ML18010A729

Semiannual Radioactive Effluent Release Rept,Jan-June 1992. W/920827 Ltr

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 !~~TRIBUTIOIX DEMOiTRATION SYSTEM REGULAlWY INFORMATION DISTRIBUTION SYSTEM (RIDS) tihEECI! DOCKET FACIL: 50-400 Shearon Harris Nuclear PoUjer Planti Unit li Carolina 05000000 AUTH. NAME AUTHOR AFFXLXATION VAUGHNi G. 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

SUBJECT:

"Shearon Harris Nuclear Power Plant Se Radioactive Effluent Release Repti Jan-June 1992. N/920827 DISTRIBUTION CODE: IE4SD COPIES RECEIVED: LTR TITLE: 50. 36a(a) (2) Semiannual E$ Iuent Releasef ENCL Reports J SIZE: 33 S

NOTES: Application for permit renewal filed. 05000400 I

REC IP IENT CQP IES REC IP IENT CQP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 3 3 PD2-1 PD 1 1 LEi N XNTERNAL: ACRS 1 NRR/DREP/PRPB11 G FILE 01 1 1 RGN2 DRSS/RPB FILE 02 1 1 EXTERNAL: BNL TICHLERi J03 1 1 EGkG SIMPSQNi F NRC PDR 1 1 R

I NOTP TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUivfEYT COYTROL 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, G. E. Vaughn Vice President Harris Nuclear Project MGW:dmw Attachment cc: Mr. S. D. Ebneter (NRC - RII)

Mr. N. B. Le (NRR)

Mr. J. E. Tedrow (NRC - SHNPP) i l0 0 5 0 MES+

MEM/HO-920122/1/OS1 iaoiso 9ap9p roan o 05000400 r PDR R .

ADOCK

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Carolina Power S Light Shearon Harris Nuclear Power Plant License No.'PP-063 SE AUANNUALRIIDKOAUTIVEEPPLUENT 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 Page No.

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

1. Lower Limits of Detection (LLD's) 2/1

2. Effluents Released 2/3

3. Solid Waste Disposal 2/11 Appendix 3. Changes to Process Control Program (PLP) 3/1 Appendix 4. Changes to Offsite Dose Calculation Manual (ODCM) 4/1 Appendix 5. Changes to the Environmental Monitoring Program

1. Environmental Monitoring Program 5/1

2. Land Use Census 5/2 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

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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 (SHNPP) Operating License No. NPF-63 't Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Plant 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 7 . 20E+01 (2) Total time period for batch releases 5.57E+04 min (3) Maximum time of a batch release 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 1.00E+00 (2) Total time period for batch releases 1.54E+02 min (3) Maximum time of a batch release 1.54E+02 min (4) Average time for a batch release 1.54E+02 min (5) Minimum Time for a batch release 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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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 2.59E-15 H-3 6.76E-09 Ar-41 3.65E-08 Kr-85m 1.81E-08 Kr-87 6.29E-08 Xe-131m 7.64E-07 Xe-133m 1.29E-07 Xe-133 6.56E-08 Xe-135 1.84E-08 Xe-135m 2.18E-07 Xe-138 6.48E-06 Kr-85 1.17E-05 Kr-88 3.55E-08 I-131 2. 11E-14 I-133 1. 55E-14 I-135 1.63E-13 Mn-54 1.24E-14 Co-58 1.21E-14 Fe-59 5. 81E-14 Co-60 2.48E-14 Zn-65 3 '8E-14 Sr-89 7. OOE-16 Sr-90 5.00E-16 Mo-99 8. 69E-14 Cs-134 8.99E-15 Cs-137 2.78E-14 Ba-140 5.36E-14 La-140 2.50E-14 Ce-141 1. 85E-14 Ce-144 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) for Liquid Effluents 'LD's Nuclide uCi/ml Gross Alpha 3.09E-08 H-3 2.16E-06 Cr-51 2.62E-07 Mn-54 2.03E-08 Fe-55 1.50E-07 Co-57 2.72E-08 Co-58 3.44E-08 Fe-59 4.51E-08 Co-60 3.00E-08 Zn-65 5.08E-08 Sr-89 5.00B-09 Sr-90 3.00E-09 Sr-92 5.93E-'08 Y-93 1.33B-07 Zr-95 4.77E-08 Nb-95 8.85E-08 Nb-97 4.39E-08 Mo-99 1.44E-07

