Text

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987
	ML18005A318
Person / Time
Site:	Harris
Issue date:	12/31/1987
From:	Palard A, Sipp J, Tearness G, Watson R; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	CON-NRC-611 HO-880072-(O), NUDOCS 8803040086
	Download: ML18005A318 (85)
	v • d • e

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'CCELERATED DI BUTJON DEMONSTRA, JON SYSTEM REGULATORY INFORMATION DXSTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:8803040086 DOC.DATE: 87/12/31 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME

'UTHOR AFFILIATION PALARD,A.D.

Carolina Power

& Light Co.

SIPP,J.R.

Carolina Power

& Light Co.

TEARNESS,G.C.

Carolina Power

& Light Co.

RECIP.NAME RECIPXENT AFFILIATION DOCKET g

05000400

SUBJECT:

"Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987."

W/880224 ltr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR l

ENCL I

SIZE: N5 TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES:Application for permit renewal filed.

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2 EPRPB LPDR COPIES LTTR ENCL 5

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TOTAL NUMBER OF COPIES REQUIRED:

LTTR 23 ENCL 22

Carolina Power h Light Shearon Harris Nuclear Power Plant License No. NPF-063 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1, 1987 to DECEMBER 31, 1987 Prepared by:

Project Specialist Radiation Control Reviewed by:

M a er Environmenta Radiation Control Approved by:

Plant General Manager 88030 oo 5000400 87123'1 PDR ADOCK 0 R

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Table of Contents Introduction Discussion Appendix 1.

Supplemental Information Page No.

Appendix l.

2.

3.

2.

Effluent and Waste Disposal Report Lower Limits of Detectability (LLD's)

Effluents Released Solid Waste Disposal 2/1 2/3 2/10 Appendix 3.

Changes to Process Control Program 3/1 Appendix 4.

Changes to Offsite Dose Calculation Manual (ODCM)

Appendix 5.

Changes to the Environmental Monitoring Program l.

Environmental Monitoring Program 2.

Land Use Census 5/1 5/2 Appendix l.

2.

3.

6.

Additional Technical Specification Responsibilities Inoperability of Liquid Effluent Monitors 6/1 Inoperability of Gaseous Effluent Monitors 6/2 Unprotected Outdoor Tanks Exceeding Limits 6/3 Gas Storage Tanks Exceeding Limits 6/4 Appendix 7.

Major Modifications to Radwaste System 7/1 Appendix 8.

Meteorological Data 8/1 Appendix l.

2.

9.

Assessment of Radiation Doses Doses Outside Site Boundary Due to Effluent Releases Doses to General Public Due to Activities Inside the Site Boundary Doses to Likely Most Exposed Member of the General Public Major Assumptions Used to Calculate Radiation Doses 9/1 9/3 9/5 9/8

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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).

Nuclide accountability and dose are based methodology in the Offsite Dose Calculation Manual (ODCM).

Although the RETS reporting requirement was not effective until initial criticality which occurred on January 3,1987, annual data in this report actually commences on January 1,

1987.

This was done for consistency with future reporting periods and because the RETS were fully implemented as of that date.

Discussion

~Aendices I end 2:

The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide le21 (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/ml) 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 actual measured 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 present in batch releases are reported differently because, on one occasion, the batch release had a positively identifiable nuclide. It should be noted that the curies reported are considered to be significantly overestimated because of the use of design fan flow rates which have consistently been found to be higher than actual flows.

Also, the use of conservatively low background monitor readings for determining the net activity released also contributes to overestimating the curies released.

No activity above background was detected in any continuous liquid release pathway.

Therefore, the summations of liquid effluents are based on the volume determinations and nuclides identified in batch releases only.

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Discussion continued A total of 105 m3 of solid waste, containing 2.6 Ci of radioactivity, was shipped for burial during the report period.

~Aendix 3:

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

~Aendix 4:

Changes made to the ODCM during this report period are listed.

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 or the Land Use Census during this reporting period.

~Aendix 6:

All effluent monitor inoperabilities greater than 30 days are with a brief explanation.

During these periods, compensatory flow rate estimations consistent with Technical Specification have provided accountability and control of effluents.

given along sampling and requirements 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.

~Aendix 6 The 1987 annual summary of meteorological data is available to the NRC upon request.

~Aendix 9 The effluent quantities reported for both semiannual periods in 1987 were combined for determining the the annual dose impact from plant operations.

These doses were calculated by the programs LADTAP XX (for liquid effluents),

GASPAR (for gaseous effluents),

and XOQDOQ (for meteorological data).

These are NRC approved programs for implementing Reg Guide 1.109 methodology, which is also the basis of the ODCM calculations.

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Discussion continued Enclosure 1 shows the 50-mile integrated population doses (in man-rem) due to liquid and gaseous releases for the various applicable pathways.

When appropriate, the doses are also broken down by age group (adult, teen, etc.)

and organ (bone, thyroid, etc.).

Also, the tritium contribution to the hydrosphere is shown.

Because of the recreational nature of Harris Lake, some portions of the lake are within the site boundary.

Enclosure 2 shows the doses (in mrem/yr) to a hypothetical member of the general public due to such recreational activities.

The highest total body dose corresponds to 0.130 of the applicable dose limit, and the highest organ dose corresponds to 0.37%%d of the applicable dose limit.

Enclosure 3 shows the hypothetical doses (in mrem/yr) for the "Likely Most Exposed Individual".

For the liquid pathways, this calculation assumes that Lillington, the closest downstream public water supply, is the source of drinking water and Harris Lake is the source of all other liquid exposure.

For liquid effluents, the highest total body dose corresponds to 0.23K of the applicable dose limit, and the highest organ dose corresponds to 0.37~a of the applicable dose limit.

The gaseous dose consider two types of individuals:

(1) the "Maximum Hypothetical Individual", who resides at the site boundary in the sector of highest plume exposure, and (2), the "Maximum Real Individual" who, based on the land use census, had the highest combined dose from his actual exposure pathways, i.e. plume, ground, vegetation, and inhalation.

Of these persons, the highest total body dose corresponds to 0.41o of the applicable dose limit, and the highest organ dose corresponds to 0.96K of the applicable dose limit.

Beta and gamma annual air doses were 0.&o and 1

O~o of their respective limits.

Enclosure 4 lists the major assumptions associated with the liquid and gaseous effluent doses.

!Sere available, site specific information is used to derive these values.

In other cases, parameter values or derivations are as given in Reg Guide 1.109.

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 1: Supplemental Information 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 noble gases.

{1)

Tritium:

MPC = 3.0E-3 uCi/ml; and

{2)

Dissolved and Entrained gases:

MPC = 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 July 1, 1987 to December 31, 1987 Appendix 1: Supplemental Information 4.

Batch Releases A.

Liquid (1) Number of batch releases:

(2) Total time period for batch releases:

(3) Maximum time for a batch release:

(4) Average time for a batch release:

(5) Minimum time for a batch release:

3.27 E+02 1.35 E+05 min.

8.64 E+02 min.

4.33 E+02 min.

2.00 E+00 min.

(6) Average stream flow during periods of release:

4.50 E+03 gpm B.

Gaseous (1) Number of batch releases:

(2) Total time period for batch releases.'3)

Maximum time for a batch release:

(4) Average time for a batch release:

(5) Minimum time for a batch release:

3.00 E+00 1.50 E+02 min.

9.00 E+Ol min.

5.00 E+Ol min.

2.00 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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LOWER LIMITS OF DETECTION (LLD)

1. LLD's for Gaseous Effluents NUCLIDB H 3~l Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Kr-85 Kr 85m Kr 87 Kr 88 Sr-89 Sr 90 Nb-95 Mo-99 Ru-103 I -131 Xe-131m I -133 Xe-133 Xe-133m Cs-134 I -135 Xe-135 Xe-135m Cs-137 Xe-138 Ba-140 La-140 Ce-141 Ce-144 Gross Alpha LLD (uCi/cc) 9.16 B-09 4.42 E-08 6.57 E-14 1,79 E-14 1.79 E-14 4.40 E-14 2.51 E-14 6.71 E-14 3.44 E-08 6.64 E-09 4.22 E-08 2.34 E-08 7.53 E-16 4.12 E-16 1.74 E-14 2.92 E-13 1.18 E-14 4.54 E-14 2.42 E-07 3.03 B-13 7.74 E-08 1.73 E-07 1.28 E-14 9.64 E-10 1.34 E-08 7.24 E-08 1.62 B-14 9.40 B-08 5.17 E-14 4.27 E-14 2.04 E-14 9.65 E-14 2.69 B-15

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LOWER LIMITS OF DETECTION (LLD) 2.

LID's for Liquid Bffluents NUCLIDE H-3 Na-24 Ar-41 Cr 51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Kr 85m Sr-89 Sr 90 Zr-95 Nb-95 Mo-99 Tc-99m Rh-105 RU-105 I -131 I -133 Xe-133 Xe-135 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 W-187 Gross Alpha LLD(uCi/ml) 2.93 E-06 5.01 E-08 6.70 E-08 3.66 E-07 6.95 E-08 3.04 E-08 7.01 E-08 4.19 E-08 7.90 E-08 4.19 E-08 8.94 E-09 5.18 E-09 5.12 E-08 4.89 E-08 2.38 E-07 2.61 E-08 1.80 E-07 6.50 E-08 1.69 E-08 2.41 E-08 9.66 B-08 3.61 E-08 2.35 E-08 2.93 E-08 1.16 E-07 5.77 E-08 3.74 E-08 2.08 E-07 9.12 E-08 6.42 E-08 2/2

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2

Effluents Released Table lA :

GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Units Quarter 3

Quarter 4

Est. Total Error 9o

1. Fission h Activation Gases A.

Total Release B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci uCi/sec 3.43 E+02 6.18 E+02 4.50 E+Ol 4.31 E+Ol 7.78 E+Ol 4.70 E-Ol 8.60 E-Ol

2. Iodines A.

Total I-131 B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci 0.00 E+00 0.00 E+00 2.00 E+Ol uCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00

3. Particulates A.

Particulates with Tl/2> 8 days B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci uCi/sec 0.00 E+00 5.57 E-13

~o 0 00 E+00 9 15 E 06 0.00 E+00 4.43 E-06 2.00 E+Ol D.

Gross Alpha Radioactivity Ci 8.37 E-08 2.96 E-07

4. Tritium A.

Total Release B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci 0.00 E+00 0.00 E+00 3.00 E+Ol uCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2/3

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2

Effluents Released Table 1B GASEOUS BFFLUENTS ELEVATED RELEASES All releases at Shearon Harris are made as ground releases.

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2

Effluents Released Table 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES Fission and Activation Gases Continuous Mode 0 Nuclides Units Quarter Quarter Released 3

4 Batch Mode-Quarter Quarter 3

H-3 Ar-41 Kr-85 Kr 85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

< LLD

< LLD LLD 7.41E+00 2.47E+00 1.23E+Ol

< LLD 2.96E+02 4.94E+00 1.73E+Ol

< LLD 2.47E+00

< LLD

< LLD 1.34E+Ol 4.44E+00 2.23E+Ol

< LLD 5.33E+02 8.90E+00 3.12E+Ol

< LLD 4.44E+00

< LLD

< LLD 6.10E-02 I LD

< LLD

< LLD LLD

< LLD Total for Period Ci 3.43E+02 6.18E+02 6.10E-02

< LLD 0 Noble Gas quantities apportioned as per GALE code.

2.

Iodines Nuclides Released Continuous Mode Units Quarter Quarter 3

Batch Mode Quarter Quarter 3,

4 I-131 I-133 I-135 Total for Period Ci Ci Ci Ci

< LLD

< LID

< LLD

< LLD 2/5

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Effluents Released Table 1C (Continued):

GASEOUS EFFIUENTS GROUND LEVEL RBLEASBS 3.

Particulates Continuous Mode C

Batch Mode Nuclides Released Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr 89 S~90 Mo-99 Cs-134 Cs-137 Ba/La-140 Ce-141 Ce-144 Gross Alpha Units Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 3

< LLD

< LLD LLD 8.37 B-08 Quarter 4

< LLD

< LLD 4.43 B-06

< LLD

< LLD LLD

< LLD

< LLD LLD

< LLD

< LLD 2.96 B-07 Quarter 3

< LLD

< LLD LLD

< LLD

< LID

< LLD

< LLD Quarter 4

< LLD

< ILD

< LLD

< LLD Total for Period Ci 8.37 E-08 4.73 E-06

< LLD

< LLD 2/6

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Semiannual Radioactive Bffluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Haste Disposal Report Enclosure 2

Effluents Released Table 2A

LIQUID EFFLUBNTS SUMMATION OF ALL RELEASES Units l.

Fission

& Activation Products Quarter 3

Quarter 4

Est. Total Error

~o A.

C.

Total Release (not including tritium,

gases, or alpha)

Average Diluted Concentration during Period Percent of Applicable Limit Ci uCi/ml 4.21 E-Ol 3.91 B-Ol 3.50 E+Ol 1.70 E-10 1.89 E-10 1.89 E-Ol 2.10 E-Ol 2.

