Text

Effluent Release Rept for Jan-June 1987
	ML20236N674
Person / Time
Site:	Oyster Creek
Issue date:	06/30/1987
From:	Fiedler P; GENERAL PUBLIC UTILITIES CORP.
To:	Russell W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	NUDOCS 8711160282
	Download: ML20236N674 (87)
	v • d • e

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SUMMARY

f OYSTER CREEK NUCLEAR GENERATING STATION , 1987-1 SEMIANNUAL EFFLUENT RELEASE REPORT The Semiannual Effluent Release Report is submitted to the United States Nuclear Regulatory Commission'(NRC) every six months in accordance with the Oyster Creek Nuclear Generating Station (OCNGS) Technical 3 Specifications. It summarizes the radioactive liquid and gaseous effluents released and solid radioactive wastes shipped from the OCNGS.'

    .In addition, meteorological data is presented in joint frequency tables per atmospheric stability claos. This report'conclules that exposures to man from OCNGS radioactive effluents are well below the federal limits contained in Title 10, part 50 of the Code of Federal Regulations which are considered by the NRC to be acceptable limits to protect the health and welfare of the public.

For clarity, the report is organized into three parts. Section I provides a brief summary of plant operations for the reporting period.

        -                                                                         1 Section II summarizes the meteorological daca and effluents released from the facility for the reporting period. It itemizes gaseous releases of 1406 curies of fission and activation gases, 0.384 curies of I

non-particulate halogens, 3.26 curies of tritium, and 0.026 curies of particulate radioactivity. In addition, 0.0000217 curies of fission and activation products,. 0.00284 curies of dissolved gases, and 1,38 curies I of tritium were released in 7 batch liquid releases. Section II also l

1 d 1 1 I' ( Ltemizes 258 curies of radioactivity, contained in 89 cubic meters of .1 waste, which was shipped offsite in 12 shipments. These releases are j ( similar to or less than releases of nuclear plants of comparable type, age, and size. The report underscores the fact that all effluents l released were within the federal regulatory requirements of OCNGS i t Technical Specifications, 1 Section III provides an assessment of Oyster Creek's radiological impact on man. Written and tabular output concludes that exposures to .) l man from facility radioactive effluents for this reporting period are 4 l well below the federal regulatory limits specified in 10CFR20, 10CFR50, 1 and the OCNGS Technical Specifications. Section IV provides a detailed listing of all changes made to the Offsite Dose Calculation Manual during the reporting period. No changes were made to the Process Control Plan. Section V reports any effluent monitoring instrument that was k inoperative as per Technical Specification 3.15 for the reporting j 4 period. One effluent monitor was deemed inoperative simoly because a

                                                                                                        *I channel functional test was not performed within the specified time                               t i

period. Cottective action was immediate upon recognition.

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t TABLE OF CONTENTS j i

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l PAGE I I LIST OF TABLES i i i LIST OF FIGURES iii 1

I INTRODUCTION 1 l 1 II EFFLUENT AND WASTE DISPOSAL

SUMMARY

4 III RADIOLOGICAL IMPACT'ON MAN 64 IV PROCESS CONTROL PLAN AND/OR 70 . I OFFSITE DOSE CALCULATION

                                                         . MANUAL CHANGES V EFFLUENT MONITORING INSTRUMENTATION   78 INOPERABILITY RECORD 1

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i l i LIST OF TABLES l r 1 Page j l Table # Title l Table 1A Effluent and Waste Disposal Semiannual Report 12 1987-1. Gaseous Effluents - Summation of all i Releases Tables 18 5 Effluent and Waste Disposal Semiannual' Report 13-14. 1C 1987-1. Gaseous Effluents - Elevated Releases Tables ID & Effluent and Waste Disposal Semiannual Report 15-16 l lE 1987-1. Gaseous Effluents - Ground Level f Releases Table 2A Effluent and Waste Disposal-Semiannual Report 17 1987-1. Liquid Effluents - Summation of all Releases Table'2B Effluent and Waste Disposal Semiannual Report 18 198'i-1, LiqJid Effluents Table 3A & Effluent and Waste Disposal Semiannual Report 19-20 3B 1987-1. Solid Waste and Irradiated Fuel l Shipments Table 4 Meteorological Data Recovery for the Oyster 24 Creek Nuclear Generating Station Table 5 Meteorological Classifications of 31 Atmospheric Stability Table 6 Oyster Creek Joint Frequency Tables of Wind 32-39 Speed and Direction (33 feet) versus Delta Temperature (150-33 feet). 1/1/87 - 3/31/87 Table 7 ' Oyster Creek Joint Frequency Tables of Wind 40-47 ) Speed and Direction (33 feet) versus Delta j Temperature (150-33 feet). 4/1/87 - 6/30/87 q k Table 8 Oyster Creek Joint Frequency Tables of Wind 48-55 J j Speed and Direction (380 f eet) versus Delta Temperature (380-33 feet). 1/1/87 - 3/31/87 Table 9 Oyster Creek Joint Frequency Tables of di'nd 56-63 i Speed and Direction (380 feet) versus Delta ] I c Temperature (380-33 feet). 4/1/87 - 6/30/87

