ML18022A688

Semiannual Radioactive Effluent Release Rept,Jan-June 1988. W/880829 Ltr

ML18022A688
Person / Time
Site:	Harris
Issue date:	06/30/1988
From:	Polard A, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-880165-(O), NUDOCS 8809010141
Download: ML18022A688 (77)

Text

AC CELEMTED DISI'RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8809010141 DOC.DATE: 88/06/30 NOTARIZED- NO DOCKET g FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina '5000400 AUTH. NAME AUTHOR AFFILIATION POLARD,A.O. Carolina Power & Light Co.

WATSON,R.A. Carolina Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION f(peg +u 4 6 ~ IW

SUBJECT:

"Semiann 'oactive Effluent Release Rept,Jan-June ~(S "1988." /880829 tr.

DISTRIBUTION CODE: 48D COPIES RECEIVED:LTR ENCL SIZE-TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports D for permit renewal filed. 05000400'OTES:Application RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 0 PD2-1 PD 5 5 A BUCKLEY,B 1 1 j D

INTERNAL: ACRS 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 NRR/3QEP/RPB 10 4 4 NUDOCS-ABSTRACT 1 E'G KJLE~ 01 1 1 RGN2 FILE 02 1 G 27DRSS EPRPB 1 1 EXTERNAL: BNL TICHLER, J03 1 1 LPDR 1 1 NRC PDR 1 1 D

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9 TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22

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CM9 Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. 0. Box 165 New Hill, North Carolina 27562 AUG 2 9 1988 File Number'. SHF/10-13510C Letter Number'. HO-880165 (0)

U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 1

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, 1988 through June 30, 1988.

Very truly yours, C.s Vice President Harris Nuclear Project MGW:acm Attachment cc. Mr. B. Buckley (NRR)

Mr. G. Maxwell (NRC SHNPP)

Dr. J. Nelson Grace (NRC RII)

MEM/HO-8803650/1/OSl

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Carolina Power &. Light Shearon Harris Nuclear Power Plant License No. NPF-063 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 1988 to June 30, 1988 Prepared by:

Project Specialist Radiation Control Reviewed by: gggI/ZI Mana r Environment 1 & adiation Control Approved by:

Plant General Manager 88090iOi4i 880630 05000400 PDR ADOCK R PDC

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Table of Contents Page No.

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

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

2. Effluents Released 2/3

3. Solid Waste Disposal 2/10 Appendix 3. Changes to Process Control Program 3/1 Appendix 4. Changes to Offsite Dose Calculation 4/1 Manual (ODCM)

Appendix 5. Changes to the Environmental Monitoring Program

l. Environmental Monitoring Program 5/1

2. Land Use Census 5/2 Appendix 6. Additional Technical Specification Responsibilities

l. Inoperability of Liquid Effluent Monitors 6/1

2. Inoperability of Gaseous Effluent Monitors 6/3

3. Unprotected Outdoor Tanks Exceeding Limits 6/4

4. Gas Storage Tanks Exceeding Limits 6/5 Appendix 7. Major Modifications to Radwaste System 7/1

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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 plants Radiological Effluent Technical Specification (RETS).

This report covers the period from January 1, 1988 to June 30, 1988.

Discussion

~Aendices 1 end 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 either measured stack flow rates or stack flow rate estimates based on design fan flow rates. Because no specific nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases, the total noble gas activities based on stack monitor readings were 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 summations of liquid effluents are based on the nuclides identified in batch releases only.

A total of 54.76 m3 of solid waste, containing 1.442 Ci of radioactivity, was shipped for burial during the report period, compared with 105 m3 and 2.6 Ci shipped during the previous report period.

~Aendix 3:

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

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~Aendix 4:

Changes made to the ODCM during this report period are listed. Most of these changes are related to the increased availability of liquid effluent dilution flow due to installation of the Cooling Tower Makeup/Blowdown Crosstie modification. All changes were reviewed and approved by the Plant Nuclear Safety Committee (PNSC). These changes do not reduce the accuracy or reliability of the dose calculations or monitor setpoint determinations.

~Aendix 5:

No changes were made to the Environmental Monitoring Program during this reporting period. Changes to the Land Use Census are based on a May, 1988 survey.

~Aendix 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.

The modification to increase cooling tower blowdown flow is expected to be completed during the second half of 1988. Upon completion, several of the liquid monitors that are inoperable should be returned to service.

Also included in this report are two inoperable periods greater than thirty days for the Cooling Tower Blowdown Flow Rate Monitor. This monitor was inadvertently omitted in the two Semiannual Reports submitted for 1987.

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

~Aendix 7:

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

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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. ' mrem to total body

b. 10 mrem to any organ

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2. Maximum permissible concentrations and dose rates which determine maximum instantaneous rates.