Tritium A.

B.

C.

Total Release Average Diluted Concentration during Period Percent of Applicable Limit Ci uCi/ml Og 1.27 B+02 6.04 E+Ol 3.50 E+Ol 5.14 B-05 2.93 E-05 1.71 B-02 9.76 E-03

3. Dissolved and Entrained Gases A.

B.

C.

Total Release Average Diluted Concentration during Period Percent of Applicable Limit Ci uCi/ml 3.24 B-02 1.15 E-03 3.50 E+Ol 1.31 E-08 5.58 E-10 6.54 B-05 2.79 E-06 4.

Gross Alpha Radioactivity Total Release Ci

< LLD

< LLD 3.50 B+Ol 5.

6.

Volume of water released (prior to dilution)

Volume of dilution water used during period liters liters 2.06 E+07 1.21 E+07 1.00 E+Ol 2.46 E+09 2.06 B+09 1.00 B+Ol 2/7

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Waste Disposal Report Bnclosure 2

Bffluents Released Table 2B LIQUID BFFLUENTS 1.

Fission and Activation Products Continuous Mode Batch Mode Nuclides Released H-3 Na-24 Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Sr 89 Sr-90 Y -91m Zr/Nb-95 Mo-99 Tc-99m Ru-103 Ru-105 Sn-113 Te-131 I -131 I -133 Cs-134 Cs-137 Ba/La-140 Ce-141 Ce-144 Hf-181 W;187 Gross Alpha Units Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Quarter 3

< LLD

< LLD LLD

< LLD

< LID

< LLD

< LID

< LLD

< LLD Quarter 4

< LLD

< ILD

< LLD

< LLD Quarter 3

1.27 E+02 1.36 E-03 1.94 E-02 5.51 E-02

< LLD

< LLD 3.18 E-Ol 7.87 B-03 9.71 E-03

< LLD

< LLD 3.26 E-05 4.47 E-03 5.86 E-05 4.42 E-04

< LLD 1.73 E-04

< LLD 2.60 E-05 1.34 E-03 2.07 E-03 LLD 1.28 E-04 1.59 E-03

< LLD

< LLD 7.47 E-05

< LLD Quarter 4

6.04 B+Ol 1.48 E-03 4.84 E-02 1.29 E-02 1.25 E-03 2.20 E-04 2.74 E-ol 2.29 B-02 1.25 E-02

< LLD LLD 6.43 E-06

< LLD 1.32 E-02 1.22 E-04 2.61 E-04 5.16 E-05 3.99 E-05 7.75 E-05

< LLD 6.60 E-04 2.35 E-03 1.01 E-05

< LLD

< LLD 9.09 E-05 3.17 B-04 3.58 E-04

< LLD Total for Period Ci

< LLD

< LLD 1.27 E+02 6.08 E+Ol 2/8

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: Effluent and Waste Disposal Report Enclosure 2

Effluents Released Table 2B (Continued)

LIQUID EFFLUENTS 2.

Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter 3

Quarter 3

Quarter 4

Ar-41 Kr-85m Xe-133 Xe-135 Ci

< LLD

< LLD Ci

< LLD

< LLD Ci

< LLD

< LLD Ci

< LLD

< LLD 2.05 E-05

< LLD

< LLD 3.24 E-02 1.13 E-03 Total for Period Ci

< LLD

< LLD 3.24 E-02 1.15 E-03 2/9

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 2: 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 CIASS A )

A.

Type of waste Units 6 month Period Est. Total Solid. Cont.

No.

Error (R)

Agent Type Form Ship a.

b.

Co Spent Resin, filter m3

sludge, evaporator bottoms, etc.

Ci Dry Compressible m3

Waste, contaminated equipment, etc.

Ci Irradiated Components, m3 Control rods, etc.

Ci 1.05 E+02 1.00 E+Gl Cement STP S/D 9

2.6l E+00

'o waste of this type shipped.

No waste of this type shipped.

d.

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

B.

Estimate of Major Nuclide Composition (by type of waste)

Type of Waste a.

Nuclide H -3 Mn-54 Co-58 Fe-55 Others WWf Percent Composition 8.40 E+Ol 1.84 E+00 1.05 E+Ol 2.34 E+00 1.35 E+00 Total Activity Ci 2.19 E+00 4.79 E-02 2.73 E-ol 6.11 E-02 3.50 E-02 b.

No waste of this type shipped.

c.

No waste of this type shipped.

d.

No waste of this type shipped.

STP Strong Tight Package S Solidified D Dewatered Others include Be-7, C-14, Cr-51, Co-57, Co-60, Fe-59, Ni-63, Nb-95, Zr-95, Tc-99, I-129, Cs-136, Cs-137, La-140.

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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 Mode of Transportation Destination 9.00 E+00 Truck 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.

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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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Semiannual Radioactive Effluent Release Report July,l, 1987 to December 31, 1987 Appendix 4:

Changes to the Offsite Dose Calculation Manual (ODCM)

Technical Specification 6.14 1.0 Explanation for changes Four changes to the ODCM were made during the specified time period.

They are described in Section 2.0 of this Appendix.

Items 1, 2, and 3 were made in response to License Change 87"001 which permitted continuous releases from the secondary waste system.

The changes are made for editorial clarity and consistency.

Item three provides guidance for reassessing the monitor set point should radioactivity be detected in the secondary system.

Change Item 4 installs the 1987 landuse data into the ODCM thereby, updating Table 3.2-2 with the most recent field information.

2.0 Change Descriptions 1.

Page 2-1, Section 2.0, Replace:

"Planned continuous liquid releases containing..radioactivity do not presently occur at SHNPP and

thus, these are considered as nonroutine release pathways."

with:

"Continuous liquid releases are considered as nonroutine radioactive release pathways.

The term nonroutine refers to the low potential for radioactivity in these effluent streams."

2.

Page 2-12, Section 2.1.2, replace the following phrase.

"Planned continuous releases do not presently occur at

SHNPP, although the potential does existed." with:

"The potential for continuous release exists in the secondary waste processing system (see Section 2.1.3) and..."

Start new paragraph at:

"The returns from..."

3 ~

Page 2-16, Section 2.1.3.3, add the following paragraph:

In the event radioactivity is

detected, the release may continue provided the effluent is periodically sampled and it is determined that the sum of the concentration of radionuclide "i" in the unrestricted area divided by that isotope's MPC is less than unity.

The monitor set point should be reassessed using either Equations 2.1-5 or 2.1-5 A thru D.

4.

Page 3-23, replace Table 3.2-2 with the attached new Table 3.2-2 containing 1987 landuse census data.

