ML18011A117

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Semiannual Radioactive Effluent Release Rept Jan-June 1993.
ML18011A117
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 06/30/1993
From: Barnes H, Robinson W, Bernie White
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A116 List:
References
NUDOCS 9308310126
Download: ML18011A117 (46)
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Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPF-063 SE IRIANNUALRADIOACTIVERSSLIIRNT RELEASE REPORT January 1, 1993 to June 30, 1993 Prepared by:

Prepared by:

Speci list - E&C Reviewed by:

Man r> - E&RC Support Reviewed by:

ager - Environmental & Radiation Control Approved by:

General Manager - Harris Plant 9308310126 930820 PDR tADOCK 05000000 R I PDR

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Table of Contents Page No.

Introduction i Discussion Appendix 1. Supplemental Information Appendix 2. Effluent and Waste Disposal Report

1. Lower Limits of Detection (LLD's) 2/1
2. Effluents Released 2/3
3. Solid Waste Disposal 2/10 Appendix 3. Changes to Process Control Program (PLP) 3/1 Appendix 4. Changes to Offsite Dose Calculation Manual (ODCM) 4/1 Appendix S. Changes to the Environmental Monitoring Program
1. Environmental Monitoring Program S/1
2. Land Use Census S/2 Appendix 6. Additional Technical Specification Responsibilities
1. Inoperability of Liquid Effluent Monitors 6/1
2. Inoperability of Gaseous Effluent Monitors 6/2
3. Unp rotected Outdoor Tanks Exceedin g Limits 6/3 4 ~ Gas Storage Tanks Exceeding Limits 6/4 Appendix 7. Major Modifications to Radwaste System 7/1

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Plant (SHNPP) Operating License No. NPF-63. It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS) .

The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987. This Report covers the period from January 1, 1993 to July 31, 1993. During this period, the plant continued in Cycle 5 operation.

Discussion Appendices 1 and 2:

The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory. Guide 1.21 (Rev. 1) Appendix B format. As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.

Except for continuous noble gas releases, liquid and gaseous average concentrations (pCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.

Continuous noble gas effluent activities were based on hourly average stack monitor readings (in pCi/cc) and stack flow rate estimates based on fan flow rates, and are apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. When specific noble gas nuclides were identified in the stack gas grab samples, their activity was added to the activity based on stack monitor readings. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release. The "Percent of Technical Specification Limit" is calculated using ODCM default methodology and parameters.

A total of 21.94 m~ of solid waste, containing 189.97 Ci of radioactivity, was shipped for burial during this Report period, compared with 44.35 m'nd 76.35 Ci shipped during the previous Report period.

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Discussion (continued)

Appendix 3:

An administrative change to the Process Control Program (PCP) was made during this Report period. The change was to include Westinghouse /

Scientific Ecology Group Process Control Program procedures as part of the PCP.

Appendix 4:

Three changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period. The changes are described as ODCM Change 3/5, ODCM Change 3/6, and ODCM Change 3/7.

Appendix 5:

The 1993 annual Land Use Census was performed during this Report period.

As a result of the census, Table 3.2-2 of the ODCM, which provides the distances to the nearest special locations, i.e. residences, milk animals, gardens, and meat animals, will be revised in the next Report period.

No changes to the Environmental Monitoring Program were made during this Report period. New sampling locations were identified during the Land Use Census and will be included in the next Report period.

To determine whether any of the new special locations yielded calculated doses greater than the locations previously used, the 1993 Land Use Census data was coupled with the SHNPP 1992 meteorology, and dose calculations were performed by the GASPAR program using the GALE source terms provided in Table 3.2-1 of the ODCM. No significant differences in estimated doses occurred as a result of the 1993 changes of the nearest resident, garden, or meat animal.

Appendix 6:

No effluent monitoring instrumentation was inoperable for greater than 30 days during this Report period.

No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this Report period.

Appendix 7:

No major modifications to the Radwaste System were made during this Report period.

