HL-9201, Semiannual Radioactive Effluent Release Rept,Jan-June 1992
| ML18010A729 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/30/1992 |
| From: | Hinnant C, Templeton B, Vaughn G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-920122, NUDOCS 9209010210 | |
| Download: ML18010A729 (68) | |
Text
ACCELERATED !~~TRIBUTIOIXDEMOiTRATION SYSTEM REGULAlWY INFORMATION DISTRIBUTION SYSTEM (RIDS) tihEECI!
FACIL: 50-400 Shearon Harris Nuclear PoUjer Planti Unit li Carolina AUTH. NAME AUTHOR AFFXLXATION VAUGHNiG. E.
Carolina Power 5 Light Co.
TEMPLETON> B.
Carolina Power fli Light Co.
HXNNANT>C. S.
Carolina PoUJer 5 Light Co.
REC IP. NAME RECIPIENT AFFILXATXON DOCKET 05000000
SUBJECT:
"Shearon Harris Nuclear Power Plant Se Radioactive Effluent Release Repti Jan-June 1992.
N/920827 DISTRIBUTION CODE:
IE4SD COPIES RECEIVED: LTR ENCL J SIZE: 33 TITLE: 50. 36a(a) (2) Semiannual E$fIuent Release Reports NOTES: Application for permit renewal filed.
S 05000400 I REC IP IENT ID CODE/NAME PD2-1 LA LEi N CQP IES LTTR ENCL 3
3 REC IP IENT ID CODE/NAME PD2-1 PD CQP IES LTTR ENCL 1
1 XNTERNAL: ACRS G FILE 01 FILE 02 EXTERNAL:
1 1
1 1
1 1
1 1
NRR/DREP/PRPB11 RGN2 DRSS/RPB EGkG SIMPSQNi F R
I NOTP TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUivfEYTCOYTROL DESK.
ROOiif PI-S7 (EXT. 504-'2065) TO ELIMIiNATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUlvfENTS YOU DON'T YEED!
TOTAL NUMBER OF COP XES REQUIRED:
LTTR 16 ENCL 16
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CHILL Carolina Power & Light Company P.O. Bpx 165 ~ New Hill,NC 27562 G. E. VAUGHN Vice President Harris Nuclear Prpjeci AUG.2'7 1992 Letter Number:
HO-920122 U.S. Nuclear Regulatory Commission ATTN:
NRC Document Control Desk Washington, D.C.
20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:
In accordance with Technical Specification 6.9.1.4.,
the Semiannual Radioactive Effluent Release Report is attached for the Shearon Harris Nuclear Power Plant.
This report covers the period from January 1,
1992 through June 30, 1992.
Very truly yours, MGW:dmw Attachment G.
E. Vaughn Vice President Harris Nuclear Project cc:
Mr. S.
D. Ebneter (NRC - RII)
Mr. N. B. Le (NRR)
Mr. J.
E. Tedrow (NRC -
SHNPP)
MEM/HO-920122/1/OS1 r
9ap9p roan o iaoiso il0 0 5 0 PDR ADOCK 05000400 R
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Carolina Power S Light Shearon Harris Nuclear Power Plant License No.'PP-063 SEAUANNUALRIIDKOAUTIVEEPPLUENT RELEASE REPORT January 1,
1992 to June 30, 1992 Prepared by:
Prepared by:
Speci list - E6C Reviewed by:
Manager
- ETC Support Reviewed by:
Manager
- Environm ntal
& Radiation Control Approved by:
General Manager
- Harris Plant P
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Table of Contents Introduction Page No.
i Discussion Appendix 1. Supplemental Information Appendix 2.
1.
2.
3.
Effluent and Waste Disposal Report Lower Limits of Detection (LLD's)
Effluents Released Solid Waste Disposal 2/1 2/3 2/11 Appendix 3.
Changes to Process Control Program (PLP)
Appendix 4.
