ML18009A637

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Semiannual Radioactive Effluent Release Rept Jan-June 1990. W/900830 Ltr
ML18009A637
Person / Time
Site: Harris Duke energy icon.png
Issue date: 06/30/1990
From: Barnes H, Pollard A, Richey R
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HO-900130-(O), NUDOCS 9009060056
Download: ML18009A637 (66)
v • d • e


Text

AC(:ELERATED DIS BUTION DEMONSTRATION SYSTEM q r REGULATORY INFORMATION DISTRXBUTXON SYSTEM (RIDS)

ACCESSION NBR:9009060056 DOC.DATE'OTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit, 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION BARNES,H.E. Carolina Power S Light Co.

POLLARD,A.D. Carolina Power S Light Co.

RXCHEY,R.B. Carolina Power S Light Co. R RECIP.NAME RECIPIENT AFFXLIATION

SUBJECT:

"Semian active Effluent Release Rept Jan-June 1990." W/900830 tr. D DISTRIBUTION CODE: SD COPIES RECEIVED:LTR TITLE: 50.36a(a)(2) Semiannual Effluent Releas~e Reports A ENCL SXZE:

NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 3 3 PD2-1 PD 1 1 D BECKER,D 1 1 INTERNAL: ACRS 1 1 AEOD/DSP/TPAB 1 1 I 8H~A V 1 1 NRR/DREP/PRPB11 2 2 EG FILE 01 1 1 RES BROOKS i B 1 1 G DRSS/RPB 2 2 RGN2 FILE 02 1 1 EXTERNAL: BNL TICHLER, J03 1 1 EGGG SIMPSON,F 2 2 NRC PDR 1 1 D

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19

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a Caroljna Power & Ught Company P. O. Box 165 ~ New Hill, N. C. 27562 A. B. RICHEY Manager Harris Nuclear Project AUG 3 0 1990 Letter Number'. HO-900130 (0)

U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk

.Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO ~ 50-400 LICENSE NO. NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen.'n 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, 1990 through June 30, 1990.

Very truly yours, R. B. Richey, Manager Harris Nuclear Project RBR:dw Attachment cc'Mr. R. A. Becker (NRR)

Mr. S. D. Ebneter (NRC RII)

Mr. J. E. Tedrow (NRC SHNPP)

FD OO>~ 9OO63O ADOCK OgOOOqOO R

POC MEM/H0-9001300/1/OS1

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Carolina Power & Light Shearon Harris Nuclear Power Plant License No. NPF-063 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January. 1, 1990 to June,30, 1990 Prepared by:

Env'nmental & Radiation Control Reviewed by: rh Vu Project Specialist - Radiation Control Reviewed by:

Manager Environmental & Radiation Control Approved by:

ant General Manager

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Table of Contents Page No.

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

1. Lover 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 4/1 Manual (ODCM)

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, 1990 to June 30, 1990 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Project (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, 1990 to June 30, 1990. During this period, the plant was in Cycle 3 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 wefe based on hourly average stack monitor readings (in uCi/cc) and stack flow rate estimates based on design fan flow rates. No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases. Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM. Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.

No activity above background was detected in any continuous liquid release pathway. Therefore, the reported activities are the summation of nuclides in batch releases only.

A total of 33.86 m of solid waste, containing 4.933 Ci of radioact)vity, was shipped for burial during this Report period, compared with 101.11 m and 20.86 Ci shipped during the previous Report period.

Two unplanned gaseous releases occurred during this Report period. The first release occurred because of an improper valve line-up in the waste gas system. Approximately 2.38 Ci of noble gases were released, Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CFR50 (total dose)

Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Discussion (continued) limits at the site boundary. The highest dose was calculated to be approximately 0.012X of its respective limit.

The second release occurred when a gas trap failed on a Waste Gas Decay Tank drain line during a routine draining of the tank. Approximately 0.0468 Ci of noble gas were released. Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CPR50 (total dose) limits at the site boundary. The highest dose was calculated to be approximately 0.001X of its respective limit.

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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. I Appendix 5:

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 be revised in the next Report Period.

To determine whether any of the new special locations yielded calculated doses greater than the locations previously used, the 1990 land use data was coupled with SHNPP 1989 meteorology, and dose calculations were performed by the GASPAR program using the GALE source terms provided in Table 3.2-1 of the ODCM. No significant differences in estimated doses occurred as a result of the 1990 changes in the locations of the nearest resident, garden, or meat animal.