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 1: Supplemental Information Regulatory Limits Fission and activation gases (1) Calendar Quarter

a. 5 mrad gamma
b. 10 mrad beta (2) Calendar Year
a. 10 mrad gamma
b. 20 mrad beta B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1) Calendar Quarter
a. 7.5 mrem to any organ (2) Calendar Year
a. 15 mrem to any organ C. Liquid effluents (1) Calendar Quarter
a. 1.5 mrem to total body
b. 5 mrem to any organ (2) Calendar Year
a. 3 mrem to total body
b. 10 mrem to any organ

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 1 (Continued): Supplemental Information

2. Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.

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A. Fission and activation gases (1) 500 mrem/year to total body (2) 3000 mrem/year to the skin B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.

1500 mrem/year to any organ.

C. Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the EC shall be equal to 2.0E-4 pCi/ml. Beginning 01-01-93, SHNPP began using Effluent Concentrations (ECs) instead of MPCs.

3. Average Energy (E)

N/A an SHNPP. SHNPP determines doses and dose rate based on actual releases, not on an average energy value.

4 Measurements and Approximations of Total Radioactivity A. Fission and activation gases Measurements by continuous monitors of activity concentrations times total stack flow, and, analysis by. gamma spectroscopy and liquid scintillation counting for specific radionuclides in representative grab samples.

B. Iodines Continuous charcoal cartridge sampling and analysis by gamma spectroscopy for specific radionuclides times total stack flow.

C. Particulates Continuous particulate sampling and analysis by gamma spectroscopy, alpha counting and radiochemical analysis for specific radionuclides times total stack flow.

D. Liquid Effluents Pre-release representative sampling and analysis by gamma spectroscopy and liquid scintillation counting for specific radionuclides times total release volume.

1/2

l)

Semiannual Radioactive Effluent Release 'Report January 1, 1993 to June 30, 1993

. Appendix 1 (Continued): Supplemental Information Batch Releases Liquid Batch Releases (1) Number of batch releases 4.50 E+01 (2) Total time period for batch releases 3.21 E+04 min (3) Maximum time of a batch release 8.63 E+02 min (4) Average time for a batch release 7.12 E+02 min (5) Minimum Time for a batch release 3.32 E+02 min (6) Average stream flow during periods of release 1.31 E+04 gpm B. Gaseous Batch Releases (1) Number of batch releases 0.00 E+00 (2) Total time period for batch releases 0.00 E+00 min (3) Maximum time of a batch release 0.00 E+00 min (4) Average time for a batch release 0.00 E+00 min (5) Minimum Time for a batch release 0.00 E+00 min Abnormal Releases A. Liquid No abnormal liquid releases were made in this period.

B. Gaseous No abnormal gaseous releases were made in this period.

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2: Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLD)

LLD'S for Gaseous Effluents Nuclide ~Ci cc Gross Alpha 1.80 E-15 H-3 7.97 E-09 Ar-41 3.79 E-08 Kr-85 6.09 E-06 Kr-85m 2. 12 E-08 Kr-87 8.88 E-08 Kr-88 2.32 E-08 Xe-131m 6.21 E-07 Xe-133 6.96 E-08 Xe-133m 4.65 E-07 Xe-135 2.07 E-08 Xe-135m 4.65 E"07 Xe-138 5.94 E-07 I-131 3.22 E-14 I-133 2.73 E-14 I-135 7.97 E-14 Cr-51 1.17 E-13 Mn-54 1.66 E-14 Co-58 1.33 E-14 Fe-59 3.87 E-14 Co-60 1.86 E-14 Zn-65 7.55 E-14 Sr-89 3.00 E-15 Sr-90 1.00 E-15 Mo-99 1.48 E-13 Cs-134 1.01 E-14 Cs-137 2. 63- E-14 Ba-140 4. 13 E-14 La-140 2.41 E-14 Ce-141 1.26 E" 14 Ce-144 3.89 E-14

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)

2. LLD's for Liquid Effluents Nuclide ~Ci ml Nuclide Ci ml Gross Alpha 4.10 E-08 Sb-122 5.06 E-08 H- 3 2.55 E-06 Sb-124 1.68 E-08 Be- 7 2.24 E-07 Sb-125 9.36 E-08 Na-24 3.15 E-08 I-131 2.67 E-08 Cr-51 2.61 E-07 I-132 3.31 E-08 Mn-54 2.01 E-08 I-133 1.33 E-07 Fe-55 2.00 E-07 1-135 1.25 E-07 Co-57 1.73 E-08 Te-132 2.31 E-08 Co-58 1.98 E-08 Xe-131m 9.21 E-07 Fe-59 4.64 E-08 Xe-133 5.36 E-08 Co-60 3.89 E-08 Xe-133m 1.91 E-07 Ni-63 2.00 E-07 Xe-135 2.59 E-08 Zn-65 8.67 E-08 Cs-134 3.08 E-08 Sr-89 1.50 E-08 Cs-137 3.38 E-08 Sr-90 5.00 E-09 Cs-138 5.62 E-07 Sr-92 4.52 E-08 Ba-140 9.60 E-08 Y-93 1.34 E-07 La-140 3.02 E-08 Nb-95 3.26 E-08 Ce-141 4.84 E-08 Zr-95 3.36 E-08 Ce-143 6.07 E-08 Mo-99 2.04 E-07 Ce-144 2.04 E-07 Tc-99m 2.46 E-08 Pr-144 1.17 E-06 Ru-103 2.51 E-08 Hf-181 2.62 E-08 Ag-110m 5.93 E-08 2/2

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A  : GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter Quarter Est.Total 1 2 Error

1. Fission & Activation Gases A. Total Release Ci 8.49 E+01 1.34 E+02 4.50 E+01 B. Average Release Rate for Period pCi/sec 1. 09 E+01 1. 71 E+01 C. Percent of Technical Specification Limit 4 ~ 60 E-01 5.02 E-01
2. Iodines (I-131, I-133, I-135)

A. Total Iodines Ci 8.93 E-06 8.32 E-07 2.00 E+01 B. Average Release Rate for Period pCi/sec 1.15 E-06 1.06 E-07 C. Percent of Technical Specification Limit See Footnote Below

3. Particulates A. Particulates with T1/2> 8 days Ci 2.58 E-05 1.04 E-05 2.00 E+01 B. Average Release Rate for Period pCi/sec 3.32 E-06 1.32 E-06 C. Percent of Technical Specification Limit 8.13 E-02 3.60 E-02 D. Gross Alpha Radioactivity Ci LLD LLD
4. Tritium A. Total Release Ci 3.93 E+00 1.89 E+00 3.00 E+01 B. Average Release Rate for Period pci/sec 5.06 E-01 2.40 E-01 C. Percent of Technical Specification Limit See Footnote Below The Percent of Technical Specification limit applies to Io'dines, Tritium, and Particulates combined, and is calculated using ODCM default methodology and parameters. The value for Iodines and Tritium is included in the Particulates summation.

2/3

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure'2 : Effluents Released Table 1B : GASEOUS EFFLUENTS - ELEVATED RELEASES All releases at Shearon Harris are made as ground releases.

i9 1

Semiannual Radioactive Bffluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C GASEOUS EFFLUBNTS - GROUND LEVEL RELEASES CONTINUOUS BATCH NUCLIDBS Units Ql Q2 Q1 Q2

1. Fission and Activation Gases H-3 Ci 3.93E+00 1.89E+00 No Batch Releases Xe-131m Ci <LLD <LLD this period.

Xe-133 Ci 7.24E+01 1.16B+02 Xe-133m Ci 1.16E+00 1.94E+00 Xe-135 Ci 5.58E+00 6.77E+00 Xe-135m Ci <LLD <LLD Xe-138 Ci 5. 81B-01 9. 68B-01 Ar-41 Ci <LLD <LLD Kr-85 Ci <LLD <LLD Kr-85m Ci 1.74E+00 2.90E+00 Kr-87 Ci 5. 81E-01 9. 68B-01 Kr-88 Ci 2.90B+00 4.84B+00 Totals Ci 8.89B+01 1.36E+02 0 2. Iodines I-131 Ci 6.52E-06 8.32E-07 I-133 Ci 2.41B-06 <LLD I-135 Ci <LLD <LLD Totals Ci 8.93B-06 8.32B-07

3. Particulates Gr. Alpha Ci <LLD <LLD Sr-89 Ci <LLD <LLD ..

Sr-90 Ci <LLD <LLD Cr-51 Ci <LLD <LLD Mn-54 Ci <LLD <LLD Co-58 Ci <LLD <LLD Fe-59 Ci <LLD <LLD Co-60 Ci 2.58B-05 1.04B-05 Zn-65 Ci <LLD <LLD Mo-99 Ci <LLD <LLD Cs-134 Ci <LLD <LLD Cs-137 Ci <LLD <LLD Ce-141 Ci <LLD <I LD Ce-144 Ci <LLD <LLD Ba-140 Ci <LLD <LLD La-140 Ci <LLD <LLD Totals Ci 2.58E-05 1.04B-05 2/5

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 .(Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A  : LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 1 2 Error

1. Fission & Activation Products Total Release (not including tritium, Ci 4.22 E-02 2.17 E" 02 3.50 E+01 gases, or alpha)

B. Average Diluted Concentration during Period pCi/ml 6.91 E-09 3.17 E-09 C. Percent of Technical Specification Limit 5.73 E-02 4.57 E-02

2. Tritium A. Total Release Ci 1.54 E+01 6.82 E+01 3.50 E+01 B. Average Diluted Concentration during Period pCi/ml 2 '3 E-06 9.96 E-06 C. Percent of Technical Specification Limit 2.53 E-01 9.96 E-01
3. Dissolved and Entrained Gases Total Release Ci 8.32 E-04 2.18 E-03 3.50 E+01 Average Diluted Concentration during Period pci/ml 1.36 E-10 3.18 E-10 C. Percent of Technical Specification Limit 6.81 E-05 1.59 E-04
4. Gross Alpha Radioactivity Total Release Ci LLD LLD 3.50 E+01 2/6

'Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A ': LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total

,. 1 2 Error

5. Volume of water released prior to dilution A. Batch Release liters 1.21 E+06 2.03 E+06 1.00 E+01 B. Continuous Release liters 3.34 E+07 2.03 E+07 1.00 E+01 C. Total Effluent Released liters 3.46 E+07 2.23 E+07 1.00 E+01
6. Volume of dilution water liters 6.07 E+09 6.82 E+09 1.00 E+01 used during period
7. Total Volume Released (Releases + Dilution) liters 6.10 E+09 6.84 E+09 2/7

Semiannual Radioactive Effluent Release Report January, 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B  : LIQUID EFFLUENTS

1. Fission and Activation Products CONTINUOUS BATCH Nuclides Released Units Ql Q2 Ql Q2 Gr. Alpha Ci <LLD (LLD '(LLD (LLD H-3 Ci 1.378-0 1 3. 188-0 2 1. 538+01 6.818+01 Fe-55 Ci <LLD <LLD 1. 718-02 1.57E-03 Ni-63 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD Be-7 Ci <LLD <LLD <<LLD <LLD Na-24 Ci <LLD <LLD <LLD <LLD Cr-51 Ci <LLD <LLD (LLD 4.308-05 Mn-54 Ci <LLD <LLD 5. 908-05 <LLD Co-57 Ci <LLD (LLD 8. 05E-05 3.868-05 Co-58 Ci <LLD <LLD l. 598-02 7.838-03 Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD 2. 66E-03 2.408-03 Sr-92 Ci <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <<LLD <LLD <LLD Y-93 Ci <LLD <LLD <LLD 5.198-05 Zr-95 Ci (LLD (LLD <LLD <LLD Nb-95 Ci <LLD <LLD 268-05 <LLD Tc-99m Ci <LLD (LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ru- 103 Ci <LLD (LLD,. (LLD (LLD Cd-109 Ci <LLD <LLD <LLD <LLD Ag-110m Ci (LLD (LLD (LLD (LLD Sb-122 Ci <LLD (LLD (LLD (LLD Sb-124 Ci <LLD <LLD (LLD <LLD Sb-125 Ci <LLD <LLD 4 898-03 8.158-03 Te-132 Ci <LLD <LLD <LLD <LLD I-131 Ci <LLD <<LLD 428-03 1.368-03 I-132 Ci <LLD <LLD <LLD <LLD I-133 Ci <LLD <LLD 2. 708-05 9.628-06 I-135 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD 1.21E-04 Cs-137 Ci <LLD <LLD 5. 108-05 1.448-04 Cs-138 Ci <LLD <LLD <LLD <LLD TABLE CONT INUED ON NEXT PAGE 2/a

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B : LIQUID EFFLUENTS (Continued)

1. Fission and Activation Products (Continued)

CONTINUOUS BATCH Nuclides Released Units Ql Q2 Ql Q2 Ce-141 Ci <LLD <LLD <LLD <LLD Ce-143 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Pr-144 Ci <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Hf -181 Ci <LLD <LLD <LLD <LLD Totals Ci 1.37E-01 3.18E-02 1.53E+01 6.81E+01

2. Dissolved and Entrained Gases CONTINUOUS BATCH Nuclides Released Units Ql Q2 Ql Q2 Xe-131m Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD 7.68E-04 2. 15E-03 Xe-133m Ci <LLD <LLD 4.47E-05 1.71E-OS Xe-135 Ci <LLD <LLD, ... 1.86E-OS 5.14E-06 Totals Ci <LLD <LLD 8.32E-04 2.18E-03 2/9

S Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3  : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )

A. Type of Waste Spent Resin, filter sludge, evaporator bottoms, etc.

Number of Shipments 2 Activity Shipped 2.45 E+01 Ci Estimated Total Error 10%.

Quantity Shipped 1.11 E+01 m~

Solidification Agent N/A Container Type Strong, Tight Package NRC-Approved Package Shipment Form Dewatered

b. Dry Compressible Waste, Contaminated Equipment, etc. ( DAW )

Number of Shipments 19 Activity Shipped 4.67 E-01 Ci Estimated Total Error 10%'.99 Quantity Shipped E+00 m~

Solidification Agent N/A Container Type Strong Tight Package Shipment Form Dewatered C. Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/10

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3  : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A ) (Continued)

Estimate of Major Nuclide Composition (by type of Waste)

a. Spent Resin, filter sludge, evaporator bottoms, etc.

Percent Total Activity Nuclide Composition Ci C-14 2.53 8-02 6. 19 8-03 Mn-54 1.90 8+00 4.66 8-01 Co-58 2.95 8+00 7.22 E-01 Co-60 2.58 E+01 6.31 8+00 Fe-55 6.10 8+01 1.49 E+01 Ni-63 5.88 8+00 1.44 8+00 Cs-137 1.27 8+00 3.11 8-01 Sr-90 8.00 8-03 1.96 E-03 Cs-134 1 ~ 19 8+00 2.92 8-01

b. Dry Compressible Waste, Contaminated Equipment, etc. ( DAW )

Percent Total Activity Nuclide Composition Ci H-3 5.95 8-01 2.77 E-03 C-14 2.22 8-01 1.04 8-03 Fe-55 5.86 8+01 2.73 8-01 ~

Co-58 1. 11 8+01 5.21 8-02 Co-60 2.25 E+01 1. 05 E-01 Ni-63 2.94 8+00 1.37 8-02 Mn-54 1.72 8+00 8.05 8-03 Cs-137 9.45 8-01 4.41 8-03 Ce-144 1.40 8+00 6.54 8-03 Irradiated Components, Control Rods, etc.

No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/11

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3  : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A ) (Continued)

C. Solid Waste Disposal Number of Shipments

  • 21 Mode of Transportation Truck Destination Barnwell, S,C.

The two type 1 .A. a shipments were made from the Harris Site.

All 19 of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.

2/12

Semiannual Radioactive Bffluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )

Type of Waste

a. Spent Resin, filter sludge, evaporator bottoms, etc.

Number of Shipments 1 Activity Shipped 1.65 E+02 Ci Estimated Total Error 10%'.85 Quantity Shipped E+00 m~

Solidification Agent N/A Container Type NRC Approved Package Shipment Form Dewatered

b. Dry Compressible Waste, Contaminated Equipment, etc. ( DAW )

No waste of this type shipped c ~ Irradiated Components, Control Rods, etc.

, So waste of this type shipped

d. . Other (Describe)

No waste of this type shipped 2/13

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B ) (Continued)

B. Estimate of Major Nuclide Composition (by type of Waste)

a. Spent. Resin, filter sludge, evaporator bottoms, etc.

