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Semiannual Radioactive Effluent Release Rept Jan-June 1990
	ML18009A637
Person / Time
Site:	Harris
Issue date:	06/30/1990
From:	Barnes H, Pollard A, Richey R; CAROLINA POWER & LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HO-900130-(O), NUDOCS 9009060056
	Download: ML18009A637 (66)
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AC(:ELERATED DIS BUTION DEMONSTRATION SYSTEM q

r REGULATORY INFORMATION DISTRXBUTXON SYSTEM (RIDS)

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

Carolina Power S Light Co.

POLLARD,A.D.

Carolina Power S Light Co.

RXCHEY,R.B.

Carolina Power S Light Co.

RECIP.NAME RECIPIENT AFFXLIATION DOCKET 05000400 R

SUBJECT:

"Semian active Effluent Release Rept Jan-June 1990." W/900830 tr.

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TITLE: 50.36a(a)(2)

Semiannual Effluent Releas~e Reports NOTES:Application for permit renewal filed.

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

HO-900130 (0)

U.S. Nuclear Regulatory Commission ATTN:

NRC Document Control Desk

.Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1

DOCKET NO ~ 50-400 LICENSE NO. NPF-63 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen.'n accordance with Technical Specification 6.9.1.4.,

the Semiannual Radioactive Effluent Release Report is attached for the Shearon Harris Nuclear Power Plant.

This report covers the period from January 1,

1990 through June 30, 1990.

Very truly yours, R.

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

Mr. S.

D. Ebneter (NRC RII)

Mr. J.

E. Tedrow (NRC SHNPP)

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ADOCK OgOOOqOO POC MEM/H0-9001300/1/OS1

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Carolina Power

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

Env'nmental

& Radiation Control Reviewed by:

rh Vu Project Specialist - Radiation Control Reviewed by:

Manager Environmental

& Radiation Control Approved by:

ant General Manager

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Table of Contents Page No.

Introduction Discussion Appendix 1.

Supplemental Information Appendix 1.

2.

3.

2.

Effluent and Waste Disposal Report Lover Limits of Detection (LLD's)

Effluents Released Solid Waste Disposal 2/1 2/3 2/11 Appendix 3.

Changes to Process Control Program (PLP)

Appendix 4.

Changes to Offsite Dose Calculation Manual (ODCM)

Appendix 5.

Changes to the Environmental Monitoring Program 1.

Environmental Monitoring Program 2.

Land Use Census 3/1 4/1 5/1 5/2 Appendix 1.

2.

3.

4.

6.

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

Major Modifications to Radwaste System 7/1

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Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Introduction This Semiannual Radioactive Effluent Release Report is in accordance with Technical Specification 6.9.1.4 to the Shearon Harris Nuclear Power Project (SHNPP) Operating License No. NPF-63. It provides effluent monitoring information obtained in fulfillment of the plant's Radiological Effluent Technical Specifications (RETS).

The Shearon Harris Nuclear Power Plant achieved initial criticality on January 3,

1987.

This report covers the period from January 1,

1990 to June 30, 1990.

During this period, the plant was in Cycle 3 operation.

Discussion Appendices 1 and 2:

The information on gaseous and liquid effluents and solid waste is given in accordance with Regulatory Guide 1.21 (Rev.

1) Appendix B format.

As required by Technical Specification 6.9.1.4, the solid waste table has been supplemented to include 10CFR61 class, type of container and solidification agent or absorbent.

Except for continuous noble gas releases, liquid and gaseous average concentrations (uCi/cc) and total curies released are for only those nuclides that were positively identified. If no activity for a nuclide is reported for a quarter, the Lower Limit of Detection (LLD) tables show a typical sensitivity level for detection of the nuclide.

Continuous noble gas effluent activities wefe based on hourly average stack monitor readings (in uCi/cc) and stack flow rate estimates based on design fan flow rates.

No specific noble gas nuclides were identified in any of the stack gas grab samples taken for characterizing continuous gaseous releases.

Therefore, the total noble gas activities are based on stack monitor readings and apportioned as per the GALE code (NUREG 0017) nuclide assumptions as given in the ODCM.

Nuclides reported in gaseous batch releases are determined from the isotopic analysis for each batch release.

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

Therefore, the reported activities are the summation of nuclides in batch releases only.

A total of 33.86 m

of solid waste, containing 4.933 Ci of radioact)vity, was shipped for burial during this Report period, compared with 101.11 m

and 20.86 Ci shipped during the previous Report period.

Two unplanned gaseous releases occurred during this Report period.

The first release occurred because of an improper valve line-up in the waste gas system.

Approximately 2.38 Ci of noble gases were released, Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CFR50 (total dose)

Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Discussion (continued) limits at the site boundary.

The highest dose was calculated to be approximately 0.012X of its respective limit.

The second release occurred when a gas trap failed on a Waste Gas Decay Tank drain line during a routine draining of the tank.

Approximately 0.0468 Ci of noble gas were released.

Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CPR50 (total dose) limits at the site boundary.

The highest dose was calculated to be approximately 0.001X of its respective limit.

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Appendix 3:

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

Appendix 4:

No changes to the Off-Site Dose Calculation Manual (ODCM) were made during this Report period.

I Appendix 5:

The annual Land Use Census was performed during this Report period.

As a result of the census, Table 3.2-2 of the ODCM, which provides the distances to the nearest special locations, i.e., residences, milk animals,

gardens, and meat animals, will be revised in the next Report Period.

To determine whether any of the new special locations yielded calculated doses greater than the locations previously used, the 1990 land use data was coupled with SHNPP 1989 meteorology, and dose calculations were performed by the GASPAR program using the GALE source terms provided in Table 3.2-1 of the ODCM.

No significant differences in estimated doses occurred as a result of the 1990 changes in the locations of the nearest

resident, garden, or meat animal.

Appendix 6:

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

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

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

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

Appendix 7:

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

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0 Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 1: Supplemental Information 1.

Regulatory Limits A.

Fission and activation gases (1)

Calendar Quarter a.

5 mrad gamma b.

10 mrad beta (2) Calendar Year a.

10 mrad gamma b.

20 mrad beta B.

I-131, I-133, I-135, H-3 and particulates with half-lives greater than eight days (1)

Calendar Quarter a.

7.5 mrem to any organ (2)

Calendar Year a.

15 mrem to any organ C.

Liquid effluents (1)

Calendar Quarter a.

1.5 mrem to total body b.

5 mrem to any organ (2)

Calendar Year a.

3 mrem to total body b.

10 mrem to any organ 2.

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

A.

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

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Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 1 (Continued):

Supplemental Information 2.

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

B.

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

1500 mrem/year to any organ C.

Liquid effluents The concentration of radioactive material released in liquid effluents to unrestricted areas after dilution shall be limited to the concentration specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.

For dissolved and entrained noble gases, the MPC shall be equal to 2.0E-4 uCi/ml.

3.

Average Energy (E)

N/A at SHNPP.

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

4.

Measurements and Approximations of Total Radioactivity A.

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

B.

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

C.

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

D.

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

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Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 1 (Continued):

Supplemental Information 5.

Routine Batch Releases A.

Liquid (1)

Number of batch releases:

(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:

8.90 E+01 5.52 E+04 min.

8.44 E+02 min.

6.20 E+02 min.

2.00 E+00 min.

(6)

Average stream flov during periods of release:

6.31 E+03 gpm B.

Gaseous (1)

Number of batch releases:

(2)

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:

2.60 E+01 1.93 E+04 min.

3.01 E+03 min.

7.44 E+02 min.

3.00 E+00 min.

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0 Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 1 (Continued):

Supplemental Information 6.

Abnormal Releases A.

Liquid No abnormal liquid releases were made in the period.

B.

Gaseous Two unplanned releases occurred during this Report period.

The first release occurred between May 3, 1990 and May 6,

1990, when an incorrect valve line-up allowed gas to escape from the Waste Gas Processing System.

Approximately 2.38 E+00 Ci of noble gas was released to the Waste Processing Building (WPB)

Vent Stack 5.

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

'rap failed on the drain line during a routine draining of a waste gas decay tank.

This allowed approximately 4.68 E-02 Ci of Noble Gas to escape to the WPB, where it was picked up by WPB ventilation and exhausted to atmosphere.

Both releases were monitored by WPB Vent Stack 5 radiation monitors.

Off-site doses were evaluated with respect to 10CFR20 (dose rate) and 10CFR50 (total dose) limits at the site boundary and the highest doses were calculated to be approximately 0.012X and of 0.001/ of their respective limit for the first and second

release, respectively.

Both of the release source terms have been added to the BATCH Mode releases in Appendix 2, Enclosure 2, Table 1.

