Text

Semiannual Radioactive Effluent Release Rept,Jan-June 1988
	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)
	v • d • e

ACCELEMTED DISI'RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

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

Carolina Power

& Light Co.

WATSON,R.A.

Carolina Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION DOCKET g

'5000400 D

05000400'OTES:Application for permit renewal filed.

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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 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B INTERNAL: ACRS AEOD/DSP/TPAB NRR/DEST/PSB 8D NUDOCS-ABSTRACT RGN2 FILE 02 EXTERNAL: BNL TICHLER,J03 NRC PDR COPIES LTTR ENCL 1

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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 PDR ADOCK 05000400 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.

Effluents Released 3.

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 4/1 5/1 5/2 Appendix l.

2.

3.

4.

6.

Additional Technical Specification Responsibilities Inoperability of Liquid Effluent Monitors 6/1 Inoperability of Gaseous Effluent Monitors 6/3 Unprotected Outdoor Tanks Exceeding Limits 6/4 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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'Semiannual Radioactive Effluent Release Report January 1,

1988 to June 30, 1988 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 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

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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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1988 to June 30, 1988 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:

1.49 E+02 7.21 E+04 min.

9.55 E+02 min.

4.84 E+02 min.

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:

(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 9.30 E+Ol min.

5.10 E+Ol min.

3.10 E+Ol min.

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 H 3 A~1 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 RQ-103 I -131 Xe-131m I -3.33 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 E-09 4.42 E-08 6.57 B-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 8.73 E-16 5.35 E-16 1.74 E-14 2.92 B-13 1.18 E-14 4.54 E-14 2.42 E-07 3.03 E-13 7.74 E-08 1.73 E-07 1.28 B-14 9.64 B-10 1.34 E-08 7.24 E-08 1.62 E-14 9.40 E-08 5.17 E-14 4.27 E-14 2.04 E-14 9.65 E-14 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 H - 3 Be-7 Na-24 A~1 Cr 51 Mn-54 Fe-55 Co-57 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 Sn-113 Sb-124 I -131 Xe-131m I -133 Xe-133 Xe-133m Xe-135 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Ce-144 Hf-181 W -187 Gross Alpha

2. 93

3. 81 5.01 6.70 3.66 6.95 9.67 2.25

, 3.04 7.01 4.19 7.90 4.19 7.08 4.33 5.12 4.89 2.38 2.61 1.80 6.50 2.27 1.62 1.69 1.31 2.41 9.66 3.17 3.61 2.35 2.93 1.16 5.77 3.74 2.08 3.82 9.12

6. 42 E-06 E-07 E-08 E-08 B-07 E-08 E-08 E-08 E-08 E-08 E-08 E-08 E-08 E-09 E-09 E-08 B-08 E-07 E-08 E-07 B-08 E-08 E-08 B-08 E-06 E-08 E-08 E-07 E-08 E-08 E-08 E-07 E-08 E-08 B-07 E-08 E-08 E-08 LLD(uCi/ml) 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 1

Quarter 2

Est. Total Error

1. Fission h Activation Gases A.

Total Release B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci uCi/sec 5.82 E+02 8.54 E+02 4.50 E+Ol 7.40 E+Ol 1.09 E+02 6.77 E-Ol 9.99 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 0.00 E+00 0.00 E+00 2.00 E+01 uCi/sec 0.00 B+00 0.00 E+00 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 B.

Average Release Rate for Period C.

Percent of Technical Specification Limit Ci 0.00 B+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

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

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1988 to June 30, 1988 Appendix 2: Effluent and Waste Disposal Report Enclosure 2

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

Fission and Activation Gases Continuous Mode 0 Quarter Quarter 1

2 Batch Mode Quarter Quarter 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 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

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< LLD 5.02E+02 8.37E+00 2.93E+Ol

< LLD 4.19E+00

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< LLD 7.37E+02 1.23E+Ol 4.30E+Ol

< LLD 6.14E+00

< LLD 3.55 E-Ol

< LLD

< LID

< LLD

< LLD Total for Period Ci 5.82E+02 8.54E+02 3.55 E-Ol 0 Noble Gas quantities apportioned as per GALE code.

< LLD 2.

Iodines Nuclides Released Continuous Mode Units Quarter Quarter 1

2 Batch Mode Quarter Quarter 1

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

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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 1C (Continued):

GASEOUS EFFLUENTS GROUND LEVEL RELEASES 3.

Particulates Continuous Mode Batch Mode Nuclides Released Mn-54 Fe-59 Co-58 Co-60 Zn-65 Sr 89 Sr-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 1

< LLD

< LLD 6.55 E-08 Quarter 2

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< LLD Total for Period Ci 6.55 E-08

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Semiannual Radioactive Bffluent Release Report January 1,

1988 to June 30, 1988 Appendix 2: Bffluent and Waste Disposal Report Enclosure 2

Bffluents Released Table 2A

LIQUID EFFLUBNTS SUMMATION OF ALL RELBASES Units 1.

Fission h Activation Products Quarter 1

Quarter Est. Total 2

Error A.

C.

