ML18011A557
| ML18011A557 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/30/1994 |
| From: | Barnes H CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18011A558 | List: |
| References | |
| NUDOCS 9408290042 | |
| Download: ML18011A557 (50) | |
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(
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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
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
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
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
- 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
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 10CFR50
- 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.
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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.
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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.
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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.
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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.).
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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.
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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.
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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.
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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.
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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.