Changes to Offsite Dose Calculation Manual (ODCM) 3/1 4/1 Appendix 5.
Changes to the Environmental Monitoring Program 1.
Environmental Monitoring Program 2.
Land Use Census 5/1 5/2 Appendix 6 ~
1.
2.
3.
4
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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
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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't 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,
1992 to June 30, 1992.
During this period, the plant was in Cycle 4 operation.
Discussion Appendices 1 and 2:
The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev.
- 1) Appendix B format.
As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.
Except for continuous noble gas releases, liquid and gaseous average concentrations (uCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.
Continuous noble gas effluent activities were based on hourly average stack monitor readings (in uCi/cc) and stack flow rate estimates based on design fan flow rates, and are apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. When specific noble gas nuclides were identified in the stack gas grab samples, their activity was added to the activity based on stack monitor readings.
Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.
The "Percent of Technical Specification Limit" is calculated using ODCM default methodology and parameters.
A total of 26.76 m~ of solid waste, containing 213.18 Ci of radioactivity, was shipped for burial during this Report period, compared with 32.95 m~ and 166.27 Ci shipped during the previous Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Discussion (continued)
Appendix 3:
No changes to the Process Control Program (PCP) were made during this Report period.
Appendix 4:
No changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.
Appendix S:
The annual Land Use Census was performed during this Report period.
As a result of the census, Table 3.2-2 of the ODCM, which provides the distances to the nearest special locations, i.e., residences, milk animals,
- gardens, and meat animals, will need to be revised in the next Report period.
To determine if any of the new special locations yielded calculated doses greater than the locations previously used, the 1991 land use data was coupled with the 1990 meteorology, and dose calculations were performed by the GASPAR program using the GALE source terms provided in Table 3.2-1 of the ODCM.
No significant differences in estimated doses occurs as a result of the 1991 changes,
- therefor, no changes to the Environmental Monitoring Program were made during this Report period.
Appendix 6:
All effluent monitor inoperabilities greater than 30 days are given along with a brief explanation.
During these periods, compensatory sampling and flow rate estimations consistent with Technical Specification requirements have provided accountability and control of effluents.
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.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 1: Supplemental Information 1.
Regulatory Limits A.
Fission and activation gases (1)
Calendar Quarter a.
5 mrad gamma b.
10 mrad beta (2) Calendar Year.
a.
10 mrad gamma b.
20 mrad beta B.
I-131, l-133, I-135, H-3 and particulates with half-lives greater than eight days (1)
Calendar Quarter a.
7.5 mrem to any organ (2)
Calendar Year a.
15 mrem to any organ C.
Liquid effluents (1)
Calendar Quarter a.
1.5 mrem to total body b.
5 mrem to any organ (2)
Calendar Year a.
3 mrem to total body b.
10 mrem to any organ
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Semi al Radioactive Effluent Relea's Report January 1,
1992 to June 30, 1992 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 concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved and entrained noble gases, the MPC shall be equal to 2.08-4 uCi/ml'.
3.
Average Energy (E)
N/A an SHNPP.
SHNPP determines doses and dose rate based on actual releases, not on an average energy value.
4.
Measurements and Approximations of Total Radioactivity A.
Fission and activation gases Measurements by continuous monitors of'ctivity 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 1
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.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 1 (Continued):
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 7. 20E+01 5.57E+04 min 1.16E+03 min (4)
Average time for a batch release 7.73E+02 min (5)
Minimum Time for a batch release 2.10E+01 min (6)
Average stream flow during periods of release 1.22E+04 gpm
, Gaseous 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 1.00E+00 1.54E+02 min 1.54E+02 min 1.54E+02 min 1.54E+02 min Abnormal Releases Liquid No abnormal liquid releases were made in the period.
Gaseous No abnormal gaseous releases were made in the period.
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Semiannual Radioactive Effluent Release Report.