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

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

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

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

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

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 1: Supplemental Information

4. Batch Releases A. Liquid (1) Number of batch releases: 1.49 E+02 (2) Total time period for batch releases: 7.21 E+04 min.

(3) Maximum time for a batch release: 9.55 E+02 min.

(4) Average time for a batch release: 4.84 E+02 min.

(5) Minimum time for a batch release: 1.95 E+02 min.

(6) Average stream flow during periods of release: 2.23 E+03 gpm B. Gaseous (1) Number of batch releases: 3.00 E+00 (2) Total time period for batch releases: 9.30 E+Ol min.

(3) Maximum time for a batch release: 5.10 E+Ol min.

(4) Average time for a batch release: 3.10 E+Ol min.

(5) Minimum time for a batch release: 1.40 E+Ol min.

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

B. Gaseous No abnormal gaseous releases were made in the period.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Enclosure 1 : LONER LIMITS OF DETECTION (LLD)

1. LLD's for Gaseous Bffluents NUCLIDB LLD (uCi/cc)

H 3 9.16 E-09 A~1 4.42 E-08 Cr-51 6.57 B-14 Mn-54 1.79 E-14 Co-58 1.79 E-14 Fe-59 4.40 E-14 Co-60 2.51 E-14 Zn-65 6.71 E-14 Kr-85 3.44 E-08 Kr 85m 6.64 E-09 Kr-87 4.22 E-08 Kr 88 2.34 E-08 Sr-89 8.73 E-16 Sr-90 5.35 E-16 Nb-95 1.74 E-14 Mo-99 2.92 B-13 RQ-103 1.18 E-14 I -131 4.54 E-14 Xe-131m 2.42 E-07 I -3.33 3.03 E-13 Xe-133 7.74 E-08 Xe-133m 1.73 E-07 Cs-134 1.28 B-14 I -135 9.64 B-10 Xe-135 1.34 E-08 Xe-135m 7.24 E-08 Cs-137 1.62 E-14 Xe-138 9.40 E-08 Ba-140 5.17 E-14 La-140 4.27 E-14 Ce-141 2.04 E-14 Ce-144 9.65 E-14 Gross Alpha 2.69 E-15

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Bffluent and Waste Disposal Report Enclosure 1 : LOWER LIMITS OF DETECTION (LLD)

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

H - 3 2. 93 E-06 Be- 7 3. 81 E-07 Na-24 5.01 E-08 A~1 6.70 E-08 Cr 51 3.66 B-07 Mn-54 6.95 E-08 Fe-55 9.67 E-08 Co-57 2.25 E-08 Co-58 , 3.04 E-08 Fe-59 7.01 E-08 Co-60 4.19 E-08 Zn-65 7.90 E-08 Kr-85m 4.19 E-08 Sr-89 7.08 E-09 Sr-90 4.33 E-09 Zr-95 5.12 E-08 Nb-95 4.89 B-08 Mo-99 2.38 E-07 Tc-99m 2.61 E-08 Rh-105 1.80 E-07 Ru-105 6.50 B-08 Sn-113 2.27 E-08 Sb-124 1.62 E-08 I -131 1.69 B-08 Xe-131m 1.31 E-06 I -133 2.41 E-08 Xe-133 9.66 E-08 Xe-133m 3.17 E-07 Xe-135 3.61 E-08 Cs-134 2.35 E-08 Cs-137 2.93 E-08 Ba-140 1.16 E-07 La-140 5.77 E-08 Ce-141 3.74 E-08 Ce-144 2.08 B-07 Hf-181 3.82 E-08 W -187 9.12 E-08 Gross Alpha 6. 42 E-08 2/2

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Enclosure 2  : Bffluents Released Table lA  : GASEOUS EFFLUENTS SUMMATION OF ALL RELEASBS Units Quarter Quarter Est. Total 1 2 Error

1. Fission h Activation Gases A. Total Release Ci 5.82 E+02 8.54 E+02 4.50 E+Ol B. Average Release Rate for Period uCi/sec 7.40 E+Ol 1.09 E+02 C. Percent of Technical Specification Limit 6.77 E-Ol 9.99 E-Ol

2. Iodines A. Total I-131 Ci 0.00 E+00 0.00 E+00 2.00 E+Ol B. Average Release Rate for Period uCi/sec 0.00 E+00 0.00 E+00 C. Percent of Technical Specification Limit 0.00 E+00 0.00 E+00

3. Particulates A. Particulates with Tl/2> 8 days Ci 0.00 E+00 0.00 E+00 2.00 E+01 B. Average Release Rate for Period uCi/sec 0.00 B+00 0.00 E+00 C. Percent of Technical Specification Limit 0.00 E+00 0.00 E+00 D. Gross Alpha Radioactivity Ci 6.55 E-08 0.00 B+00