Total Release

{not including tritium,

gases, or alpha)

Average Diluted Concentration during Period Percent of Applicable Limit Ci uCi/ml 4.12 B-03 1.45 E-02 3.50 E+Ol 3.97 E-09 1.19 E-08 5.27 E-03 3.87 E-02 2.

'ritium A.

B.

C.

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

3. Dissolved and Entrained Gases A.

B.

C.

Total Release Average Diluted Concentration during Period Percent of Applicable Limit Ci uCi/ml 3.06 B-04 2.44 E-Ol 3.50 E+01 2.94 B-10 2.00 E-07 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 B. Continuous Release liters 1.45 E+07 5.62 B+06 1.78 E+07 1.00 E+Ol 1.00 E+Ol 6.

Volume of dilution water liters 1.02 E+09 used during period 1.19 B+09 1.00 E+Ol 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 Released Units Quarter 1

Quarter 2

Quarter 1

Quarter 2

H-3 Be-7 Cr 51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Sr 89 Sr-90 Zr/Nb-95 Mo-99 Tc-99m Sn-113 Sb-124 I -131 I -133 Cs-134 Cs-137 Ba/La-140 Ce-141 Ce-144 Hf-181 Gross Alpha 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

< ILD

< LLD

< LID

< LLD

< LID

< LLD

< LID

< LLD

< LID

< LLD

< ILD

< LLD

< LLD 5.97 E+Ol

< LLD

< LLD 1.67 E-04 5.05 E-04

< LLD 3.14 E-03 2.65 E-05 2.43 E-04

< LLD

< LLD 2.52 E-06 3.97 E-05

< LLD

< LLD 4.25 E-06

< LLD

< LLD 2.55 E-06 1.80 E+02 7.41 E-04 4.27 E-02 7.11 E-04

< LLD 5.10 E-06 9.91 E-03

< LLD 2.02 E-03

< LLD

< LLD 4.40 E-04

< LLD 9.59 E-06 5.65 E-05

< LLD 8.09 E-05 7.73 E-06

< LLD 4.86 E-05

< LLD

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< LLD Total for Period Ci

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< LLD 5.97 E+Ol 1.80 E+02 2/8

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1988 to June 30, 1988 Appendix 2: Effluent and Naste'isposal Report Enclosure 2

Effluents Released Table 2B (Continued)

LIQUID BFFLUBNTS 2.

Dissolved and Entrained Gases Continuous Mode Batch Mode Nuclides Released Units Quarter 1

Quarter 2

Quarter 1

Quarter 2

A~1 Kr-85m Xe-131m Xe-133 Xe-133m Xe-135 Ci

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< LLD 2.59 B-04

< LLD 4.75 B-05

< LLD 1.01 E-04 1.26 E-04 2.19 E-Ol 4.49 E-03 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 )

A.

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

No.

Error (4)

Agent Type Form Ship a.

Spent Resin, filter m3

sludge, evaporator

bottoms, etc.

Ci b.

Dry Compressible m3

Waste, contaminated equipment, etc.

Ci c.

Irradiated Components, m3 Control rods, etc.

Ci d.

Other (Describe) m3 Ci 4.96 E+Ol 1.00 B+01 Cement STP S/D 10 1.39 E+00 5.14 E+00 1.00 E+00 NA STP D

2 4.93 B-02 No waste of this type shipped.

No waste of this type shipped.

s.

Estimate of Major Nuclide Composition (by type of waste)

Type of Waste Nuclide Percent Composition Total Activity Ci a.

b.

H -3 C -14 Mn-54 Fe-55 Co-58 Co-60 Ni-63 H -3 C -14 Co-58 4.77 E+Ol 1.15 E-03 4.71 E+00 8.65 B+00 3.25 E+Ol 4.41 B+00 2.04 E+00 9.60 B+Ol

< 0.01 E+00 3.93 E+00 6.64 E-Ol 6.13 E-04 6.55 E-02 1.21 E-Ol 4.52 E-Ol 6.15 E-02 2.84 E-02 4.74 E-02 2.00 B-06 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

Mode of Transportation Destination 1.20 E+Ol 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.

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

, Tennessee.

I F

F 4

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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.

I 1

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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.

They're described in Section 2.0 of this appendix.

Items 1-14 were editorial 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 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.

12.

Page 2-27, Figure "discharge line";

components to the identification in PCR-2103; 6

2.1"2, delete "Blowdown" and replace with add Cooling Tower and CTMU/CTBD Cross-Tie diagram and add "Cooling Tower Blowdown" the flow path.

Changes illustrate the effect of 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 diagram has been corrected to reflect this flowpath.

Also, the footnote indicated by~ has been deleted as unnecessary given this correction.

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

~

0~

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)

(P) (60)

(2.1-0) 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'.

MRR B

~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)

'nsures conformance with the test in Section F below.

DMC/ODC-2 2-4 Rev.

1.0

SP Bkg CR + Bkg + 3.3 2T.

Bkg 3 ~ 3 2T Statistical variance on the background (Bkg) 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

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

mf Spm where:

Z C

(f + B) g

(

)

(T) g (DF ) (f) m B

(2.1-5c)

SPm Set point above background (pCi/ml)

C g

Total radioactivity concentration of gamma-emitting radionuclides in liquid effluent 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

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

Conc (C.)

