ML20147D263

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Addendum 1 to Oyster Creek Nuclear Generating Station Effluent Release Rept 1986-2 for Jul-Dec 1986
ML20147D263
Person / Time
Site: Oyster Creek
Issue date: 12/31/1986
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20147D267 List:
References
NUDOCS 8801200113
Download: ML20147D263 (13)
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Text

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. Revision No. 1 April 17, 1987 GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION EFFLUENT RELEASE REPORT 1986-2 ADDENDUM 91 I

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8801200113 861231 PDR ADOCK 05000219 R DCD

  1. . Rsvision No. 1 \

. April 17, 1987 i

SUMMARY

OYSTER CREEK NUCLEAR GENERATING STATION 1986-2 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 Cree Nuclear Generating Station (OCNGS) Technical Specifications. It summarizes the radioactive liquid and gaseous effluents released and solid radioactive wastes shipped from the OCNGS.

In addition, meteorological data is p.esented in joint f requency tables per atmospheric stability class. This report concludes that exposures to man f rom OCNGS radioactive ef fluents are well below the federal limi.ts 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 welf are of the public.

For clarity, the report is organized into three parts.Section I provides a summary of plant operations for the reporting period. The reactor was shutdown during the period f rom July 1, 1986 through December 20, 1986 for maintenance and ref ueling. Reactor startup occurred on December 21, 198f for low power testing. .he generator was placed on-line on December 28, 1986.

Section II summarizes the meteorological data and effluents relcased from the facility for the reporting perlad. It itemizes gaseous releases l

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' Revision No. 1 April 17, 1987 i

of 37.1 curies of fission and activation gases, 0.0316 curies of non-particulate halogens, 4.61 curies of tritium, and 0.00232 curies of particulate radioactivity. In addition,. 0.00135 curies of dissolved gases, and 1.07 curies of tritium were released in 9 batch liquid releases.Section II also itemizes 694.2 curies of radioactivity, contained in 445 cubic meters of waste, which was shippsd offsite in 35 shipments. These releases are similar to or less than releases of '

nuclear plants of comparable type, age, and size. The report' underscores the fact that all effluents released were within the federal regulatory requirements of OCNGS Technical Specifications.

Section III provides an assessment of Oyster Creek's radiological impact on man. Written and tabular output concludes that exposures to man f rom f acility radioactive ef fluents for this reporting period are well below the federal regulatory limits specified in 10CFR20, 10CFR50, and the OCNGS Technical Specifications.

The OCNGS Technical Specifications were revised during lthe second '

quarter of the reporting period. Data are reported accordingly..

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' R$'.icion No. 1

  • April 17, 1987 II. EFFLUE IT AND WASTE DISPOSAL

SUMMARY

4_

RQvision No. 1 N'%

April 17,.1987- l EFPLUENT AND WASTE DISPOSAL

SUMMARY

A. Gaseous Effluents During the reporting period, July 1,1986 through -December 31, 1986, 3.71 El curies of fission. ?.nd activation gases, u6.07 E-4 curies of non-particulate halogens (.odines) with half-lives greacer than eight days, 4.46 E-4 curies of particulates with half-lives greater than eight days, and 4.61 curies of tritium were released. . The maximum hourly release rate of gross activity from the stack was-estimated to be 3.86 E-4 microcuries per second which waJ a result of' residual particulate activity and occurred between September 23, 1986 and September 26, 1986. The first and second quarter airborne releases for this period are summarized in Tables IA through IE which are found on pages 12 through 16.

B. Liquid Effluents A total of 1.09 E7 liters of water was processed through the radwaste system. Of this, 6.69 E5 liters containing 1.07 curies of activity were released to the environment. Prior to November 20, 1986, seven liquid releases to the environment were made. No.

' unidentified" gross radioactivity (beta-gamma) w. 3 detected prior to any of these releases, therefore, no maximum concentration of gross ,

radioactivity (beta-gamma) was released to the unrestricted area.

The first and second quarter liquid releases for this period are summarized in T* o'es 2A and 2B whic are f ound on pages 17 and 16.

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RGvis!on No. 1 April A7, 1987 C. Solid During the reporting period, a total vol.ume of 4.45 E2 cubic meters of solid waste containing 6.94 E2 curies of radioactivity was shipped of f site in 35 shipments. No irradiated fuel was c5tpped.

The solid waste shipments are summarized in Tables 3A and 3B which are f ound on pages 19 and 20.