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LIST OF TABLES I Table i Title. Page ] Table 10 Summary of Maximum Individual Doses for 67 the period f rom January,1987 through March, 1987 l

Table 11 Summary-of Maximum-Individual Doses-for 68 l the period from April, 1987 through June, 1987' l Table 12 Summary of Maximum Individual Doses for 69 the period January, 1987 through. June, 1987 l I

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LIST OF FIGURES l l

Figure 4 Title Page 4 1 Meteorological Data: . Schematic Diagram 22 ) of System Components Ond Information Flow l 2 Wind Rose - 33' J;evel - January, 1987 25 through March, 1987-3 Wind Rose - 380' Level - January, 1987 26 l through March, 1987 l 4 , Wind Rose - 33' Level - April, 1987 27 through June, 1987 5 Wind Rose - 380' Level - April,1987 28 through June, 1987 !

6- Oyster Creek Monthly Rainfall 30 l 1 1 l i l l 1 l 1 l l l l l l I 1 l

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l I. INTRODUCTION 1 i i l ? 1 - _1 i { l f i _ - _ _ . . _ - _ _ - - _ - _ _ _ _ _ _ J

I.. INTRODUCTION The Oyster Creek Nuclear Generating Station has generated ' electricity since December, 1969. The operating license permits station operation up to a power level of 1930 megawatts (thermal) at a levelized, installed annual capacity of 620 megawatts (electrical). A more detailed description of the facility can be obtained f rom the Final Environmental Statement. This report is submitted in accordance with Section 6.9 of the Technical Specifications - Appendix A of the Oyster Creek Unit 14 umber 1 Provisional Operating License, DPR-16. Section I i.ncludes a brief summary of the plant operating status f rom January 1,1987 through June 30, 1987. Section II follows the format of USNRC Regulatory Guide 1.21 for the provision of summaries of OCNGS gaseous effluents, liquid effluents and solid waste offsite shipments. In addition, this section provides information on meteorological data for the reporting period of January 1,1987 through June 30, 1987. A description of the meteorological data collection system is provided, as well as joint frequency distribution tables for the various stability classes (in USNRC Regulatory Guide 1.21 format) and cumulative wind roses. l i l O

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         ;r PLANT OPERATIONS

SUMMARY

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j. January 1, 1987 ' Reactor. Shutdown January 6, 1987 Reactor Start-up l l

January 7, 1987 Generator on Line ! January 15, 1987 Generator on line 'at 63% Rated' Power I) January 16, 1987 Reactor Scram January 19, 1987 Reactor Start-up January 20, 1987 Reactor Shutdown Reactor Start-up I January 21, 1987 Generator On Line 4 January 31, 1987 Generator on line at 96% Rated Power j February 14, 1987. Reactor Scram j February 18, 1987 Reactor Start-up February 19, 1987 Reactor Shutdown February 28, 1987 Reactor Shutdown March 9, 1987 Reactor Start-up March 10, 1987 Generator On Line March 15, 1987 Generator on line at 100% Rated Power-March 31, 1987 Generator on line at 100% Rated Power April 15, 1987 Generator on line at 93% Rated Power April 24, 198' Reactor Shutdown April 30, 1987 Reactor Shutdown May 14, 1987 Reactor Start-up May 16, 1987 Generator On Line May 31, 1987 Generator on line at 100% Rated Power June 15, 1987 Generator on line at 100% Rated Power June 30, 1987 Generator on line at 99% Rated Power l

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                                                                                                                  '5 II. EFFLUENT AND WASTE DISPOSAL

SUMMARY

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W j Q , " EFFLUENT AND WASTE OISPOSAL'

SUMMARY

                         >A.            Gaseous Effluents                                         +
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 ;w                                                     ' During the. reporting period,-January 1,l1987,through June 30,.,                                                             j
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1987,' 1.4'1 E3 curies of f,ission and-activation gases,'2.73.E-2 curiesc 7 of:noh-particulate halogensJ(todines) with. half-lives greater than )

                                                                                                                                    .                        .                     A eight- days, 7.52. E-3 curies of ' particulate with half-livos greater '

r than' eight days, and 3.26 curies .of tritium were' released. - The' first 9 ' i andL second. quarter . airborne releases for this period are , summarized

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                      ,                 lin:TflesilA through 1E which are found on pages 12 through 16, i

B. Liquid Effluents

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Al total of 1.17 - E7 -liters of water was processed through the.