MEM/MS-8820100/2/OS2 4/1

4 F

2 0

LIQUID EFFLUENT Liquid releases at SHNPP are divided into batch and continuous modes.

Each mode is further separated into routine and nonroutine release paths.

Routine 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 (SOS) are considered as nonroutine batch release points.

In the

ShTS, 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'-4) and

'should the set point.be

exceeded, releases are automatically terminated.

tion 2.1.3.

Further discussion of these effluent lines is provided in Sec-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 con 'nuous releases ia greater detail.

2.1 COMPLIANCE PITH 10CFR PART 20 (LIQU1DS) 2.1.1 Batch Releases A baton re ease 's tne c.'scnzrge o=

'cuid waste of a c'screte volume.

oaten releases from the SH liouid rzcwzste sys=e" =zy occ.r =ro= treated z.ncry and ho-shove" :znks, secondary waste treatment tznk, waste monitor :asks, and waste evaporator condensate

".asks.

"ne principal sources c= waste

=or "hese tznks are sho w n F'g re 2.1-'

Tne liouid radwzste e=fluent streams a

e snown

'n Figure 2.1-2.

A batch Tne.liouid Dilution flow liquid e=fluent s civerted to releases ('.e.,

more tnan one tank at a time) a"e made from SHNPP.

radwaste system c.'scharges to the cooling tower blowdown line.

depends primer'ly on the blowdown Flow "B."

the waste neutra ization bzs'n, some adc tionzl dilution mzy also occur at release represents tne e.pty'ng o=

one tank on y.

No concurrent liou d batch DCM/ODC-2 2-)

Rev. 2.0

I

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where:

Conc The actual concentration of radionuclide "i" during release "k"

(from Equation 2.1-8),

uCi/ml MPC 'aximum permissible concentration of radio-nuclide "i" from Appendix B, Table ZIf Column 2, of '10CFR20, yCi/ml Note:

Pursuant to 10CFR20-Appendix B, Note 5, "

~

a radionuclide may be considered as not present in a mixture if (a) the ratio of the concentration of. that radionuclide in the mixture (CA) to the concentration limit for that radionuclide specified in Table ZZ of Appendix "B" (MPCA) does not exceed 1/10 (i.e.,

CA/MPCA < 1/10) and (b) the sum of such ratios for all the radionuclides considered as not present in the mixture does not exceed 1/4, i.e.,

CA/MPCA + CB/MPCB..

+ < 1/4."

2.1.2 Continuous Releases i A continuous release is the discnarge of liquid wastes of a nondiscrete vol-

!t ume; e.g.>

=rom a volume o

system that has an 'put =low dur'ng the contin-uous release.

The potential for continuous re ease ex'sts in waste processng.

system (see Sec=ion

2..3) and

.n tne Normal (NSW) System and Emergency Serv'e Water (ESW) Syste".

the secondary Serv'e Ws,ter 2

Tne returns from the NSW Sys em "o he C rculating Wa=er System "re mon'cored by installed radiation monitors

-'.".'ch are covered by Technical Spec'='ca=ion 3.3.3.10.

In adcition, a ~eekly compos'e sample is collected and analyzec in accorcance with Technical Spec'=ication Table 4.11-

= radioactivity is detected

'n either system, 't will be even=ual y c'luted by flow =rom the C'ulating Wate" System.

~ hus, c luted effluent concentra" ions can be either computed with knowlecge o

the circulating wa" er

=" ow and/or mon'ored by pe iocic sampling of the Coolng Tower Basin.

In the event racioactivity is detected in the Emergency Service Wate"

System, then ESW flow, tne Coong DCM/ODC-2 2-12 Rev. 2.0

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determined with either Equation F 1-10 or 2.1-11 'hould the set point be

exceeded, the release is automatically terminated.

Effluent can then be diverted to the secondary waste treatment system for processing and eventual re].ease via the secondary waste treatment tank (see Figures 2 ~ 1 ~ 1 and 2'-2) ~

2.1 3.3 Secondary Waste Treatment System (SWTS)

When no radioactivity is detectable due to primary to secondary

leakage, effluent from the SWTS may be released directly to the environment.

In this event~

the set point for the radioactivity monitor can be determined with either Equation 2.1.10 or 2.1.11.

Should the set point be exceeded, the re-lease is automatically terminated.

In the event radioactivity is detected, the release may continue provided the effluent is periodically sampled and it is determined that the sum of the concentration of radionuclide "i" in the unrestricted area divided by that isotope's MPC is less than unity.

The monitor set point-should be reassessed using either Equations 2.1-5 or 2.1-5 A thru D.

2.2 COMPLIANCE WITH 10CFR50 2.2.1 Cumulation of Doses The cose contr' cion rom tne release of liou d e==luents will be calculated a-least once eve.y 31 days (month y),

and a

c at've s -~ation o

these total body and any organ coses w

1 be maintained ="" caen ca endar cuar=er.

"he dose co tr'u"ion for batch releases and a

1 defined per'ocs cf con"'nuous re ease w'll be ca culated s'ng the follow'ng eoua=ion:

D

-X.

k ik k

) (2 2 1) where'.

D k

The cumulative dose commitment to the total bocy or any organ

=

om tne liquid effluents

releases, mrem'.

ne length of time of release "k" over wnich DCH/ODC-2 2-16

Rev. 2.0

TABLE 3.2-2 DISTANCE TO THE NEAREST SPECIAL LOCATIONS FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (MILES)*

SECTOR EXCLUSION BOUNDARY RESIDENCE MILK ANENAL GARDEN MEAT ANENAL N

NE ENE ESE SSE SSW SW WSW 1 ~ 32 1.33 1.33 1.33 1.33 1.33

,1.33 1.36 1.33 1.33 1.33 1 ~ 33 1.33 1.. 33 26 1.26 2.2 1.7 2 ~ 3 2.0 1.9 2.7 4 ~ 7 4 ~ 4 3.9 2.8 4.3 2.7 2.1 1.8 1.5 2.2 4.6 2.-2 1.7 2.3 4.7 2.8 4 ~ 7 3.9 2.8 4.3 3.0 2.1 3.8 1

9 2.2 1.8 2.3 2.0 4.6 4 '

4 '

2.8 4.3 3

1 2.5 3.8 1.9 As oS May, 1987.

Dis"ance es"'=a-es a"e 0.1 aile exceD-a" inc ex clos ion bosn a a"y.

DCM/ODC-3 3-23 Rev. 2.0

Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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.

I I

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 5

Changes to the Environmental Monitoring Program Enclosure 2

Land Use Census Technical Specifications 3.12.2.a 3.12.2.b No changes were made to the Land Use Census during this report period.

