hEIEOROUXIICAL DATA AVAILAILITY Data Period: 1984 Percent of Valid Parameter Hours Durine Period

1. Wind Speed a..Al1 Sensors Combined 99.83 %

b. 10-meter Sensors 99.83 %

c. 60-meter Sensor 87.47 %

2. Wind Direction

a. All Sensors Combined 99.75 %

b. 10-meter Sensors 99.69 %

c. 60-meter Sensor ., 78.16 %

3. Indicator of Atmospheric Stability _

a. Temperature Differential or Sigma Theta 99.83 %

b. Delta Temperature 97.89 %

c. Sigma Theta 97.84 %

26

" SUSQUEHANNA 77%

NNW MC STEAM ELECTRIC STATION 5.0% 8.7 %

WIND ROSE EURP' %?V&'(8/gf'2/3v84 22 ELEVATION: 10M yg

-l . 13.1%

- 3, g y 5%

l NNH ENE

? 9.1%

2.1%

gl 3

!! E Ux ] E 11 b

6.7%

3 ggg WIND SPEED KEY 10.1- M/SEC 7.6-10.0 M/SEC

! 51- 7 5 M/SEC Sw

' SE 3.1- 5.0 M/SEC -

11.8% 3.9%

1.6- 3.0 M/SEC

$ 0.0-1.s u/SEC x

l 5.4%

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FIGURE 7

.Susquehanna' Steam Electric Station Pasquill Stability Class Prevalences Based on the 10-meter Joint Wind Frequency Distribution By Stability Class Data Period: 1984 SUGHTLY UNSTABLE 4.4%

NEUTR'AL 34.6% UNSTABLE 2.7%

HIGHLY UNSTABLE 2.5%

HTLY STABLE I LY STABLE ST BLE 13.3 %

29

6

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TABLE 13 Page 8 of 18 h

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> SUSquEMA004A CTEAM ELECTRIC STATION DETEOROLOGICAL REPORTS EBBAT4 2/14/85

! JOINT MING FRE1UENCY DI!TRI0tJTION CY STASILITt CLASS ,

DATA PERIOD (YY/tet/00/HH ): 84/01/01/01 - 04/12/31/24 STABILITY CLASS: PASGUILL D KEY )00C 0829ER OF OCCURRENCES .

DATA SOURCE: ON-SITE tPI 30 0( PERCENT OCCURRENCES THIS CLASS Hits SENSOR HEIGHT: 60M )oot PERCENT OCCURRENCES ALL CLASSES

. MINO MIND SPEE0 CATE00 RIES IMETERS PER SECOND) MEAN

SECTOR 0.0-1.5 1.5-3.0 3.0-5.0 5.0-7.5 7.5-10.0 >10.0 TOTAL SPEED 904E 13 58 80 30 1 5 187 3.85 l 0.62 2.76 3.80 1.43 0.05 0.24 8.89

, 0.21 0.94 1.29 0.49 0.02 0.08 3.02 NE 11 45 48 12 4 0 120- 3.40 0.52 2.14 2.28 0.57 0.19 0.00 5.71

, 0.18 0.73 0.78 0.19 0.06 0.00 - 1.94 i ENE 13 40 17 1 0 0 T1 2.41 0.62 1.90 0.81 0.05 0.00 0.00 3.38 0.21 0.65 0.27 . 0.02 0.00 0.00 1.15

E 11 15 11 3 0 0 40 2.51

> 0.52 0.71 0.52 0.14 0.00 0.00 1.90 0.18 0.24 0.18 0.05 0.00 0.00 0.65 l ESE 4 18 14 3 4 1 44 3.86 i 0.19 0.86 0.67 0.14 0.19 0.05 2.09 0.06 0.29 0.23 0.05 0.06 5

0.C2 0.71 64

$"i r*

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0.19 0.86 1.05 0.38 0.24 0.33 3.04 P1

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i SSE 9 18 22 13 1 0 63 3.49 02 I

0.43 0.86 1.05 0.62 0.05 0.00 3.00 0.15 0.29 0.36 0.21 0.02 1.00 1.02

! S 7 22 37 31 3 . 0 100 4.13

0.33 1.05 1.76 1.47 0.14 8 0.00 4.76 1 0.11 0.36 0.60 0.50 0.0S 0.00 1.62 l' SSH 11 66 45 36 5 0 163 3.63 O.52 3.14 2.14 1.71 0.24 0.00 7.75 0.18 1.07 0.73 0.58 0.08 ' O.00- 2.64 SH 7 64 87 26 10 0 194 3.89 1 0.33 3.04 4.14 1.24 0.48 0.00 9.22 O.11 1.04 1.41 0.42 0.16 0.00 3.14 i MSN O 22 51 69 31 8 181 5.74 -

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J-SUSQUEMM044 STEAM ELECTRIC STATIC 04 IETEOROLOGICAL REPORT 3 RISSATE: .2/14/85 l

JOINT MIPS FREQUENCY 013TRIOUTION CY ETABILITY CLASS .

I DATA Pelt 100 (YYMet/00/HH l 04/01/01/01 - 04/12/31/24

' ~

STASILITY CLASS: PASQUILL E KEY 300( MaeER OF OCCURRENCES -

DATA SOURCE: CN-SITE IP) 30 0( PEACENT OCCURRElEES THIS CLASS MIND SENSOR HEIGHT: 60M 20 0( PERCENT OCCURRENCES ALL CLASSES HIND Mile SPEED CATE00 RIES llOETERS PER SEcopel PEAN

! SECTOR' O.0-1.5 1.5-3.0 3.0-5.0 5.0-7.5 7.5-10.0 >10.0- TOTAL SPEE0

) .

DOE 42 lu ' 81 29 7 0 325 2.95 1.92 7.60 3.71 1.33 0.32 0.00 14.89 0.68 2.68 1.31 0.47 0.11 0.00 5.26 DE 61 83 35 7 1 0 187 2.26 i

l 2.79 3.80 1.60 0.32 0.05 0.00 8.57 0.99 1.34 0.57 0.11 0.02 0.00 3.02

! ENE 47 34 *10 1- 0 1 93 1.96 j 2.15 1.56 0.46 0.05 0.00 0.05 4.26

0.76 0.55 0.16 0.02 0.00 0.02 1.50

! E 39 16 10 2 0 0 67 1.89 l 1.79 0.73 0.46 0.09- 0.00 0.00 3.07 J

0.63 0.26 0.16 0.03 0.00 0.00 1.08 g ESE 26 6 9 0 0 0 41 1.77 >

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3.53 0.34 0.24 0.06 0.00 0.00 1.18 LJ

1. SSE 25 35 37 7 1 0 105 2.86 i 1.15 1.60 1.69 0.32 0.05 0.00 . 4.81 i 0.40 0.57 0.60 0.11 0.02 0.00 1.70 S 25 29 33 21 3 0 111 3.45

{

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! 0.47 0.84 1.20

SH 21 90 109 41 2 0- 263 3.48 1 0.96 4.12 4.99 1.88 0.09 0.00 12.05 i 0.34 1.46 1.76 0.66 0.05 0.00 4.25 g i NSM 9 35 70 57 8 0 179 4.28- m

! 0.41 1.60 3.21 2.61 0.37' O.00 8.20 oo 0.15 0.57 1.13 0.92 0.13 0.00 2.90 m j M 4 14 23 23' 1 0 65 4.36 i 0.18 0.64 1.05 1.05 0.05 0.00 2.98 c.

i 0.06 0.23 0.37 0.37 0.02 0.00 1.05 0

) D0et 0 8 26 2 0 0 36 3.66 "'

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1.65 l 0.00 0.13' O.42 0.03 0.00 0.00 0.58

904 1 7 34 4 . 0 0 46 3.69 CD i 0.05 0.32 1.56 0.18 0.00 0.00 2.11

! 0.02 0.11 0.55 0.06 ' 0.00 0.00 0.74

? 9084 6 17 29 6 O O 58 . 3.43 I 0.27 0.78 1.33 0.27 0.00 0.00 2.M i 0.10 0.27 0.47 0.10 0.00 0.00 0.94 1 N 42 88 148 57 6 'O 341 3.60 1 1.92 4.03 6.78 2.61 0.27 0.00 15.62 j 0.68 1.42 2.39 0.92 0.10 0.00 5.52 CALM 3 3 CALM 0.14 0.14

! 0.05 0.05 I T3TAL 410 701 743 292 33 1 2183 3.19 1 18.78 32.11 34.04 13.38 *1.51 0.05 100.00 1 6.63 11.34 12.02 4.72' O.53 0.02 35.31 1

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a SUS 9UEHAf04A STEAM ELECTRIC STATION E TEOROLOGICAL REPORTS M8 MATE: 2/14K5 JOINT HINO FREGUENCY 01CTRIBUTIO54 CY ETASILITY CLASS

< DATA PERIOD (YY/HH/00/HHl 84/01/01/01 - 84/12/31/24

- ALL CLASSES KEY 30 0( M8BER OF OCCURRENCES

i DATA SOURCE: ON-SITF iP) , 200C PERCENJ OCCURRENCES THIS CLASS .

3 MING SENSOR HEIGHT: edH ,

MOC PERCENT OCCURRENCES ALL CLASSES HINO MIDE SPEED CATEGORIES (ETERS PER SEcotel IEAN -

SECTOR 0.0-1.5 1.5-3.0 3.0-5.0 5.0-7.5 7.5-10.0 >10.0 TOTAL SPEED I

PbE 111 506 ' 215 64 8 5 909 2.86 4 1.80 8.18 3.48 1.04 8.13 0.08 14.70 1.80 8.18 3.48 1.04 0.13 0.08 14.70

NE 118 219 99 22 5 0 463 '2.47 1.91 3.54 1.60 0.36 0.08 0.00 7.49 2

1.91 3.54 1.60

0.36 0.08 0.00 7.49 4

ENE Ill 108 28 2 0 1 250 1.93 j 1.80 1.75 0.45 0.05 0.00 0.02 4.04 5 1.80 1.75 0.45 0.03 0.00* 0.02 4.04 1.88 E 89 53 22 5 0 0 169 1.44 0.86 0.36' O.08 0.00 0.00 2.73 1.44 0.86 0.36 0.08 0.00 0.00 2.73 l-ESE 56 37 25 3 4 1 126 2.44 wa 0.91 0.91 0.60 0.60 0.40 0.40 0.05 0.05 0.06

'O.06 0.02 0.02 2.04 2.04 g

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7 184 2.91 ps i 1.15 0.32 0.61 0.19 0.08 0.11 2.98 i 1.15 0.82 0.61 0.19 0.08 0.11 2.98 >"

] SSE 51 69 65 21 2 0 208 2.89 l 0.82 1.12 1.05 0.34 0.03 0.00 3.36 0.82 1.12 1.05 0.34 0.05 0.00 3.36 S 48 80 87 71 7 0 293 3.66 1 0.78 1,29 1.41 1.15 0.11 0 0.00 4.74 i 0.78 1.29 1.41 1.15 p.11 0.00 4.74 i SSH 50 170 175 94 9 0 498 3.52

! 0.81 2.75 2.83 1.52 0.15 0.00 8.05 i 0.81 2.75 2.83 1.52 0.15 0.00 8.05 4

SH 33 200 290 121 18 0 662 3.83 0.53 3.23 4.69 1.96 0.29 0.00 10.71

! 0.53 3.25 4.69 1.96 0.29 0.00 10.71

, MSN 10 71 165 177 42 8 473 4.96 ns 1 0.16 1.15 2.67 2.86 0.68 0.13 7.65 m 0,16 1.15 2.67 2.86 0.68- 0.13 7.65 DQ M S 27 60 87 15 5 199 5.14

l O.08 0.44 0.97 1.41 0.24 0.08 . 3.22 >=

0.08 0.44 0.97 1.41 0.24 0.08 3.22 '4 MNM 3 15 69 32 6 0 125 4.49 o i 0.05 0.24 1.12 0.52 0.10 0.00 2.02 rg l 0.05 0.24 1.12 0.52 0.10 0.00 2.02 i

NH 5 18 96 40 3 0 162 4.25 **

0*

I 0.08 0.29- 1.55 0.65 0.05 0.00 2.61 O.08 0.29 1.55 0.65 0.05 0.00 2.62 NNM 12 32 101 50 3 0 19C 4.12 0.19 0.52 1.63 0.81 0.05 s 0.00 3.20

, 0.19 0.52 1.63 0.81 0.05 0.00 3.20 I N 128 375 458 239 . 58 3 1261 3.79

! 2.07 6.07 7.41 3.87 0.94

0.05 20.39 2.07 6.07 7.41 3.87 0.94 0.05 20.39 ,

CALM 3 . 3 CALM

!' 0.05 0.05

. 0.05 0.05 TCTAL 901 2031 1993 1040 185 30 6183 3.49 14.57 32.85 32.23 16.82 2.99 0.49 100.00

, 14.57 32.85 32.23 16.82 2.99 0.49 100.00 1

9

SUSquENA1044 ETEAN ELECTRIC CTATION PETEOROLOGICAL REPORT 3 RiesATE: t/14/85

+

JOINT MHS FREQUENCY DISTRI0tJTIt34 FOR-ALL MIIGS ,

a DATA PERIOD (YY/901/00/HH l 84/01/01/01 - 84/12/31/24 f

i ALL IGleS KEY 30 0( 142SER OF OCCURRENCES OATA SOURCE: ON-SITE E P ) 300C PERCENT OCCURRENCES THIS CLASS -

1 MDB SENSOR HEIGHT: 60H 10 0( PERCENT OCCURRENCES ALL mites .

MING HING SPEE0 CATEGORIES (METERS PER SECONO) MEAN i SECTOR 0.0-1.5 1.5-3.0 3.0-5.0 5.0-7.5 7.5-10.0 >10.0 TOTAL- SPEE0 1

I NME 128 611 276- 83 17 5 1120 2.93 l 1.67 7.95

3.59 1.08 0.22 0.07 14.58 1.67 7.95 3.59 1.08 0.22 0.07 14.58.

NE 136 264 143 39 5 0 587 2.62

1.77 3.44 1.86 0.51 0.07 0.00 7.64 1.77 3.44 1.86 0.51 0.07 0.00 7.64 i' ENE 121 134 45 10 -

' 5 1 316 2.24 1.58 1.74 0.59 0.13 0.07' O.01 4.11 1.58 1.74 0.59 0.13 0.07 0.01 4.11

E 106 70 29 11 0 0 216 2.04 i

1.38 0.91 0.38 0.14 0.00 0.00 2.81 1.38 0.91 0.38 0.14 0.00 0.00 2.81 r4 j ESE 62 50 29 8 4 1 154 2.51 g;

0.81 0.65 0.38 0.10 0.05 0.01 2.00 p.

0.81 0.65 0.38 0.10 0.05 0.01 2.00 ps SE 80 63 49 19 16 13 240 3.44

' 1.04 0.82 0.64 0.25 0.21 0.17 3.12 ""

'd i 1.04 0.82 0.64 0.25 0.21 0.17 3.12

! SSE 59 82 97 29 2 0 769 2.99 I 0.77 1.07 1.26 0.38 0.03 0.00 3.50 l 0.77 1.07 1.26 0.38 0.05 0.00 3.50 S 53 102 102 76 7 g 0 340 3.57 i

0.69 1.33 1.33 0.99 0.09 0.00 4.43 O.69 1.33 1.33 0.99 0.09 0.00 4.43 SSH 62 200 191 102 , 15 4 574 3.56 0.81 2.60 2.49 1.33 0.20 0.05 7.47 i 0.81 2.60 2.49 1.33 0.20 0.05 7.47 i

SH 40 273 328 136 22 0 799

3.75 O.52 3.55 4.27 1,77 0.29 0.00 10.40 0.52 3.55 4.27 1.77 0.29 0.00 10.40 ms HSH 14 100 253 243 58 8 676 4.90 m i

0.18 O.18 1.30 1.30 3.29 3.29 3.16 3.16 0.76 0.76 0.10 0.10 8.80 8.80 jj i M 8 36 77 153 46 10 330 5.62 >=

0.10 0.47 1.00 1.99 0.60 0.13 4.30 00 0.10 0.47 1.00 1.99 0.60 0.13 4.30 o MNN 3 17 92 58 10 1 181 4.72 en 0.04 0.22 1.20 0.76 0.13 0.01 2.36

' O.04 0.22 1.20 0.76 0.13 0.01 2.36 $$

4 NN 7 24 126 62 3 .0 222 4.29 0.09 0.31 1.64 0.81 0.04 0.00 2.89

0.09 0.31 1.64 0.81 0.04 0.00 2.89

' HNM 17 42 123 70 3 0 255 4.14 f

0.22 0.55 1.60 0.91 0.04 0.00 3.32 l 0.22 0.55 1.60 0.91 0.04 0.00 3.32

, N 145 430 500 262 59 3 1399 3.74

1.89 5.60 6.51 3.41 0.77 0.04 18.21

' 1.89 5.60 6.51 3.41 0.77 0.04 18.21 l CALM 3 3 CAUM j 0.04 0.04

0.04 0.04 TOTAL 1941 2498 2460 1361 272 46 7681 3.58 3

13.55 32.52 32.05 17.72 3.54 0.60 100.00 13.55 32.52 32.03 17.72 3.54 0.60 100.00

AVERAGE ETEOROLOGICAL RELATIVE CopCENTRATION ANALYSI3 DATA PE;IOD : 01/01/04 TO 12/31/84 FIXE 0 AND SPECIAL DISTADCES DISPERSION ANALYSIS em RADIOLOGICAL EFFLUENT DISPERSION PROGRAM ADSSES (C N AP101 l CALEteAR YEAR 1984 $USdEJENA004A STEAM ELECTRIC STATIONS LUZERNE COLSdTY, PA PE9045YLVANIA PONER & LIGHT COWANYS ALLENTIB04, PA

, DATE 17-FES-85 ADSSES DEVELOPED BY MODIFICATIIBt OF D8M PROGRAM AfGIFF I

AFFECTED SECTORS 5 10E DE EDE E ESE SE SSE S SSN SM HSN M D006 let 10 04 N

{ 0.5 MILES (.805 KM) ------ ---

. 9.0E-06 7.8E-06 4.1E-06 2.1E-06 1.8E-06 2.6E-06 4.6E-06 1.2E-05 1.7E-05 3.3E-05 2.4E-05 1.3E-05 6.5E-06 1.0E-05 S.1E-06 6.7E-06

'0.2E-06 7.2E-06 3.8E-06 1.9E-06 1.6E-06 2.4E-06 4.2E-06 1.1E-05 1.6E-05 3.0E-05 2.2E-05 1.2E-05 6.0E-06 9.1E-06 7.4E-06 6.2E-06 i 3.2E-08 4.3E-08 2.6E-08 1.4E-OS 9.4E-09 1.3E-04 2.3E-08 3.6E-08 3.4E-OS 4.4E-08 2.9E-04 1.7E-OS 1.1E-OS 2.1E-08 1.9E-04 2.0E-08 S.9E-06 7.8E-06 4.1E-06 2.0E-06 1.7E-06 2.6E-06 4.6E-06 1.2E-05 1.7E-05 3.3E-05 2.3E-05 1.3E-05 6.5E-06 9.9E-G6 S.0E-06 6.7E-06 9.0E-06 7.8E-06 4.1E-06 2.1E-06 1.8E-06 2.6E-06 4.6E-06 1.2E-05 1.7E-05 3.3E-05 2.4E-05 1.3E-05 6.5E-06 1.0E-05 S.0E-06 6.7E-06 l 0.2E-06 7.2E-06 3.8E-06 1.9E-06 1.6E-06 2.4E-06 4.2E-06 1.1E-05 1.6E-05 3.0E-05 2.1E-05 1.2E-05 5.9E-06 9.1E-06 7.3E-06 6.1E-06 t 0.2E-06 7.2E-06 3.8E-06 1.9E-06 1.6E-06 2.4E-06 4.2E-06 1.1E-05 1.6E-05 3.0E-05 2.2E-05 1.2E-05 6.0E-06 9.1E-06 7.4E-06 6.2E-06 a05. 805. 805. a05. a05. a05. 805. a05. a05. a05. 805. a05. a05. a05, s05. 805.