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                                       . radwaste. system. Of;this, 5.31 E5 liters containing 1.'38 curies of
                                       . ' activity were' released to the environment. - The first and second t yy                                                                  >"

quarter liquid releases for this period are summarized in Tables 2A ifid$2I which are found on pages 17 and 18. . N C. ,, Solido f' D A i

During the~ reporting period, a total volume of 8.90 El cubic ,s, 1 , ' Q[g'

                                       - meters of' solid waste containing 2.58 E2 curies of radioactivity was g

shippedhffsitein12 shipments. No irradiated fuel was shipped.

                                       - The solid waste shipments are summarized in Tables'3A and 3B which are found on pages 19 and 20.                                                                                       '
                             .D.           Meteorological Data During the reporting period of January 1, 1987 thtough June 30,.

1987, onsite meteorological conditions were monitored and recorded. Joint frequency distribution of wind speed and direction data i i

obtained from the 116 meter (380 feet) and the 10 meter (33 feet) sensors are summarized for each stability class per quarter. Also included are - percent of data recovery and cumulative wind roses for 10 meter (33 f eet) and 116 meter (380 feet) elevations. The meteorological data for this reportinrj period are summarized in Tables 4 through 9 which are found on

                           .pages 26 through 58 and page 63.                                                      ..

b e J e O f L _ _ _ _ _ _ __ _ _ __ _ - -_-- -_

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f, EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FACILITY - Oyster Creek Nuclear Generating Station LICENSEE - Owner - Jersey Central Power & Light Company Operator - GPU Nuclear Corporation

1. Regulatory Limita - After November 19, 1986

a. Fission and Activation Gases:

Technical Specification 3.6.E.1 The gross radioactivity in noble gases. discharged from the main condenser air ejector shall not exceed a 0.21/E Ci/sec af ter the holdup line where F. is the average gamma energy (MeV per atomic transformation). Technical Specification 3.6.K.1 The dose equivalent rate outside of the EXCLUSION AREA due to radioactive noble gas in gaseous effluent shall not exceed 500 mrem / year to the total body or 3000 meem/ year to the skin. Technical Specification 3.6.L.1 The air dose outside of the EXCLUSION AREA due to noble gas released in gaseous effluent shall not exceed: 5 mrad / calendar quarter due to gamma radiation, 10 mead / calendar quarter due to beta radiation, 10 mrad / calendar year due to gamma radiation, or 20 mead / calendar year due to beta radiation. Technical Specification 3.6.N.1 The annual dose to a MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from the OCNGS outside of the EXCLUSION AREA shall not exceed 75 mrem to his thyroid or 25 mren to his total body or to any other organ.

b. Iodines and Particulate Technical Specification 3.6.K.2 The dose equivalent rate outside of the EXCLUSION AREA due to H-3, I-131, I-133, and to radioactive material in particulate having half-lives of 8 days or more in gaseous effluents shall not exceed 1500 mrem / year to any body organ when the dose rate

3. Average Energy

a. First Quarter - 8.20 E-1 MeV

b. Second Quarter - 6.50 E-1 MeV

4. Measurements and Approximation of Total Radioactivity

a. Fission and Activation Gases:

1. Stach - The continuous recording of gross activity and the incorporation of isotopic data obtained from a weekly grab sample analyzed using gamma spectroscopy.

2. AOG Vent - The continuous recording of gross activity and the incorporation of isotopic data obtained from a monthly grab sample analyzed using gamma spectroscopy.

c. TB/Fp Vent - A grab sample is obtained four times a week which is analyzed for isotopic activity using gamma spectroscopy.

b. Iodines:

1. Stack - Filters are changed twice weekly and analyzed using gamma spectroscopy.

2. A0G Vent - Filters are changed twice weekly and analyzed using gamma spectroscopy.

l- 3. TB/Fp Vent - Filters are changed twice weekly and analyzed using gamma spectroscopy. 1

c. particulate:

1. Stack - Filters are changed twice weekly and analyzed using a low background int.ernal proportional beta counter and gamma spectroscopy.

2. AOG Vent - Filters are changed twice weekly and analyzed using gamma spectroscopy.

3. TB/Fp Vent - Filters are changed twice weekly and analyzed using gamma spectroscopy.

d. Liquid Effluents:

Analysis per batch release using gamma ray spectrometry with a GeLi Detector, a low background beta counter, and a liquid scintillation counter.

L Analysis of Error Associated with the Measurement of Radioe7tive Materials in Effluents and Solid Wastes Effluents All stages of the production of effluent estimates.have been assigned l an estimated and conservative error potential. Stages include sample l collection, radiochemical analysis; and compilation of the effluent i estimation process. The use of these error f actors assures that l facility effluents will not be underestimated. Solid Waste The process by which the levels of radioactive materials in solid wastes are estimated is one which requires conservatism throughout. Representative sample analyses and/or surf ace contamination surveys are combined with estimatea of waste volume to provide the level of radioactive materials in solid wastes. Conservative techniques are used in all phases of this process to assure that the amount of radioactive material in solid wastes is not underestimated.

5. Batch Releases

a. Liquid

1. Number of batch releases: