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{{#Wiki_filter:Carolina Power&Light Shearon Harris Nuclear Power Plant License No.NPF-063 SE INIANNUAL RADIOACTIVE EPPLUENT RELEASE REPORT January 1, 1994 to June 30, 1994 Prepared by: S ecial t-E&C Reviewed by: Man ger-E&RC Support Reviewed by: nager-E jronmental
{{#Wiki_filter:Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPF-063 SE INIANNUALRADIOACTIVEEPPLUENT RELEASE REPORT January 1, 1994 to June 30, 1994 Prepared by:
&Chemistry Reviewed by: nvironmental
S ecial   t - E&C Reviewed by:
&Radiation Control Approved by: General Ma ager-Harris Plant q4Q82+QQ 2 qqQ822 PDR A D~
Man   ger   - E&RC Support Reviewed by:
I C('-u J 0 Table of Contents Introduction Discussion Appendix 1.Supplemental Information Appendix 2.Effluent and Waste Disposal Report 1.Lower Limits of Detection (LLDs)2.Effluents Released 3.Solid Waste Disposal Appendix 3.Changes to Process Control Program (PLP)Appendix 4.Changes to Offsite Dose Calculation Manual (ODCM)Appendix S.Changes to the Environmental Monitoring Program l.Environmental Monitoring Program 2.Land Use Census Page No.i 1/1 2/1 2/3 2/10 3/1 5/1 S/2 Appendix 6.1.2.3.4~Additional Technical Specification Responsibilities Inoperability of Liquid Effluent Monitors Inoperability of Gaseous Effluent Monitors Unprotected Outdoor Tanks Exceeding Limits Gas Storage Tanks Exceeding Limits 6/1 6/2 6/3 6/4 Appendix 7.Major Modifications to Radwaste System 7/1
nager   - E   jronmental   & Chemistry Reviewed by:
nvironmental     & Radiation Control Approved by:
General   Ma ager - Harris Plant q4Q82+QQ 2 qqQ822 PDR   A         D~


Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 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, 1994 to June 30, 1994.During this period, the plant completed Cycle 5, performed refueling outage 5, and began Cycle 6 operation.
I C(
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.
  '- u J
Liquid and gaseous average concentrations (pCi/cc)and total curies released are for only those nuclides that are positively identified.
0
Continuous noble gas effluent activities are based on hourly average stack monitor readings (in pCi/cc)times stack flow rate, and are apportioned based on nuclides last identified in the stack gas grab samples.All other liquid and gaseous activities are based on the isotopic analysis of the release.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.A total of 42.7 m~of solid waste, containing 43.9 Ci of radioactivity, was shipped for burial during this Report period, compared with 43.14 m and 183.86 Ci shipped during the previous Report period.Appendix 3: No changes were made to the Process Control Program (PCP)during this Report period.Appendix 4: The Offsite Dose Calculation Manual (ODOM)was revised to Revision 4 during this Report period.A full copy of the revised ODCM is includedg along with a description of the changes and an analysis of the impact of the changes.
, 1 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Discussion (continued)
Appendix 5: Two changes were made to the Environmental Monitoring Program during this Report period.These changes are included in ODCM Rev.4, which is included in Appendix 4.Appendix 6: During this Report period, one gaseous and one liquid instrument used for effluent monitoring was inoperable for greater than 30 days.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, 1994 to June 30, 1994 Appendix 1: Supplemental Inf ormation Regulatory Limits A.Fission and activation gases (1)Calendar Quarter a.5 mrad gamma b.10 mrad beta (2)Calendar Year C a 10 mrad gamma b.20 mrad beta 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 Liquid effluents (1)Calendar Quarter a 1.5 mrem to total body 5 mrem to any organ (2)Calendar Year a.3 mrem to total body b.10 mrem to any organ r i 1 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 1 (Continued):
Table of Contents Page No.
Supplemental Information Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.A.Fission and activation gases C.(1)500 mrem/year to total body (2)3000 mrem/year to the skin I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.1500 mrem/year to any organ Liquid effluents The annual average 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 2, Column 2, (ECs), 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.Average Energy (E)N/A at SHNPP.SHNPP determines doses and dose rate based on actual releases, not on an average energy value.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.
Introduction                                                        i Discussion Appendix 1. Supplemental Information                                1/1 Appendix 2. Effluent and Waste Disposal Report
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 1 (Continued):
: 1. Lower Limits of Detection (LLDs)                     2/1
Supplemental Information Batch Releases A.Liquid Batch Releases (1)Number of batch releases (2)Total time period for batch releases (3)Maximum time of a batch release (4)Average time for a batch release (5)Minimum Time for a batch release 7.20 E+01 5.83 E+04 min 1.11 E+03 min 8.08 E+02 min 3.06 E+02 min (6)Average stream flow during periods of release 1.50 E+04 gpm B.Gaseous Batch Releases (1)Number of batch releases (2)Total time period for batch releases (3)Maximum tj.me of a batch release (4)Average time for a batch release (5)Minimum Time for a batch release 7.00 E+00 6.98 E+03 min 3.74 E+03 min 9.97 E+02 min 1.33 E+02 min Abnormal Releases Liquid No abnormal liquid releases were made in this period.Gaseous No abnormal gaseous releases were made in this period.
: 2. Effluents Released                                    2/3
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2: Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLDs)LLDs for Gaseous Effluents Nuclide Gross Alpha H-3 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 I-131 I-133 I-135 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Mo-99 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Ci cc 1.80E-15 7.97E-09 3.79E-OS 6.09E-06 2.12E-08 8.88E-OS 7.32E-OS 6.21E-07 6.'96E-08 1..89E-07 2.07E-OS 4.65E-07 5.94E-07 2.69E-13 2.79E-13 2.58E-13 l.66E-14 1,33E-14 3.87E-14 1.86E-14 7.55E-14 1.7 E-15 1.0 E-15 1.48E-13 1.01E-14 2.63E-14 4.13E-14 2.41E-14 1.26E-14 3.89E-14 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 C Appendix 2 (Continued):
: 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)
Effluent and Waste Disposal Report Enclosure 1: LOWER LIMITS OF DETECTION (LLDs)LLDs for Liquid Effluents Nuclide Gross Alpha H-3 Be-7 Na-24 Cr-.51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Sr-89 Sr-90 Sr-92 Y-93 Nb-95 Zr-95 Mo-99 Tc-99m Ru-103 Ag-110m Sn-113~ci ml 4.10E-08 2.55E-06 2.26E-07 1.99E-08 2.34E-07 2.60E-08 1.8 E-07 7.46E-08 2.16E-08 1.18E-08 5.00E-08 2.8 E-07 3.09E-08 1.9 E-08 1.2 E-08 2.87E"08 3.44E-07 1.19E-08 6.85E-08 3.79E-07 1.67E-08 2.70E-08 1.07E-07 4.43E-08 Nuclide Sb-122 Sb-124 Sb-125 Sb-126 I-131 I-132 I-133 I-135 Te-132 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Cs-134 Cs-137 Cs-138 Ba-140 La-140 Ce-141 Ce-143 Ce-144 Hf-181 Ci ml 3.26E-08 4.62E-08 8.69E-08 3.58E-08 2.67E-08 3.89E-08 2.58E-08 6.94E-08 2.39E-08 8.29E-07 6.18E-08 1.26E-07 2.37E-08 2.98E-'08 1.35E-08 3.92E-08 1.21E-07 1.10E-07 4.70E-08 3.42E-08 3.46E-08 1.69E-07 3.30E-08 2/2
Appendix S. Changes to the Environmental Monitoring Program
: l. Environmental Monitoring Program                      5/1
: 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. Unprotected Outdoor Tanks Exceeding 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, 1994 to June 30, 1994 Appendix 2 (Continued):
Semiannual Radioactive   Effluent Release Report January 1, 1994   to June 30, 1994 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).
Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1A: GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1.Fission&Activation Ga A.Total Release ses Units Ci Q1 7.18E+01 Q2 5.11E+01 Total Estimated%Error 4.50E+01 Average Release Rate for Period C.Percent of TS Limit pCi/sec 9.23E+00 4.98E-01 6.50E+00 4.24E-01 2..Iodines (I-131, I-133, I-135)A.Total Release Average Release Rate for Period Ci pCi/sec 8.97E-05 1.15E-05 2.88E-04 3.66E-05 2.00E+01 C.Percent of TS Limit See Footnote Below 3.Particulates (with half-lives
The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3, 1987. This Report covers the period from January 1, 1994 to June 30, 1994. During this period, the plant completed Cycle 5, performed refueling outage 5, and began Cycle 6 operation.
)8 days)A.Total Release Average Release Rate for Period C.Percent of TS Limit D.Gross Alpha Radioactivity Ci pCi/sec Ci 6.59E-05 8.48E-06 8.90E-02 LLD 7.76E-06 9.86E-07 3.71E-01 LLD 2.00E+01 4.Tritium A.Total Release Average Release Rate for Period Ci pCi/sec 7.35E-03 9.45E-04 2.00E-03 2.54E-04 3.00E+01 C.Percent of TS Limit See Footnote Below The Percent of Technical Specification limit applies to Iodines, Tritium, and Particulates combined, and is calculated using ODCM default methodology and parameters.
Discussion Appendices  1 and 2:
The value for Iodines and Tritium is included in the Particulates summation.
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.
2/3 i
Liquid  and gaseous average concentrations (pCi/cc) and total curies released are for only those nuclides that are positively identified.
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued):
Continuous noble gas effluent activities are based on hourly average stack monitor readings (in pCi/cc) times stack flow rate, and are apportioned based on nuclides last identified in the stack gas grab samples. All other liquid and gaseous activities are based on the isotopic analysis of the release. 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.
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.2/4 i 4p 1 Semiannual'adioactive Effluent Release Report Janua'ry 1, 1994 to June 30, 1994 Appendix 2 (Continued):
A total of 42.7 m~ of solid waste,  containing 43.9 Ci of radioactivity, was shipped  for burial during this Report period, compared with 43.14 m and 183.86  Ci shipped during the previous Report period.
Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C: GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Nuclide Released Units ,CONTINUOUS Q1 Q2 Q1 BATCH 1.Fission.Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 and Activation Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Gases LLD 5.56E+01 LLD 7.49E+00<LLD LLD LLD LLD LLD LLD LLD LLD 3.78E+01 LLD 1.11E+01 LLD LLD LLD LLD LLD LLD (LLD 1.10E-02 1.64E-01 1.90E-03 2.92E-03 LLD LLD LLD 8.48E+00 1.28E-04 LLD LLD 3.24E-02 2.77E-01 LLD LLD (LLD LLD LLD 1.96E+00 LLD LLD LLD TOTALS 6.31E+01 4.89E+01 8.66E+00 2.27E+00 2.Iodines I-131 I-133 I-135 TOTALS Ci Ci Ci 6.21E-05 2.76E-05 LLD 8.97E-05 2.88E-04 LLD LLD 2.88E-04 LLD LLD LLD LLD 1.08E-08 LLD LLD 1.08E-08 3.Particulates Sr-89 Sr-90 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Mo-99 Cs-134 Cs-137 Ce-141 Ce-144 Ba-140 La-140 TOTALS Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci LLD LLD LLD LLD LLD 6.59E-05 LLD LLD LLD LLD LLD<LLD LLD LLD 6.59E-05 LLD LLD LLD LLD LLD 7.76E-06 LLD<LLD LLD LLD LLD LLD LLD LLD 7.76E-06 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 4.Tritium H-3 Ci 5.43E-04 1.97E-03 6.81E-03 3.09E" 05 2/5 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued):
Appendix 3:
Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Units Q1 Q2 Total Estimated%Error 1.Fission&Activation Products A.Total Release (not including tritium, gases, or alpha)Average Diluted Concentration during Period C.Percent of TS Limit Ci pCi/ml 1.35E-02 1.73E-09 2.23E-02 1.20E-01 1.72E-08 1.18E-01 3.50E+01 2.Tritium A.Total Release Average Diluted Concentration during Period C.Percent of TS Limit Ci pCi/ml 5.77E+02 7.40E-05 7.40E+00 1.02E+02 1.45E-05 1.45E+00 3.50E+01 3.Dissolved a Entrained Gases A.Total Release Ci 4.88E-03 5:67E-04 3.50E+01 B.Average Diluted Concentration during Period pCi/ml 6.25E-10 8.11E-11 C.Percent of TS Limit 3.13E-04 4.05E-05 4.Gross Alpha Radioactivity Total Release LLD LLD 3.50E+01 2/6 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued):
No  changes were made  to the Process Control    Program (PCP) during this Report period.
Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Units Ql Q2 Total Estimated 0 Error 5.Volume of Water released prior to Dilution A.Batch Releases B.Continuous Releases C.Total Effluent Rel.liters liters liters 1.06E+07 1.36E+07 3.71E+06 6.09E+06 3.03E+06 2.38E+06 1.OOE+01 1.00E+Ol 1.00E+01 6.Volume of Dilution Water used during Period liters 7.78E+09 6.99E+09 1.00E+01 7.Total Volume Released (Releases+Dilution)liters 7.80E+09 7.00E+09 1.00E+01 Semiannual Radioactive January 1, 1994 Effluent Release Report to June 30, 1994 Appendix 2 (Continued):
Appendix 4:
Effluent and Waste Disposal Enclosure 2: Effluents Released Report S Table 2B: LIQUID EFFLUENTS CONTINUOUS BATCH Nuclide Released 1.Fission and Fe-55 Ni-63 Sr-89 Sr-90 Be-7 Na-24 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Sr-92 Zn-65 Y-93 Zr-95 Nb-95 Tc-99m Mo-99 Ru-103 Ag-110m Sn-113 Sb-122 Sb-124 Sb-125 Sb-126 Te-132 I-131 1-132 I"133 I-135 Cs-134 Cs-137 Cs-138 Ce-141 Ce-143 Ce-144 Ba-140 La-140 Hf-181 TOTALS Units Activation Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Q1 Products LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Q2 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Q1 4.69E-03 LLD LLD LLD LLD LLD 3.12E-04 4.07E-OS LLD 8.71E"04 LLD 1.25E-03 LLD LLD LLD 2.53E-05 3.59E-OS LLD LLD LLD LLD LLD LLD 8.22E-OS 4.51E-03 LLD (LLD 7.32E-04 LLD 7.98E-05 LLD 1.06E-04 1.78E-04 LLD LLD LLD LLD LLD 1.51E-04 LLD 1.35E-02 Q2 2.66E-03 LLD LLD LLD<LLD LLD 1.10E-02 5.11E-04 1.79E-05 2.63E-02 3.29E-04 4.03E-03 (LLD LLD LLD 1.53E-03 2.57E-03 LLD LLD 3.80E-04 LLD 8.37E-.05 LLD 2.66E-03 6.50E-02 2.14E-04 7.09E-OS 1.33E-03 LLD LLD LLD 5.90E-04 6.82E-04 LLD 1.69E-05 LLD 8.82E-05 LLD 1.92E-05 3.36E-05 1.20E-01 2/8 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued):
The  Offsite Dose Calculation Manual (ODOM) was revised to Revision 4 during this Report period. A full copy of the revised ODCM is includedg along with a description of the changes and an analysis of the impact of the changes.
Effluent and Waste Disposal Report Enclosure 2: Effluents Released Nuclide Released 2.Tritium H-3 Units Table 2B: LIQUID EFFLUENTS CONTINUOUS Q1 Q2 BATCH Ql Q2 3.70E-02 3.29E-02 5.77E+02 1.02E+02 3.Dissolved Kr-85 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 TOTALS&Entrained Gases Ci LLD Ci LLD Ci LLD Ci LLD ,Ci LLD Ci LLD Ci LLD LLD LLD LLD'LD LLD LLD LLD LLD LLD LLD 4.82E-03 LLD 6.13E-05 4.88E-03 LLD (LLD LLD 5.67E-04 LLD LLD 5.67E-04 4.Gross Alpha Radioactivity Gr.Alpha Ci~(LLD LLD LLD LLD 2/9 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 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)Type of Waste Spent Resin, filter sludge, etc.Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 3 2.22E+01 Ci 10%1.66E+01 m~N/A Strong Tight Package NRC-Approved Package Dewatered b.Dry Compressible Waste, Contaminated Equipment, etc.(DAW)Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 72 2.17E+01 Ci 10%'.61E+01 m~N/A Strong Tight Package ,NRC-Approved Package Dewatered Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)
No waste of this type shipped 2/10