4. Tritium A. Total Release Ci 0.00 B+00 0.00 E+00 3.00 E+Ol B. Average Release Rate for Period uCi/sec 0.00 E+00 0.00 E+00 C. Percent of Technical Specification Limit 0.00 E+00 0.00 E+00

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1. Fission and Activation Gases Continuous Mode 0 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 3.55 E-Ol < LLD Kr-85 Ci < LLD < LLD < LLD < LID Kr 85m Ci 1.26E+Ol 1.84E+Ol < LLD < LLD Kr-87 Ci 4.19E+00 6.14E+00 < LLD < LLD Kr-88 Ci 2.09E+Ol 3.07E+Ol < LLD < LLD Xe-131m Ci < LLD < LLD < LLD < LLD Xe-133 Ci 5.02E+02 7.37E+02 < LLD < LLD Xe-133m Ci 8.37E+00 1.23E+Ol < LLD < LLD Xe-135 Ci 2.93E+Ol 4.30E+Ol < LLD < LLD Xe-135m Ci < LLD < LLD < LLD < LLD Xe-138 Ci 4.19E+00 6.14E+00 < LLD < LLD Total for Period Ci 5.82E+02 8.54E+02 3.55 E-Ol < LLD 0 Noble Gas quantities apportioned as per GALE code.

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-133 Ci < LLD < LLD < LLD < LLD I-135 Ci < LLD < LLD < LLD < LLD Total for Period Ci < LLD < LLD < LLD < LLD 2/5

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3. Particulates Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 Mn-54 Ci < LLD < LLD < LLD < LLD Fe-59 Ci < LLD < LLD < LLD < LLD Co-58 Ci < LLD < LLD < LLD < LLD Co-60 Ci < LLD < LLD < LLD < LLD Zn-65 Ci < LLD < LLD < LLD < LLD Sr 89 Ci < LLD < LLD < LLD < LLD Sr-90 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 6.55 E-08 < LLD < LLD < LLD Total for Period Ci 6.55 E-08 < LLD < LLD < LLD 2/6

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1. Fission h Activation Products A. Total Release

{not including tritium, Ci 4.12 B-03 1.45 E-02 3.50 E+Ol gases, or alpha)

Average Diluted Concentration during Period uCi/ml 3.97 E-09 1.19 E-08 C. Percent of Applicable Limit 5.27 E-03 3.87 E-02

2. 'ritium A. Total Release Ci 5.97 B+Ol 1.80 B+02 3.50 E+Ol B. Average Diluted Concentration during Period uCi/ml 5.74 E-05 1.47 E-04 C. Percent of Applicable Limit 1.91 E+00 4.92 E+00

3. Dissolved and Entrained Gases A. Total Release Ci 3.06 B-04 2.44 E-Ol 3.50 E+01 B. Average Diluted Concentration during Period uCi/ml 2.94 B-10 2.00 E-07 C. Percent of Applicable Limit 1.47 B-04 1.00 E-01 Gross Alpha Radioactivity Total Release Ci 2.55 B-06 < LLD 3.50 B+Ol

5. Volume of water released prior to dilution A. Batch Release liters 4.05 B+06 5.62 B+06 1.00 E+Ol B. Continuous Release liters 1.45 E+07 1.78 E+07 1.00 E+Ol

6. Volume of dilution water liters 1.02 E+09 1.19 B+09 1.00 E+Ol used during period 2/7

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Enclosure 2  : Effluents Released Table 2B LIQUID EFFLUENTS

1. Fission and Activation Products Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 H-3 Ci < ILD < LLD 5.97 E+Ol 1.80 E+02 Be-7 Ci < LLD < LLD < LLD 7.41 E-04 Cr 51 Ci < LLD < LLD < LLD 4.27 E-02 Mn-54 Ci < LID < LLD 1.67 E-04 7.11 E-04 Fe-55 Ci < LLD < LLD 5.05 E-04 < LLD Co-57 Ci < LLD < LLD < LLD 5.10 E-06 Co-58 Ci < LLD < LLD 3.14 E-03 9.91 E-03 Fe-59 Ci < LLD < LLD 2.65 E-05 < LLD Co-60 Ci < LID < LLD 2.43 E-04 2.02 E-03 Zn-65 Ci < LLD < LLD < LLD < LLD Sr 89 Ci < LLD < LID < LLD < LLD Sr-90 Ci < LLD < LLD 2.52 E-06 < LLD Zr/Nb-95 Ci < LLD < LLD 3.97 E-05 4.40 E-04 Mo-99 Ci < LLD < LLD < LLD < LLD Tc-99m Ci < LLD < LLD < LLD 9.59 E-06 Sn-113 Ci < LLD < LLD < LLD 5.65 E-05 Sb-124 Ci < LLD < LLD 4.25 E-06 < LLD I -131 Ci < LLD < LLD < LLD 8.09 E-05 I -133 Ci < LLD < LLD < LLD 7.73 E-06 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LID < LLD < LLD 4.86 E-05 Ba/La-140 Ci < LLD < LLD < LLD < LLD Ce-141 Ci < LLD < ILD < LLD < LLD Ce-144 Ci < LLD < LLD < LLD < LLD Hf-181 Ci < LLD < LLD < LLD 1.90 E-05 Gross Alpha Ci < LLD < LLD 2.55 E-06 < LLD Total for Period Ci < LLD < LLD 5.97 E+Ol 1.80 E+02 2/8