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. Modifications performed to the Radiation Monitoring System have improved system reliability.

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

Appendix 7:

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

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. 0 .. 0 Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1) Calendar Quarter
a. 7.5 mrem to any organ (2) Calendar Year
a. 15 mrem to any organ C. Liquid effluents (1) Calendar Quarter
a. 1.5 mrem to total body
b. 5 mrem to any organ (2) Calendar Year
a. 3 mrem to total body
b. 10 mrem to any organ
2. 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

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 1 (Continued): Supplemental Information

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

B. I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days.

1500 mrem/year to any organ C. Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 uCi/ml.

3. Average Energy (E)

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

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

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

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

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

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.ib e Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 1 (Continued): Supplemental Information

5. Routine Batch Releases A. Liquid (1) Number of batch releases: 8.90 E+01 (2) Total time period for batch releases: 5.52 E+04 min.

(3) Maximum time for a batch release: 8.44 E+02 min.

(4) Average time for a batch release: 6.20 E+02 min.

(5) Minimum time for a batch release: 2.00 E+00 min.

(6) Average stream flov during periods of release: 6.31 E+03 gpm B. Gaseous (1) Number of batch releases: 2.60 E+01 (2) Total time period for batch releases: 1.93 E+04 min.

(3) Maximum time for a batch release: 3.01 E+03 min.

(4) Average time for a batch release: 7.44 E+02 min.

(5) Minimum time for a batch release: 3.00 E+00 min.

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0 Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 1 (Continued): Supplemental Information

6. Abnormal Releases A. Liquid No abnormal liquid releases were made in the period.

B. Gaseous Two unplanned releases occurred during this Report period.

The first release occurred between May 3, 1990 and May 6, 1990, when an incorrect valve line-up allowed gas to escape from the Waste Gas Processing System. Approximately 2.38 E+00 Ci of noble gas was released to the Waste Processing Building (WPB)

Vent Stack 5.

The second release occurred on June 17, 1990 when a gas

'rap failed on the drain line during a routine draining of a waste gas decay tank. This allowed approximately 4.68 E-02 Ci of Noble Gas to escape to the WPB, where it was picked up by WPB ventilation and exhausted to atmosphere.

Both releases were monitored by WPB Vent Stack 5 radiation monitors. Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CFR50 (total dose) limits at the site boundary and the highest doses were calculated to be approximately 0.012X and of 0.001/ of their respective limit for the first and second release, respectively. Both of the release source terms have been added to the BATCH Mode releases in Appendix 2, Enclosure 2, Table 1.

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Semiannua Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2: Effluent and Waste Disposal Report Enclosure 1 LOWER LIMIT OP DETECTION (LLD)

1. LLD's for Gaseous Effluents NUCLIDE LLD ( uCi/cc)

H 3 1.01 E-08 Ar-41 4.42 E Cr-51 1.08 E-13 Mn-54 1.56 E-14 Co-58 1.54 E-14 Fe-59 3.72 E-14 Co-60 3.62 E-14 Zn-65 5.94 E-14 Kr-85 8 '6 E-06 Kr-85m 2.17 E-08 Kr-87 3.82 E-08 Kr-88 2.63 E-08.

Sr-89 7 '1 E-16 Sr-90 4.99 E-16 Nb-95 1.43 E-14 Mo-99 1.09 E-13 I -131 1.19 E-14 Xe-131m 7,78 E-07 I -132 3,84 E-14 I -133 1.82 E-13 Xe-133 4.48 E-08 .

Xe-133m 1,60 E-07 Cs-134 1.12 E-14 I -135 9.64 E-10 Xe-135 1.93 E-08 Xe-135m 4.88 E-07 Cs-137 1.42 E-14 Xe-138 9.68 E-07 Ba-140 3.81 E-14 La-140 4.27 E-14 Ce-141 1.70 E-14 Ce-144 7,48 E-14 Gross Alpha 4.28 E-15

~ ' t Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1 : LOWER LIMIT OF DETECTION (LLD)