January 1,
1992 to June 30, 1992 Appendix 2: Effluent and Waste Disposal Report Enclosure 1
LOWER LIMITS OF DETECTION (LLD)
LLD'S for Gaseous Effluents Nuclide uCi/cc Gross Alpha H-3 Ar-41 Kr-85m Kr-87 Xe-131m Xe-133m Xe-133 Xe-135 Xe-135m Xe-138 Kr-85 Kr-88 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 2.59E-15 6.76E-09 3.65E-08 1.81E-08 6.29E-08 7.64E-07 1.29E-07 6.56E-08 1.84E-08 2.18E-07 6.48E-06 1.17E-05 3.55E-08
- 2. 11E-14
- 1. 55E-14 1.63E-13 1.24E-14 1.21E-14
- 7. OOE-16 5.00E-16
- 8. 69E-14 8.99E-15 2.78E-14 5.36E-14 2.50E-14
- 1. 85E-14 9.13E-14
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1
LOWER LIMITS OF DETECTION (LLD)
'LD's for Liquid Effluents Nuclide uCi/ml Gross Alpha H-3 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Sr-92 Y-93 Zr-95 Nb-95 Nb-97 Mo-99
'Tc-99m Ag-110m Cd-109 Sn-113 Sb-124 Sb-125 I-131 I-132 I-133 Xe-131m Xe-133 Xe-133m Xe-135 Cs-134 Cs-137 Ba-140 La-140 La-142 Ce-141 Ce-144 3.09E-08 2.16E-06 2.62E-07 2.03E-08 1.50E-07 2.72E-08 3.44E-08 4.51E-08 3.00E-08 5.08E-08 5.00B-09 3.00E-09 5.93E-'08 1.33B-07 4.77E-08 8.85E-08 4.39E-08 1.44E-07 2.44E-08 1.86E-08 8.00E-07 4.77E-08 1.67E-08 1.01E-07 2.92E-08 3.29E-08 1.81E-08 1.19E-06 7.59E-08 1.94E-07 2.21E-08 1.68E-08 2.76E-08 5.54B-08 3.71E-08 7.83E-08 3.97E-08 2.20E-07 2/2
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 1A GASEOUS EFFLUENTS -
SUMMATION OF ALL RELEASES
- 1. Fission
& Activation Gases A.
Total Release B.
Average Release Rate for Period C.
Percent of Technical Specification Limit Ci 7.93 E+01 2.58 E+02 4.50 E+01 uCi/sec
'.02 E+01 3.28 E+01 3.76 E-01 4.66 E-01 Units Quarter Quarter Est.Total 1
2 Error
A.
Total Iodines B.
Average Release Rate for Period C.
Percent of Technical Specification Limit uCi/sec 8.58 E-06 1.40 E-06 2.00 E+01 1.10 E-06 1.80 E-07 See Footnote Below
- 3. Particulates A.
Particulates with Tl/2> 8 days B.
Average Release Rate for Period C.
Percent of Technical Specification Limit Ci uCi/sec 1.34 E-05 1.55 E-05 2.00 E+01 1.72 E-06 2.00 E-06 1.12 E-02 3.07 E-03 D.
Gross Alpha Radioactivity I
Ci
( LLD LLD
- 4. Tritium A.
Total Release B.
Average Release Rate for Period C.
Percent of Technical Specification Limit uCi/sec 3.55 E-04 2.11 E-04 3.00 E+01 4.56 E-05 2.71 E-05 See Footnote Below The Percent of Technical Specification limit applies to Zodines, Tritium, and Particulates
- combined, and is calculated using ODCM default Methodology and parameters.
The value for Zodines and Tritium is included in the Particulates summation.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES
- Noble Gas quantities apportioned as per GALE code.