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2. Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Units Quarter Quarter Quarter Quarter Released 1 2 1 2 A~1 Ci < LLD < LLD < LLD < LLD Kr-85m Ci < LLD < LLD < LLD 1.01 E-04 Xe-131m Ci < LLD < LLD < LLD 1.26 E-04 Xe-133 Ci < LLD < LLD 2.59 B-04 2.19 E-Ol Xe-133m Ci < LLD < LLD < LLD 4.49 E-03 Xe-135 Ci < LLD < LLD 4.75 B-05 1.99 E-02 Total for Period Ci < LLD < LLD 3.06 E-04 2.44 E-Ol 2/9

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Bnclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

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

6 month Bst. Total Solid. Cont. No.

A. Type of waste Units Period Error (4) Agent Type Form Ship

a. Spent Resin, filter m3 4.96 E+Ol 1.00 B+01 Cement STP S/D 10 sludge, evaporator bottoms, etc. Ci 1.39 E+00

b. Dry Compressible m3 5.14 E+00 1.00 E+00 NA STP D 2 Waste, contaminated equipment, etc. Ci 4.93 B-02

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

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

Total Type of Percent Activity Waste Nuclide Composition Ci

a. H -3 4.77 E+Ol 6.64 E-Ol C -14 1.15 E-03 6.13 E-04 Mn-54 4.71 E+00 6.55 E-02 Fe-55 8.65 B+00 1.21 E-Ol Co-58 3.25 E+Ol 4.52 E-Ol Co-60 4.41 B+00 6.15 E-02 Ni-63 2.04 E+00 2.84 E-02

b. H -3 9.60 B+Ol 4.74 E-02 C -14 < 0.01 E+00 2.00 B-06 Co-58 3.93 E+00 1.94 E-03 ci No waste of this type shipped.

d. No waste of this type shipped.

STP Strong Tight Package S Solidified D Dewatered 2/10

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Enclosure 3 : Solid Waste Disposal Table 3 : SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. Solid Waste Disposal Number of Shipments 0 1.20 E+Ol Mode of Transportation Truck Destination Barnwell, S.C.

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.

8 of these shipments were made from the Scientific Ecology Group (SEG) processing facility in Oak Ridge , Tennessee.

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Semiannual Radioactive Bffluent Release Report January 1, 1988 to June 30, 1988 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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APPENDIX 4 Semiannual Radioactive Effluent Release Report Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 January 1, 1988 to June 30, 1988 1.0 Ex lanation for Chan es Fifteen changes to the ODCM were made during the specified time period.

described in Section 2.0 of this appendix. Items 1-14 were editorial They're changes to make the manual consistent with increased availability of liquid effluent dilution flov due to installation of a Cooling Tower Makeup/Cooling Tower Blowdown Cross-Tie. Item 15 corrects Figure 2.1"4 to show that storm drain effluent does not go to the cooling tower blowdown line but directly to Harris Lake.

2.0 Chan e Descri tions

1. Page 2-1, Section 2.1.1, second paragraph, fourth sentence, replace "blovdown" vith "discharge." The term "discharge" is more accurate as blowdown can now be combined with makeup flow.

2~ Page 2-1, Section 2.1.1, second paragraph, fifth sentence, replace "blowdown" with: ". . .combination of Cooling Tower Blowdown flow and Cooling Tower Makeup/Cooling Tower Blowdown Cross-Tie (CTMU/CTBD) flov herein defined as . . ." The insert describes the effect of PCR-2103 in providing additional liquid dilution flow.

l

3. Page 2-2, Section 2.1.1, second paragraph, seventh sentence, eliminate "assumed" and replace ". .16.5 cfs (7.4E3 GPM) as

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presented in the SHNPP CESAR, Section 11.2.3. Zhis value is presently interpreted as the average blovdown flow rate but may be variable. If B is less than 16.5 cfs, then the measured flow rate should be used." Pith ". . . the measured flov rate of Cooling Tower Blowdown plus CTMU/CTBD Cross-Tie flow rate', i.e., dilution flov rate."

The change reflects the additional liquid dilution flow provided by successful completion of PCR-2103.