D. Meteorological Data During the reporting period of July 1, 1986 through December 31, 1986, onsite meteorological conditions were monitored and recorded.

Joint frequency distribution of wind speed and direction data obtained from the 116 meter (380 feet) and the 10 meter (33 feet) sensors are summarized for each stability class per que.rter. Also included are percent of data recovery and cumulative wind roses for 10 meter (33 feet) and 116 meter (380 feet) elevations. The meteorological data for this reporting period ace summarized in Tables 4 through 9 which are found on pages 26 through 58 and page 63.

Meteorological data presented in the format described above for the period of January 1, 1986 through June 30, 1986 can be found in the OCNGS Effluent Release Report 1986-1.

i Ravision il April 17, 1987 s

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SdMIANNUAL REFORT 1986-2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l

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l Unit First Second jst. Total Quarter Quarter Error %

A. rission & activation gases

1. Totsl releases (not including tritium, gases, alpha) Ci * (LLD 3.0 El
2. Average diluted concentration during period uCi/ml - -

Percent cf applicable limit l -

l l l 3. l  %

3. Tritium j 1. Total release l Ci I
  • l 1.07 l 3.0 El l
2. Average diluted concentration during period uCi/ml -

4.,56 E-8

l. Percent of applicable limit l  % l -

l 1.52E-3l C. Dissolved and entrained gases l1. Total release I Ci )

  • 1 1.35 E-3 l  ?.0 El l
2. Average diluted concentration during period uCi/ml - 5.76 E-ll l 3.

Percent of applicable limit l  % l -

l 2.87 E-5 l D. Gross alpha radioactivity l 1. Total release l Ci l -

l1.08 E-5 **l 3.0 El l E. Volume of waste released (prior to dilution) liters 0.00 6.69 E5 1.0 El F. Volume of dilution water used during period liters 5.53 E10 8.82 E10 1.0 El

  • NO RELEASES THIS EERIOD.
    • REVISED DATA PROM ORIGINAL REPORT e

Revision il 6

April 17, 1987 l l TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1986-2 LIQUID EFPLUENTS l

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BATCH MODE First Second LLD Nuclides Released Unit __

Q uarter Quarter uCi/ml Ci * ( LLD l 4.12 E-8 l l S:rontium-99 l l l l Ci

  • l ( LLD l l 5.17 E-9 l l l Strontium-00 l l Cesium-134 l Ci l l ( LLD l l 5.73 E-7 l l

Ci *

< LLD l 5.54 E-7 l l_ Cesiuy-137 l l. l l Iodine-131 l Ci l l (LLD i l 4.05 E-7 l l

Cobalt-53 l Ci l l <LLD l l 4.68 E-7 l l

Cobalt-60 l Ci l l <LLD l l 1.57 E-6 l l

Ci l

  • l ( LLD l l 8.04 E-7 l l _ Iton-59 l Ci * <LLD l 7.18 E-7 l

', Zinc-65 l l l l Manganese-54 l Ci l

! ( LLD l } 6.29 E-7 l l __

Ci i

  • i ( gD_ l _l 3.'2 E-6 l l Ch r oinium-51 l Ci * ( LLD 7.22 E-7 l Zirconium-95 l l l l l l Niobium-95 l Cl l
  • l <LLD l l 3.45 E-7 l l _

Molybdenum-99 l Ci }

l <LLD l l 2.62 E-6 _ l, l

l Technetium-99m l Cl l l ( LLD l  ! ,3.83 E-7 l I

Ba r i um -140 l Ci l l ( LLD l l 1.90 E-6 l l )

l Ci l l ( LLD l l 6.27 E-7 l )

l La nt_hanux -140 l

Corium-141 l Ci l l (LLD l l 6.91 E-7 l l

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l TOTAL POR PERIOD l Ci l l (LLD l l l l

] Xenon-133 l Ci l l 4.52 E-4 l l 2.07 E-6 l Xenon-135 l Ci i

  • l 8.95 E-4 l l 4.59 E-7 l l

\ l l l  ! l l _

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l TOTA!. FOR PERIOD l Ci l l 1.35 E-3 l l l t10 RELEASES THIS PERIOD.

- Revision No. 1

  • April 17, 1987 III. RADIOLOGICAL IMPACT ON MAN

Revision No. l' N

April 17, 1987 RADIOLOGICAL IMPACT ON MAN Two principle exposure pathways, inhalation and ingestion, are-available to gaseous and liquid effluent isotopes, respectively, in the .

vicinity of Oyster Creek. Intakes via the inhalation pathway are 'f rom.

gaseous ef fluents, while the ingestion pathway is 'via consumption of shellfish and fish f rom Oyster Creek's discharge canal and Barnegat Bey .