- 1. Fission and Activation Gases NUCLIDES Units CONTINUOUS Q1 Q2 Q1 BATCH Q2 H-3 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ar-41 Kr-85 Kr-85m Kr-87 Kr-88 Totals
- 2. Iodines Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3.55E-04
<LLD 6.79E+01 1.13E+00 3.96E+00
<LLD 5.66E-01
<LLD
<LLD 1.70E+00 5.66E-01 2.83E+00 7.87E+01 2.11E-04
<LLD 2.36E+02 3.45E+00 1.21E+00
<LLD 1.72E+00
<LLD
<LLD 5.17E+00 1.72E+00 8.61E+00 2.58E+02
<LLD
<LLD 5.17E-01 1.10E-02 4.02E-02
<LLD
<LLD
<LLD 6.22E-02 4.07E-03 3.20E-04 3.65E-03
- 6. 39E-01
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD I-131 I-133 I-135 Totals
- 3. Particulates Ci Ci Ci Ci 7.86E-06 1.40E-06
- 7. 16E-07
<LLD
<LLD
<LLD 8.58E-06 1.40E-06
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD Gr. Alpha 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
<LLD 1.34E-05
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1.34E-05
<LLD
<LLD
<LLD,
<LLD
<LLD
<LLD 1.55E-05
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1.55E-05
<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 2/5
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 2A
- LIQUID EFFLUENTS SUMMATION OF ALL RELEASES
- 1. Fission 6 Activation Products Units Quarter 1
Quarter Est. Total 2
Error B.
C.
Total Release (not including tritium,
- gases, or alpha)
Average Diluted Concentration during Period Percent of Technical Specification Limit Ci uCi/ml 3.29 E-09 7.10 E-09 2'6 E-01 9.64 E-01 1.94 E-02 4.43 E-02 3.50 E+01
- 2. Tritium A.
Total Release B.
Average Diluted Concentration during Period C.
Percent of Technical Specification Limit Ci 3.20 E+02 2.39 E+02 3.50 B+01 uCi/ml 5.42 E-05 3.84 E-05 1.81 B+00 1.28 E+00
- 3. Dissolved and Entrained Gases A.
B.
C.
Total Release Ci Average Diluted Concentration during Period uCi/ml Percent of Technical Specification Limit 9.35 B-03 3.77 E-03 3.50 B+01 1.58 E-09 6.04 E-10 1.76 B-03 6.72 E-04
- 4. Gross Alpha Radioactivity Total Release LLD LLD 3.50 E+01.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 2A: LIQUID EFFLUENTS
- SUKQTION OF ALL RELEASES Units Quarter 1
Quarter Est. Total 2
Error
- 5. Volume of water released prior to dilution A. Batch Release liters 1.95 E+06 2.33 E+06 1.00 E+01 B. Continuous Release liters 8.04 E+06 4.21 E+07 1.00 E+01 C. Total Effluent Released liters 9.99 E+06 4.44 E+07 1.00 E+01
- 6. Volume of dilution water used during period liters 5.90 E+09 6.19 E+09 1.00 E+01
- 7. Total Volume Released (Releases
+ Dilution) liters 5.91 E+09 6.23 E+09 2/7
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 2B LIQUID EFFLUENTS
- 1. Fission and Activation Products Nuclides Released Units CONTINUOUS Ql Q2 Q1 BATCH Q2 Gr. Alpha H-3 Fe-55 Sr-89 Sr-90 Cr-51 Mn-54 Co-57 Co-58 Fe-59 Co-60 Sr-92 Zn-65 Y-93 Zr-95 Nb-95 Nb-97 Tc-99m Mo-99 Cd-109 Ag-110m Sn-113 Sb-124 Sb-125 I-131 I-132 I-133 Cs-134 Cs-137 Ce-141 Ce-144 Ba-140 La-140 La-142 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 (LLD 7.86E-02
<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 3.78E-01 (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 3.20E+02 4.66E-03 (LLD
<LLD