Semiannual Radioactive Effluent Release Report January 1,-1994 to June 30, 1994'ppendix 2 (Continued):
, 1 Semiannual Radioactive   Effluent Release Report January 1, 1994   to June 30, 1994 Discussion (continued)
Effluent and Waste Disposal Report Enclosure 3: Solid Waste Disposal Table 3: SOLXD WASTE AND XRRADXATED FUEL SHXPMENTS Solid Waste Shipped for Estimate of Major k a.Spent Resin, Burial or Disposal (WASTE CLASS A)Nuclide Composition (by type of Waste)filter sludge, etc.Nuclide H-3 C-14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 Sr-90 Tc-99 Sb-125 Cs-134 Cs-137 Pu-241 Cm-242 Percent Composition 1.66E-01 1.73E-02 3.47E+00 4.67E+01 1.89E+00 2.76E+01 1.04E+01 8.44E-03 1.14E-04 2.66E-01 4.64E+00 4.79E+00 3.35E-02 2.45E-04 Total Activity Ci 3.69E-02 3.84E-03 7..70E-01 1.04E+01 4.20E-01 6.13E+00 2.3 1E+00 1.87E"03 2.52E-05 5.89E-02 1.03E+00 1.06E+00 7.42E-03 5.42E-OS b.Dry Compressible Waste,'ontaminated Equipment, etc.(DAW)Nuclide H-3 C-14 Cl-36 Mn-54 Fe-55 Co-58 Ni-59 Co-60 Ni-63 Sr-90 Nb-94 Tc-99 Sb-125 Cs-134 Cs-137 U-235 PU-239 Am-241 Pu-241 Cm-242 Percent Composition 7.13E-04 1.34E-04 5.48E-OS 1.64E+00 5.73E+01 6.03E+00 8.94E-02 2.12E+01 8.67E+00 1.18E-02 9.66E-05 1.17E-04 5.64E-01 2.28E+00 2.21E+00 5.61E-07 6.20E-06 9.62E-09 1'7E-03 3.04E-05 Total Activity Ci 1.53E-04 2.87E-05 1.18E-05 3.52E-01 1.23E+01 1.30E+00 1.92E-02 4.55E+00 1.86E+00 2.53E-03 2.07E-05 2.51E-05 1.21E-01 4.89E-01 4.74E-01 5.17E-09 1.33E-06 2.07E-09 3.37E-'04 6.54E-06 2/11 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued):
Appendix 5:
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)B.Estimate of Major Nuclide Composition (by type of Waste)Irradiated Components, Control Rods, etc.No waste of this type shipped Other (Describe)
Two changes  were made  to the Environmental Monitoring Program during this Report period. These    changes are included in ODCM Rev. 4, which is included in Appendix 4.
No waste of this type shipped Solid Waste Disposal Number of Shipments*Mode of Transportation Destination 7S Truck Barnwell, S.C.*The three type 1.A.a shipments were made from the Harris Site.Seventy of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG)processing facility in Oak Ridge, Tennessee.
Appendix 6:
Two of the type 1.A.b shipments were made from the Harris Site.2.Solid Waste Shipped for Burial or Disposal (WASTE CLASS B)No waste of this type was shipped during this Report Period.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)
During this Report period, one gaseous and one liquid instrument  used for effluent monitoring was inoperable for greater than 30 days.
No irradiated fuel was shipped during this Report Period.2/12 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 3: Changes to Process Control Program (PCP)Technical Specification 6.13 No changes were made to the PCP during the Report period.
No unprotected outdoor tank or gas storage tank exceeded Tech Spec limits during this Report. period.
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 4 Appendix 4: Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 The Offsite Dose Calculation Manual (ODCM)was revised to Revision 4 during this Report period.ODCM Rev.4 is included in its entirety since the entire document was revised and re-formatted.
Appendix 7:
Rev.4 to the ODCM makes the following changes: 1~2~3~4~Changes in methodology and terminology due to implementation of new Effluent Management System (EMS)software.Changes and additions due to NRC (EGGG)review of the ODCM.Changes to the Radiological Environmental Monitoring Program due to a new method of determining monitoring locations and addition of monitoring locations.
No major modifications to the Radwaste System were made during  this Report period.
Change in flow path of the Waste Monitoring Tank due to plant modification PCR-4746.An analysis of the changes and their affect on the ODOM is presented below.Changes in methodology and terminology due to implementation of new EMS software.The Liquid Effluent section of the ODCM has been rewritten using EMS terms and equations to show the methodology of the new EMS software.The EMS takes a different approach to the set point methodology than does the previous ODCM.This results in different terms, intermediate calculations, and input requirements.
 
However, both the previous ODCM software and the EMS software are built using the same basic assumptions.
Semiannual Radioactive    Effluent Release Report January 1, 1994  to June 30, 1994 Appendix 1: Supplemental    Information Regulatory Limits A. Fission and activation gases (1)  Calendar Quarter
Section 2.1 Compliance with 10CFR20 The primary difference in the EMS set point methodology is in the calculation of the set point adjustment factor.The EMS calculated the adjustment factor based on the dilution required by the entire mix of radionuclides including H-3 and other non>>gamma emitters.The ODCM calculated its adjustment factor based on the dilution required by the gamma emitters only.The net effect is that there is less dilution available for the adjustment factor, resulting in a lower (more conservative) set point.  
: a.     5 mrad gamma
: b. 10 mrad  beta (2) Calendar Year C
a    10 mrad gamma
: b. 20 mrad beta 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 Liquid effluents (1)  Calendar Quarter a      1.5 mrem to  total body 5 mrem  to any organ (2)  Calendar Year
: a. 3 mrem to total body
: b. 10 mrem to any organ
 
r i
1
 
Semiannual Radioactive  Effluent Release Report January 1, 1994  to June 30, 1994 Appendix  1  (Continued): Supplemental Information Maximum  permissible concentrations and dose rates which determine maximum  instantaneous release rates.
A. Fission and activation gases (1)    500 mrem/year  to total body (2)  3000 mrem/year  to the skin 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 annual average 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 2, Column 2, (ECs), 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.
Average Energy (E)
N/A  at SHNPP. SHNPP determines doses and dose rate based on actual releases, not on an average energy value.
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.
 
Semiannual Radioactive    Effluent Release Report January 1, 1994    to June 30, 1994 Appendix  1 (Continued): Supplemental Information Batch Releases A. Liquid Batch Releases (1)    Number of batch releases                      7 . 20 E+01 (2)    Total time period for batch releases          5.83 E+04 min (3)    Maximum time of a batch release                1.11 E+03 min (4)    Average time  for  a batch release            8.08 E+02 min (5)    Minimum Time  for  a batch release            3.06 E+02 min (6)    Average stream flow during periods of release                                    1.50 E+04  gpm B. Gaseous  Batch Releases (1)    Number  of batch releases                      7.00 E+00 (2)    Total time period for batch releases          6.98 E+03 min (3)    Maximum tj.me of a batch release              3.74 E+03 min (4)    Average time  for  a batch release            9.97 E+02 min (5)    Minimum Time  for  a batch release            1.33 E+02 min Abnormal Releases Liquid No abnormal    liquid releases    were made  in this period.
Gaseous No abnormal gaseous    releases were  made  in this period.
 