2. LLD's for Liquid Effluents NUCLIDE LLD(uCi/ml)

H - 3 3.22 E-06 Be- 7 2.77 e-07 Na- 24 4.63 E-08 Ar- 41 6.61 E-08 Cr- 51 2.99 E-07 Mn- 54 2.86 E-08 Fe-'5 ,1.37 E-07 Co- 57 1.69 E-08 Co- 58 2.80 E-08 Fe- 59 6.47 E-08 Co- 60 4.31 E-08 Zn- 65 7.28 E-08 Kr- 85m 3.78 E-08 Sr- 89 1.57 E-09 Sr- 90 1.43 E-09 Zr- 95 '4.72 E-08 Nb- 95 5.29 E-08 Nb- 97 4.19 E-08 Mo- 99 , 2.02 E-07 Tc- 99m 1.65 E-08 Ag-110m 2.43 E-08 Sn-113 3.63 E-08 Sb-122 3.98 E-08 Sb-124 1.62 E-08 Sb-125 7.17 E-08 Te-131 4.68 E-08 I -131 3.49 E-08 I -132 3.20 E-08 I -133 2.41 E-08 I 134 3.49 E-08 Xe-131m 1.51 E-06 Xe-133 9.45 E-08 Xe-133m 2.28 E-07 Xe-135 4.03 E-08 Cs-134 2.35 E-08 Cs-137 2.93 E-08 Cs-138 2.24 E-07 Ba-140 7.51 E-08 La-140 5.77 E-08 Ce-141 3.54 E-08 Ce-144 1.97 E-07 Pr-144 2.31 E-06 Hf-181 2.87 E-08 Gross Alpha 6.18 E-08 2/2

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Semiannua Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Paste Disposal Report Enclosure 2 : Effluents Released Table 1A : GASEOUS EFFLUENTS, SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 1 2 Error X Fission & Activation Gases A. Total Release 1.18 E+02 1.65 E+02 4.50 E+01 B. Average Release Rate for Period uCi/sec 1.52 E+01 2.09 E+01 C. Percent of Technical Specification Limit'i X 4.00 E-01 5.49 E-01

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

A. Total Iodines Ci 0.00 E+00 0.00 E+00 2.00 E+01 B. Average Release Rate for Period C. Percent of Technical Specification Limit / 0.00 E+00 0.00 E+00

3. Particulates A. Particulates with T1/2) 8 days Ci 1,68 E-05 8.99 E-06 2.00 E+01 B. Average Release Rate for Period uCi/sec 2 '6 E-06 1.14 E-06 C. Percent of Technical Sp'ecification Limit X 1.97 E-03 1.05 E-03 D. Gross Alpha Radioactivity Ci 0.00 E+00 0.00 E+00
4. Tritium A. Total Release'.

Ci 0.00 E+00 0.00 E+00 3.00 E+01 Average Release Rate for Period uCi/sec 0.00 E+00 0.00 E+00 C. Percent of Technical Specification Limit X 0.00 E+00 0.00 E+00 2/3

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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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Semiannua Radioactive Effluent Release Report I I January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 1C : GASEOUS EFFLUENTS GROUND LEVEL RELEASES

1. Fission and Activation Gases Continuous Mode
  • Batch Mode **

Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 H-3 Ci < LLD < LLD < LLD < LLD Ar-41 Ci . < LLD < LLD 5.30 E-02 7.80 E-03 Kr-85 Ci < LLD < LLD 1.40 E-02 6.56 E-02 Kr-85m Ci 2.55E+00 3.49E+00 < LLD 3.04 E-02 Kr-,87 Ci 8.48E-01 1.16E+00 < LLD 1.03 E-02 Kr-88 Ci 4.24E+00 5.81E+00 < LLD 4.07 E-02 Xe-131m Ci < LLD < LLD < LLD 1.35 E-03 Xe-133 Ci 1.02E+02 1.40E+02 1.96 E-02 1.70 E+00 Xe-133m Ci 1.70E+00 2.33E+00 < LLD 4.14 E-02 Xe-135 Ci 5.94E+00 8.14E+00 3.'45 E-04 6.69 E-01 Xe-135m Ci < LLD < LLD < LLD 2.81 E-03 Xe-138 Ci 8.48E-01 1.16E+00 < LLD < LLD Total Ci 1 '8E+02 1.62E+02 8.69 E-02 2.57 E+00

  • Noble Gas quantities apportioned as per GALE code.
    • Includes the activity from both routine and unplanned releases.
2. Iodines Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 I-131 Ci < LLD < LLD < LLD < LLD I-132 Ci < LLD < LLD < LLD < LLD I-133 Ci < LLD < LLD < L'LD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD < LLD < LLD h