<LLD 8.96E-05 2.31E-05 9.95E-03 (LLD '
<LLD
<LLD
<LLD
<LLD 4.78E-06 (LLD
<LLD
<LLD 2.22E-04 9.78E-06
<LLD 3.24E-05 1.47E-03 4.53E-04
<LLD 1.68E-05
<LLD 5.85E-05
<LLD 3.71E-06
'.00E-OS (LLD
<LLD
<LLD 2.39E+02 3.78E-03 (LLD (LLD 2.37E-04 1.81E-04 6.23E-05 3.24E-02
<LLD 4.81E-03 9.53E-06
<LLD
<LLD
<LLD 2.41E-05
<LLD
<LLD
<LLD
<LLD 4.56E-05
<LLD 5.27E-05 2.64E-03 1.20E-05
<I LD 2.82E-06 (LLD 1.33E-06
<LLD
<LLD
<LLD
<LLD
<LLD Totals 7.86E-02
- 3. 78E-01 3.20E+02 2.39E+02 2/8
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2
- Effluents Released Table 2B
- LIQUID EFFLUENTS (continued)
- 2. Dissolved and Entrained Gases E
Nuclides Rele'ased Units CONTINUOUS Q1 Q2 Ql BATCH Q2 Xe-131m Xe-133 Xe-133m Xe-135 Ci Ci Ci Ci
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 2.288-05 9.218-03 1.09E-04 1.71E-05
<<LLD 3.728-03 2.108-05 2.94E-05 Totals Ci
<LLD
<LLD 9.358-03 3.778-03 2/9
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3
- Solid Waste Disposal Table 3
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1.Solid Waste Shipped for Burial or Disposal
( WASTE CLASS A )
A.
Type of Waste a.
Spent Resin, filter sludge, evaporator bottoms, etc.
Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 2
1.61 E+02 Ci 10%
4.01 E+00 m~
N/A Strong Tight Pack'age, 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 33 1.38 E+00 Ci 10%'.89 E+01 m'/A Strong Tight Package Dewatered ce Irradiated Components, Control Rods, etc.
No waste of this type shipped d.
Other (Describe)
No waste of this type shipped 2/10
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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 )
Estimate of Major Nuclide Composition (by type of Waste) a.
Spent Resin, filter sludge, evaporator bottoms, etc.
Nuclide H-3 C-14 Mn-54 Cs-137 Co-60 Fe-55 Ni-63 Pu-238 Pu-239 Am-241 Cm-243 Percent Total Composition
. 3.54 E-03 6.16 E-04 1.94 E-01 1.68 E-01 7.00 E+01 2.90 E+01
- 6. 15 E-01 3.60 E-02 3.01 E-02 5.06 E-02 3.36 E-01 Activity Ci 5.72 E-03 9.95 E-04 3.13 E-01 2.71 E-01 1.13 E+02 4.68 E+01 9.92 E-01 5.10 E-05 4.26 E-05 7.16 E-05
'4.76 E-04 b.
Dry Compressible
- Waste, Contaminated Equipment, etc.
(
DAW )
Nuclide H-3 C-14 Mn-54 Co-58 Co-60 Fe-55 Ni-63 Cs-137 Nb-95 Cs-134 Ce-144 Ni-59 Percent Total Composition 2.27 E-01 5.28 E-02 1.83 E+00 3.31 E+00 1.49 E+01 7.30 E+01 2.88 E+00 1.32 E-04 1.13 E+00 6.90 E-05 1.84 E-04 2.72 8+00 Activity Ci 3.12 E-03
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7.27 E-04 2.52 E-02 4.55 E-02 2.05 E-01 1.01 E+00 3.96 E-02 1.80 E-06 1.56 E-02 1.00 E-06 2.50 E-06 3.75 E-02 Irradiated Components, Control Rods, etc.
No waste of this type shipped Other (Describe)
No waste of this type shipped 2/11
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h Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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 )
Solid Waste Disposal Number of Shipments Mode of Transportation Destination
- 35 Truck Barnwell, S.C.
Both of the type 1.A.a shipments were made from the Harris Site.
All 33 of the type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee.