4. Page 2-4, Section 2.1.1.1, Item c, at the definition of "B," replace "Cooling tower blowdown" vith "Dilution" and eliminate "= 7.4E3 gpm nominally or estimated available flow rate." The change provides a more generic reference to dilution flow for SHNPP liquid effluents.

5 ~ Page 2-6, Section 2.1.1.1, at paragraph discussing Alternative Set Point Method Based on I-131 MPCw, Item (2), repI.ace "cooling tower blowdown" with "dilution" and eliminate "for dilution." Change is made for editorial consistency.

6. Page 2-8, Section 2.1.1.1, at paragraph prior to Equation 2.1-5C, delete "cooling tower." Change is made for editorial consistency.

MKM/SRERReport/1/OS2 4/1

7. Page 2-8, Section 2 ~ 1 ~ 1 ~ 1, Equation 2.1-5C, at the definition of "B," replace "cooling tower blowdown" with'dilution." Change is made for editorial consistency.

8. Page 2-9, Section 2.1 1 1, Equation 2.1-5D, at the

~ ~ definition, of "B," same as Change Item 4 above.

9. Page 2"11, Section 2.1.1.1, Equation 2.1-8, at the definition of "B," same as Change Item 7 above..

10. Page 2-15, Section 2.).3.1, first sentence, replace "blowdown" with "discharge," change is made for editorial consistency.

11. Page 2-15, Section 2.1.3.2, first sentence, same as Change Item 10, above.

6

12. Page 2-27, Figure 2.1"2, delete "Blowdown" and replace with "discharge line"; add Cooling Tower and CTMU/CTBD Cross-Tie components to the diagram and add "Cooling Tower Blowdown" identification in the flow path. Changes illustrate the effect of PCR-2103;

13. Page 2-28, Figure 2.1-3, delete "Blowdown" and replace with "Discharge." Change provides editorial consistency.

14. Page 2-29, Figure 2.1-4, delete "Blowdown line" and replace with "Discharge." Change provides editorial. consistency.

15. Page 2"29, Figure 2.1-4, storm drain effluent does not go to the cooling tower blowdown line but directly to Harris Lake. The footnote indicated by correction.

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diagram has been corrected to reflect this flowpath. Also, the has been deleted as unnecessary given this MEM/SRERReport/2/OS2 4/2

" LIQUID EFFLUENT Liquid releases at SHNPP are divided into batch and continuous modes. Each mode is further separated into routine and nonroutine release paths'outine batch releases are expected via process streams described in Section 2.1.1.

Nonroutine batch releases are effluent paths that only have the potential for containing radioactivity. The outdoor tank area drain line, the turbine building floor drains effluent line (yard oil separator line), and the efflu-ent from from the secondary waste treatment system (SWTS) are considered as nonroutine batch release points. Xn the SVTS, this is true only when no radioactivity is detectable due to primary to secondary leakage. These efflu-ent paths are monitored for radioactivity (see Appendix D and Figures 2.1-2 and 2.1-4) and should the set point be exceeded, releases are automatically terminated. Further discussion of these effluent lines is provided in Sec-tion 2.1.3.

Continuous liquid releases are considered as nonroutine radioactive release pathways. The term nonroutine refers to the low potential for radioactivity in these effluent streams. Section 2.1.2 describes continuous releases in greater detail.

2.1 COMPLIANCE WITH 10CFR PART 20 (LIQUIDS) 2.1.1 Batch Releases A batch release is the discharge of liquid waste of a discrete volume. Batch releases from the SHNPP liquid radwaste system may occur from treated laundry and hot shower tanks, secondary waste treatment tank, waste monitor tanks, and waste evaporator condensate tanks. The principal sources of waste for these tanks are shown in Figure 2.1-1.

The liquid radwaste effluent streams are shown in Figure 2.1-2. A batch release represents the emptying of one tank only. No concurrent liquid batch releases (i.e., more than one tank at a time) are made from SHNPP. The liquid radwaste system discharges to the cooling tower discharge line. Dilution flow ~

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depends primarily on the combination of Cooling Tower Blowdown flow and Cooling Tower Makeup/Cooling Tower Blowdown Cross-Tie (CTMU/CTBDi flow herein Q~

DCM/ODC-2 2-1 Rev. 2.0

defined as Flow "B." If liquid effluent is diverted to the waste neutralization basing some additional dilution may also occur at this point ~

For the purpose of calculation, the value of B is the measured flow rate of Cooling Tower Blowdown plus,CTMUICTBD Cross-Tie flow rate; i.e., dilution flow rate.

The sampling and analysis frequency and the type of analyses required by the SHNPP'echnical Specifications are given in Table 4.11-1 of the specifica-tions. All applicable radiation monitoring instrument numbers are listed in Appendix D.