(U )

i k

k d

(2.1-8) 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:

E (Conc. k /MPC. )

1 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 IIOT SNOWER TANK TREAfEO LAVtlohYA IIOT SIIOWER TAIIK CTHU/CTBD Cro

-T'e O'EM REM.IWL.SS40 SECONOARYWASTE SAMPLE TANK YIASTE MOINToh TAtlK WASTE I'IONIIVII

'fAtlK O'EM REM-TIWS SSTT WASTE NEUTRALIZATION SASIN

'0Z 0OV SETTLING SASIN REM-TIWLASlt LECENOI TANKOA SASIN IIARRIS LAK'E WASt E fVAPORATOh COtlOEtlSAI\\ TAtlK WAS'fE EVAPORATOR COttOEttsnf E tANK RAOIATION EffLVENT MONITOR 0

PUMP

P~

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Figula 2.14 0 TIIEil1.lQUIO EFFLUENT MTiiWAYS TvnevIEOVILolttorLoononAIIISErrLVENrLIIIE TItnslttE Ttloo FLoon ODAltls SVMI'5 YADOoil.

sErAnATon YIA ST f.

NEVTDALIZATION SASIN nEM S

SETTLINO SASIN ovlsloF. IANKADFAOnAIIIEcrLVENT LINE o

8 OUISIDE TANK ANEAODAIN stonM onA'It/

SYSIEM I EM SSO

'AttIIE DIVED'TED 10 SFCotloAnYIYASTE lnEAIMEtlrSYSTEtl "CAIISEOlvcnTED To Lloulo nAOwAST\\

'IDEATMENTSYSTEM 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.

f ll I

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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.

B.

C.

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

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.

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 SECTOR BOUNDARY RESIDENCE 1987 1988 MILK ANIMAI 1987 1988 GARDEN 1987 1988 MEAT ANIMAL 1987 1988 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW

l. 32 1.33 1.33 1.33 1.33 1.33 1.33 1.33 1.36 1.33 1.33 1.33 1.33 1.33 1.26 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 1.8 2.3 3.6 1.9 2.7 4.3 4.4 3.9 2.8 4.3 2.7 2.1 1.8 1.5 2.2 4.6 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 1.7 2.3 1.9 2.7 4.3 3.9 2.8 4.3 3.0 2.1 1.8 1.7 2.2 2.2 1.8 1.8 2.3 2.3 2.0 4.6 1.9 4.4

4. 3 4 4 2.8 2.8 4.3 4.3 3.1 3.1 2.5 2.5

3. 8 1.8 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 SECTOR N

NNB NB ENB E

BSB SE SSB S

SSW SW WSW W

WNW NW NNW DISTANCE (MILES) 2.2 1.8 2.3 1.9 4.3 2.8 4.3 3.1 2.5 1.8 1.7 MEAT TYPE HOGS BEEF BEEF CHICKENS / RABBITS HOGS CHICKENS / GOATS HOGS RABBITS / CHICKENS CHICKENS BEEF BEEF / HOGS OWNER GOODWIN, Woodrow GUNTBR JAMES REST HOME HARRIS MCLEAN POLLARD SMITH, P.

ALLEN, S.

WILLIAMS FISH 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 Monitor Days Inop.

Reason REM-1SW-3500A 55 Service Water Return Sample flow rate measurement problems.

REM-1SW-3500B 54 Service Water Return Loop communications problems.

Extensive troubleshooting required to correct problem.

REM-01MD-3530 Tank Area Drains Drains 61 107 Failure of flow switch caused inaccurate flow measurements.

Replacement parts ordered and installed.

Same as above.

REM-1WL-3540 Treated Laundry and Hot Shower 182 Accumulation of activity in the sample chamber during releases causes the alarm setpoint to be exceeded.

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

REM-21WL-3541 Waste Monitor Tank 182 Accumulation of activity in the sample chamber during releases causes the alarm setpoint to be exceeded.

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

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

FT-1974 AhB 52 Cooling Tower Blowdown Flow Rate Monitor Monitor removed from service to allow for installation of continuous composite sampling 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 Monitor Days 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 Cooling Tower Blowdown Flow Rate Monitor Pre-operational installation and testing not completed until after reporting period 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 Cooling Tower Blowdown Flow Rate Monitor Monitors AM not within allowed tolerances.

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 Monitor Days Inop.

Reason OAI-21WG-1101 93 Waste Gas Compressor Discharge Oxygen Monitor Removed from service to perform modification on drain.

HAIC-21WG-1118B 65 Waste Gas Recombiner Bn Outlet Gas Hydrogen Monitor Component Failure.

Replacement parts ordered and installed.

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

A modification has been initiated to correct.

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

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

Modification initiated to correct.

PNL-1WV-3546 8

182 PNL-lWV-3546-1 WPB Vent Stack 5

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

Modification initiated to correct.

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

Modification initiated to correct.

6/3

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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.

6/4

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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.

6/5

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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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ML18022A688

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