Semiannual Radioactive    Effluent Release Report January 1, 1994    to June 30, 1994 Appendix 2:  Effluent  and Waste Disposal Report Enclosure 1    : LOWER LIMITS OF DETECTION (LLDs)
LLDs for Gaseous Effluents Nuclide                  Ci cc Gross Alpha              1.80E-15 H-3                      7.97E-09 Ar-41                    3.79E-OS Kr-85                    6.09E-06 Kr-85m                  2. 12E-08 Kr-87                    8.88E-OS Kr-88                    7.32E-OS Xe-131m                  6.21E-07 Xe-133                  6.'96E-08 Xe-133m                  1..89E-07 Xe-135                    2.07E-OS Xe-135m                  4.65E-07 Xe-138                    5.94E-07 I-131                    2.69E-13 I-133                    2.79E-13 I-135                    2.58E-13 Mn-54 Co-58
: l. 66E-14 1,33E-14 Fe-59                    3.87E-14 Co-60                    1.86E-14 Zn-65                    7.55E-14 Sr-89                    1.7 E-15 Sr-90                    1.0 E-15 Mo-99                    1.48E-13 Cs-134                    1.01E-14 Cs-137                    2.63E-14 Ba-140                    4.13E-14 La-140                    2.41E-14 Ce-141                    1. 26E-14 Ce-144                    3. 89E-14
 
Semiannual Radioactive    Effluent Release Report January 1, 1994 C
to June 30, 1994 Appendix 2   (Continued): Effluent and Waste Disposal Report Enclosure  1  : LOWER LIMITS OF DETECTION (LLDs)
LLDs for Liquid Effluents Nuclide            ~ci    ml                      Nuclide              Ci ml Gross Alpha        4. 10E-08                      Sb-122            3.26E-08 H- 3              2.55E-06                      Sb-124            4.62E-08 Be- 7              2.26E-07                      Sb-125            8.69E-08 Na-24              1.99E-08                      Sb-126            3.58E-08 Cr-.51            2.34E-07                        I-131            2.67E-08 Mn-54              2.60E-08                        I-132            3.89E-08 Fe-55              1.8 E-07                        I-133            2.58E-08 Fe-59              7.46E-08                        I-135            6.94E-08 Co-57              2.16E-08                      Te-132            2.39E-08 Co-58              1. 18E-08                      Xe-131m          8.29E-07 Co-60              5.00E-08                      Xe-133            6. 18E-08 Ni-63              2.8 E-07                      Xe-133m          1.26E-07 Zn-65              3.09E-08                      Xe-135            2.37E-08 Sr-89              1.9 E-08                      Xe-135m          2.98E-'08 Sr-90              1.2 E-08                      Cs-134            1.35E-08 Sr-92              2.87E"08                      Cs-137            3.92E-08 Y-93              3.44E-07                      Cs-138            1.21E-07 Nb-95              1.19E-08                      Ba-140            1.10E-07 Zr-95              6.85E-08                      La-140            4.70E-08 Mo-99              3.79E-07                      Ce-141            3.42E-08 Tc-99m            1.67E-08                      Ce-143            3.46E-08 Ru-103            2.70E-08                      Ce-144            1.69E-07 Ag-110m            1.07E-07                      Hf-181            3.30E-08 Sn-113            4.43E-08 2/2
 
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix  2  (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A  :  GASEOUS EFFLUENTS - SUMMATION OF      ALL RELEASES Total Units          Q1              Q2    Estimated
                                                                                %  Error
: 1. Fission & Activation    Ga ses A. Total Release                    Ci        7.18E+01      5.11E+01  4.50E+01 Average Release    Rate        pCi/sec      9.23E+00      6.50E+00 for Period C. Percent of  TS  Limit                      4.98E-01      4 . 24E-01
: 2.  .Iodines (I-131, I-133, I-135)
A. Total Release                    Ci        8.97E-05      2.88E-04  2.00E+01 Average Release    Rate        pCi/sec      1. 15E-05      3.66E-05 for Period C. Percent of  TS  Limit                      See  Footnote Below
: 3. Particulates (with half-lives )        8 days)
A. Total Release                    Ci        6.59E-05      7.76E-06  2.00E+01 Average Release Rate          pCi/sec      8.48E-06        9.86E-07 for Period C. Percent of TS Limit                        8.90E-02        3. 71E-01 D. Gross Alpha Radioactivity                    Ci              LLD            LLD
: 4. Tritium A. Total Release                    Ci        7.35E-03        2.00E-03  3.00E+01 Average Release    Rate      pCi/sec      9.45E-04        2.54E-04 for Period C. Percent of  TS  Limit                      See  Footnote Below The Percent  of Technical Specification limit applies to Iodines, 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.
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i Semiannual Radioactive    Effluent Release Report January 1, 1994  to June 30, 1994 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.
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i 4p 1
 
Semiannual'adioactive      Effluent Release Report Janua'ry 1, 1994  to June 30, 1994 Appendix  2  (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table  1C : GASEOUS EFFLUENTS - GROUND LEVEL RELEASES
                                        ,CONTINUOUS                  BATCH Nuclide                          Q1            Q2          Q1 Released          Units
: 1. Fission and Activation    Gases
.Xe-131m                Ci            LLD          LLD    1.10E-02    3.24E-02 Xe-133                Ci        5.56E+01      3.78E+01    1.64E-01    2.77E-01 Xe-133m                Ci            LLD          LLD    1.90E-03        LLD Xe-135                  Ci        7.49E+00      1. 11E+01    2.92E-03        LLD Xe-135m                Ci          < LLD            LLD          LLD      ( LLD Xe-138                  Ci            LLD          LLD          LLD        LLD Ar-41                  Ci            LLD          LLD          LLD        LLD Kr-85                  Ci            LLD          LLD    8.48E+00    1.96E+00 Kr-85m                Ci            LLD          LLD    1.28E-04        LLD Kr-87                  Ci            LLD          LLD        LLD          LLD Kr-88                  Ci            LLD        (  LLD        LLD          LLD TOTALS                            6. 31E+01    4.89E+01    8.66E+00    2.27E+00
: 2. Iodines I-131                  Ci        6. 21E-05    2.88E-04        LLD      1.08E-08 I-133                  Ci        2.76E-05          LLD        LLD          LLD I-135                  Ci            LLD          LLD        LLD          LLD TOTALS                            8.97E-05      2.88E-04        LLD      1.08E-08
: 3.      Particulates Sr-89                  Ci            LLD          LLD        LLD          LLD Sr-90                  Ci            LLD          LLD        LLD          LLD Mn-54                  Ci            LLD          LLD        LLD          LLD Co-58                  Ci            LLD          LLD        LLD          LLD Fe-59                  Ci            LLD          LLD        LLD          LLD Co-60                  Ci        6.59E-05      7.76E-06        LLD          LLD Zn-65                  Ci            LLD          LLD        LLD          LLD Mo-99                  Ci            LLD        < LLD          LLD          LLD Cs-134                  Ci            LLD          LLD          LLD          LLD Cs-137                  Ci            LLD          LLD          LLD          LLD Ce-141                  Ci            LLD          LLD          LLD          LLD Ce-144                  Ci          < LLD          LLD          LLD          LLD Ba-140                  Ci            LLD          LLD          LLD          LLD La- 140                Ci            LLD          LLD          LLD          LLD TOTALS                  Ci        6.59E-05      7.76E-06        LLD          LLD
: 4.      Tritium H-3                    Ci        5.43E-04      1.97E-03    6.81E-03    3.09E" 05 2/5
 
Semiannual Radioactive      Effluent Release Report January 1, 1994  to June 30, 1994 Appendix    2  (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table  2A  :  LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Total Units          Q1          Q2    Estimated
                                                                          %  Error
: 1. Fission & Activation Products A. Total Release (not including tritium,              Ci        1.35E-02    1.20E-01    3 . 50E+01 gases, or alpha)
Average Diluted Concentration during          pCi/ml      1.73E-09    1.72E-08 Period C. Percent of  TS  Limit                    2.23E-02    1.18E-01
: 2. Tritium A. Total Release                    Ci        5.77E+02    1.02E+02    3.50E+01 Average Diluted Concentration during          pCi/ml      7.40E-05    1.45E-05 Period C. Percent of  TS  Limit                    7.40E+00    1.45E+00
: 3. Dissolved  a  Entrained Gases A. Total Release                    Ci        4.88E-03    5:67E-04    3.50E+01 B. Average Diluted                pCi/ml Concentration during                      6.25E-10    8. 11E-11 Period C. Percent of  TS  Limit                    3.13E-04    4.05E-05
: 4. Gross Alpha  Radioactivity Total Release                                        LLD          LLD    3.50E+01 2/6
 
Semiannual Radioactive      Effluent Release Report January 1, 1994    to June 30, 1994 Appendix  2  (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A  :  LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Total Units          Ql          Q2  Estimated 0 Error
: 5. Volume  of Water released prior to Dilution A. Batch Releases                  liters      3.03E+06    2.38E+06  1 . OOE+01 B. Continuous Releases            liters      1.06E+07    3.71E+06  1.00E+Ol C. Total Effluent Rel.            liters      1.36E+07    6.09E+06  1.00E+01
: 6. Volume  of Dilution Water used during Period liters      7.78E+09    6.99E+09  1.00E+01
: 7. Total  Volume Released    (Releases  + Dilution) liters      7.80E+09    7.00E+09  1.00E+01
 
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2  (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released S
Table 2B : LIQUID EFFLUENTS CONTINUOUS                BATCH Nuclide                        Q1            Q2        Q1          Q2 Released        Units
: 1. Fission and Activation Products Fe-55                  Ci          LLD            LLD  4.69E-03    2.66E-03 Ni-63                  Ci          LLD            LLD        LLD          LLD Sr-89                  Ci          LLD          LLD        LLD          LLD Sr-90                  Ci          LLD          LLD        LLD          LLD Be-7                  Ci          LLD            LLD        LLD      <  LLD Na-24                  Ci          LLD          LLD        LLD          LLD Cr-51                  Ci          LLD          LLD    3.12E-04    1. 10E-02 Mn-54                  Ci          LLD            LLD  4.07E-OS    5. 11E-04 Co-57                  Ci          LLD          LLD        LLD    1.79E-05 Co-58                  Ci          LLD          LLD    8.71E"04    2.63E-02 Fe-59                  Ci          LLD          LLD        LLD      3.29E-04 Co-60                  Ci          LLD          LLD    1.25E-03    4.03E-03 Sr-92                  Ci          LLD          LLD        LLD      (  LLD Zn-65                  Ci          LLD          LLD        LLD          LLD Y-93                  Ci          LLD          LLD        LLD          LLD Zr-95                  Ci          LLD          LLD    2.53E-05    1.53E-03 Nb-95                  Ci          LLD          LLD    3.59E-OS    2.57E-03 Tc-99m                Ci          LLD          LLD        LLD          LLD Mo-99                  Ci          LLD          LLD        LLD          LLD Ru-103                Ci          LLD          LLD        LLD      3.80E-04 Ag-110m                Ci          LLD          LLD        LLD          LLD Sn-113                Ci          LLD          LLD        LLD      8.37E-.05 Sb-122                Ci          LLD          LLD        LLD          LLD Sb-124                Ci          LLD          LLD    8.22E-OS    2.66E-03 Sb-125                Ci          LLD          LLD    4.51E-03    6.50E-02 Sb-126                Ci          LLD          LLD        LLD      2.14E-04 Te-132                Ci          LLD          LLD      ( LLD      7.09E-OS I-131                  Ci          LLD          LLD    7.32E-04    1.33E-03 1-132                  Ci          LLD          LLD        LLD          LLD I"133                  Ci          LLD          LLD    7.98E-05        LLD I-135                  Ci          LLD          LLD        LLD          LLD Cs-134                Ci          LLD          LLD    1.06E-04    5.90E-04 Cs-137                Ci          LLD          LLD    1.78E-04    6.82E-04 Cs-138                Ci          LLD          LLD        LLD          LLD Ce-141                Ci          LLD          LLD        LLD      1.69E-05 Ce-143                Ci          LLD          LLD        LLD          LLD Ce-144                Ci          LLD          LLD        LLD      8.82E-05 Ba-140                Ci          LLD          LLD        LLD          LLD La-140                Ci          LLD          LLD    1.51E-04    1.92E-05 Hf-181                Ci          LLD          LLD        LLD      3.36E-05 TOTALS                                            LLD    1.35E-02    1.20E-01 2/8
 