2.1.1.1 Prerelease The radioactive content of each batch release will be determined prior to release in accordance with Table 4.11-1 of the SHNPP Technical Specifica-tions, Compliance with 10CFR20 will be shown in the following manner'.

a. Mixing Method for Isolated Liquid Effluent Tanks Prior to Sam-pling for Radioactivity Analyses Equation 2.1-0 below provides an acceptable method for ensuring a well-mixed tank so that a representative sample can be taken for adioactivity or other appropriate analyses. The method addresses the requirement found in Foot-note 2, Table 4.11-1, of Technical Specification 4.11.1.1.1.

(V) (E) (n)

(2.1-0)

(P) (60) where'.

Estimated mixing time, hr Tank volume, gal Eductor factor Pump recirculation flow rate, gpm DMC/ODC-2 Rev. 1.0

n 4

A factor of > 2; 10CFR20 limits as specified in Appendix B, Table II, Column 2. This factor represents one layer of conservatism for all releases at SHNPP DF Minimum acceptable dilution factor per Equa-tion 2.1-1

c. Maximum release rate'.

B MRR

~o~ B (2.1-3) where.'aximum release rate of the batch to be re-leased, gpm Dilution flow rate, gpm Tm Fraction of the radioactivity from the site that may be released via monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway. The T sum for the site shall not exceed one (1)

DFB Minimum acceptable dilution factor (DF ) made conservative by a factor of "n" per Equation 2.1-2 Note: This method of determining the Maximum Release Rate (MRR) conformance with the test in Section F below. 'nsures DMC/ODC-2 2-4 Rev. 1.0

Bkg SP CR + Bkg + 3.3 2T.

Bkg 3 ~3 Statistical variance on the background (Bkg) 2T counting rate quoted at the 99.95X confidence level at a time constant v (min) which is a function of Bkg. This term is included to prevent inadvertent high alarm trips due to random fluctuation in the monitor backgrounds CR Calculated, monitor count rate per Equa-tion 2.1-4, cpm Bkg Background count rate due to internal contami-nation and the radiation levels in the area in which the monitor is installed when the de-tector sample chamber is filled with an uncon-taminated fluid, cpm CAUTION: This set point must be evaluated as conforming to the test of "Section f" belo~.

ALTERNATIVE SET POINT METHOD BASED ON I-'131 MPCw This method conservatively assumes:

(1) All of the radioactivity is due to I-131, which has the lowest Maximum Permissible Concentration (MPC ), persuant to 10CFR20.

'2)

Only the minimum dilution flow rate is available.

(3) The maximum effluent discharge flow rate is utilired.

Determine SP , the set point above background in yCi/ml.

DMC/ODC-2 2-6 Rev. 1.0

~a s

This method provides a set point using a more precise evaluation which includes the actual dilution flow rate, effluent discharge flow QQ rate, and an analysis of the principal gamma emitters in the liquid effluent to the released.

Determine SP mf, the Set Point above background in- pCi/ml.

Z C (f + B)

Spm g (

(DF ) (f)

) (T) m (2.1-5c) g B

where:

SPm Set point above background (pCi/ml)

C Total radioactivity concentration of gamma-g emitting radionuclides in liquid ef fluent prior to dilution (pCi/ml).

Effluent discharge flow rate (gpm)

Dilution flow rate (gpm)

DFB Given previously in Equation 2.1-2.

m Fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from more than one pathway. The sum of T for the l

site shall not exceed one (1).

Determine SP , the monitor set point above background in cpm.

c'P m) m (2.1-SD) where:

DMC/ODC-2 2-8 Rev. le0

e 1 RR Anticipated release. rate of the batch that should not exceed the MRR as per Equation 2.1-3, gpm Dilution flow rate, gpm

f. 10CFR20 Prerelease Compliance Check:

Before initiating the batch release, perform one final check for compliance with 10CFR20 ~ If the sum of the ratio of liquid con-centration to MPC for all radionuclides at the unrestricted area is less than or equal to 1, then 10CFR Part 20 limits have been met. The following equation must be true'.

Z Conc./MPC.

1

( 1 1

1 where'.

Conc- Calculated concentration of radionuclide "i" at the unrestricted area per Equation 2.1-6, yCi/ml MPC ~ Maximum permissible concentration of radio-nuclide "i" from Appendix B, Table II, Column 2, of 10CFR20, yCi/ml 2.1.1.2 Postrelease The actual concentration of each radionuclide following a batch release from a tank will be calculated to show final compliance with 10CFR20 as follows.'.

Actual concentration at unrestricted area:

DMC/ODC-2 2-10 Rev. 1.0

(C.) (U )

Conc i k (2.1-8) k d where.'onc The actual concentration of radionuclide "i" at the unrestricted area during release "k,"

yCi/ml Ci Concentration of radionuclide "i" in the batch released, pCi/ml Uk Actual volume of liquid effluent released during release "k," gal (see Table 2.1"1 for waste tank volumes and pump capacities).