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Semiannual'adioactive 0

Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 1C (Continued): GASEOUS EFFLUENTS GROUND LEVEL RELEASES

3. Particulates Continuous Mode Batch Mode Nuclides Units Quarter . Quarter Quarter Quarter Released 1 2. 1 2 Cr-51 Ci < LLD < LLD < LLD < LLD Mn-54 Ci < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD Co-60 Ci 1.68E-05 8.99E-06 < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Sr-89 Ci < LLD < LLD < LLD < LLD Sr-90 Ci < LLD < LLD < LLD < LLD Nb-95 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 Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Gross Alpha Ci < LLD < LLD < LLD- < LLD Total Ci 1.68E-05 8.99E-06 < LLD < LLD 2/6

h Semiannual Radioactive Effluent Release Report January.1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released Table 2A : LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 1 2 Error /

1. Fission & Activation Products A. Total Release (not including tritium, Ci 1.55 E-01 5.36 E-02 3.50 E+01 gases, or alpha)

B. Average Diluted Concentration during Period uCi/ml 4.97 E-08 1.72 E-08 C. Percent of Technical Specification Limit  %%u 7.24 E-02 3.22 E-02

2. Tri tium A. Total Release Ci 3.47 E+01 1.69 E+02 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 1.11 E-05 5.39 E-05 C. Percent of Technical Specification Limit 3.71 E-01 1.80 E+00
3. Dissolved and Entrained Gases A. Total Release Ci 1.76 E-04 1.56 E-04 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 5.64 E-11 4.98 E-11 C. Percent of Technical Specification Limit 2.82 E-05 2.49 E-05
4. Gross Alpha Radioactivity Total Release Ci < LLD < LLD 3.50 E+01 2/7

I Semiannual Radioactive Effluent Release Report January 1, 1990'to June 30, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2 : Effluents Released

,Table 2A  : LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Uni ts Quarter 'uarter Est: Total 1 2 Error

5. Volume of water released prior to dilution A. Batch Release liters 3.16 E+06 2.49 E+06 1.00 E+01 B. Continuous Release liters 1.69 E+07 1.56 E+07 1.00 E+01
6. Volume of dilution water liters 3,10 E+09 3.12 E+09 1.00 E+01 used during period
7. Total Volume of water liters 3.12 Ew09 3.14 E+09 1.00 E+01 2/8

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B : LIQUID EFFLUENTS Fission and Activation Products Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 H-3 Ci < LLD < LLD 3.47 E+01 1.69 E+02 Be-7 Ci < LLD < LLD 8.03 E-05 < LLD Na-24 Ci < LLD < LLD < LLD < LLD Cr-51 Ci < LLD < LLD 1.08 E-03 6.12 E-05 Mn-54 Ci < LLD < LLD 1.63 E-03 2.92 E-04 Fe-55 Ci < LLD < LLD 1.07 E-02 7.14 E-03 Co-57 Ci < LLD < LLD 5.42 E-04 1.88 E-04 Co-58 Ci < LLD < LLD 1.22 E-01 3.59 E-02 Fe-59 Ci < LLD < LLD 5.89 E-05 < LLD Co-60 Ci < LLD < LLD 1.06 E-02 7.74 E-03 Zn-65 Ci < LLD < LLD 1.06 E-04 < LLD Sr-89 Ci < LLD < LLD 1.04 E-05 5.84 E-06 Sr-90 Ci < LLD < LLD 2.41 E-05 < LLD Y-91m Ci < LLD < LLD < LLD < LLD Zr/Nb-95 Ci < LLD < LLD 1.63 E-04 < LLD Nb-97 Ci < LLD < LLD 1.45 E-05 < LLD Mo-99 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD 1.40 E-05 < LLD Ag-110m Ci < LLD < LLD 6.48 E-06 4.86 E-05 Sn-113 Ci < LLD < LLD < LLD < LLD Sb-122 Ci < LLD < LLD 7.08 E-06 4.61 E-06 Sb-124 Ci < LLD < LLD < LLD < LLD Sb-125 Ci < LLD < LLD 6.37 E-03 9.75 E-04 I -131 Ci < LLD < LLD 8.96 E-06 5.84 E-05 Te-131 Ci < LLD < LLD < LLD 1 '6 E-04 I -132 Ci < LLD < LLD < LLD < LLD I -133 Ci < LLD < LLD < LLD < LLD I -134 Ci < LLD < LLD < LLD 1.25 E-05 Cs-134 Ci < LLD < LLD 1.93 E-04 4.39 E-04 Cs-137 Ci < LLD < LLD 2.45 E-04 4.83 E-04 Cs-138 Ci < LLD < LLD < LLD < LLD Ba/La-140 Ci < LLD < LLD < LLD < LLD, Ce-141 Ci < LLD < LLD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Pr-144 Ci < LLD < LLD 8.97 E-04 < LLD Hf-181 Ci < LLD < LLD 6.19 E-06 1.24 E-05 Gross Alpha Ci < LLD < LLD < LLD < LLD Total Ci < LLD < LLD 3.49 E+01 1.69 E+02 2/9