Semiannual Radioactive      Effluent Release Report January 1, 1994    to June 30, 1994 Appendix  2  (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table  2B  : LIQUID EFFLUENTS CONTINUOUS                    BATCH Nuclide                        Q1            Q2            Ql          Q2 Released          Units
: 2. Tritium H-3                              3.70E-02      3.29E-02    5.77E+02    1.02E+02
: 3. Dissolved  & Entrained Gases Kr-85                  Ci            LLD          LLD          LLD          LLD Xe-131m                Ci            LLD          LLD          LLD      (  LLD Xe-133m                Ci            LLD          LLD          LLD          LLD Xe-133                  Ci          LLD                'LD 4.82E-03    5.67E-04 Xe-135m                ,Ci          LLD            LLD          LLD          LLD Xe-135                Ci            LLD            LLD      6. 13E-05        LLD TOTALS                Ci            LLD            LLD      4.88E-03    5.67E-04
: 4. Gross Alpha  Radioactivity Gr. Alpha              Ci      ~  ( LLD            LLD          LLD        LLD 2/9
 
Semiannual Radioactive      Effluent Release Report January 1, 1994  to June 30, 1994 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 )
Type  of  Waste Spent Resin,    filter sludge,  etc.
Number    of Shipments            3 Activity Shipped                  2.22E+01 Ci Estimated Total Error              10%
Quantity Shipped                  1.66E+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            72 Activity Shipped                  2.17E+01 Ci Estimated Total Error Quantity Shipped                  10%'.61E+01 m~
Solidification    Agent            N/A Container Type                    Strong Tight Package
                                                ,NRC-Approved Package Shipment Form                      Dewatered Irradiated Components, Control      Rods,  etc.
No waste of this type shipped Other (Describe)
No waste    of this type shipped 2/10
 
Semiannual Radioactive      Effluent Release Report January 1, -1994  to June 30, 1994 2  (Continued): Effluent and Waste Disposal Report
                                                              'ppendix Enclosure 3 : Solid Waste Disposal Table  3  :  SOLXD WASTE AND XRRADXATED FUEL SHXPMENTS Solid  Waste Shipped      for Burial or Disposal    ( WASTE          CLASS A )
Estimate of Major Nuclide Composition (by type of Waste)
Spent Resin, filter sludge, etc.
k a.
Percent            Total Activity Nuclide        Composition              Ci H-3            1. 66E-01          3.69E-02 C-14          1.73E-02            3.84E-03 Mn-54          3.47E+00            7..70E-01 Fe-55          4.67E+01            1.04E+01 Co-58          1.89E+00            4.20E-01 Co-60          2.76E+01            6.13E+00 Ni-63          1.04E+01            2 . 3 1E+00 Sr-90          8.44E-03            1.87E"03 Tc-99          1.14E-04            2.52E-05 Sb-125        2. 66E-01          5.89E-02 Cs-134        4.64E+00            1.03E+00 Cs-137        4.79E+00            1.06E+00 Pu-241        3.35E-02            7.42E-03 Cm-242        2.45E-04            5.42E-OS
: b.      Dry Compressible Waste,'ontaminated          Equipment, etc.    ( DAW )
Percent            Total Activity Nuclide        Composition              Ci H-3            7. 13E-04          1.53E-04 C-14          1.34E-04            2.87E-05 Cl-36          5.48E-OS            1.18E-05 Mn-54          1.64E+00            3.52E-01 Fe-55          5.73E+01            1.23E+01 Co-58          6.03E+00            1.30E+00 Ni-59          8.94E-02            1.92E-02 Co-60          2.12E+01            4.55E+00 Ni-63          8.67E+00            1.86E+00 Sr-90          1.18E-02            2.53E-03 Nb-94          9.66E-05            2.07E-05 Tc-99          1.17E-04            2.51E-05 Sb-125        5. 64E-01          1.21E-01 Cs-134          2.28E+00            4.89E-01 Cs-137        2. 21E+00          4.74E-01 U-235          5.61E-07            5.17E-09 PU-239        6.20E-06            1.33E-06 Am-241          9.62E-09            2.07E-09 Pu-241        1 '7E-03            3.37E-'04 Cm-242          3.04E-05            6.54E-06 2/11
 
Semiannual Radioactive    Effluent Release Report January 1, 1994  to June 30, 1994 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 )
B. Estimate of Major Nuclide Composition (by type of Waste)
Irradiated Components, Control Rods, etc.
No waste of this type shipped Other (Describe)
No  waste of this type shipped Solid  Waste Disposal Number  of Shipments
* 7S Mode  of Transportation            Truck Destination                        Barnwell, S.C.
* The  three type 1.A.a shipments were made from the Harris Site. Seventy of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.      Two of the type 1.A.b shipments were made from the Harris Site.
: 2. Solid  Waste Shipped    for Burial or Disposal ( WASTE CLASS B )
No waste  of this type was shipped during this Report Period.
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.
2/12
 
Semiannual Radioactive  Effluent Release Report January 1, 1994  to June 30, 1994 Appendix  3 : Changes  to Process Control Program  (PCP)
Technical Specification 6.13 No changes were made  to the  PCP during the Report period.
 
Semiannual Radioactive  Effluent Release Report January 1, 1994  to June 30, 1994 4
Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specification 6.14 The Offsite Dose Calculation Manual (ODCM) was revised to Revision 4 during this Report period. ODCM Rev. 4 is included in its entirety since the entire document was  revised  and re-formatted.
Rev. 4  to the  ODCM  makes the following changes:
1~    Changes in methodology and terminology due to implementation of new Effluent Management System (EMS) software.
2~    Changes and additions due to NRC (EGGG) review of the ODCM.
3~    Changes to the Radiological Environmental Monitoring Program due to a new method of determining monitoring locations and addition of monitoring locations.
4~    Change in flow path of the    Waste Monitoring Tank due to plant modification PCR-4746.
An analysis of the changes and their affect on the      ODOM is presented below.
Changes  in methodology  and terminology due to implementation of new EMS  software.
The  Liquid Effluent section of the    ODCM has been rewritten using EMS  terms and equations to show the methodology of the new EMS software. The EMS takes a different approach to the set point methodology than does the previous ODCM. This results in different terms, intermediate calculations, and input requirements. However, both the previous ODCM software and the EMS software are built using the same basic assumptions.
Section 2.1 Compliance with    10CFR20 The  primary difference in the EMS set point methodology is in the calculation of the set point adjustment factor. The EMS calculated the adjustment factor based on the dilution required by the entire mix of radionuclides including H-3 and other non>>gamma emitters. The ODCM calculated its adjustment factor based on the dilution required by the gamma emitters only. The net effect is that there is less dilution available for the adjustment factor, resulting in a lower (more conservative) set point.
 
Semiannual Radioactive              Effluent Release Report January 1, 1994      to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation                Manual  (ODCM)
Technical Specification 6.14 Sec'tion 2.2 Compliance with lOCFR50
: a. Both the            ODCM  and the. EMS use standard NUREG-0133 equations for      dose    calculations. The major difference is in the calculation of the dose factor A<<. The EMS program includes the decay factor, e"'~ within the A<< term, while the ODCM program includes the e '> outside the A<< term.-
This leads to a difference in the A<< factors,, but not'to the final dose. Differences in the A<< tables not attributed to decay are due to rounding. differences between the manually calculated ODCM table and the computer-generated EMS table. Overall, the change to A<< has no impact on the functionality of the ODCM or on the doses                  it calculates'nother change between the current ODCM and EMS is the method used to calculate the 31-day projected dose.                  The ODCM method uses accumulated dose and a projection factor based on reactor power as follows:
ODCM        Method Dl  = D2      or    Dl
* P2 = D2 P1    P2                P1 where:
Dl                    Dose of previous month D2                      31 day projected dose P1                    Average Power Level of    previous month P2                    Average Power Level of    projected period The      EMS projects its doses using actual releases          that are occurring (open releases) and a projection factor based on time as follows:
EMS      Method (D~
* p)  + Dai 4/2
 
Semiannual Radioactive        Effluent Release Report January 1, 1994    to June 30, 1994 Appendix 4  (Continued): Changes to the Offsite Dose Calculation            Manual (ODCM)
Technical Specification 6.14 where:
D~              31 day  projected dose DI              dose  in open releases p              projection factor, which is "the result of 31 divided by the number of days from the start of the quarter to the end of the release".
Dai            Additional    Dose  (not normally used)
Both methods must compare the          resulting dose  against a value
                  ,of 0.06 mrem.
NUREG-0133 says      that  "The  calculation of projected cumulative dose impact that could result from the proposed operation should use the methodology in section 4.3 of this (NUREG-0133) manual".        Section 4.3 discusses the requirements for implementing 10CFR50. Since both the ODCM and EMS use accepted methods for calculating the dose, and NUREG-0133 does not discuss the method for calculating the projection, both methods are equally valid.
Changing    to use the EMS methodology will not have any safety impact on the operation of the SHNPP, nor does on set point calculations.
it  have any impact Changes    and  additions  due  to  NRC  (EGRG)  review of the  ODCM.
In 1992 EG&G, under contract with the NRC, performed a review of our ODCM.'G&G recommended a number of areas for improvement in the ODCM. These improvement i'tems consisted of adding text for explanation or clarification to the ODCM document. Adding this text to the ODCM document does not affect the purpose or use of the ODCM. Since there are no methodology changes proposed by this text addition, there are no impacts on the set point or dose calculations.
The  review of the ODCM is documented via EGG-PHY-10462, "Technical Evaluation Report for the Evaluation of ODCM Revision 3, Shearon Harris Nuclear Power Plant, Unit 1", dated September, 1992 . Response to specific items in the evaluation is documented via letter NSL-93-129, "Response to Request for Additional Information regarding the SHNPP ODCM", dated May 14, 1993.
4/3
 
Semiannual Radioactive ~
Effluent Release Report January 1, 1994    to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation
                ~
Manual  (ODCM)
Technical Specification 6.14 Changes to the Radiological Environmental        Monitoring Program due to a new method of determining monitoring        locations and addition of monitoring locations.
The changes  to Table 4.1 as a result of using the Global Positioning  System" (GPS)  will have no safety impact on the ODCM.
The receptors are the same, and only a new method of determining distance and direction was incorporated. The applicable revised distances and directions were used in GASPAR and the resulting doses were compared against those run with the original distances and  direction.
Sample Point 62 (Ingestion, Food Products) was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census. The change was due to the changing population surrounding the site. This addition is a routine change to ensure that all potential receptors are monitored.
The  addition of sampling location    63  is to  ensure  full coverage  of all  sectors surrounding the SHNPP. After mapping of the monitoring locations using the GPS,      it was discovered that one TLD monitoring location was actually in a sector adjacent to where          it was thought to be. Upon realizing that a sector was not being monitored, a new monitoring point, &#xb9;63, was established in that sector.
Change  in flow path of the    Waste Monitoring Tank due to    PCR-4746 Plant modification PCR-4746 was completed to allow the Waste Monitor Tanks to be used to discharge Secondary Waste water in the batch mode when there is primary;to-secondary leakage. ODCM Table 2.1-1 and Figures 2.1-1 and 2.1-2 have been changed to reflect the processing and discharge pathways. The change to the ODCM for this item is covered by the analysis done for PCR-4746.
4/4


Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 Sec'tion 2.2 Compliance with lOCFR50 a.Both the ODCM and the.EMS use standard NUREG-0133 equations for dose calculations.
The major difference is in the calculation of the dose factor A<<.The EMS program includes the decay factor, e"'~within the A<<term, while the ODCM program includes the e'>outside the A<<term.-This leads to a difference in the A<<factors,, but not'to the final dose.Differences in the A<<tables not attributed to decay are due to rounding.differences between the manually calculated ODCM table and the computer-generated EMS table.Overall, the change to A<<has no impact on the functionality of the ODCM or on the doses it calculates'nother change between the current ODCM and EMS is the method used to calculate the 31-day projected dose.The ODCM method uses accumulated dose and a projection factor based on reactor power as follows: ODCM Method Dl=D2 P1 P2 or Dl*P2=D2 P1 where: Dl D2 P1 P2 Dose of previous month 31 day projected dose Average Power Level of previous month Average Power Level of projected period The EMS projects its doses using actual releases that are occurring (open releases)and a projection factor based on time as follows: EMS Method (D~*p)+Dai4/2 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 where: D~DI p Dai 31 day projected dose dose in open releases projection factor, which is"the result of 31 divided by the number of days from the start of the quarter to the end of the release".Additional Dose (not normally used)Both methods must compare the resulting dose against a value ,of 0.06 mrem.NUREG-0133 says that"The calculation of projected cumulative dose impact that could result from the proposed operation should use the methodology in section 4.3 of this (NUREG-0133) manual".Section 4.3 discusses the requirements for implementing 10CFR50.Since both the ODCM and EMS use accepted methods for calculating the dose, and NUREG-0133 does not discuss the method for calculating the projection, both methods are equally valid.Changing to use the EMS methodology will not have any safety impact on the operation of the SHNPP, nor does it have any impact on set point calculations.
Changes and additions due to NRC (EGRG)review of the ODCM.In 1992 EG&G, under contract with the NRC, performed a review of our ODCM.'G&G recommended a number of areas for improvement in the ODCM.These improvement i'tems consisted of adding text for explanation or clarification to the ODCM document.Adding this text to the ODCM document does not affect the purpose or use of the ODCM.Since there are no methodology changes proposed by this text addition, there are no impacts on the set point or dose calculations.
The review of the ODCM is documented via EGG-PHY-10462,"Technical Evaluation Report for the Evaluation of ODCM Revision 3, Shearon Harris Nuclear Power Plant, Unit 1", dated September, 1992.Response to specific items in the evaluation is documented via letter NSL-93-129,"Response to Request for Additional Information regarding the SHNPP ODCM", dated May 14, 1993.4/3 Semiannual Radioactive Effluent Release Report~~January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 Changes to the Radiological Environmental Monitoring Program due to a new method of determining monitoring locations and addition of monitoring locations.
The changes to Table 4.1 as a result of using the Global Positioning System" (GPS)will have no safety impact on the ODCM.The receptors are the same, and only a new method of determining distance and direction was incorporated.
The applicable revised distances and directions were used in GASPAR and the resulting doses were compared against those run with the original distances and direction.
Sample Point 62 (Ingestion, Food Products)was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census.The change was due to the changing population surrounding the site.This addition is a routine change to ensure that all potential receptors are monitored.
The addition of sampling location 63 is to ensure full coverage of all sectors surrounding the SHNPP.After mapping of the monitoring locations using the GPS, it was discovered that one TLD monitoring location was actually in a sector adjacent to where it was thought to be.Upon realizing that a sector was not being monitored, a new monitoring point,&#xb9;63, was established in that sector.Change in flow path of the Waste Monitoring Tank due to PCR-4746 Plant modification PCR-4746 was completed to allow the Waste Monitor Tanks to be used to discharge Secondary Waste water in the batch mode when there is primary;to-secondary leakage.ODCM Table 2.1-1 and Figures 2.1-1 and 2.1-2 have been changed to reflect the processing and discharge pathways.The change to the ODCM for this item is covered by the analysis done for PCR-4746.4/4
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*%
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Semiannual Radioactive     Effluent Release Report January 1, 1994   to June 30, 1994 Appendix   4 (Continued): Changes to the Offsite Dose Calculation       Manual (ODCM)
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 Below is a description of the changes to the ODCM.Changes are marked on the appropriate page of the ODCM with a vertical revision bar.ODCM Section Chan e Title Page Table of Contents Update to Revision 4 Changes as required.List of Effective Pages added.Section 2.0 Stronger emphasis on not making concurrent batch releases.Text to identify key parameters in the EMS'software that define the methodology used.Section 2.1 Introductory section added to better describe the relationship between Technical Specification and 10CFR20 requirements, and to state the purpose of the High and Alert Alarm set points.Section 2.1.1 Completely rewritten to reflect the EMS calculation methodology.(Part 1 was not changed except to rename a parameter.)
Technical Specification 6.14 Below is a description of the   changes to the   ODCM. Changes are marked on the appropriate page of the     ODCM with   a vertical   revision bar.
Section 2.1.2 Terminology changes to reflect EMS.No change in methodology from previous software.Statement added to clarify that the EMS does not calculate continuous liquid release set points contrary to existing software.Calculations will be performed manually as needed.Clarify that the effluent LLD is used for activity determinations.
ODCM   Section                             Chan e Title Page                 Update   to Revision   4 Table of Contents          Changes   as required.
Section 2.1.3 Editorial Changes only.Section 2.2.1 Renamed parameters to reflect EMS terminology.
List of Effective   Pages   added.
This included relocating a variable from the dose equation to inside the A~value, necessitating a recalculation of those values.There was no change to the overall methodology.
Section 2.0                 Stronger emphasis on not making concurrent batch releases. Text to identify key parameters in the     EMS
Changed the description of our H-3 accountability to discount the effect of background H-3 in the secondary system (SWST and TB Drains)discharges.
                          'software that define the methodology used.
A S emiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Section 2.1                 Introductory section added to better describe the relationship between Technical Specification and 10CFR20 requirements, and to state the purpose of the High and Alert Alarm set points.
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 ODCM Section Chan e Section 2.2.2 Text added to better describe the differences between the ODCM methodology and the methodology in LADTAP'which is used for calculating annual doses.Section 2.2.3 New section to describe post-release compliance with 10 CFR 50.Section 2.2.4 A new methodology to calculate projected liquid dose.The old method was a ratio based on plant power level for a period of time.The new method uses the actual releases in progress or defined for release to make the projection.
Section 2.1.1               Completely rewritten to reflect the EMS calculation methodology.     (Part 1 was not changed except to rename a parameter.)
The new method is the standard EMS methodology.
Section 2.1.2               Terminology changes to reflect EMS.       No change in methodology from previous software.       Statement added to clarify that the     EMS does not calculate continuous liquid release set points contrary to existing software. Calculations will be performed manually         as needed. Clarify that the effluent LLD is used for activity determinations.
Table 2.1-1 Change to the WMT parameters to reflect its new usage as a batch secondary waste release point.Pump Discharge and rad monitor changed.Note 3 added.TLQiS pump discharge set at 35 gpm and*note deleted.Table 2.1-2 Table 2.1-3 Minor editorial changes.Minor editorial changes.Table 2.1-4 Table has been renamed and revised to include parameters in the format the EMS requires.Incorporated Table 2.2-2.Table 2.2-1 Table 2.2-2 Figure 2.1-1 Figure 2.1-2 Values are calculated using the new A;~.Deleted.Information Incorporated into Table 2.1-4.Revised to show current processing flow paths.Revised to show current effluent flow (realignment of WMT's).Section 3.1 Section 3.1.1 Remove reference to old 10 CFR 20 section.Minor Editorial Changes Section 3.2.1 Text added to better describe methodology used for gaseous release accountability.
Section 2.1.3               Editorial Changes only.
4/6 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued):
Section 2.2.1               Renamed   parameters to reflect EMS terminology. This included relocating a variable from the dose equation to inside the A~ value, necessitating a recalculation of those values. There was no change to the overall methodology.
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 ODCM Section Chan e Section 3.2.2 Text added to better describe methodology used for gaseous release accountability.
Changed the   description of our H-3 accountability to discount the effect of background H-3 in the secondary system (SWST and TB Drains) discharges.
Section 3.3 Editorial Changes (Section Numbers).Introductory section added to better describe the differences between the ODCM methodology and the methodology in GASPAR which is used for calculating annual doses.Section 3.3.1 Text added to describe noble gas source term methodology.
 
Section 3.3.2 Text added to better describe methodology used for gaseous release accountability.
A S emiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual         (ODCM)
Table 4.1 Table 4.1 was rewritten and reformatted to make the table easier to understand.
Technical Specification 6.14 ODCM Section                             Chan e Section 2.2.2             Text added to better describe the differences between the ODCM methodology and the methodology in LADTAP
In 1993, the Harris Energy&Environmental Center performed a land use census and environmental monitoring using a hand-held Global Positioning System (GPS)to determine distances and directions of receptor locations.
                        'which is used for calculating annual doses.
This differs from the previous method, which used large-scale maps and plastic overlays.Using the GPS has resulted in a number of differences from the previous year, primarily with the distance changing+0.1 miles.Using the GPS also determined that one of the TLD sample locations was actually in an adjacent sector to where it was thought to be.None of the monitoring locations have changed, just the method used to determine distance and direction.
Section 2.2.3             New section to describe post-release     compliance with 10 CFR 50.
A monitoring location was established (Sample Point 63)to ensure monitoring in all applicable sectors.Sample Point 62 (Ingestion, Food Products)was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census.The change was due to the changing population surrounding the site.4/7 Cl Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4'Continued):
Section 2.2.4             A new methodology to calculate projected liquid dose.
Changes to the Offsite Dose Calculation Manual (ODCM)Technical Specification 6.14 ODCM Section Chan e Section 5.0 Section 6.0 Appendix C Editorial changes.Text added to include TS commitment references.
The old method was a ratio based on plant power level for a period of time. The new method uses the actual releases in progress or defined for release to make the projection. The new method is the standard EMS methodology.
Removed several monitors that were process monitors, not effluent monitors (RAB Normal Exhaust, FHB Exhaust, etc.).4/S Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.1.c X.A new TLD Location N63 was added at 0.6 miles in the SW sector to complete the inner ring sector coverage.The addition was made after a study of TLD locations using a global positioning system revealed that the TLD formerly attributed to the SW sector was in the WSW.XX.Data was provided for revisions to Table 4.1 and Figure 4.1-1 of the ODCM.These changes are included in ODCM Revision 4, which is included in Appendix 4.
Table 2.1-1               Change to the WMT parameters to reflect       its new usage as a batch secondary waste release point.         Pump Discharge and rad monitor changed. Note 3 added.
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 5: Changes to the Environmental Monitoring Program Enclosure 2: Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No change to the Land Use Census was made during this Report period.5/2 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6: Additional Technical Specification Responsibilities : Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service
TLQiS pump discharge set at 35 gpm and *note deleted.
>30 Days During this Report Period FT-21WL-6119, Waste Monitor Tanks Discharge Flow Transmitter, was declared inoperable from 1/27/94 to 5/21/94 (-113 days).The instrument was originally declared inoperable due to the failure to pass an Operations Surveillance Test (OST), OST-2044.By 1/29/94 the maintenance work had been completed on the transmitter (recalibration)
Table 2.1-2               Minor  editorial    changes.
.The inoperability required that the OST be performed successfully prior to declaration of operability.
Table 2.1-3               Minor editorial   changes.
~To perform the OST, the flow transmitter must have liquid flow.Tbus, the OST can only be performed during an actual tank release.However, no releases were made from the Waste Evaporator Condensate Tanks (WECT)or the Waste Monitor Tanks (WMT)until 5/21/94 at which time the OST was successfully performed and the instrument was declared operable.So, despite the fact that the instrument was inoperable for-113 days, no releases were made during the period of inoperability that required the invocation of the TS action statement.
Table 2.1-4               Table has been renamed and revised to include parameters in the format the EMS requires.
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued):
Incorporated Table 2.2-2.
Additional Technical Specification Responsibilities : Znoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service
Table 2.2-1               Values are calculated using the new      A;~.
)30 Days During this Report Period REM-01AV-3509SA, the Plant Vent Stack 1 Particulate, Zodine, and Gas (PZG)Noble Gas Activity Monitor, was inoperable for 33 days due to flow problems, the"A" electrical bus outage during RF05, and a 18 month calibration on the Plant Vent Stack Flow monitor, which required this monitor to remain inoperable.
Table 2.2-2               Deleted. Information Incorporated into Table 2.1-4.
During this time, the PVS-1 Wide Range Gas Monitor (WRGM)was operable and being used as the Noble Gas monitor.6/2 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued):
Figure 2.1-1             Revised to show current processing flow paths.
Additional Technical Specification Responsibilities : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.6/3  
Figure 2.1-2              Revised  to show current effluent flow (realignment of WMT's) .
Section 3.1               Remove   reference to old   10 CFR 20 section.
Section 3.1.1            Minor Editorial   Changes Section 3.2.1             Text added to better describe methodology used         for gaseous release accountability.
4/6
 