i 1.5 MILES I 2.41 KM I -------------

i 1.9E-06 1.6E-06 8.6E-07 3.7E-07 3.1E-07 5.2E-07 S.5E-07 2.3E-06 3.7E-06 7.0E-06 5.8E-06 2.4E-06 1.3E-06 E.1E-06 1.8E-06 1.4E-06 l 1.6E-06 1.4E-06 7.3E-07 3.1E-07 2.6E-07 4.4E-07 7.2E-07 2.0E-06 3.1E-06 5.9E-06 4.9E-06 2.0E-06 1.1E-06 1.4E-06 1.6E-06 1.2E-06

! 5.5E-09 7.6E-09 4.6E-09 2.1E-09 1.4E-09 2.1E-09 3.5E-09 5.7E-09 6.1E-09 8.2E-09 6.1E-09 2.5E-09 1.9E-09 3.5E-09 3.6E-09 3.4E-09 1.9E-06 1.6E-06 8.6E-07 3.7E-07 3.1E-07 5'.2E-07 S.4E-07 2.3E-06 3.6E-06 6.9E-06 5.7E-06 2.3E-06 1.3E-06 2.0E-06 1.SE-06 1.4E-06 I 1.9E-06 1.6E-06 8.6E-07 3.7E-07 3.1E-07 5.2E-07 S.5E-07 2.3E-06 3.6E-06 7.0E-06 5.7E-06 2.3E-06 1.3E-06 2.1E-06 1.8E-06 1.4E-06 g 1.6E-06 1.4E-06 7.3E-07 3.1E-07 2.6E-07 4.4E-07 7.1E-07 1.9E-06 3.1E-06 5.SE-06 4.8E-06 2.0E-06 1.1E-06 1.7E-06 1.5E-06 1.2E-06 >

1.CE-06 1.4E-06 7.3E-07 3.1E-07 2.6E-07 4.4E-07 7.2E-07 2.0E-06 3.1E-06 5.9E-06 4.8E-06 2.0E-06 1.1E-06 1.7E-06 1.5E-06 1.2E-06 ts l

2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. 2414. y

! 2.5 MILES ( 4. 02 KM ) ------------ - - - - - - - - - - - -

] 9.5E-07 8.2E-07 4.4E-07 1.7E-07 1.3E-07 2.2E-07 4.0E-07 1.0E-06 1.7E-06 3.3E-06 2.9E-06 1.1E-06 6.0E-07 9.5E-07 S.7E-07 7.2E-07 e

' d 7.6E-07 6.6E-07 3.5E-07 1.4E-07 1.0E-07 1.8E-07 3.2E-07 8.4E-07 1.4E-06 2.7E-06 2.4E-06 8.7E-07 4.8E-07 7.6E-07 7.0E-07 5.8E-07 i CD 2.5E-09 3.5E-09 2.1E-09 8.8E-10 5.1E-10 8.4E-10 1.5E-09 2.3E-09 2.5E-09 3.3E-09 2.7E-09 1.0E-09 7.5E-10 1.4E-09 1.5E-09 1.6E-09

! 9.(E-07 8.1E-07 4.3E-07 1.7E-07 1.3E-07 2.2E-07 3.9E-07 1.0E-06 1.7E-06 3.3E-06 2.9E-06 1.1E-06 5.9E-07 9. 2E-07 S.5E-07 7.1E-07 i 2.9E-06 1.1E-06 6.0E-07 9.4E-07 8.6E-07 7. 2E-07

! 9.5E-07 6.5E-07 7.5E-07 8.2E-07 3.5E-07 4.4E-07 1.4E-07 1.7E-07 1.0E-07 1.3E-07 1.8E-07 2.2E-07 3.1E-07 4.0E-07 8.2E-071.0E-06 1.4E-06 1.7E-06 2.6E-06 3.3E-06 l2.3E-06 8.4E-07 4.7E-07 7.4E-07 6.8E-07 5.7E-07 4

7.CE-07 6.6E-37 3.5E-07 1.4E-07 1.0E-07 1.8E-07 3.2E-07 8.3E-07 1.4E-06 2.7E-06 2.3E-06 S.6E-07 4.8E-07 7.6E-07 6.9E-0Z 5.8E-07 4723. 4023. 4025. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023. 4023.

l l 3.5 MILES (5.63 KMI ---- --------------

5.2E-07 4.7E-07 2.6E-07 9.3E-08 7.0E-08 1.1E-07 2.1E-07 5.3E-07 S.7E-07 1.8E-06 1.6E-06 5.7E-07 3.3E-07 5.5E-07 4.6E-07 4.0E-07

4.1E-07 3.6E-07 2.0E-07 7.2E-08 5.4E-08 8.2E-08 1.6E-07 4.1E-07 6.7E-07 1.4E-06 1.2E-06 4.4E-07 2.6E-07 4.2E-07 3.6E-07 3.1E-07 j 1.3E-09 1.8E-09 1.2E-09 4.5E-10 2.6E-10 3.7E-10 7.1F-10 1.1E-09 1.1E-09 1.6E-09 1.3E-09 4.7E-10 3.7E-10 7.5E-10 7.4E-10 7.8E-10 g 5.1E-07 4.6E-07 2.6E-07 9.2E-08. 6.8E-08 1.0E-07 2.0M-07 5.2E-07 0.5E-07 1.8E-06 1.5E-06 5.5E-07 3.2E-07 5.3E-07 4.5E-07 3.9E-07 m 5.2E-07 4.7E-07 2.6E-07 9.3E-08 6.9E-08 1.1E-07 2.1E-07 5.3E-07 8.6E-07 1.8E-06 1.6E-06 5.6E-07 3.3E-07 5.4E-07 4.6E-07 3.9E-07 00 4.0E-07 3.6E-07 2.0E-07 7.1E-08 5.3E-08 8.1E-08 1.6E-07 4.0E-07 6.5E-07 1.4E-06 1.2E-06 4.2E-07 2.5E-07 4.1E-07 3.5E-07 3.0E-07 (D 4.0E-07 3.6E-07 2.0E-07 7.2E-08 5.3E-08 8.2E-08 1.6E-07 4.1E-07 6.7E-07 1.4E-06 1.2E-06 4.4E-07 2.5E-07 4.2E-07 3.6E-07 3.0E-07 y 5632. 5632. 5632. 5632. 5632. 5632. 5632. 5632. 5632. 5632, 5632. 5632. 5632. 5632. 5632. 5632.

- k j TOTAL OBS 8783 TOTAL INV OSS - 228 CALMS LONER LEVEL - 58.00 co

KEY: ENTRY 1 RELATIVE CONCENTRATION - XOG (S/Mmm33 ENTRY 2 DEPLETED RELATIVE CONCENTRATION IS/Mem3) i ENTRY 3 RELATIVE OEPOSITION RATE (1/MEm2) ENTRY 4 DECAYED XOQ IS/ Hum 3) - HALF LIFE 2.26 DAYS 1 ENTRY 5 DECAYED XOG (S/ Hum 3) - HALF LIFE 8.00 DAYS ENTRY 6 DEC+DPL XOQ IS/ Man 3B - HALF LIFE 2.26 DAYS

] ENTRY 7 DEC+0PL XOG IS/Mem33 - HALF LIFE 8.00 DAYS ENTRY 8 - DISTANCE IN METERS 1

1 l

l 4

l

l AVE 2 AGE M TEGA0 LOGICAL RELATIVE CONCENTRATION AN6 LYSIS

DATA PERIOD 01/01/84 TO 12/31/84 i

FIXED AND SPF01AL DISTANCES DISPERSION ANALYSIS me RADIOLOGICAL EFFLUENT DISPERSIt34 PROGRAM ASSSES (CNDAP101 l . CALENDAR YEAR 1904 "MHAB04A STEAM ELECTRIC STATIONS LUZERIE COL 84TY, PA pef 445VLVANIA PCHER 4 LIGHT COWANYl ALLENTEDee, PA

! DATE 17-FES-88 ADSSES DEVELOPES SY MODIFICATION OF dan PA0 GRAM AleIFF i '

i . AFFECTED SECTORS j IGE DE EtE E ESE SE SSE S. SSM SM MSN N B004 900 . Dett N 4.5 MILES (7.24 KM) - - - - - - - - - - - - - - - - - - - - - - - -

! 3.6E-07 3.3E-07 1.9E-07 6.2E-OS 4.0E-08 6.0E-08 1.1E-07 3.3E-07 5.3E-07 1.2E-06 1.1E-06 3.7E-07 2.2E-07 3.6E-07 3.3E-07 2.7E-07

? 2.7E-07 2.5E-07 1.4E-07 4.7E-04 3.0E-08 4.5E-04 S.4E-08 2.5E-07 4.0E-07 8.6E-07 7.9E-07 2.8E-07 1.6E-07 2.7E-07 2.5E-07 2.0E-07 i O.1E-10 1.2E-09 8.2E-10 2.8E-10 1.4E-10 1.9E-10 3.6E-10 6.0E-10 6.2E-10 9.1E-10 7.6E-10 2.8E-10 2.3E-10 4.5E-10 4.8E-10 5.0E-10 1 3.5E-07 3.2E-07 1.9E-07 6.1E-OS 4.0E-DS 5.8E-08 1.1E-07 3.2E-07 5.1E-07 1.1E-06 1.0E-06 3.6E-07 2.1E-071.4E-07 3.2E-07 2.6E-07 i

3.6E-07 3.3E-07 1.9E-07 6.2E-OS 4.0E-08 5.9E-OS 1.1E-07 3.3E-07 5.2E-07 1.1E-06 1.0E-06 3.7E-07 2.2E-07 3.5E-07 3.2E-07 2.7E-07 1 2.cE-07 2.4E-07 1.4E-07 4.6E-08 3.0E-08 4.4E-08 8.2E-08 2.4E-07 3.8E-07 S.3E-07 7.6E-07 2.7E-0T 1.6E-07 2.6E-07 2.4E-07 2.0E-07

! 2.7E-07 2.5E-07 1.4E-07 4.6E-OS 3.0E-04 4.4E-06,8.3E-08 2.4E-07 3.9E-07 S.5E-07 7.8E-07 2.8E-07 1.6E-07 2.7E-07 2.4E-07 2.0E-07 7241. 7241.~ 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241. 7241.

7.5 MILES (12.07 KM) ------- ---- -

1.7E-07 1.6E-07 9.0E-OS 2.8E-OS 1.4E-08 1.9E-04 3.7E-04 1.3E-07 2.1E-07 4.8E-07 4.6E-07 1.5E-07 9.3E-08 1.6E-07 1.5E-07 1.7E-07 ,

1.2E-07 1.1E-07 6.3E-04 1.9E-OS 9.8E-09 1.3E-08 2.6E-08 8.7E-08 1.4E-07 3.4E-07 3.2E-07 1.0E-07 6.5E-04 1.1E-07 1.1E-07 1.2E-07 3.1E-10 4.9E-10 3.3E-10 1.1E-10 4.2E-11 5.1E-11 1.0E-10 1.9E-10 2.0E-10 3.1E-10 2.6E-10 8.9E-11 S.0E-11 1.6E-10 1.9E-10 2.6E-10 1.6E-07 1.5E-07 8.7E-08 2.7E-OS 1.4E-08 1.8E-08 3.5E-08 1.2E-07 1.9E-07 4.5E-07 4.3E-07 1.3E-07 8.6E-08 1.5E-07 1.4E-07 1.6E-07 1.(E-07 1.5E-07 8.9E-OS 2.7E-08 1.4E-08 1.9E-04 3.6E-08 1.2E-07 2.0E-07 4.7E-07 4.5E-07 1.4E-07 9.1E-04 1.5E-07 1 5E-07 1.7E-07 1.1E-07 1.0E-07 6.1E-08 1.9E-08 9.5E-09 1.3E-OS 2.5E-08 S.2E-08 1.3E-07 3.2E-07 3.0E-07 9.4E-08 6.0E-08 1.0E-07 1.0E-07 1.1E-07 bs

}' 1.1E-07 1.1E-07 6.2E-08 1.9E-04 9.7E-09 1.3E-08 2.5E-OS 8.6E-08 1.4E-07 3.3E-07 3.1E-07 9.9E-04 6.3E-OS 1.1E-07 1.0E-07 1.2E-07 M 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12068. 12064, 12068. 12068. tus 15.0 MILES (24.1 KM) -------- - - - - - - - - - - - 5 d

2.8E-08 3.5E-08 2.9E-08 6.1E-09 3.3E-09 4.6E-09 S.1E-09 1.6E-08 3.7E-06 S.1E-08 7.0E-08 2.2E-08 1.8E-08 3.2E-OS 2.9E-08 2.6E-08 e 1.7E-08 2.1E-08 1.8E-08 3.8E-09 2.0E-09 2.8E-09 5.0E-09 9.7E-09 2.3E-08 5.0E-04 4.3E-08 1.3E-08 1.1E-08 2.0E-04 1.8E-08 1.6E-08

3.9E-11 8.4E-11 8.2E-11 1.8E-11 7.5E-12 9.4E-12 1.7E-11 1.8E-11 2.6E-11 3.6E-11 2.8E-11 9.5E-12 1.1E-11 2.5E-11 2.7E-11 2.9E-11 2.6E-08 3.3E-08 2.7E-08 5.7E-09 3.1E-09 4.2E-09 7.4E-09 1.4E-08 3.3E-08 7.2E-08 6.2E-08 1.9E-08 1.6E-08 2.8E-08 2.6E-08 2.3E-08 2.7E-08 3.4E-08 2.9E-08 6.0E-09 3.2E-09 4.5E-09 7.9E-09 1.5E-08 3.6E-04 7.8E-08

! 1.6E-08 2.0E-08 1.7E-08 3.5E-09 1.9E-09 2.6E-09 4.6E-09 8.7E-09 2.0E-08 4.4E-08l6.8E-08 2.1E-08 9.5E-09 3.8E-08 1.1E-04 1.7E-08 1.7E-08 3.1E-08 1.6E-08 2.8E-08 1.4E-08 2.5E-08 4

1.7E-08 2.1E-08 1.8E-08 3.7E-09 2.0E-09 2.7E-09 4.9E-09 9.4E-09 2.2E-04 4.8E-08 4.2E-08 1.3E-04 1.1E-04 1 9E-04 1.7E-08 1.5E-08 24135. 24135. 24135. 24135. 24135. 24135. 24135. 24135. 24135. 24135, 24135. 24135. 24135. 24135. 24135. 24135.

]

j 25.0 MILES I40.2 KMt - - - - - - - - - - - - - - - - - - - - - -

l 4.8E-09 4.7E-09 8.9E-09 1.7E-09 1.0E-09 6.6E-10 1.3E-09 2.6E-09 6.5E-09 1.9E-08 1.2E-08 2.6E-09 3.2E-09 4.3E-09 4.4E-09 6.0E-09 1 2.(E-09 2.6E-09 4.9E-09 9.3E-10 5.6E-10 3.6E-10 7.2E-10 1.4E-09 3.6E-09 1.0E-08 6.5E-09 1.4E-09 1.8E-09 2.4E-09 2.4E-09 3.3E-09 l 5.1E-12 8.8E-12 2.0E-li 4.0E-12 1.8E-12 1.1E-12 2.1E-12 2.3E-12 3.4E-12 6.2E-12 3,5E-12 s.5E-13 1.5E-12 2.5E-12 3.0E-12 5.2E-12 ee 4

4.1E-09 4.2E-09 8.0E-09 1.EE-09 9.0E-10 5.8E-10 1.1E-09 2.2E-09 5.2E-09 1.6E-08 9.5E-09 2.0E-09 2.5E-09 3.5E-09 3.6E-09 5.0E-09 co I 4.6E-09 4.6E-09 8.6E-09 1.6E-09 9.8E-10 6.4E-10 1.3E-09 2.5E-09 6.1E-09 1.8E-08 1.1E-08 2.4E-09 3.0E-09 4.1E-09 4.1E-09 5.7E-09 00 m

1 2.3E-09 2.3E-09 4.4E-09 8.4E-10 4.9E-10 3.2E-10 6.3E-10 1.2E-09 2.9E-09 8.5E-09 5.2E-09 1.1E-09 1.4E-09 1.9E-09 2.0E-09 2.8E-09 2.5E-09 2.5E-09 4.7E-09 9.0E 'to 5.4E-10 3.5E-10 6.9E-10 1.4E-09 3.3E-09 9.8E-09 6.1E-09 1.3E-09 1.6E-09 2.2E-09 2.3E-09 3.1E-09 w 1 40225. 40225. 40225. 40MS. 40225. 40225. 40225. 40225. 40225. 40225. 40225. 40225. 40225. 40225, 40225. 40225.

1 O I

~

f TOTAL OBS - 8783 TOTAL INV OSS - 228 CALMS LOHER LEVEL - 58.00 co KEY: ENTRY 1 RELATIVE CONCENTRATION - XOG (S/ Man 3) ENTRY Z DEPLETED RELATIVE CONCENTRATION IS/ Hem 33 ENTRY 3 RELATIVE DEPOSITION RATE (1/Hmm2) ENTRY 4 DECAYED XOG ES/Hemll - HALF LIFE 2.26 DAYS ENTRY 5 DECAYE0 XO4 IS/Ma*3) - HALF LIFE 8.00 DAYS ENTRY 6 DEC+DPL XOQ IS/ Hum 3) - IIALF LIFE 2.26 DAYS ENTRY 7 DEC+DPL N04 IS/ Mum 3) - HALF LIFE 8.00 DAYS ENTRY 8 - DISTANCE IN METERS 1

0 I

i- _ _ _ _ .

1 1 .

AVERAGE DETE0A0 LOGICAL AELATIVE CEBCE9fTRATICDI ANALYSI3 DATA PERIOD : 01/C1/84 TO 12/31/34 i FINES Ape SPECIAL DISTABEES DISPERSION ANALYSIS me RADIOLOGICAL EFFLUENT DISPERSION l'A00RAN ASSSES (CNDAP10) 4 CALEteAR YEAR 1984 SUSSENAIStA STEAM ELECTRIC STATIt316 LUZEIDE CotAITY, PA PE800SYLVAttIA PCHER & LIGHT COPFANYS ALLENTE3ete PA l DATE 17-FE8-85 ADSSES DEVELOPES DY MODIFICATION OF GaN PA0 GRAM AleIFF AFFECTED SECTORS 600! M EDE E ESE SE SSE S SSN SN NSM N lett let lett ~N 33.8 MILES (56.3 KM) ----

, 1.3E-%9 1.2E-09 2.3E-09 3.5E-10 1.4E-10 1.3E-10 2.8E-10 6.6E-10 1.1E-09 6.1E-09 2.5E-09 5.2E-10 2.2E-10 5.5E-10 1.6E-09 1.1E-09 6.4E-10 6.1E-10 1.2E-09 1.8E-10 7. N-11 6.3E-11 1.4E-10 3.3E-10 5.7E-10 3.0E-09 1.2E-09 2.6E-10 1.1E-10 2.8E-10 7.8E-10 5.4E-10 I 1.1E-12 1.9E-12 4.2E-12 6.9E-13 2. N-13 1.7E-13 3.8E-13 4.6E-13 4.8E-13 1.6E-12 5.9E-13 1.4E-13 8.4E-14 2.6E-15 S.8E-13 7.6E-13 l 1.0E-09 1.0E-09 2.0E-09 3.0E-10 1.2E-10 1.1E-10 2.3E-10 5.1E-10 8,4E-10 4.6E-09 1.9d-09 3.6E-10 1.6E-10 4.1E-10 1.2E-09 8.5E-10 +

! 1.2E-09 1.2E-09 2.2E-09 3.4E-10 1.3E-10 1.2E-10 2.7E-10 6.1E-10 1.0E-09 5.6E-09 2.3E-09 4.6E-10 2.0E-10 5.0E-10 1.4E-09 1.0E-09 i 5.2E-10 5.2E-10 9.9E-10 1.5E-10 5.9E-115.3E-11 1.2E-10 2.6E-10 4.2E-10 2.3E-09 9.3E-10 1.8E-10 7.9E-11 2.0E-10 6.0E-10 4.3E-10 i

5.0E-10 5.8E-10 1.1E-09 1.7E-10 6.7E-11 6.0E-11 1.3E-10 3.1E-10 5.2E-10 2.8E-09 1.1E-09 2.3E-10 9.9E-11 2.5E-10 7.2E-10 5.0E-10 l 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315. 56315.