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as well as the consumption of garden vegetables. Additionally, a third-means of exposure is from direct radiation from Oyster Creek effluents.

The maximum hypothetical exposure to any individual f rom liquid pathways would occur to someone standing at the of fsite boundary on the shore of, the discharga canal (direct exposure) and who consumes shellfish and fish (ingest.on). For purposes of this report this hypothetical individual is designated as Receptor $1. Maximum exposure due to gaseous pathways (inhalation, ingestion, and direct radiation) would depend on the predominant wind direction and the location of persons living in a sector around the plant. The direction and distance for this individual is given in Tables 10 and 11, pages 67 and.68.

The f ollowing tables represent the of f site dose summary for the two quarters of the six-month reporting period. The information provided was calculated using the models and methodology outlined in NRC Regulatory Guide 1.109 and proposed NRC Regulatory Guide 1.111. The analysis herein represents the maximum hypothetical liquid and gaseous pathway individual doses (Tables 10, 11, and 12, pages 67, 68, and 69). Also included are the doso limits as given in the Oyster Creek Technical Specifications, the age group, and the receptor location.

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4 Rsvision No. 1

, April 17, 1987 i

For both quarterly periods, the maximum individual exposures resulting from OCNGS operation from all pathways are below the Technical Specification limits.

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RGYision No. 1 April 17, 1987 TABLE 11

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR THE PERIOD FROM OCTOBER 1, 1986 THROUGH DECEMBER 31, 1986 REPORTING PERIOD - OCTOBER 1, 1986 THROUGH NOVEMBER 19, 1986 APP LIC ABLE ESTIMATED AGE LOCATION EFFLUENT ORGAN DOSE GROUP DIST DIR (mrem) (m) (TOWARD)

LIQUID TOTAL BODY 6.71 E-6 ADULT RECEPTOR 1 LIQUID LIVER 6.71 E-6 ADULT RECEPTOR 1 AIR DOSE (T -MRAD) - -

NOBLE GAS * -

NOB LL G AS

  • AIR DOSE (0-MRAD) - -

IODINE &

  • P ARTICULATE - -
  • NO RELEASES DURING THIS PERIOD.

REPORTING PERIOD - NOVEMBER 20, 1986 THROUGH DECEMBER 31, 1986 APPLIC ABLE ESTIMATED AGE ,

LOCATION TECH SPEC EFFLUENT ORGAN DOSE GROUP DIST DIR LIMIT (mrem) (m) (TOWARD)

LIQUID TOTAL BODY 8.77 E-6 ADULT RECEPTOR 1 1.5 mrem /

quarter LIQUID LIVER 8.77 E-6 ADULT RECEPTOR 1 5 mrem /

quarter NOBLE GAS AIR DOSE ( T -MRAD) 1.35 E-3 T - AIR 430 ESE 5 MRAD /

DOSE quarter NOBLE GAS AIR DOSE (B-MRAD) 1.15 E-4 8-AIR 522 SE 10 MRAD /

DOSE quarter I-131, I-133 PARTICULATE THYROID 9.47 E-4 INFANT 966 SE 7.5 mrem /

quarter 4 ;f

. Revision No.J1

,- April 17, 1987 3

-TABLE 12- 4

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES FOR THE PERIOD FROM JULY 1, 1986 THROUGH-DECEMBER 31, 1986 i

APPLICABLE' ESTIMATED TECH SPEC ORGAN SEMIANNUAL .. LIMIT -

EFFLUENT DOSE (mrem)

TOTAL BODY 8.77 E-6 3 mrem / year L10UID LIVER 8.77 E-6 10 mrem / year.

LIQUID TOTAL BODY 2.75 E-31 500 mrem / year NOBLE GAS NOBLE GAS SKIN 2.83 E-3 3000 mrem / year AIR DOSE T (mrad) 1.35 E-3 10 MRAD / year.

NOBLE GAS NOBLE GAS AIR DOSE - 0 (mrad) 1.15 E-4_ 20 MRAD / year H-3, I-1 31, I-133

& PARTICULATES BONE / THYROID 1.06 E-3 1500 mrem / year I-131, I-133 BONE / THYROID 1.06 E-3 15 mrem / year'

& PARTICULATES l

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