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2 : Effluents Released Table 2B (Continued)  : LIQUID EFFLUENTS

2. Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter

' Quarter Released 1 2 2 Ar-41 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD Xe-133 Ci < LLD < LLD 1.55 E-04 1.28 E-04 Xe-133m Ci < LLD < LLD < LLD < LLD Xe-135 Ci < LLD < LLD 2.09 E-05 2.81 E-05 Total Ci < LLD

' LLD 1.'76 E-04 1.56 E-04 2/10

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 3 : Solid Vaste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

6 month Est. Total Solid. Cont. No.

A. Type of waste Units Period Error (/') Agent Type Form Ship a ~ Spent Resin, filter m3 5.53 E+00 1.00 E+01 N/A STP D 1 sludge, evaporator bottoms, etc. Ci 3.35 E+00

b. Dry Compressible m3 2.76 E+01 1.00 E+01 N/A STP D 14 Vaste, contaminated equipment, etc. Ci 1.58 E+00
c. Irradiated Components, m3 No waste of this type shipped.

Control-rods, etc. Ci

, d. Other (Describe) m3 No waste of this type shipped.

Ci

  • STP Strong Tight Package
    • S Solidified D Dewatered

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SemiannUal Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

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

Only nuclides with ) 0.1/ composition are listed.

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Type of Percent Total Activity Waste Nuclide Composition Ci a ~ Mn-54 2.55 E+00 8.55 E-02 Fe-55 4.33 E+01 1.45 E+00 Co-58 3.94 E+01 1.32 E+00 Co-60 5.88 E+00 1.97 E-01 Ni-63 8.81 E+00 2.95 E-01

b. H -3 4.70 E-01 7.51 E-03 Cr-51 1.12 E+00 1.79 E-02 Mn-54 1.86 E+00 2.97 E-02 Fe-55 8.61 E+01 1.37 E+00 Co-58 3.69 E+00 5.89 E-02 Co-60 5.50 E+00 8.78 E-02 Ni-63 5.53 E-01 8.82 E-04 Nb-95 4.18 E-01 6.68 E-03 Cs-137 1.19 E-01 1.90 E-03 Co No waste of this type shipped.
d. No waste of this type shipped.

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

C., Solid Waste Disposal Number of Shipments

  • 1.50 E+01 Mode of Transportation Truck Destination Barnwell, S.C.
  • All 14 of th'e type 1.A.b shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge, Tennessee. The other shipment (type 1.A.a) was 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.

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

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

4. Irradiated Fuel Shipments (Disposition)

No irradiated fuel was shipped during this Report period.

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 3 : Changes to Process Control Program (PCP)

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

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Semiannua Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 Appendix 4  : Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 No changes vere made to the Offsite Dose Calculation Manual (ODCM) during the Report period.

As a result of the 1990 Land Use Census, Table 3.2-2, Distance to the Nearest Special Locations for the Shearon Harris Nuclear Pover Plant, vill 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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- a Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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 No changes were made to the Environmental Monitoring Program during the Report period.

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Semiannual Radioactive Effluent Release Report

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e January 1, 1990 to June 30, 1990 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 1990. Several changes have occurred in the locations of the nearest resident, garden, and meat animal.