'Tc-99m 2.44E-08 Ag-110m 1.86E-08 Cd-109 8.00E-07 Sn-113 4.77E-08 Sb-124 1.67E-08 Sb-125 1.01E-07 I-131 2.92E-08 I-132 3.29E-08 I-133 1.81E-08 Xe-131m 1.19E-06 Xe-133 7.59E-08 Xe-133m 1.94E-07 Xe-135 2.21E-08 Cs-134 1.68E-08 Cs-137 2.76E-08 Ba-140 5.54B-08 La-140 3.71E-08 La-142 7.83E-08 Ce-141 3.97E-08 Ce-144 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 Units Quarter Quarter Est.Total 1 2 Error

1. Fission & Activation Gases A. Total Release Ci 7.93 E+01 2.58 E+02 4.50 E+01 B. Average Release Rate for Period uCi/sec '.02 E+01 3.28 E+01 C. Percent of Technical Specification Limit 3.76 E-01 4.66 E-01

2. Iodines (I-131, I-133, I-135)

A. Total Iodines 8.58 E-06 1.40 E-06 2.00 E+01 B. Average Release Rate for Period uCi/sec 1.10 E-06 1.80 E-07 C. Percent of Technical Specification Limit See Footnote Below

3. Particulates A. Particulates with Tl/2> 8 days Ci 1.34 E-05 1.55 E-05 2.00 E+01 B. Average Release Rate for Period uCi/sec 1.72 E-06 2.00 E-06 C. Percent of Technical Specification Limit 1.12 E-02 3.07 E-03 D. Gross Alpha Radioactivity Ci ( LLD LLD I

4. Tritium A. Total Release 3.55 E-04 2.11 E-04 3.00 E+01 B. Average Release Rate for Period uCi/sec 4.56 E-05 2.71 E-05 C. Percent of Technical Specification Limit 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 CONTINUOUS BATCH NUCLIDES Units Q1 Q2 Q1 Q2 H-3 Ci 3.55E-04 2.11E-04 <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD Xe-133 Ci 6.79E+01 2.36E+02 5.17E-01 <LLD Xe-133m Ci 1.13E+00 3.45E+00 1.10E-02 <LLD Xe-135 Ci 3.96E+00 1.21E+00 4.02E-02 <LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 Ci 5.66E-01 1.72E+00 <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD 6.22E-02 <LLD Kr-85m Ci 1.70E+00 5.17E+00 4.07E-03 <LLD Kr-87 Ci 5.66E-01 1.72E+00 3.20E-04 <LLD Kr-88 Ci 2.83E+00 8.61E+00 3.65E-03 <LLD Totals Ci 7.87E+01 2.58E+02 6. 39E-01 <LLD

2. Iodines I-131 Ci 7.86E-06 1.40E-06 <LLD <LLD I-133 Ci 7. 16E-07 <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD <LLD Totals Ci 8.58E-06 1.40E-06 <LLD <LLD

3. Particulates Gr. Alpha Ci <LLD <LLD <LLD <LLD 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 1.34E-05 1.55E-05 <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 1.34E-05 1.55E-05 <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 Units Quarter Quarter Est. Total 1 2 Error

1. Fission 6 Activation Products Total Release (not including tritium, Ci 1.94 E-02 4.43 E-02 3.50 E+01 gases, or alpha)

B. Average Diluted Concentration during Period uCi/ml 3.29 E-09 7.10 E-09 C. Percent of Technical Specification Limit 2 '6 E-01 9.64 E-01

2. Tritium A. Total Release Ci 3.20 E+02 2.39 E+02 3.50 B+01 B. Average Diluted Concentration during Period uCi/ml 5.42 E-05 3.84 E-05 C. Percent of Technical Specification Limit 1.81 B+00 1.28 E+00

3. Dissolved and Entrained Gases A. Total Release Ci 9.35 B-03 3.77 E-03 3.50 B+01 B. Average Diluted Concentration during Period uCi/ml 1.58 E-09 6.04 E-10 C. Percent of Technical Specification Limit 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 Quarter Est. Total 1 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 liters 5.90 E+09 6.19 E+09 1.00 E+01 used during period