45.0 MILES E 72.4 KM ) ------------------ ---- -

5.0E-10 4.1E-10 8.1E-10 1.1E-10 3.4E-11 1.8E-11 8.8E-11 2.9E-10 3.3E-10 2.5E-09 6.1E-10 1.3E-10 5.3E-11 1.3E-10 5.1E-10 3.0E-10 2.3E-10 1.9E-10 3.7E-10 5.2E-11 1.6E-11 8.6E-12 4.1E-11 1.4E-10 1.6E-10 1.1E-09 2.9E-10 5.9E-11 2.5E-11 6.3E-11 2.4E-10 1.4E-10 i 3.7E-13 5.4E-13 1.3E-12 1.9E-13 4.3E-14 2.1E-14 1.0E-13 1.7E-13 1.2E-13 5.4E-13 1.2E-13 2.8E-14 1.7E-14 5.4E-14 2.4E-13 1.8E-13 *1 3.9E-10 3.4E-10 6.7E-10 9.3E-11 2.7E-11 1.5E-11 6.9E-11 2.1E-10 2.3E-10 1.7E-09 4.3E-10 8.1E-11 3.5E-11 9.1k-11 3.6E-10 2.3E-10 j

4 fE-10 3.9E-10 7.6E-10 1.1E-10 3.ZE-11 1.7E-11 8.2E-11 2.6E-10 3.0E-10 f.2E-09 5.5E-10 1.1E-10 4.7E-11 1.2E-10 4.6E-10 2.8E-10 1.8E-10 1.6E-10 3.1E-10 4.3E-11 1.3E-11 6.8E-12 3.2E-11 9.8E-11 1.1E-10 8.0E-10 2.0E-10 3.8E-11 1.6E-11 4.3E-11 1.7E-10 1.1E-10 t-*

i 2.2E-10 1.8E-10 3.5E-10 4.9E-11 1.5E-11 8.0E-12 3.8E-11 1.2E-10 1.4E-10 1.0E-09 2.6E-10 5.2E-11 2.2E-11 5.6E-11 E.1E-10 1.3E-10 t1

! 72 W5. 72405. 72405. 72405. 72405. 72405. 72405. Lt405. 72405. 72405. 72405. 72405. 72405. 72405. 72405. 72405.

O.4 MILES'(0.6% KMi ----- --------

. 1.1E-05 1.1E-05 5.6E-06 2.8E-06 2.5E-06 3.6E-06 6.1E-06 1.6E-05 2.5E-05 4.7E-05 3.2E-05 1.8E-05 9.1E-06 1.4E-05 1.1E-05 9.5E-06 i

l uO 1.0E-05 9.9E-06 4.1E-08 6.1E-08 5.2E-06 3.7E-08 2.0E-08 2.6E-06 1.4E-08 2.3E-06 1.8E-08 3.3E-06 5.7E-06 3.1E-08 4.9E-08 1.5E-05 5.0E-08 6.2E-082.3E-05 3.9E-084.4E-05 3.0E-052.9E-08 2.3E-08 1.6E-08 1.7E-05 8.4E-06 2.6E-08 1.3E-05 9.7E-06 8.8E-06 2.9E-08 1 1.1E-05 1.1E-05 5.6E-06 2.8E-06 2.5E-06 3.6E-06 6.1E-06 1.6E-05 2.5E-05 4.7E-05 3.2E-05 1.8E-05 9.1E-06 1.4E-05 1.0E-05 9.4E-06 i 1.1E-C5 1.1E-05 5.6E-06 2.8E-06 2.5E-06 3.6E-06 6.1E-06 1.6E-05 2.5E-05 4.7E-05 3.2E-05 1.8E-05 9.1E-06 1.4E-05 1.1E-05 9.5E-06 1.0E-05 9.9E-06 5.2E-06 2.6E-06 2.3E-06 3.3E-06 5.7E-06 1.5E-0E 2.3E-05 4.31-05 3.0E-05 1.7E-05 8.4E-06 1.3E-05 9.7E-06 8.7E-06 l 1.0E-05 9.9E-06 5.2E-06 2.6E-06 2.3E-06 3.3E-06 5.7E-06 1.5E-05 2.3E-05 4.4E-05 3.0E-05 1.7E-05 8.4E-06 1.3E-05 9.7E-06 8.8E-06

! 6%. 6%. 6%. 6%. 6%. 6%. 644. 6%. 644. 6%. 644. 6%. 644. 644. 6%. 6%.

I 0.6 MILES 10.965 KM I------- - - - - - - - - - - - - - - - - -

6.9E-06 6.2E-06 3.2E-06 1.6E-06 1.4E-06 2.0E-06 3.6E-06 9.4E-06 1.4E-05 2.6E-05 2.0E-05 1.0E-05 5.2E-06 7.8E-06 6.3E-06 5.3E-06 6.2E-06 5.6E-06 2.9E-06 1.4E-06 1.2E-06 1.8E-06 3.3E-06 8.5E-06 1.2E-05 2.4E-05 1.8E-05 9.4E-06 4.7E-06 7.1E-06 5.7E-06 4.8E-06

! 2.4E-08 3.3E-08 2.0E-08 1.0E-08 7.0E-09 9.6E-09 1.7E-08 2.7F-08 2.7E-08 3.5E-08 2.4E-08 1.3E-08 8.8E-09 1.6E-08 1.5E-08 1.5E-08 [

? 6.9E-06 6.2E-06 3.2E-06 1.6E-06 1.3E-06 2.0E-06 3.6E-06 9.3E-06 1.4E-05 2.6E-05 2.0E-05 1.0E-05 5.2E-06 7.7E-06 6.2E-06 5.3E-06 og

{ 6.9E-06 6.2E-06 3.2E-06 1.6E-06 1.4E-06 2.0E-06 3.6E-06 9.4E-06 1.4E-05 2.6E-05 2.0E-C5 1.0E-05 5.2E-06 7.8E-06 6.3E-06 5.3E-06 (D

. 6.2E-16 5.6E-06 2.9E-06 1.4E-06 1.2E-06 1.8E-06 3.3E-06 8.5E-06 1.2E-05 2.4E-05 1.8E-05 9.3E-06 4.7E-06 7.0E-06 5.7E-06 4.8E-06 W 6.2E-06 5.6E-06 2.9E-06 1.4E-06 1.2E-06 1.8E-06 3.3E-06 8.5E-06 1.ZE-05 2.4F-05 1.4E-05 9.3E-06 4.7E-06 7.0E-06 5.7E-06 4.8E-06 965. 965. 965. 965. 965. 965. 965. 965. 965. . 965. 965. 965. 945. 965. 965. 965. o CALHS LOHER LEVEL - 58.00 TOTAL OBS - 8783 TOTAL INV OSS - 228 -

KEY: ENTRY 1 RELATIVE CONCENTRATION - NOQ IS/ Man 38 ENTRY 2 DEPLETED RELATIVE CONCENTRATION (S/Mem3) j ENTRY 3 RELATIVE DEPOSITION RATE II/ Hum 2) ENTRY 4 DECAYED XOG (S/Muu33 - HALF LIFE 2.26 DAYS ENTRY 5 DECAYED N00 IS/Ma*3) - HALF LIFE 8.00 DAYS ENTRY 6 DEC+0PL XOQ IS/Me*31 - HALF LIFE 2.26 DAYS -

i - ENTRY 7 DEC4DPL N04 IS/Hmm31 - HALF LIFE 8.00 DAYS ENTRY 8 - DISTANCE IN HETERS I

I i

i 3 .

,1

I AVERAGE BETEOROLOGICAL RELATIVE CGCENTRATION ANALYSI2 DATA PERICO : 01/01/84 TO 12/31/84 FINED Ale SPECIAL DISTANCES DISPERSION ANALYSIS me RADIOLOGICAL EFFLUENT DISPERSIt34 PROGRAM ADSSES (CleAP101 CALEteAR YEAR 1984 SUSSEMA804A STEAM ELECTRIC STATIEpis Lu2ENE COLMTY, PA PE900SYLVANIA P0HER 6 LIGHT C(30bANY5 ALLENTIB04, PA l DATE 17-FES-85 ADSSES DEVELOPES SY MODIFICATION OF BSN PAGGRAM AleIFF 1

~AFFECTED SECTORS DOE DE EDE E ESE SE SSE S SSN SM MSN M B006 9M . 88 04 N i

1 0.7 MILES 11.126 KM) - - ---

1 5.7E-06 5.0E-06 2.6E-06 1.3E-06 1.1E-06 1.6E-06 2.9E-06 7.6E-06 1.1E-05 1.1E-05 1.6E-05 7.9E-06 4.0E-06 6.1E-06 5.3E-06 4.1E-06 3 5.2E-06 4.5E-06 2.3E-06 1.1E-06 9.5E-07 1.4E-06 2.6E-06 6.8E-06 9.8E-06 1.9E-05 1.4E-05 7.1E-06 3.6E-06 5.4E-06 .4E-06 3.7E-06 l 1.9E-06 24 5d8 1.6E-08 S.2E-09 5.4E-09 7.6E-09 1.4E-04 2.1E-06 2.1E-OS 2.9E-08 1.9E-08 9.9E-09 6.7E-09 1.2E-08 .tE-08 1.2E-08 1 5.7E-06 5." J6 2.6E-06 1.3E-06 1.1E-06 1.6E-06 2.9E-06 7.6E-06 1.1E-05 2.1E-05 1.6E-05 7.9E-06 4.0E-06 6.0E-06 .3E-06 4.1E-06 1 5.7E-06 5. 46 2.6E-06 1.3E-06 1.1E-06 1.6E-06 2.9F-06 7.6E-06 1.1E-05 2.1E-05 1.6E-05 7.9E-06 4.0E-06 6.1E-06 5.3E-06 4.1E-06 j 5.1E-06 4.L.-06 2.3E-06 1.11-06 9.5E-07 1.4E-06 2.66-04 6.SE-06 9.8E-06 1.9E-05 1.4E-05 7.1E-06 3.6E-06 5.4E-06 4.7E-06 3.7E-06 5.1E-06 4.5E-06 R.3E-06 1.1E-06 9.5E-07 1.4E-06 2.6E-06 6.SE-06 9.8E-06 1.9E-05 1.4E-05 7.1E-06 3.6E-06 5.4E-06 4.4E-06 3.7E-06 l' 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1126. 1186. 1126. 1126.

I 0.0 MILES 11.287 KMI ------- -----

l 4.5E-06 4.2E-06 2.2E-06 1.1E-06 9.tE-07 1.5E-06 2.5E-06 6.2E-06 9.1E-06 1.8E-05 1.3E-05 6.tE-06 3.5E-06 5.5E-06 4.4E-06 3.5E-06

) 4.0E-06 3.7E-06 2.CE-06 9.4E-07 8.2E-07 1.3E-06 2.2E-06 5.5E-06 8.1E-06 1.6E-05 1.2E-05 5.5E-06 3.1E-06 4.9E-06 3.9E-06 3.1E-06

1.5E-08 2.2E-08 1.3E-08 6.6E-09 4.6E-09 6.7E-09 1.1E-04 1.7E-08 1.7E-08 2.3E-OS 1.6E-08 7.7E-09 5.7E-09 1.1E-04 1.0E-08 9.8E-09 4.5E-06 4.1E-06 2.2E-06 1.1E-06 9.tE-07 1.4E-06 2.5E-06 6.2E-06 9.1E-06 1.8E-05 1.3E-05 6.tE-06 3.5E-06 5.4E-06 4.4E-06 3.5E-06 g i 4.5E-06 4.2E-06 2.2E-06 1.1E-06 9.2E-07 1.5E-06 2.5E-06 6.2E-06 9.1E-06 1.8E-05 1.3E-05 6.tE-04 3.5E-06 5.5E-06 4.4E-06 3.5E-06 >

l 4.0E-06 3.7E-06 2.0E-06 9.3E-07 8.1E-07 1.3E-06 2.2E-06 5.5E-06 S.1E-06 1.6E-05 1.2E-05 5.5E-04 3.1E-06 4.88-06 3.9E-06 3.1E-06 to M

i 4.0E-06 3.7E-06 2.0E-06 9.4E-07 S.2E-07 1.3E-06 2.2E-06 5.5E-06 S.1E-06 1.6E-05 1.2E-05 5.5E-06 3.1E-06 4.9E-06 3.9E-06 3.1E-06 M

! 1287. 1287. 1287. 1247. 1287. 1287. 1287. 1287. 1287. 1287. 1287. 1287. 1287. 1887. 1287. 1287.

! 0.9 MILES 11.448 KMI ---------- - - - - - - - - - - e 1 3.9E-06 3.5E-06 1.8E-06 8.7E-07 7.5E-07 1.2E-06 2.1E-06 5.3E-06 7.6E-06 1.5E-05 1.2E-05 5.5E-06 2.9E-06 4.4E-06 3.9E-06 2.8E-06 1 3.5E-06 3.1E-06 1.6E-06 7.6E-07 6.6E-07 1.0E-06 1.8E-06 4.7E-06 6.7E-06 1.3E-05 1.1E-05 4.8E-06 2.6E-06 3.9E-06 3.4E-06 2.5E-06 i 1.3E-08 1.8E-08 1.1E-08 5.3E-09 3.7E-09 5.3E-09 9.4E-09 1.4E-08 1.4E-OS 1.?E-08 1.4E-08 6.6E-09 4.7E-09 . 4E-09 8.5E-09 7.7E-09 -

1 3.9E-06 3.5E-06 1.8E-06 8.6E-07 7.5E-07 1.2E-06 2.1E-06 5.3E-06 7.5E-06 1.5E-05 1.2E-05 5.4E-06 2.9E-06 4.4E-06 3.9E-06 2.8E-06

3.9E-06 3.5E-06 1.8E-06 4.7E-07 7.5E-07 1.2E-06 2.1E-06 5.3E-06 7.5E-06 1.5E-05 1.2E-05 5.4E-06 2.9E-06 4.4E-06 3.9E-06 2.8E-06 1 3.5E-06 3.1E-06 1.6E-06 7.6E-07 6.6E-07 1.0E-06 1.8E-06 4.6E-06 6.6E-06 1.3E-05 1.1E-05 4.8E-06 2.6E-06 3.9E-06 3.4E-06 2.5E-06

$3.5E-063.1E-061.6E-067.6E-076.6E-071.0E-061.8E-064.7E-066.6E-061.3E-051.1E-054.8E-062.6E-063.9E-063.4E-062.5E-06 l' 1448. 1448. 1448. 1448. 1448. 1448. 1448. 1448. 1448. 1444. 1448, 1448, 1448. 1448, 1448. 1448.

' 1.0 MILES 11.609 KM ) ---------- -

3.5E-06 2.9E-06 1.6E-06 7.0E-07 6.0E-07 1.0E-06 1.6E-06 4.4E-06 6.3E-06 1.3E-05 1.0E-05 4.4E-06 2.4E-06 3.7E-06 3.4E-06 2.4E-06

! 3.1E-06 2.5E-06 1.4E-06 6.1E-07 5.2E-07 8.7E-07 1.4E-06 3.9E-06 5.5E-06 1.1E-05 8.9E-06 3.9E-06 2.1E-06 3.tE-06 3.0E-06 2.1E-06 t

! 1.1E-08 1.4E-08 9.3E-09 4.2E-09 2.8E-09 4.4E-09 7.2E-09 1.2E-08 1.1E-08 1.6E-08 1.2E-08 5.2E-09 3.7E-09 6.9E-09 7.4E-09 6.3E-09 . [

i '3.5E-06 2.9E-06 1.6E-06 7.0E-07 5.9E-07 9.9E-07 1.6E-06 4.4E-06 6.2E-06 1.3E-05 1.0E-05 4.4E-06 2.3E-06 3.7E-06 3.4E-06 2.4E-06 og i 3.5E-06 2.9E-06 1.6E-06 7.0E-07 5.9E-07 1.0E-06 1.6E-06 4.4E-06 6.3E-06 1.3E-05 1.0E-05 4.4E-06 2.4E-06 3.7E-06 3.4E-06 2.4E-06 (D ,

j 3.0E-06 2.5E-06 1.4E-06 6.1E-07 5.2E-07 8.7E-07 1.4E-06 3.8E-06 5.4E-06 1.1E-05 8.8E-06 3.8E-06 2.1E-06 3.2E-06 3.0E-06 2.1E-06 y l 3.0E-06 2.5E-06 1.4E-06 6.1E-07 5.2E-07 S.7E-07 1.4E-06 3.9E-06 5.5E-06 1.1E-05 8.8E-06 3.9E-06 1.1E-06 3.tE-06 3.0E-06 2.1E-06 l 1609. 1609. 1609. 1609. 1609. 1609. 1609. 1609. 1609. 1607. 1609. 1609. 1609. 1609. 1609. 1609. o I .

TOTAL OBS - 8783 TOTAL INV OSS - 228 CALMS LONER LEVEL - 58.00 KEY: ENTRY I RELATIVE CONCENTRATION - XOQ (S/ Man 3 8 ENTRY 2 DEPLETED RELATIVE CONCENTRATION IS/Mme3t i ENTRY 3 RELATIVE OEPOSITION RATE (1/Mmm23 ENT'tY 4 DECAYED XOQ IS/ Man 31 - HALF LIFE 2.26 DAYS

ENTRY 5 DECAYE0 M00 (S/ Mum 3) - HALF LIFE 8.00 DAYS ENTRY 6 DEC+DPL XOQ IS/ Man 31 - HALF LIFE 2.26 DAYS l

ENTRY 7 DEC+DPL h04 (S/Ma*31 - HALF LIFE 8.00 DAYS EN RY 8 - DISTANCE IN METERS l

I 4

1

1 AVERAGE 9ETEOROLOGICAL RELATIVE C(BCENTRATIE36 ANALYSI3 DATA PE"IOD : 01/01/94 TO 12/31/84 FINED AND SPECIAL DISTANCES DISPERSION ANALYSIS #e RADIOLOGICAL EFFLUENT DISPERSION PROGRAN ADSSES (CNDAP10 3 CALEfmAR YEAR 1984 SU54UENA804A STEAN ELECTRIC STATION 6 LUZERDE COLs4TYe PA PEfteSYLVANIA PODEER & LIGelT COMPANYl ALLENTt304, PA DATE 17-FES-85 ADSSES DEVELOPE 0 SY NODIFICATION OF 08N PROGRAN ANDIFF .

AFFECTED SECTORS 904E ME ENE E ESE SE SSE S SSN SN NSM N D004 let D004 d

]

EITE BOL4 GARY (INCLUDIleB PURCllASEO FAlWI IN SNI 1.1E-05 7.1E-06 2.0E-06 1.0E-06 1.7E-06 4.4E-06 6.5E-06 1.7E-05 2.3E-85 2.6E-05 2.0E-05 1.1E-05 5.1E-06 1 18-05 1.0E-05 9.5E-06 9.9E-06 6.4E-06 1.7E-06 9.2E-07 1.5E-06 4.1E-06 6.0E-06 1.6E-05 2.1E-05 2.4E-05 1.8E-05 9.6E-06 4.7E-06 1.0E-05 9.7E-06 8.8E-06 3.9E-08 3.9E-08 1.1E-OS 6.5E-09 8.8E-09 2.2E-08 3.3E-00 5.1E-08 4.5E-OS 3.5E-OS 2.4E-08 1.3E-08 8.7E-09 2.3E-04 2.6E-08 2.9E-08 ,

1.1E-05 7.0E-06 1.9E-06 1.0E-06 1.7E-06 4.4E-06 6.5E-06 1.7E-05 2.3E-05 2.6E-05 2.0E-05 1.1E-05 5.1E-06 1.1E-05 1.02-05 9.4E-06 1.1E-05 7.0E-06 2.0E-06 1.0E-06 1.7E-06 4.4E-06 6.5E-06 1.7E-05 2.3E-05 2.6E-05 2.0E-05 1.1E-05 5.1E-06 1.1E-05 1.0 505 9.5E-06 9.9E-36 6.4E-06 1.7E-06 9.2E-07 1.5E-06 4.1E-06 6.0E-06 1.6E-05 2.1E-05 2.4E-05 1.8E-05 9.5E-06 4.6E-06 1.0E-05 9.7E-06 8.7E-06 9.9E-06 6.4E-06 1.7E-06 9.2E-07 1.5E-06 4.1E-06 6.0E-06 1.6E-05 2.1E-05 2.4E-05 1.8E-05 9.6E-06 4.6E-06 1.0E-05 9.7E-06 S.8E-06

,664. 875. 1395. 1298. 837. 558. 587. 587. 682. 965. 972. 943. 972. 742. 645. 644.