The change shown in Appendix 4 of this report was made during the first six months of 1987 and reported in Appendix 5 of the previous semiannual report.

5/2

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I Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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 Monitor Days Inop.

Reason REM-01MD-3528 Turbine Building Drains Loss of sample flow due to lack of water caused by the dry weather conditions at the time.

REM-1WL-3540 Treated Iaundry and Hot Shower 33 Accumulation of activity in the sample chamber during releases causes the alarm setpoint to be exceeded.

Modification initiated to increase cooling tower blowdown flow will permit a more flexible alarm setpoint.

REM-21WL-3541 Waste Monitor Tank 72 Accumulation of activity in the sample chamber during releases causes the alarm setpoint to be exceeded.

Modification initiated to increase cooling tower blowdown flow will permit a more flexible alarm setpoint.

120 Same as above.

REM-1WS-3542 Secondary Waste Sampling Tank 80 Monitor detector damaged by high temperature water.

Modification initiated to provide cooling water for sample line.

50 Monitor removed from service to prevent damage to the detector due to high temperature water.

A modification was installed to provide cooling water to the sample line.

6/1

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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 Monitor Days Inop.

Reason OAI-21WG-1101 37 Waste Gas Compressor Discharge Oxygen Monitor Component Failure.

Replacement parts ordered and installed.

REM-01AV-3509SA 97 Plant Vent Stack Noble Gas Activity Monitor Background subtract factor being used incorrectly in the firmware of the monitor.

A modification has been initiated to correct.

REM-01TV-3536-1 52 Turbine Building Vent Stack Flow Rate Monitor 37 Failure of flow transmitter.

Replacement parts ordered and installed.

Same as above.

WPB Vent 184 Stack 5

Flow Rate Monitor Problems with calibration of flow control system resulting in discrepancies between actual and expected flow rates.

Modification initiated to correct.

WPB Vent 184 Stack 5A Flow Rate Monitor Problems with calibration of flow control system resulting in discrepancies between actual and expected flow rates.

Modification initiated to correct.

6/2

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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.

6/3

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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 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.