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 CONTINUOUS BATCH Released Units Ql Q2 Q1 Q2 Gr. Alpha Ci (LLD <LLD (LLD <LLD H-3 Ci 7.86E-02 3.78E-01 3.20E+02 2.39E+02 Fe-55 Ci <LLD (LLD 4.66E-03 3.78E-03 Sr-89 Ci <LLD <LLD (LLD (LLD Sr-90 Ci <LLD <LLD <LLD (LLD Cr-51 Ci <LLD <LLD <LLD 2.37E-04 Mn-54 Ci <LLD <LLD 8.96E-05 1.81E-04 Co-57 Ci <LLD <LLD 2.31E-05 6.23E-05 Co-58 Ci <LLD <LLD 9.95E-03 3.24E-02 Fe-59 Ci <LLD (LLD (LLD ' <LLD Co-60 Ci <LLD <LLD '1E-03 4.81E-03 Sr-92 Ci <LLD <LLD <LLD 9.53E-06 Zn-65 Ci "<LLD <LLD <LLD <LLD Y-93 Ci <LLD (LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD 4.78E-06 2.41E-05 Nb-97 Ci <LLD <LLD (LLD <LLD Tc-99m Ci (LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Cd-109 Ci <LLD (LLD 2.22E-04 <LLD Ag-110m Ci <LLD , <LLD 9.78E-06 4.56E-05 Sn-113 Ci (LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD 3.24E-05 5.27E-05 Sb-125 Ci <LLD <LLD 1.47E-03 2.64E-03 I-131 Ci <LLD <LLD 4.53E-04 1.20E-05 I-132 Ci (LLD (LLD <LLD <I LD I-133 Ci <LLD <LLD 1.68E-05 2.82E-06 Cs-134 Ci <LLD <LLD <LLD (LLD Cs-137 Ci <LLD <LLD 5.85E-05 1.33E-06 Ce-141 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD 3.71E-06 <LLD Ba-140 Ci <LLD <LLD '.00E-OS

<LLD La-140 Ci <LLD <LLD (LLD <LLD La-142 Ci <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 CONTINUOUS BATCH Rele'ased Units Q1 Q2 Ql Q2 Xe-131m Ci <LLD <LLD 2.288-05 <<LLD Xe-133 Ci <LLD <LLD 9.218-03 3.728-03 Xe-133m Ci <LLD <LLD 1.09E-04 2.108-05 Xe-135 Ci <LLD <LLD 1.71E-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 2 Activity Shipped 1.61 E+02 Ci Estimated Total Error 10%

Quantity Shipped 4.01 E+00 m~

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

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

Number of Shipments 33 Activity Shipped 1.38 E+00 Ci Estimated Total Error 10%'.89 Quantity Shipped E+01 Solidification Agent m'/A Container Type Strong Tight Package Shipment Form 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.

Percent Total Activity Nuclide Composition Ci H-3 . 3.54 E-03 5.72 E-03 C-14 6.16 E-04 9.95 E-04 Mn-54 1.94 E-01 3.13 E-01 Cs-137 1.68 E-01 2.71 E-01 Co-60 7.00 E+01 1.13 E+02 Fe-55 2.90 E+01 4.68 E+01 Ni-63 6. 15 E-01 9.92 E-01 Pu-238 3.60 E-02 5.10 E-05 Pu-239 3.01 E-02 4.26 E-05 Am-241 5.06 E-02 7.16 E-05 Cm-243 3.36 E-01 '4.76 E-04

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

Percent Total Activity Nuclide Composition Ci H-3 2.27 E-01 3.12 E-03 ~

C-14 5.28 E-02 7.27 E-04 Mn-54 1.83 E+00 . 2.52 E-02 Co-58 3.31 E+00 4.55 E-02 Co-60 1.49 E+01 2.05 E-01 Fe-55 7.30 E+01 1.01 E+00 Ni-63 2.88 E+00 3.96 E-02 Cs-137 1.32 E-04 1.80 E-06 Nb-95 1.13 E+00 1.56 E-02 Cs-134 6.90 E-05 1.00 E-06 Ce-144 1.84 E-04 2.50 E-06 Ni-59 2.72 8+00 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 *35 Mode of Transportation Truck Destination 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.

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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 B )

A. Type of Waste

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

Number of Shipments 1 Activity Shipped 5.08 E+01 Ci Estimated Total Error 10%'.85 Quantity Shipped E+00 m~

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

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

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

I No waste of this type shipped

d. Other (Describe)

No waste of this type shipped 2/13

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e 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.