Ud Actual volume of dilution water during release "k," gal (B) (tk) where:

Dilution flow rate, gpm tk Duration of release "k," min

b. 10CFR20 Postrelease Compliance Check:

To show final compliance with 10CFR20, the following relationship must hold:

(Conc. k /MPC. ) < 1 E

1 (2.1-9)

DMC/ODC-2 2-11 Rev. 1.0

0 Engineering factor .to account for spurious alarms Em The monitor efficiency for the mixture of radionuclides in the liquid effluent (cpm/

pCi/ml) bkg Background count rate due to internal radia-tion levels in the area in which the monitor is installed when the detector views an uncon-taminated fluid (cpm)

Method 2 is acceptable from an effluent release standpoint because NSW is not discharged directly to the environment and it undergoes significant dilution in the cooling tower basin.

2.1.3 Nonroutine Li uid Releases 2.1.3.1 Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rainwater collected in the outdoor tank area to the storm drain system and from there to the cooling tower discharge line for release to the environment- The line is monitored for radioactivity and is capable of automatic termination of effluent release. Because no radioactivity is normally ,expected in this line, the monitor set point can be determined with either Equation 2.1-10 or 2.1-11. If the set point is exceeded, the release is automatically terminated. Effluent can then be diverted to the floor drain system for processing and eventual release via the waste monitor tanks (see Figures 2.1-) and 2.1-2).

2.1.3.2 Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the yard oil separator for release to the environment via the waste neutralization system and then to the cooling tower discharge line. Because no radioactivity is normally expected in this path, the set point for the radioactivity can be DMC/ODC-2 2-15 Rev. 1.0

FIItula 2.I.2 LIQUIVEFFLUENT FLow sTrIEAM DIAGBAM Cooling ToweL TflEATEO LAVNORYII TREAfEO LAVtlohYA IIOT SNOWER TANK IIOT SIIOWER TAIIK CTHU/CTBD Cro -T'e O'EM REM.IWL.SS40 SECONOARYWASTE SAMPLE TANK

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O'EM 0

O REM-TIWS SSTT V WASTE NEUTRALIZATION YIAST E MOINToh WASTE I'IONIIVII SASIN TAtlK 'fAtlK SETTLING SASIN REM-TIWLASlt LECENOI TANK OA SASIN IIARRIS LAK'E f

WASt E VAPORAT Oh

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r Figula 2.14 0 TIIEil 1.lQUIO EFFLUENT MTiiWAYS TvnevIEOVILoltto rLoononAIIISErrLVENrLIIIE YIA ST f.

TItnslttE Ttloo SVMI'5 YADO oil. NEVTDALIZATION FLoon ODAltls sErAnATon SASIN nEM S SETTLINO SASIN o

8 ovlsloF. IANKADFAOnAIIIEcrLVENT LINE OUI SIDE TANK stonM onA'It/

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'IDEATMENT SYSTEM IIAhnls LAKE.

Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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 were made to the Environmental Monitoring Program during this report period.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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 May of 1988. Table 1 summarizes the location of the nearest milk animal, meat animal, residence and garden in each of the 16 compass sectors. Comparison with the 1987 land-use survey indicates the following:

A. Milk goats are still not located within the five-mile radius.

B. Milk cows continue to be located in the N and NNE sectors. These locations are commercial dairies that are currently'included in the SHNPP environmental sampling program.

C. The nearest locations for gardens and meat animals in the E and NW sectors are significantly closer to the plant.

Table 2 lists the kinds of meat animals at each meat animal location. Cattle and hogs are the predominate animals nearest the site.

TABLE 1 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE HARRIS NUCLEAR PROJECT (MILES)4 (Comparison of 1987/1988)

EXCLUSION MILK MEAT SECTOR BOUNDARY RESIDENCE ANIMAI GARDEN ANIMAL 1987 1988 1987 1988 1987 1988 1987 1988 N l. 32 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 NNE 1.33 1.7 1.8 4.6 4.6 1.7 1.7 1.8 1.8 NE 1.33 2.3 2.3 2.3 2.3 2.3 2.3 ENE 1.33 2.0 3.6 2.0 E 1.33 1.9 1.9 4.7 1.9 4.6 1.9 ESE 1.33 2.7 2.7 2.8 2.7 4.4 4. 3 SE 1.33 4.7 4.3 4.7 4.3 SSE 1.33 4,4 4.4 S 1.36 SSW 1.33 3.9 3.9 3.9 3.9 4 4 SW 1.33 2.8 2.8 2.8 2.8 2.8 2.8 WSW 1.33 4.3 4.3 4.3 4.3 4.3 4.3 W 1.33 2.7 2.7 3.0 3.0 3.1 3.1 WNW 1.33 2.1 2.1 2.1 2.1 2.5 2.5 NW 1.26 1.8 1.8 3.8 1.8 3. 8 1.8 NNW 1.26 1.5 1.5 1.9 1.7 1.9 1.7 0 Distance Estimates are +- 0.1 miles except at the exclusion boundary 5/2