NEAREST DAIRY ANIMALS (PER 1994 LAsm-USE CENSUSB----

3.1E-07 2.8E-07 3.9E-07 6.2E-08 1.4E-07 2.1E-07 2.5E-07 1.1E-06 1.2E-06 1.8E-06 4.SE-06 3.1E-07 1.eE-07 3.5E-06 3.6E-07 2.5E-07 2.3E-07 2.1E-07 3.1E-07 4.7E-08 1.1E-07 1.7E-07 1.9E-07 9.0E-07 9.5E-07 1.4E-06 4.0E-06 2.3E-07 1.4E-07 3.1E-06 2.7E-07 1.8E-07 6.7E-10 1.0E-09 1.9E-09 2.8E-10 5.6E-10 7.8E-10 8.6E-10 2.5E-09 1.6E-09 1.6E-09 5.0E-09 2.2E-10 1.8E-10 6.7E-09 3.4E-10 4.3E-10 3.0E-07 2.8E-07 3.8E-07 6.1E-OS 1.4E-07 2.1E-07 2.4E-07 1.1E-06 1.2E-06 1.8E-06 4.8E-06 3.0E-07 1.8E-07 3.5E-06 3.5E-07 2.4E-07

! 3.1E-07 2.8E-07 3.9E-07 6.2E-08 1.4E-07 2.1E-07 2.5E-07 1.1E-06 1.2E-06 1.8E-06 4.8E-06 3.1E-07 1.8E-07 3.5E-06 3.6E-07 2.4E-07 I 2.2E-07 2.0E-07 3.1E-07 4.6E-08 1.1E-07 1.7E-07 1.9E-07 8.8E-07 9.3E-07 1.4E-06 4.0E-06 2.2E-07 1.3E-07 3.1E-06 2.6E-07 1.8E-07 [

l 2.3E-07 2.1E-07 3.1E-07 4.6E-08 1.1E-07 1.7E-07 1.9E-07 8.9E-07 9.5E-07 1.4E-06 4.0E-06 2.3E-07 1.3E-07 3.1E-06 2.7E-07 1.8E-07 8045. 8045. 4344. 7241. 3862. 4183. 5149. 3862. 4827. 5632. 2735. 8045. 8045. 1448. 6758. 8045. **-

V NEAREST GARDENS IPER 1984 LAIS-USE CENSUSI----------

3.0E-06 9.2E-07 4.6E-07 1.8E-06 3.0E-07 3.6E-06 2.9E-06 3.4E-06 3.7E-66 1.4E-05 7.9E-06 3.0E-06 3.5E-06 4.2E-06 2.0E-06 5.3E-06 2.6E-06 7.4E-07 3.7E-07 1.7E-06 2.6E-07 3.3E-06 2.6E-06 2.9E-06 3.1E-06 1.6E-05 6.8E-06 2.5E-06 3.1E-06 3.7E-06 1.7E-06 4.8E-06 u 9 (E-09 3.9E-09 2.3E-09 1.3E-08 1.4E-09 1.8E-08 1.4E-08 8.6E-09 6.1E-09 2.3E-08 8.8E-09 3.3E-09 5.7E-09 8.0E-09 4.0E-09 1.5E-08 N 3.0E-06 9.1E-07 4.6E-07 1.8E-06 3.0E-07 3.6E-06 2.9E-06 3.3E-06 3.6E-06 1.8E-05 7.8E-06 2.9E-06 3.5E-06 4.2E-06 2.0E-06 5.3E-06 i 3.0E-06 9.1E-07 4.6E-07 1.8E-06 3.0E-07 3.6E-06 2.9E-06 3.3E-06 3.6E-06 1.8E-05 7.8E-06 2.9E-06 3.5E-06 4.ZE-06 2.0E-06 5.3E-06 i 2.6E-06 7.4E-07 3.7E-07 1.7E-06 2.6E-07 3.3E-06 2.6E-06 2.9E-06 3.1E-06 1.6E-05 6.7E-06 2.5E-06 3.1E-06 3.7E-06 1.7E-06 4.8E-06 i 2.(E-06 7.4E-07 3.7E-07 1.7E-06 2.6E-07 3.3E-06 2.6E-06 2.9E-06 3.1E-06 1.6E-05 6.7E-06 2.5E-06 3.1E-06 3.7E-06 1.7E-06 4.8E-06 !

1770. 3701. 3862. 805 2253. 644. 1126, 1931, 2414. 1287. 1931. 2092. 1287. 1448. 2253. 965.

MEAREST RESIDENCES 184 CENSUS B---------------------- -

4 3.5E-06 9.2E-07 5.5E-07 1.8E-06 1.8E-06 3.6E-06 2.9E-06 3.8E-06 3.7E-06 2.8E-05 7.9E-06 6.2E-06 3.5E-06 4.4E-06 5.3E-06 5.3E-06 3.1E-06 7.4E-07 4.5E-07 1.7E-06 1.6E-06 3.3E-06 2.6E-06 3.3E-06 3.1E-06 2.5E-05 6.8E-06 5.5E-06 3.1E-06 3.9E-06 4.8E-06 4.8E-06 *ts l 1.1E-08 3.9E-09 2.8E-09 1.3E-04 9.4E-09 1.8E-08 1.4E-04 9.9E-09 6.1E-09 3.7E-08 8.8E-09 7.7E-09 5.7E-09 8.4E-09 1.2E-08 1.5E-08 W 3.5E-06 9.1E-07 5.4E-07 1.8E-06 1.7E-06 3.6E-06 2.9E-06 3.8E-06 3.6E-06 2.8E-05 7.8E-06 6.2E-06 3.5E-06 4.4E-06 5.3E-06 5.3E-06 $

i 3.5E-06 9.1E-07 5.5E-07 1.8E-06 1.8E-06 3.6E-06 2.9E-06 3.8E-06 3 6E-06 2.8E-05 7.8E-06 6.2E-06 3.5E-06 4.4E-06 5.3E-06 5.3E-06 1 3.0E-06 7.4E-07 4.4E-07 1.7E-06 1.6E-06 3.3E-06 2.6E-06 3.3E-06 3.1E-06 2.5E-05 6.7E-06 5.5E-06 3.1E-06 3.9E-06 4.7E-06 4.8E-06 u i 3.CE-06 7.4E-07 4.5E-07 1.7E-06 1.6E-06 3.3E-06 2.6E-06 3.3E-06 3.1E-06 2.5E-05 6.7E-06 5.5E-06 3.1E-06 3.9E-06 4.8E-06 4.8E-06 1609. 3701. 3379. 805. 805. 644. 1126. 1770. 2414. 965. 1931. 1287.' 1287. 1448. 1126. 965. S i . .

TOTAL OBS - 8783 TOTAL INV OSS - 228 CALHS LONER LEVEL - 58.00 4 KEY: ENTRY-1 RELATIVE CONCENTRATION - NOG (S/ Man 3) FNTRY 2 DEPLETED RELATIVE CONCENTRATION IS/Mem33

) ENTRY 3 RELATIVE DEPOSITION RATE (1/Mem2) ENTRY 4 OECAYED XOG IS/Mem33 - HALF LIFE 2.26 OAYS 4 ENTRY 5 DECAYED MOS ES/Mem33 - HALF LIFE 8.00 DAYS ENTRY 6 DEC+DPL XOQ IS/Mem3B - HALF LIFE 2.26 DAYS i ENTRY 7 DEC+DPL Noe IS/M**11 - HALF LIFE 8.00 DAYS ENTRY 8 - DISTANCE IN HETERS i

j 4

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] AVERAGE 8ETEGROLOGICAL RELATIVE CCDCENTRATION ANALYSIS 4

I DATA PECIOS : 01/01/04 TO 12/31/84

) FIXE 0 Ate SPECIAL DISTAfCES DISPERSION ANALYSIS me. RADIOLOGICAL EFFLUENT OISPERSImi PROGRAN ADSSES (CleAP10)

CCLEleAR YEAR 1994 SUSIBJENA804A STEAN ELECTRIC STATIONS LUZEREE ColefTY, PA PEDetSYLVANIA PONER & LIGHT CW9ANV) ALLENTIBede PA 1 DATE 17-FE8-85 ADSSES DEVELOPE 0 SY DWDIFICATION OF DAM PROGRAN A8SIFF t

AFFECTE0 SECTORS .

10E DE E8E E ESE SE SSE S SSN SN NSN N Dett let lett N 1 LON POPULATION ZONE RADIUS - ~~-- .

6.9E-07 6.1E-07 3.3E-07 1.2E-07 9.3E-08 1.5E-07 2.8E-07 7.3E-07 1.2E-06 2.4E-06 2.1E-06 7.7E-07 4.4E-07 7.1E-47 6.2E-07 5.2E-07 3 5.4E-07 4.8E-07 2.6E-07 9.8E-08 7.3E-08 1.2E-07 2.2E-07 5.8E-07 9.5E-07 1.9E-06 1.7E-06 6.1E-07 3.4E-07 5.6E-07 4.9E-07 4.1E-07

' 1.7E-09 2.5E-09 1.6E-09 6.1E-10 3.6E-10 5.5E-10 1.0E-09 1.5E-09 1.6E-09 2.3E-09 1.8E-09 6.7E-10 5.2E-10 1.0E-09 1.0E-09 1.1E-09 6.8E-07 6.0E-07 3.3E-07 1.2E-07 9.1E-08 J.5E-07 2.8E-ts? 7.2E-07 1.2E-06 2.4E-06 2.1E-06 7.5E-07 4.2E-07 6.9E-07 6.1E-07 5.1E-07 j 6.9E-07 6.1E-07 3.3E-07 1.2E-07 9.2E-06 1.5E-07 2.8E-07 7.3E-07 1.2E-06 2.4E-06 2.1E-06 7.7E-07 4.3E-07 7.0E-07 6.2E-07 5.2E-07 5.4E-07 4.7E-07 2.6E-07 9.6E-08 7.2E-08 1.2E-07 2.2E-07 5.7E-07 9.3E-07 1.*E-06 1.6E-06 5.9E-07 3.3E-07 5.4E-07 4.8E-07 4.0E-07 1

5.4E-07 4.8E-07 2.6E-07 9.7E-08 7.3E-08 1.2E-01 2.2E-07 5.7E-07 9.5E-07 1.9E-06 1.7E-06 6.0E-07 3.4E-07 5.5E-07 4.9E-07 4.1E-07

. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827. 4827.

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l TOTAL OSS - 8783 TOTAL INV OSS - 228 CALMS LODER LEVEL - 58.00

KEY: ENTRY 1 RELATIVE C(NCENTRATION - XOG (S/Mmell ENTRY 2 DEPLETED RELATIVE CotCENTRATION IS/Mem3 B j ENTRY 3 RELATIVE DEPOSITION RATE 11/ Man 21 ENTRY 4 OECAYED XOQ (S/Ma#3) - IlALF LIFE 2.26 DAYS 1 ENTRY 5 DECAYED XOG (S/Mem31 - HALF LIFE 8.00 DAYS ENTRY 6 DEC+DPL XOg (S/Mem3) - HALF LIFE 2.26 DAYS

] ENTRY 7 DEC+0PL XO4 IS/Ma#3) - HALF LIFE 8.00 DAYS ENTRY 8 - DISTANCE IN METERS I

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RECIRCULATION / TERRAIN CORRECTICB4 FACTORS RIMS NME BSE DE E9E E' ESE SE SSE 2 SSN SM MSM M 90 04 ' 9e . . Otti . N

, 0.5 MILES t.405 KM) 2.34 2.21 2.34 2.32 2.54 2.43 2.68 2.44 2.27'1.92 1.82 2.52 2.56^ 3.00 2.50 2.15 1.5 MILES (2.41 KM) 2.42 2.33 2.50 2,08 2.24 2.44 2.44 2.35 2.41 2.14'. 2.35 2.10 2.60 3.10 2.79' 2.19 -

2.5 MILES 84.02 KM) 2.54 2.50 2.72 2.06 2.00 2.25 2.45 1.20 2.55 2.06 2.40 1.96 2.41 2.95 2.75 2.37

, 3.5 MILES 65.63 EMI 2.32. 2.36 2.75 1.46 1.78 1.75 2.06 1.42 1.88 1.77 2.03 1.64 2.15 2.75 2.58 2.11 4.5 96LES 87.24 KM) 2.31 2.41 2.87 1.80 1.50 1.41 1.65 1.60 1.61 1.55 1.89. 1.51 2.00 2.56 2.41 2.08 7.5 MILES 112.07 KMI 2.19 2.34 2.84 1.69 1.10' O.95 1.12 1.24 1.25 1.27 1.60 1.18 1.72 2.24 E.31 2.70 15.0 MILES I24.1 KM) 0.96 1.41 2.46 1.00 0.68 0.59 0.65 0.40 0.57 0.52 0.60 0.44 0.84 1.19 1.15' 1.04 25.0 MILES E40.2 KM) 0.32 0.38 1.50 0.56 0.42 0.17 0.21 0.15 0.19 0.25 0.19 0.10 0.29 0.31 0.35 0.47 1 35.0 MILES (56.3 KMI 0.13 0.15 0.60 0.14 0.09 0.05 ts.07 0.05 0.05 0.11. 0.06 0.05 0.05 0.06 0.18 0.15 1 45.0 MILES 172.4 KM) 0.07 0.07 0.29 0.08 0.05 0.01 0.05 0.05 0.02 0.06 0.02 0.01 0.01 0.02 0.04 0.05 0.4 IGLES 10.644 EMI 2.15 2.17 2.37 2.31 2.71 2.45 2.56 2.35 2.30 1.90. 1.75 2.29 2.55 3.00 2.55 1.17 1 0.6 MILES (0.965 KMI 2.35 2.27 2.37 2.32 2.58 2.44 2.71 2.46 2.36 2.04 2.05 2.45 2.67 5.06 2.53 2.20 0.7 MILES 41.126 KMI 2.45 2.31 2.42 2.32 1.55 2.46 2.77 2.50 2.58 2.14 2.10 2.37 2.54 3.00 2.69 2.15 i 0.0 MILES (1.287 KM) 2.35 2.33 2.55 2.35 2.67 2.70 2.e2 2.50 2.45 2.18 2.20 2.29. 2.74 3.50 2.75 2.25-

0.9 MILES I1.444 KMI 2.43 2.33 2.50 2.27 2.60 2.59 2.85 2.53 2.39 2.17 2.34 2.38 2.75 3.18 2.85 2.14

1.4 MILES 11.609 KMn 2.50 2.25 2.57 2.15 2.39 2.57 2.59 2.46 2.31 2.16 2.30 2.25 2.57 3.07 2.91 2.08 i KITE SOUlWARY EINCLU 2.15 2.24 2.51 2.33 2.54 2.57 2.34 2.09 2.29 2.04 2.05 2.40 2.67 3.00 2.35 2.17 IEAREST DAIRY ANIMAL 2.29 2.41 2.72 1.80 2.02 2.25 2.18 2.21. 2.11 1.77 2.34 1.46 1.*5 2.51 2.40 2.18 I

DEAREST GARDENS IPER 2.44 2.47 2.70 2.09 2.00 2.45 2.77 2.45 2.41 2.18 2.51 2.15 2.74 3.01 2.75 2.20 i SEAREST RESIDENCES I 2.50 2.47 2.63 2.09 2.58 2.45 2.77 2.45 2.41 2.18 2.51 2.29 2.74 5.18 2.69 1.20 LOM POPULATION ZONE 2.45 2.45 2.73 1.96 1.89 2.00 2.26 2.01 2.11 1.92 2.22 1.80 2.27 2.45 2.57 2.22 1 -

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DI2TRIStNIt010F CALF 5 SY MDS SECTOR PASS CLASS DOE DE Ehi! , E ESE SE SSE S SSN SN NSM N D004'. Det 9000 - N A 0.0 0.0 0.200 0.0 0.0 0.0 0.0 0.0 0.600 0.0 0.0 0.0 0.0 0.t00 0.0 0.0 0 0.0 0.0 0.0 0.0 0.250 0.250 0.0 0.250 0.250 0.0 0.0 - 0.0 0.0 0.0 0.0 0.0 -

C 0.0 0.0 0.250 0.003 0.0 0.003 0.160 0.0 0.003 0.333 0.0 0.0 '0.0 0.0 0.0- 0.0 "

O 0.116 0.063 0.009 0.007 0.051 0.100 0.005 0.007 0.109 0.003 0.036 0.001 0.005 0.007 0.016 0.065 E 0.112 0.143 0.121 0.003 0.050 0.066 0.075 0.074 0.001 0.040 0.'025 0.012 P.006 0.012 0.014 0.079 F 0.090 0.315 0.202 0.105 0.034 0.031 0.032 0.023 0.024 0.006 0.003 0.003 0.005 0.004 0.009 0.029 8 0.106 0.441 0.303 0.061 0.015 0.025 0.006 0.006 0.006 0.002 0.0 0.0 0.0 0.004 0.002 0.021-HEIGHT OF %#TICAL MIXING LAYER = 1050.0 IETERS HEIGHT OF CONTAIMENT STRUCTURE = 1.0.4 DETERS THRESH 0LO OF ANEMOMETER = 0.34 IFS DET DATA FILE USEO - MET 04 HEADER FILES USEO - FIXE 0 , FLUID -

DUTPUT FILES USEO - APPO1 e APPOR THERE MERE S SPECIAL RECEPTOR RINGS INCLUDED IN THIS RLat. e4 USER-SPECIFIES RECIRCULATION / TERRAIN CORRECTION FACTORS DERE APPLIED TO THE MODEL CALCULATIONS. p2 DEPLETION MAS APPLIED TO THE MODEL CALCULATIONS. g DEPOSITION MAS CALCULATED.

ALL OUTPUT DATA DERE MRITTEN TO THE GASPAR FORMAT FILE.

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9 SECTION 4 DOSE MEASUREMENTS AND ASSESShENIS e

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1, TABLE 15 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT MAXIMUM

OFF-SITE DOSES AND DOSE COMMITMENIS TO MEMBERS OF 711E PUBLIC Data Period: 1984 1

DOSE *** (mi11Irem)

Source 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr ' Year **

1 s 's is 17 A. Waterborne Effluents 2.66E-4 6.06E-5 7.80E-5 3.40E-5 3.82E-4 2 s is 14 1e B. Airborne Effluents 1.05E-2 8.12E-2 -1.71E-1 '4.52E-2 3.07E-1 i) Iodines & Particulates 3 7 11 15 19 1i) Noble Gases 5.31E-4 3 68E-2 8.00E-2 '1.96E-2 1.39E-1 4 e 12 16 20 C. Direct Radiation 0 0 0 0 0 i

Based on meteorological data provided in Section 3. Data for the entire ,

year was used for the calculations for airborne effluents.

'I11ERE ARE NO OINER URANIUM FUEL CYCLE FACILITIES WIIIIIN 8 KM of SSES

" Maximum" means the largest fraction of the corresponding Appendix I dose design objective.

- " Maximum" dose for the year may not equal the sun of the quarterly maximum doses because the doses may be to different organs or may be at different receptor locations.

'*** The numbered footnotes on the following page briefly explain how each maximum dose was calculated, including the organ and predominant' pathway (s).

57

Footnotes for Table 15

1. Dose to the teen total body, primarily by the drinking water and fish pathways. Calculated at the closest down-stream drinking water user on the Susquehanna River (Danville, PA) using the TADTAP II program.

2. Dose to the child lung via the vegetation, inhalation, and ground pathways. Calculated at the residence at 0.8 mi SW using the GASPAR program.

3. -Dose to the total body via the plume pathway. Calculated at the residence at 0.8 mi SW using GASPAR. .

4. Based on environmental themoluninescent dosimeters placed near SSE3 in unrestricted areas (See " Method for IID Data Analysis" on the following page).