6/4

Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9

Assessment of Radiation Doses Enclosure 1: Population Doses Outside Site Boundary Due to Bffluent Releases l.
Integrated Population Dose Due to Liquid Effluents (man-rem)
A.
50 mile Ingestion Zone Total T. Body GI-LLI 5.29 E-02 7.13 E-02 Bone Liver 1.44 E-03 4.92 E-02 Kidney 4.84 E-02 Thyroid Lung Skin 5.07 E-02 4.47 E-02 6.80 E-03 ADULT TEEN CHILD 3.84 B-02 3.61 E-03 1.09 E-02 5.36 E-02 3.61 E-03 1.20 E-02 9.58 E-04 5.77 E-03 3.25 E-04 3.41 E-02 1.52 E-04 1.12 E-02 3.16 B-02 3.91 E-03 1.32 E-02 3.68 E-02 3.53 E-03 1.05 B-02 3.09 E-02 3.41 E-03 1.05 E-02 6.80 E-03 ~
3.41 E-03 ~
0.00 E+00 Fish Consumption Total 2.73 E-03 2.39 E-02 1.29 E-03 5.08 E-03 2.11 E-03 9.32 E-04 1.10 E-03 ADULT TEBN CHILD 2.14 E-03 2.56 E-04 3.3& E-04 2.05 E-02 2.17 E-03 1.27 E-03 8.67 E-04 1.40 E-04 2.79 E-04 3.78 E-03 5.57 E-04 7.41 E-04 1.60 E-03 2.21 E-04 2.85 E-04 7.29 E-04 8.67 E-05 1.16 E-04 8.47 E-04 1.10 E-04 1.44 E-04 Drinking Mater Total 4.42 E-02 4.74 E-02 1.50 E-04 4.42 E-02 4.37 E-02 4.38 B-02 4.36 E-02 0.00 E+00 ADULT TEEN CHILD 3.03 E-02 3.35 B-03 1.05 E-02 3.31 E-02 3.60 E-03 1.07 E-02 9.13 E-05 1.18 E-05 4.63 E-05 3.03 E-02 3.35 E-03 1.05 E-02 3.00 E-02 3.31 E-03 1.04 E-02 3.01 E-02 3.32 E-03 1.04 E-02 3.00 E-02 3.30 B-03 1.03 B-02 0.00 E+00 0.00 B+00 0.00 E+00 Shoreline Swimming Boating 5.78 E-03 7.75 E-05 3.88 E-05 5.78 E-03 7.75 E-05 3.88 B-05 6.80 E-03
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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9
Assessment of Radiation Doses Enclosure 1 (Continued):
Population Doses Outside Site Boundary Due to Effluent Releases B.
Tritium (Hydrosphere)
T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin Total 3.31 E-03 3.31 E-03 0.00 E+00 3.31 E-03 3.31 E-03 3.31 E-03 3.31 E-03 0.00 E+00 2.
Integrated Population Dose Due to Gaseous Effluents (man-rem) 50 mile Ingestion Zone T. Body GI-LLI Bone Liver Kidney Thyroid Skin Total 3.498 E-01 3.498 E-Ol 3.498 E-Ol 3.498 E-Ol 3.498 E-Ol 3.498 E-Ol 3.731 E-Ol 1.181 E+00 Plume Ground Inhalation Vegetation Cow Milk Meat h Poultry 3.498 E-ol 1.115 E-06 9.346 E-09 7.447 E-08 7.286 E-09 5.296 E-08 3.498 E-Ol 1.115 E-06 3.673 E-07 4.271 E-07 3.756 E-08 3.799 E-07 3.498 E-ol 1.115 E-06 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 3.498 E-ol 1.115 E-06 6.659 E-09 2.946 E-08 2.817 E-09 2.215 E-08 3.498 E-Ol 1.115 E-06 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 3.498 E-ol 1.115 E-06 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 3.731 E-01 1.115 E-06 4.007 E-06 0.000 E+00 0.000 E+00 0.000 E+00 1.181 E+00 1.306 E-06 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 9/2
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Semiannual Radioactive Effluent Release Report July 1, 198V to December 31, 198V Appendix 9
Assessment of Radiation Doses Enclosure 2: Doses to General Public Due to Activities Inside Site Boundary l.
Individual Dose Due to Liquid Effluents (mrem/yr.)
ADULT Fish Shoreline Swimming Boating T. Body 4.31 E-03 3.52 E-03 6.07 E-04 8.45 E-05 9.68 E-05 GI-LLI 3.67 E-02 3.59 E-02 6.07 E-04 8.45 B-05 9.68 E-05 Bone 2.21 E-03 1.42 E-03 6.07 E-04 8.45 E-05 9.68 E-05 Liver 7.00 E-03 6.21 B-03 6.07 E-04 8.45 E-05 9.68 E-05 Kidney 3.40 E-03 2.61 E-03 6.07 E-04 8.45 E-05 9.68 E-05 Thyroid 2.01 E-03 1.22 B-03 6.07 E-04 8.45 E-05 9.68 E-05 Lung 2.17 E-03 1.38 E-03 6.07 E-04 8.45 E-05 9.68 E-05 Skin 7.14 E-04 7.14 E-04 TEBN 6.42 E-03 2.86 E-02 5.15 E-03 9.64 E-03 6.02 E-03 4.61 E-03 4.83 E-03 8.98 E-03 Fish Shoreline Swimming Boating 2.V6 E-03 3.39 B-03 1.27 E-04 1.41 E-04 2.49 E-02 3.39 E-03 1.27 E-04 1.41 E-04 1.49 E-03 3.39 E-03 1.27 E-04 1.41 E-04 5.98 E-03 3.39 E-03 1.27 E-04 1.41 E-04 2.36 E-03 3.39 E-03 1.27 E-04 1.41 E-04 9.50 E-04 3.39 E-03
'.27 E-04 1.41 E-04 1.17 E-03 3.39 E-03 1.27 E-04 1.41 E-04 8.98 B-03 CHILD 3.07 E-03 9.85 E-03 2.65 E-03 5.75 E-03 2.70 E-03 1.60 E-03 1.76 E-03 8.32 E-04 Fish Shoreline Swimming Boating 2.27 E-03 V.08 E-04 4.23 E-05 5.28 E-05 9.05 E-03 7.08 E-04 4.23 E-05 5.28 E-05 1.85 E-03 7.08 E-04 4.23 E-05 5.28 E-05 4.95 E-03 7.08 E-04 4.23 E-05 5.28 E-05 1.90 B-03 7.08 E-04 4.23 E-05 5.28 E-05 7.99 E-04 7.08 E-04 4.23 E-05 5.28 E-05 9.57 E-04 7.08 E-04 4.23 B-05 5.28 E-05 8.32 E-04 9/3
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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9
Assessment of Radiation Doses Enclosure 2 (Continued):
Doses to General Public Due to Activities Inside Site Boundary 2.
Individual Dose Due to Gaseous Effluents (mrem/yr.)
ADULT Plume Ground Inhalation T. Body 2.934 E-03 2.934 E-03 1.760 E-08 3.154 E-ll GI-LLI 2.934 E-03 2.934 E-03 1.760 E-08 1.629 E-09 Bone 2.934 E-03 2.934 B-03 1.760 E-08 0.000 E+00 Liver 2.934 E-03 2.934 E-03 1.760 E-O&
2.411 E-ll Kidney 2.934 E-03 2.934 B-03 1.760 E-O&
0.000 B+00 Thyroid 2.934 E-03 2.934 E-03 1.760 E-O&
0.000 E+00 Lung 3.012 E-03 3.012 B-03 1.760 B-08 1.413 B-08 Skin 6.607 E-03 6.607 E-03 2.062 E-O&
0.000 E+00 TBBN 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 3.012 E-03 6.607 E-03 Plume Ground Inhalation 2.934 B-03 1.760 E-08 4.226 B-ll 2.934 B-03 1.760 E-O&
1.449 E-09 2.934 E-03 1.760 E-08 0.000 B+00 2.934 E-03 1.760 E-O&
3.154 E-ll 2.934 B-03 1.760 E-08 0.000 E+00 2.934 E-03 1.760 E-08 0.000 E+00 3.012 E-03 1.760 B-08 2.046 E-08 6.607 E-03 2.062 E-O&
0.000 E+00 CHILD 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 3.012 E-03 6.607 E-03 Plume Ground Inhalation 2.934 E-03 1.760 E-O&