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c Semiannual Radioactive Effluent Release Report January 1, 1987 to June 30, 1987 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 NEARBST LOCATION TO SHNPP BY SECTOR DISTANCE MEAT SECTOR (MILES) TYPE OWNER N 2.2 HOGS GOODWIN, Woodrow NNB 1.8 BEEF GUNTBR NB 2.3 BEEF JAMES REST HOME ENB E 1.9 CHICKENS / RABBITS HARRIS BSB 4.3 HOGS MCLEAN SE SSB S

SSW SW 2.8 4.3 CHICKENS / GOATS POLLARD WSW HOGS SMITH, P.

W WNW 3.1 2.5 RABBITS CHICKENS

/ CHICKENS ALLEN, S.

WILLIAMS NW 1.8 BEEF FISH NNW 1.7 BEEF / HOGS GOODWIN, Winston 5/3

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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 For the Report Period Effluent Days Monitor Inop. Reason REM-1SW-3500A 55 Sample flow rate measurement problems.

Service Water Return REM-1SW-3500B 54 Loop communications problems. Extensive Service Water Return troubleshooting required to correct problem.

REM-01MD-3530 61 Failure of flow switch caused inaccurate flow Tank Area Drains measurements. Replacement parts ordered and Drains installed.

107 Same as above.

REM-1WL-3540 182 Accumulation of activity in the sample Treated Laundry chamber during releases causes the alarm and Hot Shower setpoint to be exceeded. Modification to increase cooling tower blowdown flow will permit a more flexible alarm setpoint.

REM-21WL-3541 182 Accumulation of activity in the sample Waste Monitor chamber during releases causes the alarm Tank setpoint to be exceeded. Modification to increase cooling tower blowdown flow will permit a more flexible alarm setpoint.

REM-1WS-3542 80 Monitor removed from service to allow for Secondary Waste installation of equipment for modification to increase cooling tower blowdown flow.

FT-1974 AhB 52 Monitor removed from service to allow for Cooling Tower Blowdown installation of continuous composite sampling Flow Rate Monitor equipment.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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 For the Report Period Effluent Days Monitor Inop. Reason The following period of inoperability occurred during the first six month period of 1987 and was inadvertently ommitted from the Semiannual Report for the period from January 1, 1987 to June 30, 1987.

FT-1974 ARB 143 Pre-operational installation and testing not Cooling Tower Blowdown completed until after reporting period Flow Rate Monitor initiated.

The following period of inoperability occurred during the second six month period of 1987 and was inadvertently ommitted from the Semiannual Report, for the period from July 1, 1987 to December 31, 1987.

FT-1974 ARB 31 Monitors AM not within allowed tolerances.

Cooling Tower Blowdown Troubleshooting required to determine problem.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 6 : 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 For the Report Period Effluent Days Monitor Inop. Reason OAI-21WG-1101 93 Removed from service to perform Waste Gas modification on drain.

Compressor Discharge Oxygen Monitor HAIC-21WG-1118B 65 Component Failure. Replacement parts Waste Gas Recombiner ordered and installed.

Bn Outlet Gas Hydrogen Monitor REM-01AV-3509SA 170 Background subtract factor being used Plant Vent Stack incorrectly in the firmware of the monitor.

Noble Gas Monitor A modification has been initiated to correct.

PNL-21AV-3509-SA 104 Problems with calibration of flow measurement PNL-21AV-3509-1SA system resulting in discrepancies between Plant Vent Stack actual and expected flow rates.

Flow Rate Monitor REM-01TV-3536-1 142 Moisture interferences with the flow measurement TB Vent Stack 3A system resulting in discrepancies between Flow Rate Monitor actual and expected flow rates.

Modification initiated to correct.

PNL-1WV-3546 8 182 Problems with calibration of flow measurement PNL-lWV-3546-1 system resulting in discrepancies between WPB Vent Stack 5 actual and expected flow rates.

Flow Rate Monitor Modification initiated to correct.

PNL-1WV-3547 h 182 Problems with calibration of flow measurement PNL-lWV-3547-1 system resulting in discrepancies between WPB Vent Stack 5A actual and expected flow rates.

Flow Rate Monitor Modification initiated to correct.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 6  : 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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<" v Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 Appendix 6  : Additional Technical Specification Responsibilities Enclosure 4 : Gas Storage Tanks Exceeding Limits Technical Specification 3.11.2.6, Action a No gas storage tank exceed the Technical Specification limit during this report period.

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Semiannual Radioactive Effluent Release Report January 1, 1988 to June 30, 1988 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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