Semiannual Radioactive     Effluent Release Report January 1, 1994   to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation     Manual (ODCM)
Technical Specification 6.14 ODCM Section                           Chan e Section 3.2.2           Text added to better describe methodology used     for gaseous release accountability.
Section 3.3             Editorial   Changes   (Section Numbers).
Introductory section added to better describe the differences between the ODCM methodology and the methodology in GASPAR which is used for calculating annual doses.
Section 3.3.1           Text added to describe noble gas source term methodology.
Section 3.3.2           Text added to better describe methodology used for gaseous release accountability.
Table 4.1               Table 4.1 was rewritten and reformatted to make the table easier to understand.
In 1993, the Harris Energy & Environmental Center performed a land use census and environmental monitoring using a hand-held Global Positioning System (GPS) to determine distances and directions of receptor locations. This differs from the previous method, which used large-scale maps and plastic overlays. Using the GPS has resulted in a number of differences from the previous year, primarily with the distance changing +0.1 miles.
Using the GPS   also determined that one of the TLD sample locations   was actually in an adjacent sector to where it was thought to be. None of the monitoring locations have changed, just the method used to determine distance and direction. A monitoring location was established (Sample Point 63) to ensure monitoring in all applicable sectors.
Sample Point 62 (Ingestion, Food Products) was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census.     The change was due to the changing population surrounding the site.
4/7
 
Cl Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix   4'Continued):   Changes to the Offsite Dose Calculation Manual   (ODCM)
Technical Specification 6.14 ODCM Section                           Chan e Section 5.0               Editorial  changes.
Section 6.0               Text added to include   TS commitment references.
Appendix  C              Removed several monitors that were process monitors, not effluent monitors (RAB Normal Exhaust, FHB Exhaust, etc.).
4/S
 
Semiannual Radioactive   Effluent Release Report January 1, 1994   to June 30, 1994 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program Technical Specifications   3.11.2.3
: 3. 12. 1 3.12.1.c X. A new TLD Location N63 was added at 0.6 miles in the SW sector to complete the inner   ring sector coverage. The addition was made after a study of TLD locations using a global positioning system revealed that the TLD formerly attributed to the SW sector was in the WSW.
XX. Data was provided   for revisions to Table 4.1 and Figure 4.1-1 of the ODCM.
These changes are included in   ODCM Revision 4, which   is included in Appendix 4.
 
Semiannual Radioactive   Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a
: 3. 12.2.b No change to the Land Use Census was made during   this Report period.
5/2
 
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1: Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During this Report Period FT-21WL-6119, Waste Monitor Tanks Discharge Flow Transmitter, was declared inoperable from 1/27/94 to 5/21/94 (-113 days) . The instrument was originally declared inoperable due to the failure to pass an Operations Surveillance Test (OST), OST-2044. By 1/29/94 the maintenance work had been completed on the transmitter (recalibration) .
The inoperability required that the OST be performed successfully prior to declaration of operability. To perform the OST, the flow transmitter
                                ~
must have liquid flow. Tbus, the OST can only be performed during an actual tank release. However, no releases were made from the Waste Evaporator Condensate Tanks (WECT) or the Waste Monitor Tanks (WMT) until 5/21/94 at which time the OST was successfully performed and the instrument was declared operable. So, despite the fact that the instrument was inoperable for -113 days, no releases were made during the period of inoperability that required the invocation of the TS action statement.
 
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Znoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service ) 30 Days During this Report Period REM-01AV-3509SA, the   Plant Vent Stack 1 Particulate, Zodine, and Gas (PZG) Noble Gas Activity Monitor, was inoperable for 33 days due to flow problems, the "A" electrical bus outage during RF05, and a 18 month calibration on the Plant Vent Stack Flow monitor, which required this monitor to remain inoperable. During this time, the PVS-1 Wide Range Gas Monitor (WRGM) was operable and being used as the Noble Gas monitor.
6/2
 
Semiannual Radioactive   Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.
6/3


Semiannual Radioactive Effluent Release Report January=1, 1994 to June 30, 1994 Appendix 6 (Continued):
Semiannual Radioactive   Effluent Release Report January =1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded   the Technical Specification limit during this Report period.
Additional Technical Specification Responsibilities : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.6/4  
6/4


Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 7: Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste System during this Report period.}}
Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 7 : Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste System during this Report period.}}

Revision as of 06:14, 22 October 2019

Semiannual Radioactive Effluent Release Rept for Jan-June 1994.
ML18011A557
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Text

Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPF-063 SE INIANNUALRADIOACTIVEEPPLUENT RELEASE REPORT January 1, 1994 to June 30, 1994 Prepared by:

S ecial t - E&C Reviewed by:

Man ger - E&RC Support Reviewed by:

nager - E jronmental & Chemistry Reviewed by:

nvironmental & Radiation Control Approved by:

General Ma ager - Harris Plant q4Q82+QQ 2 qqQ822 PDR A D~

I C(

'- u J

0

Table of Contents Page No.

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

1. Lower Limits of Detection (LLDs) 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)

Appendix S. Changes to the Environmental Monitoring Program

l. Environmental Monitoring Program 5/1
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. Unprotected Outdoor Tanks Exceeding 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, 1994 to June 30, 1994 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, 1994 to June 30, 1994. During this period, the plant completed Cycle 5, performed refueling outage 5, and began Cycle 6 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.

Liquid and gaseous average concentrations (pCi/cc) and total curies released are for only those nuclides that are positively identified.

Continuous noble gas effluent activities are based on hourly average stack monitor readings (in pCi/cc) times stack flow rate, and are apportioned based on nuclides last identified in the stack gas grab samples. All other liquid and gaseous activities are based on the isotopic analysis of the release. 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.

A total of 42.7 m~ of solid waste, containing 43.9 Ci of radioactivity, was shipped for burial during this Report period, compared with 43.14 m and 183.86 Ci shipped during the previous Report period.

Appendix 3:

No changes were made to the Process Control Program (PCP) during this Report period.

Appendix 4:

The Offsite Dose Calculation Manual (ODOM) was revised to Revision 4 during this Report period. A full copy of the revised ODCM is includedg along with a description of the changes and an analysis of the impact of the changes.

, 1 Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Discussion (continued)

Appendix 5:

Two changes were made to the Environmental Monitoring Program during this Report period. These changes are included in ODCM Rev. 4, which is included in Appendix 4.

Appendix 6:

During this Report period, one gaseous and one liquid instrument used for effluent monitoring was inoperable for greater than 30 days.

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, 1994 to June 30, 1994 Appendix 1: Supplemental Information Regulatory Limits A. Fission and activation gases (1) Calendar Quarter

a. 5 mrad gamma
b. 10 mrad beta (2) Calendar Year C

a 10 mrad gamma

b. 20 mrad beta 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 Liquid effluents (1) Calendar Quarter a 1.5 mrem to total body 5 mrem to any organ (2) Calendar Year
a. 3 mrem to total body
b. 10 mrem to any organ

r i

1

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 1 (Continued): Supplemental Information Maximum permissible concentrations and dose rates which determine maximum instantaneous release rates.

A. Fission and activation gases (1) 500 mrem/year to total body (2) 3000 mrem/year to the skin 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 annual average 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 2, Column 2, (ECs), 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.

Average Energy (E)

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

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.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 1 (Continued): Supplemental Information Batch Releases A. Liquid Batch Releases (1) Number of batch releases 7 . 20 E+01 (2) Total time period for batch releases 5.83 E+04 min (3) Maximum time of a batch release 1.11 E+03 min (4) Average time for a batch release 8.08 E+02 min (5) Minimum Time for a batch release 3.06 E+02 min (6) Average stream flow during periods of release 1.50 E+04 gpm B. Gaseous Batch Releases (1) Number of batch releases 7.00 E+00 (2) Total time period for batch releases 6.98 E+03 min (3) Maximum tj.me of a batch release 3.74 E+03 min (4) Average time for a batch release 9.97 E+02 min (5) Minimum Time for a batch release 1.33 E+02 min Abnormal Releases Liquid No abnormal liquid releases were made in this period.

Gaseous No abnormal gaseous releases were made in this period.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2: Effluent and Waste Disposal Report Enclosure 1  : LOWER LIMITS OF DETECTION (LLDs)

LLDs for Gaseous Effluents Nuclide Ci cc Gross Alpha 1.80E-15 H-3 7.97E-09 Ar-41 3.79E-OS Kr-85 6.09E-06 Kr-85m 2. 12E-08 Kr-87 8.88E-OS Kr-88 7.32E-OS Xe-131m 6.21E-07 Xe-133 6.'96E-08 Xe-133m 1..89E-07 Xe-135 2.07E-OS Xe-135m 4.65E-07 Xe-138 5.94E-07 I-131 2.69E-13 I-133 2.79E-13 I-135 2.58E-13 Mn-54 Co-58

l. 66E-14 1,33E-14 Fe-59 3.87E-14 Co-60 1.86E-14 Zn-65 7.55E-14 Sr-89 1.7 E-15 Sr-90 1.0 E-15 Mo-99 1.48E-13 Cs-134 1.01E-14 Cs-137 2.63E-14 Ba-140 4.13E-14 La-140 2.41E-14 Ce-141 1. 26E-14 Ce-144 3. 89E-14

Semiannual Radioactive Effluent Release Report January 1, 1994 C

to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1  : LOWER LIMITS OF DETECTION (LLDs)

LLDs for Liquid Effluents Nuclide ~ci ml Nuclide Ci ml Gross Alpha 4. 10E-08 Sb-122 3.26E-08 H- 3 2.55E-06 Sb-124 4.62E-08 Be- 7 2.26E-07 Sb-125 8.69E-08 Na-24 1.99E-08 Sb-126 3.58E-08 Cr-.51 2.34E-07 I-131 2.67E-08 Mn-54 2.60E-08 I-132 3.89E-08 Fe-55 1.8 E-07 I-133 2.58E-08 Fe-59 7.46E-08 I-135 6.94E-08 Co-57 2.16E-08 Te-132 2.39E-08 Co-58 1. 18E-08 Xe-131m 8.29E-07 Co-60 5.00E-08 Xe-133 6. 18E-08 Ni-63 2.8 E-07 Xe-133m 1.26E-07 Zn-65 3.09E-08 Xe-135 2.37E-08 Sr-89 1.9 E-08 Xe-135m 2.98E-'08 Sr-90 1.2 E-08 Cs-134 1.35E-08 Sr-92 2.87E"08 Cs-137 3.92E-08 Y-93 3.44E-07 Cs-138 1.21E-07 Nb-95 1.19E-08 Ba-140 1.10E-07 Zr-95 6.85E-08 La-140 4.70E-08 Mo-99 3.79E-07 Ce-141 3.42E-08 Tc-99m 1.67E-08 Ce-143 3.46E-08 Ru-103 2.70E-08 Ce-144 1.69E-07 Ag-110m 1.07E-07 Hf-181 3.30E-08 Sn-113 4.43E-08 2/2

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1A  : GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Total Units Q1 Q2 Estimated

% Error

1. Fission & Activation Ga ses A. Total Release Ci 7.18E+01 5.11E+01 4.50E+01 Average Release Rate pCi/sec 9.23E+00 6.50E+00 for Period C. Percent of TS Limit 4.98E-01 4 . 24E-01
2. .Iodines (I-131, I-133, I-135)

A. Total Release Ci 8.97E-05 2.88E-04 2.00E+01 Average Release Rate pCi/sec 1. 15E-05 3.66E-05 for Period C. Percent of TS Limit See Footnote Below

3. Particulates (with half-lives ) 8 days)

A. Total Release Ci 6.59E-05 7.76E-06 2.00E+01 Average Release Rate pCi/sec 8.48E-06 9.86E-07 for Period C. Percent of TS Limit 8.90E-02 3. 71E-01 D. Gross Alpha Radioactivity Ci LLD LLD

4. Tritium A. Total Release Ci 7.35E-03 2.00E-03 3.00E+01 Average Release Rate pCi/sec 9.45E-04 2.54E-04 for Period C. Percent of TS Limit See Footnote Below The Percent of Technical Specification limit applies to Iodines, 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

i Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 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.