None of the changes would necessitate a change in the SHNPP Environmental Monitoring program. These 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 Harris Nuclear Project (Miles)*

(Comparison of 1989/1990 Data)

Exclusion Residence "

Milk, Animal Garden Meat Animal Sector Boundary 1989 1990 1989 1990 1989 1990 1989 1990 N 1.32 2.2 2.2 2.2 2.2 2.2 2.2 2.8 2.2 NNE 1.33 1.8 1.8 4.6 4.6 1.7 1.7 3.6 3.5 NE 1.33 2.3 2.3 2.3 2' 2.3 2.3 ENE 1.33 2.0 2.0 2.0 3.6 E 1.33 1.9 1.9 1.9 4.7 2.2 2.2 ESE 1.33 2.7 2.7 4' 2.7 2.9 4.4 SE 1.33 4.3 4.3 4.3 4.3 4.3 4.3 SSE 1.33 4,4 4,4 S 1.36 SSW 1.33 3.9 3.9 3,9 3,9 SW 1.33 2.8 2.8 2.8 2.8 2.8 VSV 1.33 4.3 4.3 4.3 4.3 4.3 4.3 W 1.33 2.8 2.8 2.9 2.9 3.1 2.9 WNW 1.33 2.1 2.1 2.1 2.1 2.5 3.6 NW 1.26 1.8 2.1 1.8 3.8 1.8 3.8 NNW 1.26 1.5 1.7 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

~ C January 1, 1990 to June 30, 1990 Appendix 5 : Changes to the Environmental Monitoring Program Enclosure 2 : Land Use Census Technical Specifications'.12.2.a 3.12.2.b Table 2 Meat Animal Type at Nearest Location to SHNPP

( by Sector )

Distance Sector (miles) Meat Type(s) Owner N 2.2 Beef/Hogs/Chickens Goodwin, W.

NNE 3.5 Chickens Hudson, H.

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

ESE 4,4 Chickens McLean, E.

SE 4,3 Chickens Taylor, M.

SSE S

SSW SV WSV 4,3 Chickens Smith, P.

W 2.9 Chickens Hill) A.

VNW 3.6 Chickens Unknown NW 3.8 Hogs Stone, D.

NNW 1.7 Beef Godwin, V, 5/3

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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 Days Monitor Xnop. Reason FT-01MP-1968 A&B 181 Flow monitors A & B are not within the Cooling Tower Make-up required tolerances, resulting in Bypass Line inaccurate flow measurements.

Flow Rate Monitors FT-21WL-6119 Modification to increase the accuracy and Monitor Tank/

181'aste reliability of the readings has been Waste Evaporator Condensate Tank initiated.

Flow Rate Monitors FT-*1WL-6193 181 Modification to increase the accuracy and Treated Laundry & reliability of the readings has been Hot Shower Tanks initiated.

Flow Rate Monitor

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Semiannual Radioactive Effluent Release Report

( Il January 1, 1990 to June 30, 1990

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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 Days Monitor Inopo Reason PNL-21AV-3509-SA 181 Problems with calibration of flow PNL-21AV-3509-1SA measurement system resulting in Plant Vent Stack discrepancies between actual and expected Flow Rate Monitor flow rates. Modification initiated to correct, RM-01TV-3536-1 181 Moisture interferences with the flow TB Vent Stack 3A measurement system resulting in Flow Rate Monitor discrepancies between actual and expected flow rates. Modification initiated to correct.

PNL-1WV-3546 & 181 Problems with calibration of flow PNL-1WV-3546-1 measurement system results in WPB Vent Stack 5 discrepancies between actual and expected Flow Rate Monitor flow rates. Modification initiated to correct.

PNL-1WV-3547 & 181 Problems with cal'ibration of flow PNL-1WV-3547-1 measurement system resulting in WPB Vent Stack 5A discrepancies between actual and expected Flow Rate Monitor flow rates. Modification initiated to correct.

HAI-21WG-1118AW 181 Modification to improve the reliability of Waste Gas Recombiner the monitor has been initiated.

"B" Outlet Gas Hydrogen Monitor OARC-21WG-1119A 181 Modification to improve the reliability of Waste Gas Recombiner the monitor has been "B" Outlet Gas Oxygen Monitor initiated.'/2

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Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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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I Semiannual Radioactive Effluent Release Report January 1, 1990 to June 30, 1990 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, 1990 to June 30, 1990 Appendix 7: Major Modifications to Radwaste System Technical Specification 6.15.1 No major modifications were made to the Radwaste system during this Report period.

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