5. Dose to the child total body, primarily via the drinking water and fish pathways'. Location: Danville PA.

6. Dose to the child thyroid via the vegetation, grcund, and inhalation l pathways. Location: Residence 0.8 mi SW.

7. See Footnote 3.

8. See Footnote 4. _

9. See Footnote 5.

10. See Footnote 6.

11. See Footnote 3.

12. See Footnote 4.

13. See Footnote 5.

l l

14. See Footnote 6.

15. See Footnote 3.

l l 16. See Footnote 4.

l

17. See Footnote 1. -

18. See Footnote 2.

19. See Footnote 3. -

20. See Footnote 4.

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4 58

[

IElHOD FOR 'lLD DATA ANALYSIS The historical relationships between SSES Radiological Environmental Monitoring Program (REMP) control TLD location data points and the indicator TID location data points are used to predictively model the expected radiation levels at the indicator locations. Preoperational data from third quarter 1980 through second quarter 1982 were used to calculate the predictive model for 19 indicator locations *. For each of the 8 preoperational quarterly readings, the ratio of the indicator reading to the average'of four contr'1 oreadings (4G1, 7G1, 12G1, and 3G3) was calculated for all 19 indicator locations. The average and standard

. deviation of the ratio for the 8 quarterly readings were calculated for each indicator location. This constitutes the predictive model.

The 1984 data was compared to the predictive model. For each quarter of 1984, the ratio of the indicator reading to the average of the four control readings was calculated for all 19 indicator locations. The four quarterly values calculated for each of the 19 indicator locations were compared to the respective predictive model via a Student's t-test. In all cases the 1984 data were not significantly different from the preoperational data at the 95% confidence level. It is therefore concluded that the radiation levels at the indicator locations are not higher than expected from natural background, and direct radiation from SSES la estimated to be O mR.

Indicator locations used: IS2, 2S2, 2S3, 4S1, 3S4, 4S3, SS7, 6S4, 7S3, 8S2, 9S1, 10S1, 11S2, 12S3, 13S2, 14S5, 15S3, 16S1, and 7A1.

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I DOSES 'IT) MEMBERS OF DE PUBLIC WIDlIN DE SITE BOUNDARY SSES Technical. Specification 6.9.1.8 requires that the Semiannual Effluent Release Reports include an assessment of the radiation dose from radioactive effluents to members of the public within the site boundary. Within the SSES site boundary there are two areas which are open to members of the public (See Figure 8):

The Susquehanna Riverlands Recreation Area /

Energy Information Center

A Residential Area in the Southeast Sector In the area comprising the Riverlands recreation area, which surrounds the Energy Infomation Center, four pathways of radiation exposure can ,

be identified: plume, ground, inhalation, and direct radiation. There l are no significant exposure pathways from waterborne effluents in this area. !

Based on calendar year 1983, there are approximately 50,000 visitors to l the Riverlands/Information Center complex each year. In order to l facilitate dose calculations, it is assumed that each visitor stays in 2

the area xor one hour.

, Thermoltaninescent dosimeters are positioned near the information center and at another location within the Riverlands. Readings from 1984 Indicate radiation levels are not significantly different than observed natural background (See " Methods of TLD Data Analysis" on page 59).

Use of the GASPAR code yields calculated doses for the Riverlands area for the report period % s doses are the total doses at the location .

from gaseous effluen' ~ alng the report period. In order to compute doses to members of the public who stay for only short periods of time, these doses are converted to dose rates. Taking into account the estimated 50,000 person-hours of occupancy, the collective (man-rom) doses shown in Table 16 are calculated.

Doses at the residence at 0.4 mi SE are representative of the residential

~ ~

area in the southeast sector within the site boundary. The exposure pathways present in this area are plume, ground, vegetation, inhalation, and direct radiation. The calculated doses for this location are shown in Table 17. A themoluminescent dosimeter placed at the residence at 0.4 mi in the SE sector indicated radiation levels that are not significantly different from background (See " Methods of TU) Data Analysis" on page 59).

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Suscuehanna i River ancs ' '

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RECREATION AREA , /

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.. ] , Houses ,

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FIGURE 8: AREAS WITHIN THE SSES SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC r.

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TABLE 16 COLLECTIVE DOSES TO MEMBERS OF '11E PUBLIC WI'111IN TIE RIVERLANDS/INFORMATION CENIER COMPLEX Data Period: 1/1/84 - 12/31/84 Exposure Pathway Organ (s) Collective Dose (man-rem) plume

total body, GI-tract, bone, l ive;,*, thyroid 9.70E-05 lung 9.76E-05 skin 1.56E-04 ground

total body, GI-tract, bone,-liver, kidney, -

thyroid, lung, skin 4.78E-06 skin 5.64E-06 inhalation teen total body 1.87E-05 teen, adult GI-tract 1.8.7E-05 child bone 2.91E-07 teen liver 1.89E-05 teen kidney 1.91E-05 child thyroid 1.06E-04 teen lung 1.90E-05 teen skin 1.86E-05

Doses via these pathways are not age-group dependent.

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TABLE 17 CAIEULATED DOSES FOR DE RESIDENIIAL AREA IN DE SOUIREAST SECIOR WIDlIN DE SSES SITE BOUNDARY Data Period: 1/1/84 - 12/31/84 Exposure Pathway Organ (s) Dose (mrem) plume

total body, GI-tract, bone, liver, kidney, thyroid, 2.78E-02 lung 2.80E-02 skin' 4.46E-02 ground

total body, GI-tract,

. bone, liver, kidney, thyroid, lung 1.16E-03 skin 1.37E-03 vegetation child total body 1.46E-02 child GI-tract 1.46E-02 child bone 5.21E-04 child liver __ 1.47E-02 child kidney 1.48E-02 child thyroid 7.88E-02 child lung, skin 1.44E-02 inhalation teen total body 5.37E-03 teen GI-tract 5.35E-03 child bone 8.37E-05 teen liver 5.42E-03 teen kidney 5.48E-03 child thyroid 3.05E-02 teen lung 5.45E-03 teen skin 5.33E

Doses via these pathways are not age-group dependent.

63

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SECTION 5 N TO THE OFF-SITE DOSE CALCULATION MANUAL AND TliE SOLID WASTE PROCESS CONIROL PROGM O

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- . - - _ - - . . . _ _ _ _ _ _ _ . - - _ . . . _ - . - _ . _ . . _ _ . , . . . _ , _ _ _ _ _ . . - ~ _ _ _ _ , . _ _ . - - . _ _ _ - . - - . . . _ . _ _ _ _ . - . . _ . -

CHANGES 'IU 'I1E OFFSITE DOSE CATIUTATION MANUAL h e ODCM revision which became effective on July 9, 1984 incorporated a new method for calculation of airborne effluent monitor alarm setpoints.

his method is based on the actual (or expected) nuclide mixture in the effluent streams instead of being based on a setpoint, for example, for Xe-133 alone for noble gases. Setpoint methodology for noble gases, iodine-131, and particulate monitors are included.

R ese changes improve the technical basis of the affected monitor setpoints.

D ese changes.will not reduce the accuracy or reliability of dose calculations or setpoint determinations..

H ere were no milk animal, residence, or garden locations identified in the 1984 SSES land use census which yield calculated doses or dose commitments greater than the values currently being calculated for Technical Specification 4.11.2.3. No locations were identified which yield calculated doses or dose connitments 20 percent greater than at a location from which samples are currently being taken as part of the Radiological Environmental Monitoring Program. No sampling locations were added to the program for this reason via the mechanism of Technical

' Specification 3.12.2.

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PENNSYLVANIA POWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE. DOSE CALCULATION MANUAL

~

.J Prepared By

. C Date 27, .7 Y Reviewed By Date 2 d PORC R,eview Required Yes ( ) No (d Date Approved By .C $ Date 7 h M -

' Manager-Nuc1har Support

r. 00tG01 iED . .

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TABLE OF CONTENT $

Pm Revision Date 1.0 INT 10 DUCTION.................................. 1 7/12/82 2 5/11/82

. 3 4/27/83 4 5/11/82 5 5/11/82 6 4/27/83 2.0 SETP0INTS..................................... 7 4/27/83 2.1 LIQUID EFFLUENT MONITORS.................. 7 4/27/83 8 10/25/83 8b 1/20/84-2.2 GASEOUS EFFLUENT MONITORS................. 9 1/20/84 10 7/09/84 7/09/84 11 12- 7/09/84 13 7/09/84 3.0 LIQUID EFFLUENT CONCENTRATION MEASURDENTS... . 14 10/25/83 15 10/25/83 4.0 GASEOUS EFFLUENT DOSE RATE MEASUREMENTS....... 16 4/27/83 4.1 NOBLE GASES............................... 16 4/27/83

'- *^"' """ '" '"^"~" " ' - ' ' '

C's . 17A 7/09/84

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18 4/27/83 19 4/27/83 20 4/27/83 5.0 INDIVIDUAL DOSE DUE TO LIQUID EFFLUENT. . . . . . . . 21 4/27/63 22 10/25/83

". 23 5/11/82 24 5/11/82 6.0 INDIVIDUAL DOSE DUE TO GASEOUS -EFFLUENT. ..... . 25 4/27/83 6.1 NOBLE CASES............................... 25 4/27/83 6.2 RADIONUCLIDES OTHER THAN NOBLE GASES...... 26 4/27/83 27 4/27/83 28 5/11/82 29 5/11/82 7.0 TOTAL DOSE.................................... 30 4/27/83 31 5/11/82 8.0 OPERABILITY OF WASTE TREATDiENT SYSTEMS. . . . . . . 32 4/27/83 ~

8.1 LIQUID WASTE TREATDiENT. . . . . . . . . . . . . . . . . . . 32 4/27/83 8.2 GASEOUS WASTE TREATMENT................... 32 4/27/83 33 5/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83 35 5/14/84 36 5/11/82-37 5/11/82 38 5/11/82 c .

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9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 39 7/12/82 9.1 DEFINITIONS............................... 39 7/12/82 9.2 MONITORING PROGRAM........................ 39a 5/14/84 9.3 CENSUS PR0 GRAM............................ 40 5/14/84 40a 7/12/82 41 10/25/83 42 10/25/83 43 5/14/84 44 ' 5/11/82 l

45 5/14/84 46 5/11/82 47 5/11/82 48 4/27/83 APPENDIX A - SAMPLE CALCULATIONS OF ODCM PARAMETERS........................... A-1 10/25/83 A-2 7/09/84 A-3 7/09/84 A-4 7/09/84 i A-4A 7/09/84 A-43 '

7/09/84 A-4C 7/09/84 A-5 5/11/82 A-6

..('T 5/11/82 U A-7 5/11/82 A-8 5/11/82

. A-9 5/11/82 A-10 5/11/82 A-11 5/11/82 .

A-12 5/11/82 A-13 5/11/82-APPENDIX B - REPORTING REQUIREMENTS............... B-1 5/11/82 B-2 5/11/82 B-3 5/11/82 B-4 5/11/82 APPENDII C - SITE SPECIFIC INYORMATION USED IN GASPAR....................... C-1 5/11/82

. s APPENDII D - SITE SPECIFIC INFORMATION ~

USED IN LADTAP....................... D-1 4/27/83

, . D-2 4/27/83 D-3 4/27/83

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aut 0 9 54 u

W e C0iFR0_ _ED LIST OF TABLES

. t P g Revision Date Table 1 - Radiological Effluent Objectives and Standards... . 6 4/27/83 Table 2 Dose Factors for Noble Gases and Daughters........ 17A 7/09/84

. Table 3 Annual Average Relative Concentrations and Deposition Rates.................................. 18 5/11/82 Table 4 Dose Parameters for Radionuclides Other Than .

Noble Gases....................................... 20 4/27/83 Table 5 Liquid Dose Parameters for Adults......... ....... 23 5/11/82 Table 6 Hart == Pathway Dose Factors Due to Radionuclides Other Than Noble Gases. . . . . . . . . . . . . . 28 5/11/82 Table 7 Operational Radiological Environmental Monitoring Program...........~................... 41 10/25/83 42 10/25/83

. 43 5/12/84 Table 8 Detection Capabilities for Invironmental Sample Analys,is......;............................ 46 5/11/82 Table B-1 Radiological Environmental Monitoring Program Annual Summary.................................... .

B-3 5/11/82 Table B-2 Reporting Levels for Nonroutine' Operating Reports........................................... B-4 5/11/82 3.09 W J

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1. All exposure pathways of significance at the critical receptor locations;

2. Dose contributions to critical receptors from multiple release points; and

3. Dose contributions from major radioisotopes expected to be present in gaseous affluents.

The general methodology for establishing plant ventilation ,

gaseous' effluent monitor setpoints is based upon vent release rates derived from site-specific meteorological dispersion conditions, vent flow races, and measured or expected radioiso-topic mixtures in the gaseous affluents. .The vent release rates can then be converted to vent concentrations for input as set-points for the applicable detectors. Since the vent monitors are programmed to calculate concentrations of iodine-131 and particulate being released based on the rate of accumulation of activity on the filters, setpoints can be established for the iodine ar.d particulate channels.

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JUL 091984 lf L.V

- . - . . . . . . . . . - . - - - - . . .. - .. .- - _ -.-,- - _ _ ~ , - - . , . . - -

j' The following method is used for calculating vent' monitor high radiation

's alarm setpoints:

1. An isotopic mixtura is selected for the detector in question, if applicable. Noble gas and. particulate detector setpoints are based on actual isotopic mixtures obtained from vent sample analysis or the FSAR/FES expected release mixtures if actual samples do not contain sufficient detectable activity to accurately estimate the mixtures.

The assumed isotopic mixtures are periodically reviewed to verify that.they remain representative of plant effluents.

2. The selected noble gas,or particulate mixture is used in the GASPAR program run to calculate the associated doses. The total source term (total curies used for the calculation) does not matter as long as the proper nuclides are present in the relative proportions indicated in sample analysis data or FSAR/FES tables.

. For the iodine-131 setpoint, any release total for I-131 can be s

i . entered. The highest calculated annual average relative concentra-tions (X/Qs) at the site boundary are used for these GASPAR calcula-tions.

3. The following ratic; concept is used to calculate a release rate limit for the assumed mixture- (or I-131):

Calculated Dose (arem) = Dose Rate Limit (arem/yr)

Total GASPAR Source Term (C1) Limiting Release Rate (C1/yr)

The limiting release race of the assumed mixture (or I-131) can therefore be calculated; Limiting Release (C1/yr) =

(Total GASPAR Source Term, Ci) (Dose Rate Limit, mrem /yr)

(Calculated Dose, mram)

Jul. 0 91984 (v

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.,.'.. For the noble gas setpoint,.the calculated whole body and skin dose r-rates via the plume pathway are subject to the 10CFR20-derived limits of 500 and 3000 arem/yr, respectively. The whole body dose rate limit is usually most restrictive. For particulates and for iodine-131, the maximum calcuAated organ dose via the inhalation pathway is subject to he limit of 1500 mram/yr.

- 4. The limiting release rates are converted to limiting vent concentra-tions using high limit vent flow rates.

. Limiting Vent Concentration, uCi/cc =

(Limiting Release Rate, C2./yr) (10E6uci/C1)

(5.26ES min /yr) (Vent High Limit Flow Rate, cc/ min)

Sample calculations of liquid and gaseous effluent monitor setpoints are presented in Appendi: A. _

1/^'s

Vent flow rates and sample flow rates are monitored and recorded for s

Q.- -

each of the five SSES release points. The measured flow rates are used to calculate vent concentrations and release rates. Flow

_. channel setpoints are set at 10%'and 90% of the calibrated sensor ranges to provide inoication of possibly abnormal flow rates.

l SPECIFICATION' 3.11.2.6 - THE CONCENTRATION OF HYDROGEN OR OXYGEN IN i THE MAIN CONDDISER OFFGAS TREATHENT SYSTEM SHALL BE LIMITED TO LESS l THAN OR EQUAL TO 4% BY VOLUME.

l Hydrogen recombiners are used at SSES to maintain the relative concentration of componena of potentially -explosive gas mixtures,

. , outside the explosive envelope. The main condenser offgas treatman ,

system explosive gas monitoring system (offgas hydrogen analyzers) have setpoints of 1% hydrogen to alarm and 2% hydrogen to isolate.

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TABLE 2 - ,

DOSE FACTOR!i FOR NOBLE CASES AND DAUGHTERS" Whole Body Camer.a Air. Beta Air j .

i Dose Factor !ikin Dose Factor Dose Factor Dose Factor

~

K L M N (aren/yr her pCi/m - paren/yrherpCi/m (arad/yr pkr pCi/m ) (arad/yr phr pCi/m )

I Radionuclide i

7.56'E-02 1.93E+01 2.88E+02 Kr-83m '

I Kr-85m 1.17E+03 1.46E+03 1.23E+03 .1.97E103 4 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 5.92E+03 9.73E+03 6.17 E+03 1.03E+04

Kr-87 ~

Kr-88 1.47E+04 2.37E+03 1.52E+04 .2.93E+03 .

i Kr-89 1.66E+04 1.01E+04 1.73E+04 -

1.06E+04 i

7.29E+03 1.63E+04 7.83E+03 j C Kr-90 1.56E+04 i > 9.15E+01 4.76E+02 1.56E+02 1.11E+03 -

Xe-131m Xe-133m 2.51E+02 9.94E+03 3.27E+02 1.48E+03 l 3.53E+02 1.05E+03 i Xe-133 2.94E+02 3.06E+02 Xe-135m 3.12E+03 7.I1E+02 3.36E+03 7.39E+02 l 1.86E+03 1.92E+03 2.46E+03 1 Xe-135 1.81E+03

1.42E+03 l'.22E+04 1.51E+03 1. 27 E+04 Xe-137 8.83E+03 4.13E+ 03 9.21E+03 4.75E+03 Xc-138

! Ar-41 .8.84E+03 ,

2.69E*03 9.30E+03 3.28E*03 i

l l

The listed dose factors are for radionuclides that may be detected in gaseous effluents and derived l

Irom Table B-1 in Reg. Cuide 1.109.

D -2 7.56E-02 = 7.56 x 10 ,

! ta O

4 C ,

Sf .

j 4

5000 + f = 10+(1E-5)

V, f IE-7 f = 5 gym For an identified mixture with an actual MPC of 7.22E-7 pCi/ml and the same activity, blowdown flow and I and Y values as above, the LRW discharge monitor setpoint value and LRW dis-charge flow setpoint become:

~

Satpoint concentration (c) = 3E-5 pCi/a1 Satpoint value = 2.3E3 cpm + Background LRW discharge fl6v setpoint (f) = 36 gym ,

A.1.2 Gaseous Effluene Monitors A.1.2.1 Noble Gas Monitor To determine the release rate limit for noble gases, 3 an isotopic mixture representative of plant effluents

~

is selected. For example, the following mixture from Table 4.4.of the SSES Final Environmental Statement (FES) can be used: .

Argon-41 25 Ci/yr per reactor Krypton-83m 4 Krypton-85m 1,700 Krypton-85 270 Krypton-87 . 32 Krypton-88 660 Xenon-131m 71

~ Xenon-133m 14

. Xenon-133 12,500 Xenon-135m 220 Xenon-135 590 M 290 Total. 16,376 Ci/yr per reactor

~i JUL 091984 A-2

.. - . _. . __. - ~ . . - .-

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.s The above annual release quantities are entered into

GASPAR with the following annual average dispersion !

estimates (

Reference:

1982 SSES Meteorology Report):

i i Relative Concentration 4.lE-5 sec/m*

Decayed Relative Concentration 4.lE-5 sec/as Decayed Depleted Relative 1 Concentration 3.8E-5 sec/ms Deposition Rate 4.2E-8 m"8 L

This set of annual average meteorological parameters is the most conservative over the period 1973-1982.

t The total body dose via the plume pathway which results is 18.3 area. Equation 5 of the ODCM is then ,

used to calculage the limiting release rate from each of the five plant release points:

O .

Limiting Release Rate =

- (32.752 C1) (500 ares /yr) = 8.95E4 Ci/yr per vent (36.6 ares)_ _(5 venta) .

This limiting release race is then converted to limiting (setpoint) concentrations using Equation 6 of the ODCM and high limit vent flow races.