Percent Total Activity Nuclide Composition Ci H"3 1.66 E-02 2.74 E-02 C-14 5.51 E-02 9.11 E-02 Mn-54 1.08 E+01 1.78 E+01 Co-58 7.55 E-01 1.25 E+00 Co-60 2.83 E+01 4.69 E+01 Fe-55 1.87 E+01 3.09 E+01 Ni-63 3.96 E+01 6.56 E+01 Sr-90 6 '5 E-03 1.15 E-02 Cs-137 8.46 E-01 1.40 E+00 Pu-238 6.10 E-05 1.01 E-04 Pu-239/240 6.00 E-05 9.96 E-05 Am-241 3.90 E-05 6.39 E-05 Cm-243/244 3.80 E-05 6.28 E-05 Pu-241 9.97 E-03 1.65 E-02 Cs-134 4.10 E-01 6.78 E-01 Sb-125 4.80 E-01 7.95 E-01 Dry Compressible Waste, Contaminated Equipment, etc. ( DAW )

No waste of this typed, shipped Irradiated Components, Control Rods, etc.

No waste of this type shipped Other (Describe)

No waste of this type shipped 2/14

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure .3 : Solid Waste Disposal Table 3  : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B) (Continued)

Solid Waste Disposal Number of Shipments 1 Mode of Transportation Truck Destination Barnwell, S.C.

h Solid Waste Shipped for Burial or Disposal ( WASTE CLASS C )

No waste of this type was shipped during this Report Period.

Irradiated Fuel Shipments (Disposition)

No irradiated fuel was shipped during this Report Period.

I*I

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 3  : Changes to Process Control Program (PCP)

Technical Specification 6.13 An initial review and appr'oval of the following Westinghouse/ Scientific Ecology Group procedures as part of the Harris Nuclear Plant Process Control Program was performed by the PNSC in March, 1993.

STD-P-05-004 Process Control Program for Incontainer Solidification of Bead Resin.

STD-P-05-029 Process Control Program for Incontainer Solidification of Filter Sludge.

SHNP-PCP-03-003 Mobile Incontainer Dewatering and Solidification System Process Control Program.

Because these procedures contain vendor proprietary information they are not included in this Report. The procedures have been submitted to the NRC as part of Westinghouse Hittman Nuclear Topical Report STD-R-05-011P in July, 1986 and accepted by the NRC Staff for referencing in October 1986.

The change was made in accordance with the requirement of Technical Specification 4.11.3.c for contract capability when the installed equipment is incapable of meeting Specification 3.11.3. These changes did not reduce the overall conformance of solidified waste product to existing criteria for solid waste. Attached is the documentation of the review and approval by the PNSC as required by Technical Specification 6.13.

Radwaste Uendor Procedure Approval Form Procedure Number: 5/ D - -d5-Dd4 Procedure

Title:

/?d C~S D~PHd~ PD

~iOiPic ~~a d W SW'pproved By PNSC:

7-a C CFsnnn/

Signature/ Title

Radwaste Vendor Procedure Approval Form Procedure Number: & P-05 -629'ev: C9 Procedure

Title:

466665 6n/HXd~ Con/7 Ave S Ic 6' J=IL78%

Approved By PNSC:

I PIPS'QPAJ Date 9 /71'8Z Signature/ Title

Radvaste Vendor Procedure Approval Form Procedure Number: 6 - C/ " D3-009 Rev".

Procedure

Title:

Db/Ld M n/7 /n/84 D8N M40i / N 5i S EN CS&

Approved By PNSC:

~~A PhQcc'@~V Signature/ Title

Semiannual Radioactive Effluent Release Report January 1, 1993 to June 30, 1993 Appendix 4  : Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 The following changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.

ODCM Change 3/5 incorporated the 1992 Land Use Census into the ODCM document and also changed the location description of a sample point.

ODCM Change 3/6 changed the ODCM document to reflect the usage of the new 10CFR20 terms, especially the use of Effluent Concentrations (ECs) instead of MPCs. Also, the ODCM software was changed to use the EC values.

ODCM Change 3/7 changed the definition and value of the A factor in the liquid effluent dose equation. This change is the result of the NRC's review of the SHNPP ODCM.

All of the ODCM changes described above are attached. Each change includes a full description of the changes that were made.

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