2/12
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r Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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 B
)
A.
Type of Waste a.
Spent Resin, filter sludge, evaporator bottoms, etc.
Number of Shipments Activity Shipped Estimated Total Error Quantity Shipped Solidification Agent Container Type Shipment Form 1
5.08 E+01 Ci 10%'.85 E+00 m~
N/A NRC Approved Package Dewatered b.
Dry Compressible
- Waste, Contaminated Equipment, etc.
(
DAW )
C.
d.
No waste of this type shipped Irradiated Components, Control Rods, etc.
I No waste of this type shipped Other (Describe)
No waste of this type shipped 2/13
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3
- Solid Waste Disposal Table 3
- SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 2.
Solid Waste Shipped for Burial or Disposal
( WASTE CLASS B
)
B.
Estimate of Major Nuclide Composition (by type of Waste) a.
Spent Resin, filter sludge, evaporator bottoms, etc.
Nuclide H-3 C-14 Mn-54 Co-58 Co-60 Fe-55 Ni-63 Cs-137 Sr-90 Pu-238 PQ-239 Am-241 Cm-243 Percent Total Composition 1.21 E-02 5.65 E-02 2.92 E+00 6.76 E+00 2.93 E+01 1.95 E+01 4.08 E+01 6.54 E-01 5.38 E-03 4.70 E-05 4.60 E-05 3.00 E-05 2.90 E-05 Activity Ci 6.15 E-03 2.87 E-02 1.48 E+00 3.43 E+00 1.49 E+01 9.88 E+00 2.07 E+01 3.32 E-01 2.73 E-03 2.39 E-05 2.36 E-05 1.51 E-05 1.49 E-05 b.
C.
Dry Compressible
- Waste, Contaminated Equipment, etc.
(
DAW )
No waste of this typed shipped Irradiated Components, Control Rods, etc.
No waste of this type shipped d.
Other (Describe)
No waste of this type shipped Solid Waste Shipped for Burial or Disposal
(
WASTE CLASS B)
C.
Solid Waste Disposal Number of Shipments Mode of Transportation Destination 1
Truck Barnwell, S.C.
2/14
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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 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.
2/1S
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 3
- Changes to Process Control Program (PCP)
Technical Specification 6.13 No changes to the Process Control Program (PCP) were made during this Report period.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 4
- Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specification 6.14 No changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.
As a result of the 1992 Land Use Census, Table 3.2-2, "Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant", will be changed.
These changes are shown in Appendix 5 and will be included in the next Report, after approval and incorporation into the ODCM.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 5
- Changes to the Environmental Monitoring Program Enclosure 1
- Environmental Monitoring Program Technical Specifications 3.11.2.3 3.12.1 3.12.l.c No changes to the Environmental Monitoring Program were made during this Report period.
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g I Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 5
- Changes to the Environmental Monitoring Program Enclosure 2
- Land Use Census Technical Specifications 3.12.2.a 3.12.2.b A Land Use Census was performed in June of 1992.
Changes have occurred in the locations of nearest garden and meat animal.
None of these changes necessitate a change to the SHNPP Environmental Monitoring Program.'hese changes will be included as changes to the ODCM in the next Report; Table 1 summarizes these locations and the changes.
Table 2 lists the kinds of meat animal at each meat animal location.