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Semiannua Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 2: Effluent and Waste Disposal Report Enclosure 1

LOWER LIMIT OP DETECTION (LLD)

1. LLD's for Gaseous Effluents NUCLIDE H 3 Ar-41 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 I -131 Xe-131m I -132 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 (

1.01 4.42 1.08 1.56 1.54 3.72 3.62 5.94 8'6 2.17 3.82 2.63 7'1 4.99 1.43 1.09 1.19 7,78 3,84 1.82 4.48 1,60 1.12 9.64 1.93 4.88 1.42 9.68 3.81 4.27 1.70 7,48 4.28 E-08 E E-13 E-14 E-14 E-14 E-14 E-14 E-06 E-08 E-08 E-08.

E-16 E-16 E-14 E-13 E-14 E-07 E-14 E-13 E-08 E-07 E-14 E-10 E-08 E-07 E-14 E-07 E-14 E-14 E-14 E-14 E-15 uCi/cc)

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Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 1

LOWER LIMIT OF DETECTION (LLD) 2.

LLD's for Liquid Effluents NUCLIDE H -

3 Be-7 Na-24 Ar-41 Cr-51 Mn-54 Fe-'5 Co-57 Co-58 Fe-59 Co-60 Zn-65 Kr-85m Sr-89 Sr-90 Zr-95 Nb-95 Nb-97 Mo-99 Tc-99m Ag-110m Sn-113 Sb-122 Sb-124 Sb-125 Te-131 I -131 I -132 I -133 I

134 Xe-131m Xe-133 Xe-133m Xe-135 Cs-134 Cs-137 Cs-138 Ba-140 La-140 Ce-141 Ce-144 Pr-144 Hf-181 Gross Alpha LLD(uCi/ml) 3.22 E-06 2.77 e-07 4.63 E-08 6.61 E-08 2.99 E-07 2.86 E-08

,1.37 E-07 1.69 E-08 2.80 E-08 6.47 E-08 4.31 E-08 7.28 E-08 3.78 E-08 1.57 E-09 1.43 E-09

'4.72 E-08 5.29 E-08 4.19 E-08

, 2.02 E-07 1.65 E-08 2.43 E-08 3.63 E-08 3.98 E-08 1.62 E-08 7.17 E-08 4.68 E-08 3.49 E-08 3.20 E-08 2.41 E-08 3.49 E-08 1.51 E-06 9.45 E-08 2.28 E-07 4.03 E-08 2.35 E-08 2.93 E-08 2.24 E-07 7.51 E-08 5.77 E-08 3.54 E-08 1.97 E-07 2.31 E-06 2.87 E-08 6.18 E-08 2/2

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Semiannua Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Paste Disposal Report Enclosure 2

Effluents Released Table 1A GASEOUS EFFLUENTS, SUMMATION OF ALL RELEASES Units Quarter Quarter Est. Total 1

2 Error X

Fission

& Activation Gases A.

Total Release B.

Average Release Rate for Period C.

Percent of Technical Specification Limit'i 1.18 E+02 1.65 E+02 4.50 E+01 uCi/sec 1.52 E+01 2.09 E+01 X

4.00 E-01 5.49 E-01 2.

0.00 E+00 0.00 E+00 2.00 E+01 Iodines (I-131, I-133, I-135)

A.

Total Iodines Ci B.

Average Release Rate for Period C.

Percent of Technical Specification Limit

/

0.00 E+00 0.00 E+00

3. Particulates A.

Particulates with T1/2) 8 days B.

Average Release Rate for Period C.

Percent of Technical Sp'ecification Limit Ci uCi/sec 2'6 E-06 1.14 E-06 X

1.97 E-03 1.05 E-03 1,68 E-05 8.99 E-06 2.00 E+01 D.

Gross Alpha Radioactivity Ci 0.00 E+00 0.00 E+00

4. Tritium A.

Total Release'.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci 0.00 E+00 0.00 E+00 3.00 E+01 uCi/sec 0.00 E+00 0.00 E+00 X

0.00 E+00 0.00 E+00 2/3

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Semiannual Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Waste Disposal Report Enclosure 2

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

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Semiannua Radioactive Effluent Release Report January 1,

1990 to June 30, 1990 Appendix 2 (Continued): Effluent and Vaste Disposal Report Enclosure 2

Effluents Released Table 1C GASEOUS EFFLUENTS GROUND LEVEL RELEASES 1.

Fission and Activation Gases Nuclides Released Continuous Mode

Batch Mode **

Units Quarter Quarter Quarter Quarter 1

2 1

2 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

< LLD Ci

< LLD Ci 2.55E+00 Ci 8.48E-01 Ci 4.24E+00 Ci

< LLD Ci 1.02E+02 Ci 1.70E+00 Ci 5.94E+00 Ci

< LLD Ci 8.48E-01

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