Sample High Limit Vent flow Rates:

o Unit 1 Reactor Building Vent 4.75E9 cc/ min Unit 2 Reactor Building Vent 4.75E9 cc/ min Standby Gas Treatment System Vent 5.04E8 cc/ min Unit 1 Turbine Building Vent 8.63E9 cc/ min Unit-2 Turbine Building Vent 6.50E9 cc/ min

.p

.:V Jul 0 9 Na4 A-3

g.

Limiting Vent Concentration =

1 (8.95E4'Ci/yr/vant)

(IE6 uCi/Ci) = 3.58E-5 uCi/cc for (5.26ES min /yr) (4.75E9 cc/ min) Reactor Buildings 1&2 Substituting the other vent flow rates into Equation 6 as above, the following noble gas high radiation set-point concentrations are calculated for the remaining

. vents:

Standby Gas Treatment System 3.37E-4 uCi/cc Unit 1 Turbine Building 1.97E-5 uC1/cc Unit 2 Turbine Buildine, 2.62E-5 uCi/cc A.1.2.2 Iodine-131 Moni.cor When the FES expected annual release quantity for

. 1-131 (2.40E-1 curies) is entered into GASPAR with the dispersion estimates of A.1.2.1, the maximum calculated organ dose via the inhalation pathway is 4.88 area to the child thyroid. Using Equation 5 of the ODCM, the limiting I-131 release race is calcu-i laced as follows:

Limiting Release Rata =

(.24 C1) (1500 arem/yr) = 1.48E1 Ci/yr/ vent (4.88 mren) (5 vents)

Using Equation 6 of the ODCM, the limiting (setpoint)

I-131 cone.entrations can be calculated for each of the five plant vents.

a Jul. 091984 A-4

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- Limiting Vent Concentration =

(14.8 Ci/yr/ vent) (1E6 uCi/Ci) = 5.92E-9 uC1/cc for *

(5.26ES min /yr) (4.75E9 cc/ min) Reactor Buildings 152 Substituting the other vent flow rates into Equation 6 of'the ODCM above, the high radiation setpoints for the remaining plant vents are calculated to be the following:

Standby Gas Treatment System 5.58E-8 uCi/cc Unit 1 Turbine Building 3.26E-9 uCi/cc Unit 2 Turbine Building 4.33E-9 uCi/cc

~

A.1.2.3 Particulate Monitor Following are the SSES Final Environmental Statement (FES) expected annual release; quantities for particu-

! late radionuclides:

Cr-51 1.2E-4 Ci/yr per reactor Ma-54 3.6E-4 Fe-59 1.6E-4 Co-58 5.8E-5 Co-60 1.1E-3 Zn-65 5.5E-5 .

i Sr-89 1.8E-5 Sr-90 3.1E-6

. Zr-95 8.7E-6 Sb-124 5.1E-6

- Cs-134 1.3E-4 JUL 091984

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Cs-136 1.3E-3 Cs-137 2.1E-4 Ba-140 4.2E-5 Ca-141 2.9E-5 Total 3.6E-3 C1/yr per reactor When the above annual release quantities are entered into GASPAR with the annual average dispersion esti- ,

mates of A.1.2.1, the maximum calculated organ dose via the inhalation pathway ~is 1.33E-2 area to the teen lung. Using Equation 5 of the ODCM, the limit-ing release rate of particulates can be calculated:

Limiting Relecase Rate =

t- (7.2E-3 C ) (1500 aren/yr) = 8.12E1 C1/yr/vant

{}y '(2.66E-2 area) (5 vents)

Using Equation 6 of the ODCM, the limiting (setpoint) particulate concentrations can be calcul'ated for each of the five plant vents.

Limiting Vent Concentration =

(81.2 Ci/yr/ vent) (1E6 uci/C1) = 3.25E-8 uci/cc for (5.26E5 min /yr) (4.75E9 cc/ min) Reactor Buildings 1&2 When the vent flow rates for the reraining five plant

~

vents are substituted into Equation 6 as above, the following high radiation setpoint concentrations result.

JUL 09 W gj._

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- Standby Gas Treatment System 3.06E-7 uCi/cc Unit 1 Turbine Building 1.79E-8 uCi/cc Unit 2 Turbine Building 2.38E-8 uC1/cc 9

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NES 10 ITE SOLID WASIE PROCESS CONIROL PROGRAM e

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PRCCEDURE COVER SHEET ;

PENNSYLVANIA POWER & LIGHT CO.

SUSQUEHANNA STEAM ELECTRIC STATION AD-QA-311 SOLIO WASTE PROCESS CONTROL PROGRAM Revision 4 Page 1 of 54 Effective Date //-/4 -8 f , Expiration Date //'/6-8[o -

Revised Expiration Date PROCEDURE TYPE: PORC N , NON-PORC , Alternate Review 4

DORC MTG. NO. 8# ,73(, (If applicable)

CONTROLLED Prepared by 3_ b . O _ _ __ Date n l 2, su Reviewed by _

Date//[6/%

Recommended: > Date // k Qd S on Head / Manager ,

! v/ h $b n.u w L Dateso/ch4 ~'

l SuperinYeMent af PlanC .

FORM AD-QA-101-1, Rev. 2, Page 1 of 1

AD-QA-311 Revision 4 Page 2 of 54 PROCEDURE REVISION INDEX

Title:

Procedure No. AD-QA-311 Solid Waste Process Control Program

~

Effective Rev. No.. Description of Revision Date 4 1. Added requirements and uses of high integrity containers.

2. Added Senior Project Engineer Radwaste in respansibilities.

3. Revised capping requirements to comply with burial site criteria.

4. Revised handling requirements for unacceptable waste containers.

6 i

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AD-QA-311 Revision 4 Page 3 of 54 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 5 2.0 SCOPE 5

3.0 REFERENCES

5 4.0 RESPONSIBILITIES 7

4.1 Senior Project Engineer - Radwaste 7 4.2 Shift Supervision 7 4.3 Radwaste Supervisor 7

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4.4 Chemistry Group 8 4.5 Health Physics Radwaste Specialist 8 4.6 Quality Control 9 4.7 I & C Supervisor 9 l

4.8 Auxtlary System Operator 10 4.9 Vendors providing solicification and/or Dewatering Services 10 4.10 Technical Group Supervisor 10 5.0 DEFINITIONS 10 6.0 PROCEDURE 12 6.1 Waste Types 12 6.2 Sriidification Product Control 15 .

6.3 Solidification Agent Control 21

' 6.4 Equipment Calibrations 22 6.5 Solidification Record Sheet 23 6.G Solidification Processing 23 i

AD-QA-311 Revision 4 Page 4 of 54 SECTION PAGE 6.7 Radioactive Spent Resin Dewatering 24 6.8' Changes to the Solid Process Control 25 6.9 Container Inspections 25 6.10 Storage of High Integrity Containers 25 6.11 Uses of High Integrity Containers 25 6.12 Closure of High Integrity Containers 28 7.0 RECORDS 28 T

AT'ACHMENTS ATTACHMENT PAGE A So1Jdification Record Sheet 29 B Dewatering Record Sheet 45 C Susquehanna Guaranteed Waste Volume Record 53 e

4 0

6 9

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A0-QA-311 Revision 4

. Page 5 of 54 1.0 PURPOSE Provide Administrative control and guidance for the solidification and dewatering of applicable forms-of Radwaste for ultimate disposal.

2.0 SCOPE

.This procedure is applicable to SSES installed systems and temporary systems and equipment provided by vendors for solidification and dewatering of applicable waste forms.

3.0 REFERENCES

3.1 49 CFR 173 3.2 10 CFR 20,61,71 3.3 SSES Technical Specifications Section 3.11.3, 4.11.3.1 and 4.11.3.2.

3.4 Standard review plan 11.4 .

3.5 HNDC " Liner Dewatering Test Report" Report No. I-843-3.

3.6 HNDC report on Dewatering of Bead Ion Exchange Resin and Activated Carbon, report No. Std-R-03-001.

3.7 HNDC Process Control Program for Dewatering Ion-Exchange Resin and Activated Charcoal filter media to 1/2% drainable liquid, Report No.

Std.-P-04-002.

3.8 HNDC Report on Dewatering of Bead Ion Exchange Resin and activated Carbon in Hittman Radiok 100 High Integrity containers, Report No.

Std.-R-03-002 3.9 HNDC Report on Dewaterig Hittman Radiok 100 containers with Rigid Underdrains to less than UE Orainable Liquid, Report No. Std.-P-03-005.

3.10 HNDC Report on Dewatering Hittman Radiok 100 containers with Flexible

- Underdrains to less than 1% Orainable Liquid, Report No. Std.-P-03-005.

3.11 HNDC Radioactive Waste Container General Specification, HNOC-5-1001.

.- 3.12 South Carolina Department of Health and Environmental Control Bureau of Radiological Health Certificate of Compliance No. DHEC-HIC-PL-005 HNOC '

Radlok 100 container.

3.13 Burial Site Criteria for Barnwell S.C..

. AD-QA-311

. Revision 4 Page 6 of 54 3.14~ Burial Site Criteria for Richland, Washington as indicated in the site license Amendments 13 and 14.

3.15 AD-QA-765'" Solid Radwaste Program" 3.16 AD-QA-605 Calibration of Installed Plant Instrumentation 3.17 CNSI Topical Report " Mobile Cement' Solidification System" 4313-01354-O1P-A 3.18 CNSI Topical Report " Polyethylene High Integrity Containers" CNSI-HIC-14571-01-P 3.19 CNSI Topical Report "CNSI Dewatering Control Process Containers Topical Report" CNSI-DW-11118-01-P 3.20 DHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers 3.21 DHEC-HIC-PO-006 South Carolina Certificate of Compliance for CNSI Overpak High Integrity Container 1 3.22 DHEC-HIC-FRP-003 South Carolina Certificate of Compliance for CNSI Fiberglass Reinforced Polyester 24 Inch Pressure Vessel as a High Integrity Container 3.23 CNSI FO-AD-002 Operating Guidelines for use of Polyethylene High Integrity Containers _,

3.24 CNSI FO-AS-004 Operating Guidelines for use of Fiberglass Reinforced l Plastic High Integrity Containers 3.25 CNSI FO-OP-019 Polyethylene High Integrity Container Overpak Handling Procedure

! 3.26 HNDC STD-0-03-009 USERS MANUAL for HNDC RADLOK-100 and RADLOK-200 containers 3.27 HNDC STD-D-03-008 USERS MANUAL for HNDC RADLOK-55 container 3.28 DHEC-HIC-PL-005 South Carolina Certificate of Compliance for HNDC

. RADLOK-100 container l

3.29 DHEC-HIC-PL-007 South Carolina Certificate of Compliance for HNDC l

RADLOK-100 container 3.30 DHEC-HIC-PL-004 South Carolina Certificate of Compliance for HNDC RADLOK-55 container l

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t i AD-QA-311 Revision 4 Page 7 of 54

'4.0 RESPONSIBILITIES 4.1 Senior Project Engineer - Radwaste f.

, 4.1.1 Ensure procedures are adequate to provide for proper i

solidification and dewatering.

4.1.2 Ensure test dat$ is available to justify appitcable solidification and dewatering functions.

3 4.1.3 Evaluate services provided by various vendors to ensure that contracted solidification and dewatering operations are performed in the most efficient and economical method as required by applicable regulatory agencies.

4.2 Shift Supervision shall assume the responsibility of the Radwasta Supervisor in his/her absense.

4.3 Radwaste Supervisor responsibiltt,tes:

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

4.3.2 Ensure the appropriate waste solidification and dewatering records are generated.

4.3.3 Interface with station support groups to ensure proper implementation of process controls programs.

4.3.4 Interface with contractor personnel involved in solid waste processing activities of Solidification and Dewatering.

a. Ensure that test data is ava.11able to justify specific functions.

i

b. Applicable vendor procedures may be used if approved by PORC.

4.3.5 Ensures Solidification and Dewatering operations are carried out in an ALARA manner.

4.3.6 Interface with H. P. Radwaste Specialist on liner and cask selection for solid waste shipping activities.

4.3.7 Ensures proper marking of containers prior to filling.

4.3.8 Maintains a log of Batch processes for test Solidification requirements.

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_ AD-QA-311 Revision 4 ;

Page 8 of 54 '

4.3.9 Ensure Radwaste solidification personnel are adequately trained per NTI-QA-3020.

4.3.10 Classification of waste to be processed.

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

4.3.12 Assure prop'er selection of High Integrity Containers for the waste stream being processed and packaged.

4.4 Chemistry Group responsibilities:

4.4.1_ Sampling as required.

4.4.2 Performing required analysis in accordance with approved '

chemistry procedures. -

4.4.3 Performing test solidification if required.

4.4.4 Providing the Isotopic mii and concentration of isotopes detected in the material sampled for solidification.

4.4.5 Providing mix ratios to the Radwaste Supervisor if analysis results indicate the waste type is out of the normal envelope for Solidification or an abnormal waste type is encountered.

( 4.4.6 Completing Chemistry portion of the Solidification Record Sheet. (Attachment A) and Dewatering Record Sheet.

(Attachment B).

4.4.7 Ensures personnel are adequately trained per NTI-QA-3081A.

4.4.8 Provide sampling and analysis support as necessary for the use of High Integrity Containers.

4.5 Health Physics Radwaste Specialist responsibilities:

4.5.1 Provide the Radwaste Supervisor with the type and specification of' the liner to be used for solidification or dewatering.

4.5.2 Determining the type and specification of Casks which may be required.

4.5.3 Completing applicable portions of the Solidification or Dewatering Record Sheet.

o AD-QA-311 Revision 4 Page 9 of 54 4.5.4 Retention of the Solidification and Dewatering Record Sheet.

4.5.5 Storage of packaged solidified and dewatered material.

4.5.6 For determining curie content of solidified and dewatered material. .

4.5.7 Final disposition of solidified and dewatered material.

4.5.8 Ensures SSES is a, registered user of applicable High Integrity containers.

4.5.9 Ensures Radwaste Worker training has been conducted per-AD-QA-765.

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

4.5.11 Assure spicific approv.al is requested and obtained for the use of High Integrity Containers as required by applicable '

regulatory agencies. .

4.6 Quality Control is' responsible for:

4.6.1 Ensuring process controls are adhered to 4.6.2 Review of Solidification and Dewatering record sheet.

4.6.3 Inspection of Liners and High Integrity Containers as required by appl.icable procedures.

4.6.4 Checking containers for free standing water through applicable procedural methods.

4.6.5 Verification of product acceptability when containers are checked through applicable procedural methods.

4.6.6 Receipt inspection of cement and additives including vendor supplied material. .

4.7 I&C Supervisor Ensure that periodic calibrations and inspections are performed as required.

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. AD-QA-311 Revision 4 Page 10 of 54 4.8 Auxiliary Systems Operator is responsible for:

4.8.1 Operating the solidification and dewatering equipment in accordance with approved operating procedures as directed by the Radwaste Supervisor.

4.8.2 Completing applicable portions of the Solidification and Dewatering Record Sheet.

4.9 Vendors providing Solidification and/or Dewatering services.

4.9.1 Vendors providing solidification and/or dewatering service .

shall have in place 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 Vendors shall provide raining documentation to demonstrate that the personnel being crov!ced, to conduct the applicable service, are infact trained and knowledgable in the applicable functions. _

l 4.9.3 Vendors shall provide procedure that are or can be placed into the SSES procedure format for the functions being provided.

4.9.4 Vendors shall have an acceptable Quality Assurance Program that covers the services being provided. The vendor shall

! work within the SSES Quality Assurance Program when applicable. .

4.9.5 Vendors shall complete applicable sections of Attachments A,B i and C as required for each line processed.

4.10 TECHNICAL GROUP SUPERVISOR Assure all testing that may be required to support solidification and dewataring is complete and satisfactory.

5.O.0EFINITIONS 5.1 Batch - The total volume of waste contained in a waste mixing tank, spent resin tank concentrates tank or phase separator that has been sampled for solidification.

4

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AD-QA-311 Revision 4 page 11 of 54 2 5.2 Salidification - 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 water content of less than

.55 by volume. -

I 5.3 Waste Type - The specific content of the waste to be solidified and may be Evaporator Concentrates, Filter Domineralizer Media, Dewatered Filter Sludges, Dewatered Bead resins or a combination of each.

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

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 amounts of waste, cement and additive required.

for satisfactory solidification.

5.7 Test Solidification - The mixing of waste and solidification agents in the labratory to support selection of mixing ratios.

5.8- Dewatered - The removal of water from solid materill to a point where less than 1% or'O.5% by volume remains as applicable to containers used and burial site limits.

5.9 Liner - The physical container in which the solidification product is

. deposited.

5.10 High Integrity Conta_iner - An approved container for burial that has an expected 1tfe of 300 years.

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 specificatien as stated in 49 CFR 173.403 (N).

1

. AD-QA-311 Revision 4 Page 12 of 54 4

6.0 PROCEDURES 6.1 Waste Types - The following waste types may be solidified individually or in combinations as defined by specific chemistry procedures. '

6.1.1 Evaporator Concentrates

a. Normally Evaporator Concentrates will be in the range of 5-25 weight % sodium sulfate waste.

b. Concentrates are the product o'f Condensate Domineralizer Regeneration OR

c. From processing of Chemical Waste Tank which may have low concentrations of the following:

(1) Tri Sodium Phophate i (2) Sodium sulfa,te (3) Minute amounts of other chemicals used for chemistry analysis ,

(4) Decontamination Solutions (not including Phosphoric Acid)

(5) Phosphoric Acid i

6.1.2 Filter /Demineralizer Media l a. Filter /Demineralizer media will consist of one or more of the following:

l (1) Diatomaceous Earth (2) Powdered Resin (3) Carbon Materials j (4) Various solids, airt and corrosion products in l

taall concentrations

b. Filter /Demineralizer media may be dried to approximately 50 weight % moisture by air drying after removal of gross water volumes by draining.

e

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AD-QA-311 Revision 4 Page 13'of 54

c. Filter /Demineralizer media is discharged to the waste mixing tanks at the end of the filter run on a batch basis resulting in a minimum addition of 150 gal to the Waste Mixing Tank.

d. Filter /Demineralizer media may also be pumped from the Waste Mixing Tank to the appropriate container and dewatered/ solidified. 6.1.3 Dewatered Filter Sludges for Solidification and Dewatering

a. RWCU Filter sludges are dewatered in the LRW Filter /Demineralizer from the RWCU Phase Separator where they are collected and allowed to decay.

(1) RWCU Phase Separator sludges are dewatered in volumes of approximately 20 cubic feet resulting in approximately 150 gallons of dewatered waste to the

Waste Mixing Tanks. .

i.

! (2) It is estimated that 7 to 10 Filter /Demineralizer

! batches will be required to process the RWCU Phase Separator sludge.

1

b. Fuel Pool Filter sludges and condensate domineralizer i slucges are dewatered in the LRW Filter /Demineralizer from the Waste Sludge Phase Separator where they are i collected.

I i (1) Waste Sludge Phase Separator sludges are dewatered in batches of approximately 20 cubic feet per batch resulting in approximately 150 gallons per batch of dewatered waste to tha Waste Mixing Tank.

(2) It is estimated that 10-14 Filter /Demineralizer batches will be required to process the Waste Sludge Phase Separator.

c. Filter sludges may also be pumped directly from the appropriate phase separator to appropriate, containers and dewatered/ solidified.

. 6.1.4 Dewatered Bead Resin for Solidification

a. Bead Resins from the Condensate Domineralizers and the Liquid Radwaste Domineralizer are collected in the Spent Resin Tank.

I

b. Spent Resin Tank contents are Dewatered in the LRW Filter /Demineralizer.

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. AD-QA-311 Revision 4 Page 14 of 54

c. Spent Resin Tank is cewatered in batches of approximately 20 cubic feet per batch. Resulting in approximatley 150 gallons per batch of resin addition to the Waste Mixing Tank,

d. It is estimated that approximately 21 batches will be required to process the Spent Resin Tank assuming that it contains resin from 1 Condensate Demineralizer and 1 LRW Domineralizer.

e. Spent Resin may.also be transfered directly to appropriate liners and dewatered for solidification.