2/4

i 4p 1

Semiannual'adioactive Effluent Release Report Janua'ry 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2: Effluents Released Table 1C : GASEOUS EFFLUENTS - GROUND LEVEL RELEASES

,CONTINUOUS BATCH Nuclide Q1 Q2 Q1 Released Units

1. Fission and Activation Gases

.Xe-131m Ci LLD LLD 1.10E-02 3.24E-02 Xe-133 Ci 5.56E+01 3.78E+01 1.64E-01 2.77E-01 Xe-133m Ci LLD LLD 1.90E-03 LLD Xe-135 Ci 7.49E+00 1. 11E+01 2.92E-03 LLD Xe-135m Ci < LLD LLD LLD ( LLD Xe-138 Ci LLD LLD LLD LLD Ar-41 Ci LLD LLD LLD LLD Kr-85 Ci LLD LLD 8.48E+00 1.96E+00 Kr-85m Ci LLD LLD 1.28E-04 LLD Kr-87 Ci LLD LLD LLD LLD Kr-88 Ci LLD ( LLD LLD LLD TOTALS 6. 31E+01 4.89E+01 8.66E+00 2.27E+00

2. Iodines I-131 Ci 6. 21E-05 2.88E-04 LLD 1.08E-08 I-133 Ci 2.76E-05 LLD LLD LLD I-135 Ci LLD LLD LLD LLD TOTALS 8.97E-05 2.88E-04 LLD 1.08E-08
3. Particulates Sr-89 Ci LLD LLD LLD LLD Sr-90 Ci LLD LLD LLD LLD Mn-54 Ci LLD LLD LLD LLD Co-58 Ci LLD LLD LLD LLD Fe-59 Ci LLD LLD LLD LLD Co-60 Ci 6.59E-05 7.76E-06 LLD LLD Zn-65 Ci LLD LLD LLD LLD Mo-99 Ci LLD < LLD LLD LLD Cs-134 Ci LLD LLD LLD LLD Cs-137 Ci LLD LLD LLD LLD Ce-141 Ci LLD LLD LLD LLD Ce-144 Ci < LLD LLD LLD LLD Ba-140 Ci LLD LLD LLD LLD La- 140 Ci LLD LLD LLD LLD TOTALS Ci 6.59E-05 7.76E-06 LLD LLD
4. Tritium H-3 Ci 5.43E-04 1.97E-03 6.81E-03 3.09E" 05 2/5

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A  : LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Total Units Q1 Q2 Estimated

% Error

1. Fission & Activation Products A. Total Release (not including tritium, Ci 1.35E-02 1.20E-01 3 . 50E+01 gases, or alpha)

Average Diluted Concentration during pCi/ml 1.73E-09 1.72E-08 Period C. Percent of TS Limit 2.23E-02 1.18E-01

2. Tritium A. Total Release Ci 5.77E+02 1.02E+02 3.50E+01 Average Diluted Concentration during pCi/ml 7.40E-05 1.45E-05 Period C. Percent of TS Limit 7.40E+00 1.45E+00
3. Dissolved a Entrained Gases A. Total Release Ci 4.88E-03 5:67E-04 3.50E+01 B. Average Diluted pCi/ml Concentration during 6.25E-10 8. 11E-11 Period C. Percent of TS Limit 3.13E-04 4.05E-05
4. Gross Alpha Radioactivity Total Release LLD LLD 3.50E+01 2/6

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2A  : LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Total Units Ql Q2 Estimated 0 Error

5. Volume of Water released prior to Dilution A. Batch Releases liters 3.03E+06 2.38E+06 1 . OOE+01 B. Continuous Releases liters 1.06E+07 3.71E+06 1.00E+Ol C. Total Effluent Rel. liters 1.36E+07 6.09E+06 1.00E+01
6. Volume of Dilution Water used during Period liters 7.78E+09 6.99E+09 1.00E+01
7. Total Volume Released (Releases + Dilution) liters 7.80E+09 7.00E+09 1.00E+01

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released S

Table 2B : LIQUID EFFLUENTS CONTINUOUS BATCH Nuclide Q1 Q2 Q1 Q2 Released Units

1. Fission and Activation Products Fe-55 Ci LLD LLD 4.69E-03 2.66E-03 Ni-63 Ci LLD LLD LLD LLD Sr-89 Ci LLD LLD LLD LLD Sr-90 Ci LLD LLD LLD LLD Be-7 Ci LLD LLD LLD < LLD Na-24 Ci LLD LLD LLD LLD Cr-51 Ci LLD LLD 3.12E-04 1. 10E-02 Mn-54 Ci LLD LLD 4.07E-OS 5. 11E-04 Co-57 Ci LLD LLD LLD 1.79E-05 Co-58 Ci LLD LLD 8.71E"04 2.63E-02 Fe-59 Ci LLD LLD LLD 3.29E-04 Co-60 Ci LLD LLD 1.25E-03 4.03E-03 Sr-92 Ci LLD LLD LLD ( LLD Zn-65 Ci LLD LLD LLD LLD Y-93 Ci LLD LLD LLD LLD Zr-95 Ci LLD LLD 2.53E-05 1.53E-03 Nb-95 Ci LLD LLD 3.59E-OS 2.57E-03 Tc-99m Ci LLD LLD LLD LLD Mo-99 Ci LLD LLD LLD LLD Ru-103 Ci LLD LLD LLD 3.80E-04 Ag-110m Ci LLD LLD LLD LLD Sn-113 Ci LLD LLD LLD 8.37E-.05 Sb-122 Ci LLD LLD LLD LLD Sb-124 Ci LLD LLD 8.22E-OS 2.66E-03 Sb-125 Ci LLD LLD 4.51E-03 6.50E-02 Sb-126 Ci LLD LLD LLD 2.14E-04 Te-132 Ci LLD LLD ( LLD 7.09E-OS I-131 Ci LLD LLD 7.32E-04 1.33E-03 1-132 Ci LLD LLD LLD LLD I"133 Ci LLD LLD 7.98E-05 LLD I-135 Ci LLD LLD LLD LLD Cs-134 Ci LLD LLD 1.06E-04 5.90E-04 Cs-137 Ci LLD LLD 1.78E-04 6.82E-04 Cs-138 Ci LLD LLD LLD LLD Ce-141 Ci LLD LLD LLD 1.69E-05 Ce-143 Ci LLD LLD LLD LLD Ce-144 Ci LLD LLD LLD 8.82E-05 Ba-140 Ci LLD LLD LLD LLD La-140 Ci LLD LLD 1.51E-04 1.92E-05 Hf-181 Ci LLD LLD LLD 3.36E-05 TOTALS LLD 1.35E-02 1.20E-01 2/8

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B  : LIQUID EFFLUENTS CONTINUOUS BATCH Nuclide Q1 Q2 Ql Q2 Released Units

2. Tritium H-3 3.70E-02 3.29E-02 5.77E+02 1.02E+02
3. Dissolved & Entrained Gases Kr-85 Ci LLD LLD LLD LLD Xe-131m Ci LLD LLD LLD ( LLD Xe-133m Ci LLD LLD LLD LLD Xe-133 Ci LLD 'LD 4.82E-03 5.67E-04 Xe-135m ,Ci LLD LLD LLD LLD Xe-135 Ci LLD LLD 6. 13E-05 LLD TOTALS Ci LLD LLD 4.88E-03 5.67E-04
4. Gross Alpha Radioactivity Gr. Alpha Ci ~ ( LLD LLD LLD LLD 2/9

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 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 )

Type of Waste Spent Resin, filter sludge, etc.

Number of Shipments 3 Activity Shipped 2.22E+01 Ci Estimated Total Error 10%

Quantity Shipped 1.66E+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 72 Activity Shipped 2.17E+01 Ci Estimated Total Error Quantity Shipped 10%'.61E+01 m~

Solidification Agent N/A Container Type Strong Tight Package

,NRC-Approved Package Shipment Form Dewatered Irradiated Components, Control Rods, etc.

No waste of this type shipped Other (Describe)

No waste of this type shipped 2/10

Semiannual Radioactive Effluent Release Report January 1, -1994 to June 30, 1994 2 (Continued): Effluent and Waste Disposal Report

'ppendix Enclosure 3 : Solid Waste Disposal Table 3  : SOLXD WASTE AND XRRADXATED FUEL SHXPMENTS Solid Waste Shipped for Burial or Disposal ( WASTE CLASS A )

Estimate of Major Nuclide Composition (by type of Waste)

Spent Resin, filter sludge, etc.

k a.

Percent Total Activity Nuclide Composition Ci H-3 1. 66E-01 3.69E-02 C-14 1.73E-02 3.84E-03 Mn-54 3.47E+00 7..70E-01 Fe-55 4.67E+01 1.04E+01 Co-58 1.89E+00 4.20E-01 Co-60 2.76E+01 6.13E+00 Ni-63 1.04E+01 2 . 3 1E+00 Sr-90 8.44E-03 1.87E"03 Tc-99 1.14E-04 2.52E-05 Sb-125 2. 66E-01 5.89E-02 Cs-134 4.64E+00 1.03E+00 Cs-137 4.79E+00 1.06E+00 Pu-241 3.35E-02 7.42E-03 Cm-242 2.45E-04 5.42E-OS

b. Dry Compressible Waste,'ontaminated Equipment, etc. ( DAW )

Percent Total Activity Nuclide Composition Ci H-3 7. 13E-04 1.53E-04 C-14 1.34E-04 2.87E-05 Cl-36 5.48E-OS 1.18E-05 Mn-54 1.64E+00 3.52E-01 Fe-55 5.73E+01 1.23E+01 Co-58 6.03E+00 1.30E+00 Ni-59 8.94E-02 1.92E-02 Co-60 2.12E+01 4.55E+00 Ni-63 8.67E+00 1.86E+00 Sr-90 1.18E-02 2.53E-03 Nb-94 9.66E-05 2.07E-05 Tc-99 1.17E-04 2.51E-05 Sb-125 5. 64E-01 1.21E-01 Cs-134 2.28E+00 4.89E-01 Cs-137 2. 21E+00 4.74E-01 U-235 5.61E-07 5.17E-09 PU-239 6.20E-06 1.33E-06 Am-241 9.62E-09 2.07E-09 Pu-241 1 '7E-03 3.37E-'04 Cm-242 3.04E-05 6.54E-06 2/11

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 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 )

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

Irradiated Components, Control Rods, etc.

No waste of this type shipped Other (Describe)

No waste of this type shipped Solid Waste Disposal Number of Shipments

  • 7S Mode of Transportation Truck Destination Barnwell, S.C.
  • The three type 1.A.a shipments were made from the Harris Site. Seventy of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee. Two of the type 1.A.b shipments were made from the Harris Site.
2. Solid Waste Shipped for Burial or Disposal ( WASTE CLASS B )

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

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.

2/12

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 3 : Changes to Process Control Program (PCP)

Technical Specification 6.13 No changes were made to the PCP during the Report period.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 4

Appendix 4 : Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 The Offsite Dose Calculation Manual (ODCM) was revised to Revision 4 during this Report period. ODCM Rev. 4 is included in its entirety since the entire document was revised and re-formatted.

Rev. 4 to the ODCM makes the following changes:

1~ Changes in methodology and terminology due to implementation of new Effluent Management System (EMS) software.