Table 1
Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant (miles)*
(Comparison of 1991/1992 Data)
Residence Milk Animal Garden Meat Animal Exclusion Boundary 1991 1992 1991 1992 1991 1992 1991 1992 N
1.32 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 NE ENE ESE SE SSE SSW SW WSW 1.33 1.33 1.33 1'3 1.33 1.33 1.33 1.36 1.33 1.33 1.33 1.33 1.33 1.8 2.3 3.6 1.9 2.7 4.3 4
~ 4 3.9 2.8 4.3 2.8 2.1 1.8 2.3 3.6 1.9 2.7 4.3 4.4 3.9 2.8 4.3 2.8 2.1 WW 1.7 2.3 3.8 4.7 4,4 4,4 4.6 3.9 2.8 4.3 2.9 2.9 1.7 2.3 3.8 4.7 4.4 4.6 3.9 2.8 4.3 2.9 2.1 2.2 2.2 4,4 4.3 4,4 4.3 2.9 2.9 3.5 3.1 2.3 2.3 1.26 1.26 2.1 2.1 1.5 3.8 1.7 3.8 1.7 3.8 1.7 3.8 1.7
- Distance estimates are g 0.1 miles except at the exclusion boundary.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 5
- Changes to the Environmental Monitoring Program Enclosure 2
- Land Use Census Technical Specifications 3.12.2.a 3.12.2.b Table 2
Meat Animal Type at Nearest Location to SHNPP (by Sector)
SECTOR N
ENE SE SSE Distance (miles) 2.2 3.5 2.3 2.2 4
4 4.3 Meat Type(s)
Beef/Hogs/Chickens Chickens Beef/Chickens Chickens/Hogs Chickens Chickens Owner
- Goodwin, W.
McGee, J.
James Rest Home
- Harris, H.
- Mclean, E.
- Taylor, M.
SSW SW WSW 2.9 Chickens Hill, A.
3.8 1.7 Hogs Beef
- Stone, D.
- Godwin, W.
5/3
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Semiannual Radioactive Effluent Release 'Report January 1,
1992 to June 30, 1992 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 the Report Period Effluent Monitor Days Inop I
Reason for Inoperability FT-21WL-6119 Waste Monitor Tank / Waste Evaporator Condensate Tank Discharge Flow Rate Monitor FT-*1WL-6193 Treated Laundry
& Hot Shower Tanks Discharge Flow Rate Monitor 121 128 Both of these flow indi.'cators have been inoperable because of a scaling problem between the readout and the associated measuring orifice.
A modification to correct this has been completed and the monitors have been returned to operability.
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 Appendix 6 (Continued): Additional Technical Specification Responsibilities Enclosure 2 :,Inoperability of Gaseous Effluent Monitors Technical Specification 3.3.3.11, Action a Monitors Out-of-Service
> 30 Days During the Report Period Effluent Monitor Days Inop Reason for Inoperability PNL-21AV-3509-SA PNL-21AV-3509 "1SA Plant Vent Stack Flow Rate Monitor RM-01TV-3536-1 Turbine Building Vent. Stack 3A Flow Rate Monitor 164 182 Problems with calibration of flow
~measurement system resulting in discrepancies between actual and expected flow rates.
Modification initiated to correct has been completed and equipment has been returned to operability.
Moisture interferences with the flow measurement system resulting in discrepancies between actual and expected flow rates. Modification initiated to correct.
PNL-1WV-3546 6
PNL-1WV-3546-1 WPB Vent Stack 5 Flow Rate Monitor PNL-1WV-3547 PNL-1WV-3547 - 1 WPB Vent Stack SA Flow Rate Monitor HAIC-21WG-1118BW Waste Gas Recombiner "B"
Outlet Gas Hydrogen Monitor OARC-21WG-1119B Waste Gas Recombiner "B"
Outlet Gas Oxygen Monitor 115 115 105 Problems with calibration of flow measurement system resulting in discrepancies between actual and expected flow rates.
Modification initiated to correct has been completed and equipment has been returned to operability.
Problems with calibration of flow measurement system resulting in discrepancies between actual and expected flow rates.
Modification initiated to correct has been completed and equipment has been returned to operability.
A modification to improve the reliability of the waste gas analyzers has been completed and the equipment has been returned to operability.
6/2
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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
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Semiannual Radioactive Effluent Release Report January 1,
1992 to June 30, 1992 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,
1992 to June 30, 1992 Appendix 7
- Major Modifications to Radwaste System Technical Specification 6.1S.1 No major modifications to the Radwaste System were made during this Report period.
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