6.1.5 Bead Resin For Dewatering

a. Bead resins from Condensate Demineralizers and the Liquid Radwaste Demineralizer are collected in the Spent Resin Tank.

b. Spent Resin Tank contents may also be pumped directly to appropriate containers and dewatered.

6.1.6 Cartrige Filters

a. CartrigeFiltersmaybedisposedofbyemplacementina cement matrix in steel drums / liners.

b. Cartrige Filters may be disposed of by placement in a high integrity container (HIC).

6.1.7 011y Waste ,

a. Oily Waste may be solidified on a routine basis to a l maximum of 12% oil as a contaminate. To other waste forms provided the following are adhered to:

(1) An emulsification agent is added at the required concentrations.

(2) The Liner affecte'd is NOT SHIPPED T0 the Barnwell, S.C. Disposal Facility,

b. Oily Waste may be solidified without the use of emulsifier at concentrations less than 3% oil by volume.

c. Oily Waste less than UE'by volume of unintentional oil may be shipped to the Barnwell Disposal Facility.

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AD-QA-311 Revision 4 Page 15 of 54

d. Oily Waste at concentrations 1.25 to 40% may be solidified in cement provided :he following are adhered to:

p. (1) An emulsification agent is added at the required concentrations.

~(2) The Liner used for oil solfdification is not shipped to the Barnwell disposal facility,

e. For d above the non-oil portion of the waste must be water or other approved aqueous wastes. ,

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 Solidification and Dewatering Product Control 6.2.1 Sampling

, a. Samples shall be obtained, and analyzed, for each batch of waste if possible.

b. Deviations from the sampling requirement shall be approved by the Chemistry Supervisor,

c. The tank to be sampled shall be recirculated for a minimum of 1/2 hour prior to sampling.

t

d. The Chemistry Group shall obtain the required samples l

after the specified recirculation time is complete.

j .

e. Material to be solidified may also be processed by

' sobile solidification equipment.

f. For the purpose of liner selection, if a sample point of 1

' the Batch tank is not available, a dose rate may'be taken on the bottom of the tank with recirculation shut down.to estimate the curie concentration. ;

. 6.2.2 Waste Preconditioning

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

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

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. AD-QA-311 Revision 4 Pag <a 16 of 54

c. Waste preconditioning is required when any of the following is not met.

(1) A high or low pH condition, out of the acceptable band of 4 to 11, exists in the Batch.

. (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' evevelope for solidification.

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

Group.

e. Up6n completion of Waste Preconditioning Chemistry Group will obtain addit _fonal samples as required to determine mixing ratios. ,

6.2.3 Determination of Mixing _Rattos

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

b. Deviation from the recommended mixing ratios shall be approved by the Chemistry Supervisor.

c. ChemistryGroupdeterminesthewastetypeasdetermined by checking:

(1) Density of the liquid l (2) Specific density of Sodium Sulfate l (3) Volumetric content of settled solids (4) Type of solids contained in the waste,

d. Chemistry Group shall perform test solidification of waste as required in section 6.2.4. <

e. Chemistry Group determines mixing ratios to ensure l

proper solidification.

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

(Form AD-QA-311-1) :

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AD-QA-311 Revision 4 Page 17 of 54 I

g. Chemistry Group shall provide the projected total curie concentration to the Health Physics Specialist Radwaste.

\

h. Chemistry Group shall provide variation of the mixing ratios if the projected liner dose rates will exceed the required maximum ~ levels.

6.2.4 Test Solidification

a. 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 analysis fall outside the normal envelope established indicating a change in the ,

, waste type.

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

(4) When requested by the Chemistry Supervisor or '

Radwaste Supervisor, t

i b. Upon failure of a test solidification additional samples will be obtained and testing will continue until a successful test solidification has been completed with revised mixing ratios as determined by Chemistry.

c. 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.

d. Quality Control shall verify test solidification I acceptability.

6.2.5 Curing Time

a. A minimum of 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months shall be allowed for curing prior 4

. to capping or transporting the container, ,

b. The liner may be moved during the first hour after.

solidification but must remain undisturbed for the remaining 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months .

. _ _ . - , - . _ _ , . . , _ _ _ _ _ _ . . _ - , .______.-_.__,.,______,,,____,_.,,m.- -

. A0-QA-311

< Revision 4 Page 18 of 54 E

c. Deviations from the minimum required curing time shall be approved by the Radwaste Supervisor and justifications documented in the remarks section of Solidification Data Sheet. (Form AD-QA-311-1) 6.2.6 Solidification Product Quality

a. Solidification product. quality is assured by use of the

predetermined mixing ratios of waste, cement and additive.

b. Mixing ratios are based on labratory testing non-radioactive waste materials.

. c. Mixing ratios are re-enforced by the fo11' owing:

(1) Test solidifications performed periodically as stated in 6.2. 4.

(2) Visually and physically checking at least every fifth (5th) container of the same waste type.

d. Container checks shall consist of:

-(1) A visual check of the solidified product for water on the surfact of the product.

t l

(2) Physically poking the surface of the solidified product with a ridgfd unyielding device prior to capping (Nominal penetration is acceptable).

e. Quality Control shall verify acceptability of the l

solidified product when containers are checked.

f. Deviation from the container checking requirement shall be approved by the Radwaste Supervisor.

6.2.7 Handling of Unacceptable Solidified Waste Containers.

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

(1) The free standing water will be removed or

~

(2) Extra cement / additive Will be added to solidify the free water. ,

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AD-QA-311 Revision 4 Page 19 of 54

b. If portions or all of the product did not solidify:

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

~

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

d. Quality Control shall verify acceptability of the solidified product.

(1) Less than 0.M free standing water.

(2) The solidified product appears to be able to hold its, shape if it were removed from the liner. .

e. If the product solidifies prematurely prior to complete addition of the required amount of cement and additive as calculated on the solidification calculation sheet for the specific procedure used. At a minimum the following are required.

(1) Chemistry Group shall perform a test solidification l at the actual ratio of cement and waste in the

' liner, provided Chemistry Group has sufficient sample volume remaining to complete this item.

l *

(2) Quality Control shall check the product for acceptability in accordance with 6.2.6.d of this procedure.

(3) T'e h liner may be shipped provided the subsequent test solidification and/or product quality checks are acceptable to Quality Control and concurrence of the Radwaste Supervisor obtained.

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

1

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. AD-QA-311 Revision 4 4 ,

Page 20 of 54 i

f. If the product is a class which requires stability as i

defined in 10CFR Part 61 and does not solidify properly

in accordance with the specific operating procedure, the

following are required.

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

(a) Radwaste Supervisor (b) Health Physics Specialist - Radwaste t

4 (c) Solidification vendor - Operations

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(d) Solidification vendor - Engineering (2) Burial sites shall be contacted and requirements for receipt of the Ifner in question shall be defined. -

(3) Alternative packaging / processing shall be

evaluated.

(4) Recommendations for final disposition shall be made

, to the Senior Project Engineer - Radwaste.

(5) Racords shall be kept and documentation supportive

' of the final disposition attached-to the liner j document package.

(6) The liner may be shipped after Q.C. review of

! documentation is complete and burial site concurrence is received in letter form.

6.2.8 Waste Container Space Utilization 1

a. Waste volume shall.be maximized within the guidelines of the specific operating procedures to minimize potential void space at the top of the waste container after

' solidifcation or dewatering is complete.

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

c. Attachment C shall be used to track the waste volumes achieved in each individual liner; this form ~shall be completed by vendor personnel for each liner processed.

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AD-QA-311 Revision 4 Page 21 of 54 l

6.2.9 Capping of Solidified Waste Containers

a. At a minimum the requirements of 6.2.5 af 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:

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

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

c. If the container exceeds the limits for Low Specific Activity and contain water and/or organic substances which could radiolytically generate combustible gasus, 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.

(1) The hydrogen generated raust 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 $5% by volume in those portions of the package which could have hydrogen greater than 5%.

6.3 Solidification Agent Control 6.3.1 Portland Type I/ Type II Cement

a. Portland Cement - ASTM C-lii0 Type I shall be used for ths solidification process,

b. Portland Cement - ASTM C-150 Type II shall be used for '

the designed in hcuse solidification of Class A waste

. only,

c. Certification of the type of cement received shall be provided by the vendor and signed by a responsible representative of that vendor.

j d. Quality Control shall verify receipt of the proper

' cement upon delivery.

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. AD-QA-311 Revision 4 Page 22 of 54 6.3.2 Sodium Silicate

a. Solidum Silicate from the PQ Corporation Type N, or equivalent shall meet the following specifications:

(1) Weight Ratio S102/Na20 3.20 (2) Percent Na20 8.90 (3) Percent SiO2 28.70

(~4) Degrees Baume 41.00 (5) Density, lb/ gal 11.60 (6) Viscosity 180.00

b. Certification of the sodium silicate received shall be provided by the vendor and signed by a responsible representative of that vendor.

~

c. Quality Control shall verify receipt of the proper sodium silicate upon delivery.

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

. acceptable solidification.

6.3.4 VENDOR SUPPLIED SOLIDIFICATION AGENT. Documented Certification is not required for materials received in bags provided material verification can be obtained as follows:

a. Cement is acceptable provided the bag containing the cement indicates that the cement is Portland Type !.

~

b. Sodium $111cate is acceptable provided the bag containing the additive indicates Anhydrous Sodium Metasilicate and is a product of PQ Corporation.

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

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

6.4 Equipment Calibrations shall be in accordance with AD-QA-605 Calibration of Installed Plant Instruesntation.

4 u_

I AD-QA-311 !

Revision 4 Page 23 of 54 6.5 Solidification Record Sheet

'6.5.1 A Solidification Record Sheet (Form A0-QA-311-1) shall be completed for each liner filled with solidification products.

6.5.2

^

Guidelines ~ for completing 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.

- Part III, Container selection shall be completed by the

- HP Radwaste Specialist or his designee.

Part IV, System Preparation and Processing shall be' completed by the Auxiliary System Operator. Part IIIa shall be used with vendor supplied equipment and is completed by vendor personnel and the Radweste Supervisor.

Part V, Solidified Liner Data shall be completed by the i HP Technician, HP Radwaste Specialist and the Radwaste Supervisor.

Quality Control shall provide verification as required in the 6.5.3 Solidification Record Sheet.

j 6.6 Solidification Processing 6.6.1 Solidification processing shall be conducted by qualified SSES or vendor personnel.

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

6.6.3 Quality Control personnel shall verify preser system variable '

settings and material additions to the solidification

! container. ,

. AD-QA-311 Revision 4 Page 24 of 54 i 6.7 Radioa: tive Waste Dewatering 6.7.1 Dewatering of Radioactive Waste shall be performed by qualified SSES or vendor personnel.

6.7.2 Dewatering of Radioactive Waste shall be performed in accordance with approved operating procedures. 4 6.7.3 Dewatering procedures shall be based on documented test data ,

that has demonstrated the ability to achieve drainable water. i limits as specified by applicable regulatory agencies.

6.7.4 A Dewatering Record Sheet (Attachment 8, Form AD-QA-311-2)

shall be completed for each container filled with dewatered resins. Guides for completing the Dewatering Record Sheet '

are attached to each part of the form. Parts of the form .

shall be completed by the following responsible individuals ;

or goups,

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

b. Part II Sampling and pre dewatering analysis shall be 1

completed by the Chemistry Group

c. Part III container selection shall be completed by the HP Radwaste Specialist and Radwaste Supervisor.

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

e. Part V Dewatered container data shall be completed by the HP technicians, and HP Radwaste Specialist as applicable,

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

6.7.5 The Health Physics Specialist Radwaste shall assure that SSES is a registered user of High Integrity Containers (HIC) used l at SSES for the purpose of Radwaste disposal prior to the use of a specific type HIC.

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AD-QA-311 Revision 4 Page 25 of 54

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6.8 Changes to the Solid Waste Process Control Program.

6.8.1 Any changes to the Solid Waste Process Control Program shall be provided in the sentannual Radioactive Effluent Release l Report filed with the NRC.

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

6.9 Container Inspections !

6.9.1 Quality Control shall inspect the containers to be used for solidification and devatoring. [

a. This inspection shall assure and document that the conditions of the Certificate of Compliance for High -

Integrity Containers have been met.

b. This inspection shall assure that prior to use, the i i containers to be used for solidification or dewatering l are intact and their internals are free of any visual damage that would prevent them from performing their intended function, l 6.10 Storage of High Integrity Containers 6.10.1 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 the date of ,

manufacture, ,

I 6.10.2 High Integrity Containers stored away from any sources of

ultraviolet radiation must be filled within two years of the manufacture date. l l

! 6.10.3 Once filled a High Integrity Container may be stored in an l 1 approved storage facility for up to (5) five years prior to burial.

Short exposures to sunlight, such as occurring during 6.10.4 l shipment and on site transfer need not be counted when

< determining total ultraviolet exposure.

6.11 Uses of High Integrity Containers J

i 6.11.1 High Integrity Containers may be used to pa:kage the following waste materials for burial at the Barnwell South :

Carolina low level waste burial site.

1 ;

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<-w*- y-c---r,-- p-,. *,=wmww-,c-w-o-----,wg&w ,,-.w,-we,-prew.--y-p,

AD-QA-311 Revision 4 Page 26 of 54

a. Dewatered bead ion exchange resin >

b. Dewatered powdered ion exchange resin

c. Activated carbon, powdered carbon, diatamaceous earth and other granular or fibrous filter media

d. Cartridge filter elements

e. Miscel,laneous components

f. Filter Sludge

g. Sand blasting grit and crud

h. Stabilized incinerator ash

1. Other dewatered and dry material provided concurrence is received from the container vendor 6.11.2 High Integrity containers are approved for use provided the

- following physical and chemical limitations of the waste are met.

a. Bulk density : 0.7 to 2.5 g/cc

b. pH : 4 to 11

~

c. Loading temperature : <150*F

d. Radlok 100 loaded weight: 10500 lb

e. Radlok 200 loaded weight: 5500 lb

f. Radiok '55 loaded weight : 950 lb

g. CNSI 14-195 loaded weight : 12200 lb

h. CNSI 14-170 loaded weight : 10800 lb ,

1. CNSI 8-120 loaded weight : 7500 lb

> j CNSI 6-80 loaded weight : 5000 lb k CNSI 24-INCH FRP loaded l

weight: 1600 lb l

AD-QA-311 Revision 4 Page 27 of 54

1. 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 utt/ce.

6.11.3 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 1 yC1lcc.

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

a. Aqua Regia

b. Bromine

c. Chronic / Sulfuric Acid

d. FumIngSulfuricAcid

e. Nitric Acid >50%

f. Organic peroxides

g. Phenol-concentrated

h. Acetone

1. Butane .

J. Carbon Otsulphide

k. Chloroform

1. Ethyl Ether

m. Ethylene Dichloride

n. Methylene Chloride -

o. Methyl Ethyl Ketone

p. Propane

q. Pentane i

__ , , _ , , _ . , _ . . , , , _ , . _ _ _ . ...~.-,,_,,_.s_-_,_ . . - . . _ - - , . . , _ _ _ , . - - - - . _ , _ _ _ _ _ _ _ . _ _ _ _ , . . . , _ _ _ _ . _ , _ _ . _ _-- __

A0-QA-311 Revision 4 page 28 of 54 6.12 Closure of High Integrity Containers 6.12.1 Closure of High Integrity Containers shall be completed in accordance with approved procedures.

6.12.2 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 may be opened, vented, and then closed and shipped within (10) days.

6.12.3 If the container exceeds the limits for Low Specific Activity and contains water aqd/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 dilutent to assure that oxygen is limited to <5%

by volume in those portions of the package which couTd have hydrogen greater than 5%.

7.0 RECORDS 7.1 Th's Solidification Record Sheet or Dewatering Record Sheet and the attached Isotopic Analysis shall be forwarded to the HP Radwaste Specialist for retention until such time as the Liner identified on the Record Sheet is shipped for final disposition.

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

6 m.. ,.-. . ~ , _ .. - . -- _ ,m._-.f., . _ _ , _ , - - ,,,-,-,_.,.,-__---,.___-._,---e--.-

Attachment A AD-QA-311 Revision 4 Page 29 of 54 SOLIDIFICATION RECORD SHEET Part I Cover Sheet

a. Step 1 - Enter PP&L Liner identification number. .

b. Step 2 - Enter waste type to be processed,

c. Step 3 - Enter process number for this waste type from the Radwaste Supervisor's log book; this is the next sequential number for this waste type.

d. Step 4 - Enter the batch number associated with this process; this is obtained from the Radwaste Supervisor's log book for this waste type,

e. Step 5 - Identify if a test solidification is required based on the information contained in the Radwaste Supervisor's log book for this waste type.

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

FORM AD-QA-311-1, Rev. 4, Page 1 of 16

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Attachment A AD-QA-311 Revision 4 Page 30 of 54 Solidification Record Sheet Part II Sampling and Pre-Solidification Analysis Instructions ,

a. Step 1 - Identify which mixing tank A or B or other tank that is to be processed by a check mark, or identify. '

b. Step 2 - Check that the pH of the sample taken from the tank to be processed is within a range acceptable for solidification.

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

d. Step 4 - Enter the density of the sample taken from the tank. Be sure to use the density of the whole sample '

not just of the liquid phase.

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

, indicating the percentage of oil,

f. Step 6 - Check that a copy of the radionuclide analysis is attached.

g. Step 7 - Based on the isotopic analysis attached enter the total curie concentration.

h. Step 8 - Determine final product density.

1. Step 9 Identify here the type of cer.ient used (i .e. ,

Type I)

j. Step 10a - For the process feed pump (Op-304) provide

! the pump flow rate to be used for the solidification process. If a Vendor Supplied system is provided enter waste volume.

FORM AD-QA-311-1, Rev. 4, Page 2 of 16 ,

I

- - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . . . ~ _ _ _ _ _ _ _ _ _ . _ . . _ . . . _ _ _ _ . - . _ _ _ _ _ _ _ .

_ . . . _ . ~ .

Attachment A AD-QA-311 Revision 4

, Page 31 of 54 Part II cont'd Instructions

~

k. Step 10b For the cement feed system (05-305) provide the cement feed rate to be used for the solidification process. If vendor supplied System is provided, enter Cement Volume in 1b/ft'.

1. Step-10c - For the liquid sodium silicate feed pump (OP-309) provide the pump feed rate to be used in the solidification process. If Sodium Silicate or other-agent is used with vendor provided systems, enter volume in 1b/ft 8or liters / gallon.

m. Step 11 Enter the curing time required based on the most recent test solidification of that waste type. At

' a minimum 30 hrs, cure time will be^ required. .

n. Step 12 - Chemistry Supervision shall sign with the date and time signed that the waste in the identified tank has been sampled and analyzed in accordance with approved procedures and is acceptable for solidification at the indicated mixing ratios.

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FORM AD-QA-311-1, Rev. 4, Page 3 of 16 I

Attachment A AD-QA-311

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Revision 4 Page 32 of 54 Solidification Record Sheet Part III Container Selection Instructions

a. Step 1 - Based on the isotopic analysis of the 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 the projected curie concentration of the -

solidified waste.

c. - Step 3 Enter the waste classification based en the Isotopic analysis per 10CFR part 61.

d. Step 4 - Identify the type of liner 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 the. PP&L liner identification number. <

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

k FORM AD-QA-311-1, Rev. 4, Page 4 of 16

--, - --n,.r-,.-,-,,~-,m-,,,,,m -,--,~n-,,-- .-...,.---,.,,--w,,--,- ,, - ------,.,--n- , --,-n, r-n-,,-- c -----.n

Attachment A AD-QA-311 Revision 4 Page 33 of 54 ,

Solidification Record Sheet-Part IV System Preparation and Processing Instructions

a. Step 1 - Enter the serial number of the liner to be used.

b. Step 2 - Enter the PF&L identification number on the liner. (This must be the same as the number in Part II step 5)

c. Step 3 - Verify that the liner is properly loaded on the correct transfer cart.

d. Step 4 - After the ca.t is moved to the fill position verify that the liner is properly positioned under the fill port. ,,

e. Step 5 - Check that the mating surface between the fill flange and the liner is proper and will not leak.

f. Step 6a - Enter the process speed control setting for the appropriate waste feed pump (OP-304 A or 8). (As determined by the Radwaste Supervisor)

g. Step 6b - Enter the process speed control setting for the cement feed system, (05-305). (As determined by the Radwaste Supervisor) i

h. Step 6c - Enter the process speed control setting for the sodium silicate pump, (OP-309). (As determined by j

the Radwaste Supervisor) f 1. Step 6d - Verify that the Process Mix Pump (OP-307) process speed control setting is on 10.

j. Step 7 - Shift Supervisor /RW Supervisor shall sign, with date and time, that the process control speed settings are proper and consistent with Section 6.5.2.

Step 8 - Verify that sufficient cement is available for

~

k.

solidification of the tank contents, i 1. Step 9 - Verify that sufficient ifquid sodium silicate is available for solidification of the tank contents.

1

{ FORM AD-QA-311-1, Rev. 4, Page 5 of 16 i

. . - . - . _ - - - _ . _,.. _ .--_, .-, _._ - ._ ., _ - - . _ _ _ _ ,_ - ., _ __ _ _ ,_,. _ .,_ ,_l_._..__

Attachment A AD-QA-311 Revision 4 Page 34 of 54 Part IV cont'd Instructions

m. Step 10 - Enter the quanitity of waste in the Waste Mixing Tank to be processed.

n. Step 11 - Shift Supervision shall verify and sign, with

+ date and time, that all requirements of the Process Control Program have been met and that the authorization to proceed with the solidification process is granted.

o. Step 12 - Enter the time and solidification process is initiated.

p. Step 13 - Enter the time the solidification process is stopped.

q. Step 14 - Enter eement level in silo at completion of solidification process.

r. Step l'5 - Enter liquid solium silicate tank level at completion of solidification process.

s. Step 16 - Enter final Waste Mixing Tank level,

t. Step 17 - Enter estimated weight of the liner with the solidified material.

u. Step 18 - The.Radwaste Operator shall sign, with date and time, that the process has been completed.

v. Step 19 - QC verification o 'f fifth (5th) filled liner check. ,

w. Step 20 - Enter the curing time between Steps 13 and 19.

x. Step 21 - Verify that the liner has been moved to the

- washdown area.

y. Step 22 - Shift Supervision shall sign, with date and time, that the solidification process has been accomplished according to the requirements of this procedure and that Health Physics has been notified.

b FORM AD-QA-311-1, Rev. 4, Page 6 of 16

Attachment A AD-QA-311

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Revision 4 Page 35 of 54 Solidification Record Sheet Part IVa System Preparation and Processing Instruction (Vendor or alternate system)

a. Step 1 - Enter the serial number of liner to be used.

b. Step 2 - Check that PP&L identification number is stenciled on the liner. (This must be the same as the number in Part-II step 5).

c. Step 3 - Verify that the liner is properly positioned and ALARA consideration has been made for spills and expected dose rates.

d. Step 4 - Shift Supervision authorize start of processing.

e. Step 5 - Enter process parameters in appropriate units.

f. Step 6 - Enter processing start time.

g. Step 7 - Enter processing stop time

h. Step 8 - QC verification for hardness / solidification by manual penetration tests visual observations for water in the liner.

1. Step 9 - The actual curing time prior to capping shall be entered here.

j. Step 10 - Enter the Final solidified waste volume in cubic feet.

I k. Step 11 - Supervisor review and release liner to Health Physics.

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FORM AD-QA-311-1, Rev. 4, Page 7 of 16 i

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Attachment A j' AD-QA-311

- Revision 4 Page 36 of 54 Solidification Record Sheet Part V Filled Liner Data Instructions

a. Stes la - The contact radiation levels on the top and bottom of the liner and at four points, 90* apart, r around the centerline of the liner shall be recorded.

b. Step lb - Enter the level of external contamination on the liner as determined by an analysis of a swipe smear.

c. Step ic - Based on the data entered in 6.5.5.b of this procedure determine whether or not a liner washdown is to be performed. If a washdown is requir'e d signify by entering "yes", if a washdown is not required signify by entering "NR".

' d. Step Id - Enter the level of external contamination on the liner as determined by an analys.is of a swipe smear.

If a second, or subsequent, swipe smear is not required enter "NR".

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

f. Step 2 - Enter the storage location liner is transfered to. Enter "NA" if the liner is not stored prior to shipment.

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

l

h. Step 4 - Enter the transportation shipment number.

1. Step 5 - Enter the name of the burial site the liner is being shipped to Health Physics and QC shall sign, with date and time, that his procedure has been properly followed.

FORM AD-QA-311-1, Rev. 4, Page 8 of 16

Attachment A AD-QA-311 Revision 4 Page 37 of 54 SOLIDIFICATION RECORD SHEET Part I Cover Page

1. LINER Identification No.

2. WASTE TYPE

3. Sequential Liner No. of Waste Type

4. BATCH No. ,

5. Test Solidification required Yes/No

6. Approval for use Shift Supervision /Radwaste Supervisor t

4 FORM AD-QA-311-1, Rev. 4, Page 9 of 16

-- - - - - - - e, -y-,-,, - - , , - ,-w -,w, c,,e ,- , -m--- -,, - . . -g-,,,-.w-iv-,-w ----w --f.,-+-----.,- - - , ,,-.,7---------- .--m-, .-----.+c-, -

-er--

Attachment A AD-QA-311 Revision 4

~ Page 38 of 54 SOLIDIFICATION RECORD SHEET Part II Sampling and Pre Solidification Analysis Waste Mixing Tank Sampled A B 1.

Other Date/ Time

2. Waste Stream pH 4-11 Check

3. Type of Waste *

a. Wet WT. % settled solids

b. WT. % Sodium Sulfate

c. % Water by volume

4. Waste sample density gm/ml

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

a. None

b. Less UE

c. % oil

6. Isotopic Analysis Attached Check

7. Estimated Total Curie Concentration uCi/cc

8. Final product density gm/cc

9. Type of cement to be used

Include no.menclature of type of waste, i.e. bead resin, powdered resin, carbon, oil, diatomaceous earth sodium sulfate or combination, etc, FORM AD-QA-311-1, Rev. 4, Page 10 of 16

Attachment A AD-QA-311

. Revision 4 Page 39 of 54

10. Mixing Ratios SSES INPLANT SYSTEM VENDOR SYSTEM .

j -l Initial Initial I

a. Waste (OP-304) gpm

b. Cement (05-305) lb/ min Cement lbs/ft' of waste

c. Sodium Silicate (OP-309) gpm Sodium Silicate

lb/ft' of waste Other additive liters / gallons

11. Cure time required hours.

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

Chemistry Supervision Date Time

)

FORM AD-QA-311-1, Rev. 4, Page 11 of 16

Attachment A AD-QA-311

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Revision 4 Page 40 of 54 4

PART III CONTAINER SELECTION

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

2. Projected Curie Loading uci/gm

3. Waste Classification

4. Liner type used ,

TYPE

5. Type cask to be used TYPE

6. PP&L Liner Identificiation Number

7. The above specified Liner and crsk have been determined appropriate for the solidified waste based on projected curie loading and dose rates l Radwaste Supervisor Date Time

l. or His Designee i

l 1

l FORM AD-QA-311-1, Rev. 4, Page 12 of 16

Attachment A AD-QA-311 Revision 4 Page 41 of 54 PART IV SYSTEM PREPARATION AND PROCESSING (Use Part IVa if vendor supplied system is used)

1. Liner Serial Number

2. PP&L Liner Identification Number on liner Checx

3. Liner Properly Loaded on Transfer Cart Check

4. Liner Properly Positioned Under Fill Port.

Check

5. Fill Flange Properly Mated To Liner Check

6. Process Speed Control Setting. (obtained form Radwaste Supervisor)'

j

a. Water Feed (OP-304) A B

b. Cement Feed (05-305) A B _

c. Sodium Sili.cate (OP-309) A B f d. Process Mix Pump (OP-307) 10 A 10 B

7. Process speed control settings verified l

t Shift Supervision /RW Supervisor Date Time

QC Verification Date Time ,

8. Sufficient Cement Available Check

> 9. Sufficient Sodium Silicate Check

10. Waste Mixing Tank Level %

FORM AD-QA-311-1, Rev. 4, Page 13 of 16 l

Attachment A AD-QA-311 Revision 4

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Page 42 of 54

11. Authorization to Commence Process Shift Supervision Date Time

12. Time process started Time

13. Time Process Stopped Time

14. Cement Silo Level %

15. Sodium Silicate Tank Level %

16. Waste Mixing Tank Level %

17. Liner Weight

18. Process completed Operator Date Time

19. Liner Check (5th liner) complete (6.2.6.d)

QC Verification

20. . Curing time allowed prior to capping hours

21. Liner Transfered to wash down station Check

22. Supervircry review and Health . Physics notification v Shift Supervision Date Time FORM AD-QA-311-1, Rev. 4, Page 14 of 16

Attacnment A AD-QA-311 Revision 4 Page 43 of 54 Part IVa System Preparation and Processing (Vendor or alternate system).

1. Liner Serial Number

2. PP&L Liner Identification' Number on liner .

Check

3. Liner properly positioned and ALARA consideration made .

Check

4. Authorization to commenca processing Shift Supervision Date Time

5. Process parameters 9

~

Waste in liner _. actual ft8 Cement to be added to liner lbs actual lbs Sodtum Silicate to be added to liner lbs actual lbs Other additive added to liner -

actual lbs/ft'/ gallon l Calcium Hydroxide to be added*to liner lbs Tank from which waste is to be transferred QC Verification Date Time

6. Time processing started

7. Time processing stopped

8. Liner check for complete solidification and visible water or drainable water.

a. Penetration check (6.2.6.d)

QC Verification /Date/ Time

b. Visible water (6.2.6.d)

QC Verification /Date/ Time

' 9. Curing time actual (A minimum of 30 hrs is required.)

10. Final container solidified waste volume ft' FORM AD-QA-311-1, Rev. 4, Page 15 of 16 s e

r ' w- MMF " a M w ce7ywwe-'-twg-+mWM--

-rwa---- pr et wy- - * -

o . .

Attachment A AD-QA-311 Revision 4 Page 44 of 54

11. Supervisory review and Health Physics notification.

Shift Supervision Date Time PART V Filled Liner Data i

1. Filled Liner Radiation Levels

a. Top ar/hr Bottom ar/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 fes/NR

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

e. Liner ready for transfer to storage HP Tecn. Date Time

2. Storage Location: RW / /

Date Time Initials LLWHF Date Time Initials

3. Liner Capped / /

Date Time Inittals

4. Shipment #

S. Solidified waste acceptable for disposal at l burial site 4

HP Radwaste Spec. Date Time Quality Control Review Date Time FORM AD-QA-311-1, Rev. 4, Page 16 of 16

Attachment 8 AD-QA-311 Revision 4 Page 45 of 54 DEWATERING RECORD SHEET Part I Cover Page

a. Step 1 - Enter the liner identification number from Radwaste Supervisor Log Book.

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

Part II Sampling and Pre-Dewatering Analysis

a. Step 1 - Sample the appropriate tank after a recire period of'1/2 hour or 1 tank volume as a minimum.

b. Step 2 - Same as Step 1.

c. Step 3 - Collect a liquid sample from the material to be dewatered to assure the liquid will not be corrosive to a carbon steel liner.

d. Step 4 - Determine the oil content of the material to be dewatered'.

e. Step 5 - Conduct an isotopic analysis of the material to be dewatered.

f. Step 6 - Enter the specific activity.

FORM AD-QA-311-2, Rev. 4, Page 1 of 8

, p. - - - - - . - - - - v-p-nv-mw--w g -. p---w + --- - - ~

-gr.--ew-,-- ---.----m wye----- y- iw-..-r,--- - - m-m- y- ,r-1 m. ---*

Attachment B AD-QA-311 Revision 4 Page 46 of 54 Part III Container Selection

a. Step 1 - Based on the 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 the projected curie concentration on the dewatered waste.

c. Step 3 - Enter waste classification per 10CFR part 61 (i.e., A, B or C).

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

e. Step 5 - Enter the appropriate cask designation to be used for the container if required. -

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

g. Step 7 - The Rac! waste Supervisor or NTs designee shall sign, with d' ate and time, that the cask (s) and container identified above are appropri' ate for the waste to be dewatered.

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FORM AD-QA-311-2, Rev. 4, Page 2 of 8 P

-,---,,o,~.-nv wp-r - - - , ., e- .,w- , - ,,-n.,,, .-n ,--,,w----,--r,n-----,.,n-------r-.,-- - - - , --,an ,--,- .r. - _ . - - . , - ,.n,~.,

Attachment B AD-QA-311 Revision 4

~

Page 47 of 54 Part IV Dewatering Operations Documentation

a. Step 1 - A specific operating procedure for the container will be used to document the appitcable dewatering functions.

b. Step 2 - Enter Final Dewatered Waste volume.

c. Step 3 - Supervision review of dewatering documentation.

Part V Dewatered Container Data

a. Step 1 - Document the container radiological data on a blank survey form and attach the form to the Dewatering Record Sheet.

Use HP-TP-800 to assist in determining the transport groups and curie content of material Lcing dewatered.

b. Step 2 - The storage location sha,11 be assi.gned by the HP Specialist Radwaste. .

l c. Step 3 - Enter date and time liner is capped or sealed.

d. Step 4 - The shipment # and destination shall be designated by the HP Specialist Radwaste.

4 l

FORM AD-QA-311-2, Rev. 4, Page 3 of 8

Attachment B AD-QA-311 Revision 4 Page 48 of 54 i

DEWATERING RECORD SHEET Part I Cover Page

1. Liner Identification Number

2. Waste Identification Shift Supervision /

Radwaste Supervisor I

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FORM AD-QA-311-2, Rev. 4, Page 4 of 8 l

a, Attachm'ent B AD-QA-311

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Revision 4 Page 49 of 54 Part II Sampling and Pre-Dewatering Analysis

, 1. Waste Mixing Tank Sampled A B Check /NA Check /NA

2. Other tank sampled Name

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

4. Oil Content (check one)

None

[ 1ess than UE

5. Isotopic Analysis attached --

Check

6. Specific activity of Dewatered Sample vC1/gm The above tank containing solids has been sampled and found to contain the isotopes and specific activities as indicated on the attached data sheets.

Chemistry Supervisor Date Time

! T l

l f

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FORM AD-QA-311-2, Rev. 4, Page 5 of 8 l

i i G w - - , - -- e,-n,. ,---~,.,mn~m,-e~,,,,wn-----r,-,,s._a,-,,----,-er,r, , , , , , - , ,--vr, ,,--m,v -

,-,w. .v---

.i..

Attachnent B AD-QA-311 Revision 4 Page 50 of 54 Part III Container Selection

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

2. Projected Curie Loading UCi/gm

3. Waste Classification

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 Date Time

/or His Designee l

i i

l FORM AD-QA-311-2, Rev. 4, Page 6 of 8 l .

. . . . -a Attachment B A0-QA-311 Revision 4 Page 51 of 54 Part IV Dewatering Operations Documentation

1. Attach the complete specific sperating procedure check off sheet for the specific dewatering container being used Check i

2. Final Dewatered Waste Volume , Ft*

3. Dewatering check off sheet review and .

(Use specific check sheet for liner being used) transferred to HP Specialist Rad Waste ,

Shift Supervision Date Time Part V Dewatered Container Data -

1. Container Radiation Levels _

a. Top mr/hr i

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

4 mr/hr

b. Smearable Activity dpa/100cm 8

c. Contairer washdown/decon performed '

Yes/No 4

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

(attach radiological survey form)

e. Liner ready for transfer to storage HP Tech Date Time FORM AD-QA-311-2, Rev. 4, Page 7 of 8 ,

w -w ~e---- ~wes-e----, w~m>---mwwm----w. .m---vs- w e, n-ee ,w w vw. .-m-w-ww- --

w -=-+.w.+v-- ww-or--~---e-w

Attachment B AD-QA-311 Revision 4

~

Page 52 of 54 Part V (Cont'd.)

2. Storage location: RW / /

Date Time Initials LL'WHF / /

Date Time Initials

3. Liner capped or sealed / /

. Date Time Initials Shipment #

4.

Destination HP Specialist Radwaste Date Time Date Time Quality Control Review J

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l l FORM AD-QA-311-2, Rev. 4, Page 8 of 8

Attachment C AD-QA-311 Revision 4 Page 53 of 54 SUSQUEHANNA GUARENTEED WASTE VOLUME RECORD

a. Step 1 - Enter the date and PP&L Liner Identification number,

b. Step 2 - Enter the type of waste processed and its source (i.e., Waste Mix tank, Phase Seperator, etc..)

c. Step 3 - Describe the physical appearance of the waste (i.e., color clarity, etc..)

d. Step 4 - Enter liner type used.

e. Step 5 - Enter burial volume associated with this liner.

f. Step 6 - Enter the Q.C. verified waste volume from FORM AD-QA-311-1~or 2.

g. Step 7 - Enter usable liner volume far liner'specified in Step 4.

h. Step 8 - Enter. Guaranteed minimum waste volume in inches

- (measured from top of liner) and cubic feet.

I

i. Step 9 - Enter waste volume attained in inches (measured from top of liner) and cubic feet.

J. Step 10 - Enter the wasta volume difference (i) from the guaranteed volumes as per Steps 8 and 9.

l l k. Step 11 - Remarks - this section is used to explain.all waste :5ortages.

1. Step 12 - The solidification vendor representative signs indicating all the information contained on this document is correct.

s. Step 13 - The Radwaste Supervisor signs indicating agreement with the information contained on this documents.

l ,

l FORM AD-QA-311-3, Rev. O, Page 1 of 2 i

L

Attachment C AD-QA-311

~

Revision 4 Page 54 of 54 SUSQUEHANNA GUARANTEED WASTE VOLUME RECORD

1. Date Liner number

2. Type of wasta Source

3. Physical appearance

4. Liner Type

5. Burial Volume

6. Waste Volume

7. Useable Liner Volume

8. Guaranteed Minimum Waste Volume _

9. Waste Volume Attained inches ft8

10. Waste Volume Difference inches ft8

11. Remarks:

12. Signature Solidification Vendor Representative

13. Signature Radwaste Supervisor SSES FORM AD-QA-311-3, Rev. O, Page 2 of 2

i SECTION 6 REPORTS OF EXCEPIION 10 TIE SSES EFFLUENT MONITORING PROGRAM Based on a review of the Significant Operating Occurence Reports (S00Rs)

.for SSES Unita 1 and 2 for the report period, there were no cases in which effluent monitoririg instrumentation was inoperable and was not restored to operability within the' applicable time period specified in Technical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

M 4

+

l i

I r

I 137

PP&L Pennsylvania Power & Light Company Two North Ninth Street

Allentown, PA 18101

215 / 770 5151 Bruce D. Kenyon Vice President-Nuclear Operations - .

215/770-7502 l

MAR 1 1985

,Dr. Thomas E. Murley.

, Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Pa.rk Avenue King of Prussia, PA 19406 l l

l SUSQU"HANNA STEAM ELECTRIC STATION j SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ER 100450/100508 FILES 890-13/841 Docket Nos. 50-387/NPF-14 PLA-2420 and 50-388/NPF-22

Dear Dr. Murley:

i In accords.nea with 10CFR50.36a(a)(2) and the Susquehanna SES Unit I and 2 Technical Speciffcations, attached is the Semi-Annual Radioactivo Effluent Release Rep rt for SSES Units 1 and 2 covering the period July 1 through December 31, 1984.

Very truly yours, s

4 A B. D. ICenyon Vice President-Nuclear Operations cc: Director Office.of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing )

U.S. Nuclear Regulatory Commission j Washingtc,n, D.C. 20555 l Ms. M. J. Campagnone - USNRC Mr. R. H. Jacobs - USNRC l l

/2 .R x~~

PLA-2420, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1984

Contents

Text

* -ss-ss-as ss-ss as-ss-ss-ss-ns-ss ss ss ss ss :

Reference:

Title:

3.0 REFERENCES

3.0 REFERENCES

Dear Dr. Murley:

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PLA-2420, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1984

Text

* -ss-ss-as ss-ss as-ss-ss-ss-ns-ss ss ss ss ss :

Reference:

Title:

3.0 REFERENCES

3.0 REFERENCES

Dear Dr. Murley:

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