4.817 E-ll 2.934 E-03 1.760 E-O&
5.233 E-10 2.934 E-03 2.934 E-03 2.934 E-03 1.760 E-08 1.760 E-08 1.760 E-O&
0.000 E+00 2.698 E-ll 0.000 B+00 2.934 E-03 3.012 E-03 6.607 E-03 1.760 E-08 1.760 E-O&
2.062 E-O&
0.000 E+00 1.684 E-08 0.000 E+00 INFANT 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 2.934 E-03 3.012 E-03 6.607 E-03 Plume Ground Inhalation 2.934 E-03 3.854 E-07 2.771 E-ll 2.934 E-03 3.854 E-07 1.694 E-10 2.934 E-03 3.854 E-07 0.000 E+00 2.934 E-03 3.854 E-07 1.857 E-ll 2.934 E-03 3.854 E-OV 0.000 E+00 2.934 E-03 3.854 E-07 0.000 E+00 3.012 E-03 3.854 E-07 1.183 B-08 6.607 E-03 4.515 E-07 0.000 E+00
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Semiannual Radioactive Bffluent Release Report July 1, 1987 to December 31, 1987 Appendix 9
Assessment of Radiation Doses Enclosure 3:
Doses to likely Most Bxposed Member of the Public l.
Individual Dose Due to Liquid Effluents (mrem/yr.)
ADULT Fish Drinking Shoreline Swimming Boating T. Body 4.98 E-03 3.52 E-03 6.70 E-04 6.07 B-04 8.45 E-05 9.68 E-05 GI-LLI 3.74 E-02 3.59 E-02 V.31 E-04 6.07 E-04 8.45 E-05 9.68 E-05 Bone 2.21 B-03 1.42 E-03 2.02 E-06 6.07 E-04 8.45 B-05 9.68 E-05 Liver 7.67 E-03 6.21 E-03 6.70 E-04 6.07 E-04 8.45 E-05 9.68 B-05 Kidney 4.06 E-03 2.61 E-03 6.63 E-04 6.07 E-04
, 8.45 E-05 9.68 B-05 Thyroid 2.67 E-03 1.22 B-03 6.65 E-04 6.07 B-04 8.45 E-05 9.68 E-05 Lung 2.83 E-03 1.38 E-03 6.62 E-04 6.07 E-04 8.45 E-05 9.68 E-05 Skin 7.14 E-04 V.14 E-04 TEEN 6.89 E-03 2.91 B-02 5.15 E-03 1.01 E-02 6.49 E-03 5.G8 E-03 5.30 E-03 8.98 E-03 Fish Drinking Shoreline Swimming Boating 2.76 E-03 4.74 E-04 3.39 E-03 1.27 E-04 1.41 E-04 2.49 B-02 5.10 E-04 3.39 E-03 1.27 B-04 1.41 B-04 1.49 E-03 1.69 E-06 3.39 E-03 1.27 E-04 1.41 E-04 5.98 E-03 4.74 B-04 3.39 B-03 1.27 E-04 1.41 E-04 2.36 B-03 4.68 E-04 3.39 B-03 1.27 E-04 1.41 E-04 9.50 E-04 4.69 B-04 3.39 E-03 1.27 E-04 1.41 E-04 1.17 B-03 4.67 E-04 3.39 E-03 1.27 E-04 1.41 E-04 8.98 B-03 CHILD 3.98 E-03 1.08 E-02 2.66 E-03 6.66 E-03 3.60 E-03 2.50 E-03 2.66 E-03 8.32 E-04 Fish Drinking Shoreline Swimming Boating 2.27 E-03 9.11 E-04 7.08 E-04 4.23 E-05 5.28 E-05 9.05 B-03 9.28 B-04 7.08 E-04 4.23 E-05 5.28 E-05 1.85 E-03 4.02 E-06 V.G8 E-04 4.23 E-05 5.28 E-05 4.95 E-03 9.0V B-04 7.08 E-04 4.23 E-05 5.28 E-05 1.90 B-03 8.96 E-04 7.08 B-04 4.23 E-05 5.28 E-05 7.99 B-04 9.00 E-04 7.08 B-04 4.23 E-05 5.28 E-05 9.57 E-04 8.95 E-04 7.08 E-04 4.23 E-05 5.28 E-05 8.32 E-04 CHILD 3.07 E-03 9.85 E-03 2.65 E-03 5.75 B-03 2.70 E-03 1.60 E-03 1.76 E-03 8.32 E-04 Fish Drinking Shoreline Swimming Boating 2.27 E-03 9.11 E-04 7.08 E-04 4.23 E-05 5.28 E-05 9.05 B-03 9.28 E-04 7.08 E-04 4.23 E-05 5.28 E-05 1.85 E-03 4.06 E-06 7.08 E-04 4.23 E-05 5.28 B-05 4.95 E-03 9.07 E-04 7.08 E-04 4.23 E-05 5.28 E-05 1.90 B-03 8.96 E-04 7.08 E-04 4.23 E-05 5.28 E-05 7.99 B-04 9.00 E-04 7.08 E-04 4.23 E-05 5.28 B-05 9.57 E-04 8.95 E-04 7.08 E-04 4.23 E-05 5.28 E-05 8.32 B-04 9/5
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Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9:Assessment of Radiation Doses Enclosure 3 (Continued):
Doses to Likely Most Exposed Member of the Public 2.
Individual Dose Due to Gaseous Effluents (mrem/yr.)
A.
Maximum Hypothetical Individual Exposure from Noble Gases, Particulates,
Iodines, and Tritium T. Body GI-LLI Bone Liver Kidney Thyroid Skin ADULT 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.357 E-02 1.438 E-ol Plume Ground Inhalation Vegetation Milk Meat h Poultry 6.176 E-02 2.044 E-07 V.403 B-10 3.275 E-08 2.320 E-09 8.975 E-09
6. 176 E-02 2.044 E-OV 3.801 E-08 2.962 E-07 2.097 E-08 8.115 E-08
6. 176 E-02 2.044 E-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 6.176 E-02 2.044 E-07 5.659 E-10 1.461 B-08 1.035 B-09 4.004 E-09 6.176 E-02 2.044 E-OV 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 6.176 E-02 2.044 B-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 6.357 E-02 2.044 E-07 3.316 E-07 0.000 E+00 0.000 E+00 0.000 E+00 1.438 2.394 0.000 0.000 0.000 0.000 E-ol 0-07~
E+00 E+00 B+00 TEEN Plume Ground Inhalation Vegetation Milk Meat h Poultry CHILD Plume Ground Inhalation Vegetation Milk Meat 8 Poultry INFANT 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.357 E-02 1.438 E-ol 6.176 B-02 2.044 E-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 6.176 B-02 2.044 E-07 7.403 E-lo 2.158 E-08 1.742 E-09 3.087 E-09 6.176 E-02 2.044 E-07 9.918 E-lo 4.973 E-08 4.014 E-09 7.114 E-09 6.176 E-02 2.044 B-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00 6.176 B-02 2.044 E-07 0.000 E+00 0.000 B+00 0.000 B+00 0.000 E+00
6. 176 E-02 2.044 E-07 4.802 E-07 0.000 E+00 0.000 E+00 0.000 E+00 6.357 E-02 2.044 E-07 3.401 E-08 2.975 E-07 2.402 E-08 4.256 E-08 1.438 2.394 0.000 0.000 0.000 0.000 B-01 E-07 E+00 E+00 E+00 E+00
6. 176 E-02 2.044 E-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 E+00
6. 176 E-02 2.044 E-07 6.332 E-lo 3.230 E-08 2.661 E-09 3.606 E-09
6. 176 E-02 2.044 E-07 1.228 E-08 1.884 E-OV 1.552 E-08 2.103 E-08
6. 176 E-02 2.044 E-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 B+00 6.176 E-02 2.044 B-07 0.000 E+00 0.000 E+00 0.000 E+00 0.000 B+00
6. 176 E-02 2.044 B-07 3.953 E-07 O.OOO E+OO 0.000 E+00 0.000 E+00 6.357 E-02 2.044 E-07 1.228 E-08 1.884 E-07 1.552 E-07 2.103 E-08 1.438
2. 394 0.000 0.000 0.000 0.000 B07+