2~ Changes and additions due to NRC (EGGG) review of the ODCM.

3~ Changes to the Radiological Environmental Monitoring Program due to a new method of determining monitoring locations and addition of monitoring locations.

4~ Change in flow path of the Waste Monitoring Tank due to plant modification PCR-4746.

An analysis of the changes and their affect on the ODOM is presented below.

Changes in methodology and terminology due to implementation of new EMS software.

The Liquid Effluent section of the ODCM has been rewritten using EMS terms and equations to show the methodology of the new EMS software. The EMS takes a different approach to the set point methodology than does the previous ODCM. This results in different terms, intermediate calculations, and input requirements. However, both the previous ODCM software and the EMS software are built using the same basic assumptions.

Section 2.1 Compliance with 10CFR20 The primary difference in the EMS set point methodology is in the calculation of the set point adjustment factor. The EMS calculated the adjustment factor based on the dilution required by the entire mix of radionuclides including H-3 and other non>>gamma emitters. The ODCM calculated its adjustment factor based on the dilution required by the gamma emitters only. The net effect is that there is less dilution available for the adjustment factor, resulting in a lower (more conservative) set point.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 Sec'tion 2.2 Compliance with lOCFR50

a. Both the ODCM and the. EMS use standard NUREG-0133 equations for dose calculations. The major difference is in the calculation of the dose factor A<<. The EMS program includes the decay factor, e"'~ within the A<< term, while the ODCM program includes the e '> outside the A<< term.-

This leads to a difference in the A<< factors,, but not'to the final dose. Differences in the A<< tables not attributed to decay are due to rounding. differences between the manually calculated ODCM table and the computer-generated EMS table. Overall, the change to A<< has no impact on the functionality of the ODCM or on the doses it calculates'nother change between the current ODCM and EMS is the method used to calculate the 31-day projected dose. The ODCM method uses accumulated dose and a projection factor based on reactor power as follows:

ODCM Method Dl = D2 or Dl

  • P2 = D2 P1 P2 P1 where:

Dl Dose of previous month D2 31 day projected dose P1 Average Power Level of previous month P2 Average Power Level of projected period The EMS projects its doses using actual releases that are occurring (open releases) and a projection factor based on time as follows:

EMS Method (D~

  • p) + Dai 4/2

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 where:

D~ 31 day projected dose DI dose in open releases p projection factor, which is "the result of 31 divided by the number of days from the start of the quarter to the end of the release".

Dai Additional Dose (not normally used)

Both methods must compare the resulting dose against a value

,of 0.06 mrem.

NUREG-0133 says that "The calculation of projected cumulative dose impact that could result from the proposed operation should use the methodology in section 4.3 of this (NUREG-0133) manual". Section 4.3 discusses the requirements for implementing 10CFR50. Since both the ODCM and EMS use accepted methods for calculating the dose, and NUREG-0133 does not discuss the method for calculating the projection, both methods are equally valid.

Changing to use the EMS methodology will not have any safety impact on the operation of the SHNPP, nor does on set point calculations.

it have any impact Changes and additions due to NRC (EGRG) review of the ODCM.

In 1992 EG&G, under contract with the NRC, performed a review of our ODCM.'G&G recommended a number of areas for improvement in the ODCM. These improvement i'tems consisted of adding text for explanation or clarification to the ODCM document. Adding this text to the ODCM document does not affect the purpose or use of the ODCM. Since there are no methodology changes proposed by this text addition, there are no impacts on the set point or dose calculations.

The review of the ODCM is documented via EGG-PHY-10462, "Technical Evaluation Report for the Evaluation of ODCM Revision 3, Shearon Harris Nuclear Power Plant, Unit 1", dated September, 1992 . Response to specific items in the evaluation is documented via letter NSL-93-129, "Response to Request for Additional Information regarding the SHNPP ODCM", dated May 14, 1993.

4/3

Semiannual Radioactive ~

Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation

~

Manual (ODCM)

Technical Specification 6.14 Changes to the Radiological Environmental Monitoring Program due to a new method of determining monitoring locations and addition of monitoring locations.

The changes to Table 4.1 as a result of using the Global Positioning System" (GPS) will have no safety impact on the ODCM.

The receptors are the same, and only a new method of determining distance and direction was incorporated. The applicable revised distances and directions were used in GASPAR and the resulting doses were compared against those run with the original distances and direction.

Sample Point 62 (Ingestion, Food Products) was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census. The change was due to the changing population surrounding the site. This addition is a routine change to ensure that all potential receptors are monitored.

The addition of sampling location 63 is to ensure full coverage of all sectors surrounding the SHNPP. After mapping of the monitoring locations using the GPS, it was discovered that one TLD monitoring location was actually in a sector adjacent to where it was thought to be. Upon realizing that a sector was not being monitored, a new monitoring point, ¹63, was established in that sector.

Change in flow path of the Waste Monitoring Tank due to PCR-4746 Plant modification PCR-4746 was completed to allow the Waste Monitor Tanks to be used to discharge Secondary Waste water in the batch mode when there is primary;to-secondary leakage. ODCM Table 2.1-1 and Figures 2.1-1 and 2.1-2 have been changed to reflect the processing and discharge pathways. The change to the ODCM for this item is covered by the analysis done for PCR-4746.

4/4

  • %

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 Below is a description of the changes to the ODCM. Changes are marked on the appropriate page of the ODCM with a vertical revision bar.

ODCM Section Chan e Title Page Update to Revision 4 Table of Contents Changes as required.

List of Effective Pages added.

Section 2.0 Stronger emphasis on not making concurrent batch releases. Text to identify key parameters in the EMS

'software that define the methodology used.

Section 2.1 Introductory section added to better describe the relationship between Technical Specification and 10CFR20 requirements, and to state the purpose of the High and Alert Alarm set points.

Section 2.1.1 Completely rewritten to reflect the EMS calculation methodology. (Part 1 was not changed except to rename a parameter.)

Section 2.1.2 Terminology changes to reflect EMS. No change in methodology from previous software. Statement added to clarify that the EMS does not calculate continuous liquid release set points contrary to existing software. Calculations will be performed manually as needed. Clarify that the effluent LLD is used for activity determinations.

Section 2.1.3 Editorial Changes only.

Section 2.2.1 Renamed parameters to reflect EMS terminology. This included relocating a variable from the dose equation to inside the A~ value, necessitating a recalculation of those values. There was no change to the overall methodology.

Changed the description of our H-3 accountability to discount the effect of background H-3 in the secondary system (SWST and TB Drains) discharges.

A S emiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 ODCM Section Chan e Section 2.2.2 Text added to better describe the differences between the ODCM methodology and the methodology in LADTAP

'which is used for calculating annual doses.

Section 2.2.3 New section to describe post-release compliance with 10 CFR 50.

Section 2.2.4 A new methodology to calculate projected liquid dose.

The old method was a ratio based on plant power level for a period of time. The new method uses the actual releases in progress or defined for release to make the projection. The new method is the standard EMS methodology.

Table 2.1-1 Change to the WMT parameters to reflect its new usage as a batch secondary waste release point. Pump Discharge and rad monitor changed. Note 3 added.

TLQiS pump discharge set at 35 gpm and *note deleted.

Table 2.1-2 Minor editorial changes.

Table 2.1-3 Minor editorial changes.

Table 2.1-4 Table has been renamed and revised to include parameters in the format the EMS requires.

Incorporated Table 2.2-2.

Table 2.2-1 Values are calculated using the new A;~.

Table 2.2-2 Deleted. Information Incorporated into Table 2.1-4.

Figure 2.1-1 Revised to show current processing flow paths.

Figure 2.1-2 Revised to show current effluent flow (realignment of WMT's) .

Section 3.1 Remove reference to old 10 CFR 20 section.

Section 3.1.1 Minor Editorial Changes Section 3.2.1 Text added to better describe methodology used for gaseous release accountability.

4/6

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4 (Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 ODCM Section Chan e Section 3.2.2 Text added to better describe methodology used for gaseous release accountability.

Section 3.3 Editorial Changes (Section Numbers).

Introductory section added to better describe the differences between the ODCM methodology and the methodology in GASPAR which is used for calculating annual doses.

Section 3.3.1 Text added to describe noble gas source term methodology.

Section 3.3.2 Text added to better describe methodology used for gaseous release accountability.

Table 4.1 Table 4.1 was rewritten and reformatted to make the table easier to understand.

In 1993, the Harris Energy & Environmental Center performed a land use census and environmental monitoring using a hand-held Global Positioning System (GPS) to determine distances and directions of receptor locations. This differs from the previous method, which used large-scale maps and plastic overlays. Using the GPS has resulted in a number of differences from the previous year, primarily with the distance changing +0.1 miles.

Using the GPS also determined that one of the TLD sample locations was actually in an adjacent sector to where it was thought to be. None of the monitoring locations have changed, just the method used to determine distance and direction. A monitoring location was established (Sample Point 63) to ensure monitoring in all applicable sectors.

Sample Point 62 (Ingestion, Food Products) was added to the Radiological Environmental Monitoring Program as a result of the 1993 Land Use Census. The change was due to the changing population surrounding the site.

4/7

Cl Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 4'Continued): Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 ODCM Section Chan e Section 5.0 Editorial changes.

Section 6.0 Text added to include TS commitment references.

Appendix C Removed several monitors that were process monitors, not effluent monitors (RAB Normal Exhaust, FHB Exhaust, etc.).

4/S

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 1 : Environmental Monitoring Program Technical Specifications 3.11.2.3

3. 12. 1 3.12.1.c X. A new TLD Location N63 was added at 0.6 miles in the SW sector to complete the inner ring sector coverage. The addition was made after a study of TLD locations using a global positioning system revealed that the TLD formerly attributed to the SW sector was in the WSW.

XX. Data was provided for revisions to Table 4.1 and Figure 4.1-1 of the ODCM.

These changes are included in ODCM Revision 4, which is included in Appendix 4.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 5  : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications 3.12.2.a

3. 12.2.b No change to the Land Use Census was made during this Report period.

5/2

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 : Additional Technical Specification Responsibilities Enclosure 1: Inoperability of Liquid Effluent Monitors Technical Specification 3.3.3.10, Action b Monitors Out-of-Service > 30 Days During this Report Period FT-21WL-6119, Waste Monitor Tanks Discharge Flow Transmitter, was declared inoperable from 1/27/94 to 5/21/94 (-113 days) . The instrument was originally declared inoperable due to the failure to pass an Operations Surveillance Test (OST), OST-2044. By 1/29/94 the maintenance work had been completed on the transmitter (recalibration) .

The inoperability required that the OST be performed successfully prior to declaration of operability. To perform the OST, the flow transmitter

~

must have liquid flow. Tbus, the OST can only be performed during an actual tank release. However, no releases were made from the Waste Evaporator Condensate Tanks (WECT) or the Waste Monitor Tanks (WMT) until 5/21/94 at which time the OST was successfully performed and the instrument was declared operable. So, despite the fact that the instrument was inoperable for -113 days, no releases were made during the period of inoperability that required the invocation of the TS action statement.

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 : Znoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service ) 30 Days During this Report Period REM-01AV-3509SA, the Plant Vent Stack 1 Particulate, Zodine, and Gas (PZG) Noble Gas Activity Monitor, was inoperable for 33 days due to flow problems, the "A" electrical bus outage during RF05, and a 18 month calibration on the Plant Vent Stack Flow monitor, which required this monitor to remain inoperable. During this time, the PVS-1 Wide Range Gas Monitor (WRGM) was operable and being used as the Noble Gas monitor.

6/2

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 3 : Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4, Action a No unprotected outdoor tank exceeded the Technical Specification limit during this Report period.

6/3

Semiannual Radioactive Effluent Release Report January =1, 1994 to June 30, 1994 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceeded the Technical Specification limit during this Report period.

6/4

Semiannual Radioactive Effluent Release Report January 1, 1994 to June 30, 1994 Appendix 7 : Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste System during this Report period.

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