Percent Total Activity Nuclide Composition Ci H-3 1.21 E-02 6.15 E-03 C-14 5.65 E-02 2.87 E-02 Mn-54 2.92 E+00 1.48 E+00 Co-58 6.76 E+00 3.43 E+00 Co-60 2.93 E+01 1.49 E+01 Fe-55 1.95 E+01 9.88 E+00 Ni-63 4.08 E+01 2.07 E+01 Cs-137 6.54 E-01 3.32 E-01 Sr-90 5.38 E-03 2.73 E-03 Pu-238 4.70 E-05 2.39 E-05 PQ-239 4.60 E-05 2.36 E-05 Am-241 3.00 E-05 1.51 E-05 Cm-243 2.90 E-05 1.49 E-05

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

No waste of this typed shipped C. 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 1 Mode of Transportation Truck Destination Barnwell, S.C.

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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.

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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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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 1.33 1.8 1.8 1.7 1.7 3.5 3.1 NE 1.33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.33 3.6 3.6 3.8 3.8 1 '3 1.9 1.9 4.7 4.7 2.2 2.2 ESE 1.33 2.7 2.7 WW 4,4 4,4 4,4 SE 1.33 4.3 4.3 4,4 4.4 4.3 4.3 SSE 1.33 4 ~4 4.4 4.6 4.6 1.36 SSW 1.33 3.9 3.9 3.9 3.9 SW 1.33 2.8 2.8 2.8 2.8 WSW 1.33 4.3 4.3 4.3 4.3 1.33 2.8 2.8 2.9 2.9 2.9 2.9 1.33 2.1 2.1 2.9 2.1 1.26 2.1 2.1 3.8 3.8 3.8 3.8 1.26 1.5 1.7 1.7 1.7 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 Distance Meat Type(s) Owner (miles)

N 2.2 Beef/Hogs/Chickens Goodwin, W.

3.5 Chickens McGee, J.

2.3 Beef/Chickens James Rest Home ENE 2.2 Chickens/Hogs Harris, H.

4 4 Chickens Mclean, E.

SE 4.3 Chickens Taylor, M.

SSE SSW SW WSW 2.9 Chickens Hill, A.

3.8 Hogs Stone, D.

1.7 Beef Godwin, W.

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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 Days I Effluent Monitor Inop Reason for Inoperability FT-21WL-6119 Both of these flow indi.'cators have Waste Monitor Tank / Waste been inoperable because of a scaling Evaporator Condensate Tank 121 problem between the readout and the Discharge Flow Rate Monitor associated measuring orifice. A modification to correct this has been FT-*1WL-6193 completed and the monitors have been Treated Laundry & Hot returned to operability.

Shower Tanks Discharge Flow 128 Rate Monitor

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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 Days Effluent Monitor Inop Reason for Inoperability PNL-21AV-3509-SA Problems with calibration of flow PNL-21AV-3509 "1SA ~

measurement system resulting in Plant Vent Stack Flow Rate 164 discrepancies between actual and Monitor expected flow rates. Modification initiated to correct has been completed and equipment has been returned to operability.

RM-01TV-3536- 1 Moisture interferences with the flow Turbine Building Vent. Stack measurement system resulting in 3A Flow Rate Monitor 182 discrepancies between actual and expected flow rates. Modification initiated to correct.

PNL-1WV-3546 6 Problems with calibration of flow PNL- 1WV-3546- 1 measurement system resulting in WPB Vent Stack 5 Flow Rate 115 discrepancies between actual and Monitor expected flow rates. Modification initiated to correct has been completed and equipment has been returned to operability.

PNL- 1WV-3547 & Problems with calibration of flow PNL- 1WV-3547 - 1 measurement system resulting in WPB Vent Stack SA Flow Rate 115 discrepancies between actual and Monitor expected flow rates. Modification initiated to correct has been completed and equipment has been returned to operability.

HAIC-21WG-1118BW A modification to improve the Waste Gas Recombiner "B" 105 reliability of the waste gas Outlet Gas Hydrogen Monitor analyzers has been completed and the equipment has been returned to OARC-21WG-1119B operability.

Waste Gas Recombiner "B" Outlet Gas Oxygen Monitor 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.

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0 fi 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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