E+00 E+00 E+00 E+00 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.357 E-02 1.438 E-ol 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.176 E-02 6.357 E-02 1.438 E-Ol Plume Ground Inhalation Milk 6.176 E-02 2.044 E-OV 0.000 E+00 0.000 E+00 6.176 E-02 2.044 E-07 4.357 E-10 5.323 E-09 6.176 B-02 2.044 E-OV 6.502 E-lo 1.328 E-08 6.176 E-02 2.044 E-07 0.000 E+00 0.000 E+00 6.176 B-02 2.044 E-07 0.000 E+00 0.000 E+00 6.176 B-02 2.044 E-07 2.776 B-07 0.000 E+00 6.357 E-02 2.044 E-OV 3.977 E-09 1.326 E-08 1.438 E-ol 2.394 E-07 0.000 E+00 0.000 E+00 9/6
0 4
)
)I
Semiannual Radioactive Effluent Release Report July 1, 19&7 to December 31, 1987 Appendix 9
Assessment of Radiation Doses Enclosure 3 (Continued):
Doses to Likely Most Exposed Member of the Public 2.
Individual Dose Due to Gaseous Effluents (mrem/yr.)
B.
Maximum Real Individual Exposure from Noble Gases, Particulates,
Iodines, and Tritium T. Body GI-LLI Bone Liver Kidney Thyroid Lung Skin ADULT 2.163 8-02 2.163 8-02 2.163 E-02 2.163 E-02 2.163 E-02 2.163 E-02 2.225 8-02 4.996 8-02 Plume Ground Inhalation Vegetation 2.163 8-02 9.564 8-08 2.451 8-10 1.533 8-08 2.163 8-02 9.564 8-08 1.259 8-08 1.386 8-07 2.163 E-02 9.564 8-08 0.000 8+00 0.000 8+00 2.163 8-02 9.564 8-08 1.874 8-10 6.837 8-09 2.163 8-02 9.564 E-08 0.000 E+00 0.000 8+00 2.163 8-02 9.564 E-O&
0.000 8+00 0.000 8+00 2.225 8-02 9.564 8-08 1.098 8-07 0.000 8+00 4.996 8-02 1.120 8-07 0.000 8+00~
0.000 8+00 TEEN 2.163 E-02 2.163 8-02 2.163 8-02 2.163 8-02 2.163 8-02 2.163 8-02 2.225 E-02 4.996 E-02 Plume Ground Inhalation Vegetation 2.163 8-02 9.564 8-08 3.284 8-10 2.327 8-08 2.163 8-02 9.564 8-08 1.126 8-08 1.392 8-07 2.163 8-02 9.564 E-08 O.OGO 8+00 0.000 8+00 2.163 E-02 9.564 8-08 2.451 8-10 1.010 8-08 2.163 E-02 9.564 8-08 0.000 8+00 0.000 E+00 2.163 8-02 9.564 8-08 0.000 8+00 0.000 8+00 2.225 8-02 S.564 8-08 1.590 8-07 0.000 8+00 4.996 8-02 1.120 8-07 0.000 E+00 O.GOO 8+00 CHILD 2.163 E-02 2.163 E-02 2.163 8-02 2.163 E-02 2.163 8-02 2.163 E-02 2.225 8-02 4.996 E-02 Plume Ground Inhalation Vegetation 2.163 8-02 9.564 8-08 3.742 8-10 4.627 8-08 2.163 8-02 9.564 E-08 4.066 8-09 8.817 8-08 2.163 E-02 9.564 8-08 0.000 8+00 0.000 8+00 2.163 8-02 9.564 8-08 2.0S6 8-10 1.511 8-08 2.163 8-02 9.564 8-08 0.000 8+00 0.000 8+00 2.163 8-02 9.564 E-O&
0.000 8+00 0.000 E+00 2.225 8-02 9.564 8-08 1.309 8-07 0.000 8+00 4.996 8-02 1.120 8-07 0.000 8+00 0.000 8+00 INFANT 2.163 8-02 2.163 E-02 2.163 8-02 2.163 8-02 2.163 8-02 2.163 8-02 2.225 E-02 4.9S6 8-02 Plume Ground Inhalation 2.163 8-02 9.564 8-08 2.153 8-10 2.163 8-02 S.564 8-08 1.317 8-09 2.163 8-02 9.564 E-08 0.000 8+00 2.163 8-02 9.564 8-08 1.442 8-10 2.163 8-02 9.564 8-08 0.000 8+00 2.163 8-02 9.564 8-08 0.000 8+00 2.225 8-02 9.564 E-G&
9.191 8-08 4.996 8-02 1.120 8-07 0.000 8+00 3.
Annual Air Dose (mrad)
A.
Maximum Hypothetical Individual:
Beta
=
1.807 8-01 Gamma
= 9.871 8-02 B.
Maximum Real Individual:
Beta
=
6.196 8-02 Gamma
= 3.45G 8-02 9/7
~
~
h
Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9
Assessment of Radiation Doses
Major Assumptions Used to Calculate Radiation Doses 1.
Doses Due to Liquid Effluents A.
Dilution Factors Iocation Harris Lake Value 1.00 E+Ol Cape Fear River/
Raven Rock Park 1.62 E+03 Cape Fear River 6.67 E+02 Exposure Pathways Shoreline, Swimming, Boating, Fish Consumption Shoreline, Drinking Water (for Lillington, Dunn, and Fayetteville)
Boating B.
Populations Affected Location Value Exposure Pathways Harris Lake Lillington Dunn Fayetteville Harris Lake/
Cape Fear River Cape Fear River/
Raven Rock Park Raven Rock Park 1.10 E+05 person-hours 1.95 E+03 persons 9.00 E+03 persons 1.15 E+05 persons Shoreline, Swimming Drinking Water Drinking Water Drinking Water 5.00 E+04 person-hours 4.40 E+05 person-hours Boating Shoreline 7.84 E+03 person-hours Fishing C.
Doses for Inside Site Boundary and Likely Most Exposed Individuals use the Cape Fear River as the Drinking Water supply and Harris Lake as the source of all other liquid pathway dose.
9/8
~I
'.i II'
.E
Semiannual Radioactive Effluent Release Report July 1, 1987 to December 31, 1987 Appendix 9
Assessment of Radiation Doses Enclosure 4
(Continued):
Major Assumptions used to Calculate Radiation Doses 2.
Doses Due to Gaseous Effluents A.
The 50 mile Ingestion Zone population is 1.47 E+06 persons.
B.
The Maximum Real Individual is located at 1.7 miles in the NNE sector.
C.
The Maximum Hypothetical Individual is located on the site boundary at 1.33 miles in the SSW sector.
D.
For the Inside Site Boundary Individual, access time is assumed to be 400 hour0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />s/yr at 3/4 mile from the plant, which is the closest accessible lake location.
E.
Concurrent meteorology is applied separately to batch vs. continuous release source terms.
The dose commitment from each mode was summed to obtain annual dose.
9/9
OE
~
(
Carolina Power & Light Company HARRIS NUCLEAR PROJECT P. 0.
Box 165 New Hill, North Carolina 27562
.FEB 2 4 1988 File Number'.
SHF/10-13510C Letter Number:
HO-880072 (0)
NRC-611 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 July 1, 1987 through December 31, 1987.
Very truly yours, II R. A. Watson Vice President Harris Nuclear Project MGW:mdt Attachment cc'.
Messrs.,
B. Buckley (NRR)
G. Maxwell (NRC SHNPP)
Dr.
J. Nelson Grace (NRC RII)
MEM/HO-8800720/1/OS1
'0
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~
~
4.
,1

ML18005A318

Text

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