ML20212B574
| ML20212B574 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/05/1999 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20212B562 | List: |
| References | |
| 2000-ADM-4532.0, NUDOCS 9909200144 | |
| Download: ML20212B574 (130) | |
Text
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l OYSTER CREEK POLICY AND Numb 2r spgp PROCEDURE MANuAt 2000-ADM-4532.04 NUCLEAR
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Title Revision No.
V Oyster Creek Offsite Dose Calculation Manual 11 Applicability / Scope Responsible Office Environmental Affairs All GPUN Employees 2870 This document is within QA plan scope X Yes No Effective Date Safety Reviews Required X Yes No (09/08/99) 09/18/99 Prior Revision 10 incorporated the This Revision 11 incorporates the j
following Temporary Changes:
following Temporary Changes:
l N/A N/A List of Pages (all pages rev'd to Rev. 11) j 1.0 to 84.0 El-1 E2-1 E3-1 E4-1 ES-1 E6-1 E7-1 E8-1 E9-1 E10-1 to E10-2
-s (v)
E11-1 E12-1 to E12-2 E13-1 to E13-2 E14-1 to E14-3 E15-1 to E15-3 E16-1 to E16-2
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E17-1 to E17-2 E18:
NON-CONTROLLED E20-1 THIS DOCUMENT WILL NOT g:
BE KEPT UP TO DATE E23-1 IRMC 0YSTER CREEK E24-1 to E24-3 E25-1 E26-1 E27-1 Signature Concurring Organization Element Date ncurred Manager - Environmental Affairs
(/ g,,, 1 ) / f g w Manager - Radiological Engineering 9/f/95 l
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Hanager - Radwaste & Chemistry f/gg
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Director, Radiological Health and By N. s).
Approved
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Safety M -tf
' 9909200144 990910 1.0 PDR ADOCK 05000219 F
9 OYSTER CREEK POLICY AND Numb 2r gpg PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
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Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11 DOCUMENT HISTORY PREPARED BY:
EFFECTIVE REVIEWED BY:
REVISION DATE DESCRIPTION OF CHANGE APPROVED BY:
4 11/91 As a " PLAN /RELATED PROCEDURE" the P:
ODCM needs to be formatted as per R:
1000-ADM-1218.01 with an A:
appropriate ID.
5 11/92 As per USNRC Generic Letter 89-01, P:
the RETS and REMP sections of the R:
OCNGS Technical Specifications have A:
been written into the ODCM.
6 01/94 This revision is the initial change P:
to incorporate 10CFR20 updates that R:
are contained within the scope of A:
the ODCM.
Existing levels of effluent control are retained.
7 Clarification and addition of P:
monitoring requirements to match R:
surveillance requirements in ODCM.
A:
8 05/95 Delete the requirements to P:
(N functionally test the overboard R:
(,)
discharge flow element.
At This revision is the second phase designed to incorporate 10 CFR 20 updates found in the ODCM.
In addition, the air dispersion and
~
deposition (D/Q) values are being j
gamma dose factors calculated in a previous revision using the USNRC RABFIN code.
9 01/98 Revise Remp section, add P:
references, revise dispersion X/Q's R:
and make title changes and other A:
non-substantive changes.
10 07/98 Revise Section 4.5 to clea' : y state the method of implementatt or. of the Land-Use Survey specification in accordance with corrective action for violation #2 with USNRC Inspection Report IR 97-011.
Update REMP station azimuths and distances. Update distances to site boundary.
11 08/99 Revised procedure due to CAPS 01999-0492 and 0493.
Corrected references, typographical errors,
('N and replaced boundary diagrams.
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11
)
Oyster Creek Offsite Dose Calculation Manual (ODCM)
Table of Contents Section Page Cover Page 1.0 Document History 2.0 4
Table of Contents 3.0 1.0 Purpose 8.0 2.0 Applicability / Scope 8.0 1
3.0 Definitions 8.0 4.0 Procedure 13.0 l
(
4.1 Effluent Monitor Setpoints 13.0 l
4.1.1 Aqueous Effluent Radioactivity Monitor Setpoints 13.0 4.1.1.1 General 13.0 4.1.1.2 Batch Release 16.0 l
4.1.1.3 Continuous Release 16.0 4.1.2 Gaseous Effluent Monitor Setpcints 17.0 4.1.2.1 General 17.0 4.1.2.2 Setpoint Based on Dose Equivalent Rate 19.0 4.2 Radioactive Liquid Effluent 22.0 4.2.1 Radioactive Concentration in Liquid Effluent-Limits 22.0 4.2.2 Liquid Effluents - 10CFR50 Appendix I Limits 23.0 4.2.3 Projected Dose - Liquid 24.0 I
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 Oyster Creek Offsite Dose Calculation Manual (ODCM)
)
i Table of contents l
Section Page 4.3 Radioactive Gaseous Effluent 25.0 4.3.1 Dose Rate - 10 CFR Part 20 25.0 4.3.1.1 Noble Gases 25.0 4.3.1.2 Total Body Dose Rate 27.0 4.3.1.3 Skin Dose Rate 28.0 4.3.1.4 Radioactive Iodines and Particulates 30.0 4.3.2 Dose - 10 CFR Part 50, Appendix I 32.0 4.3.2.1 Noble Gases 32.0 4.3.2.2 Radioiodine, Particulates, and Other Radionuclides 35.0 4.3.3 Projection of Doses 36.0 4.4 Total Dose - Compliance with 40CFR190.10a 37.0 4.4.1 General 37.0 4.4.2
' Irradiation 40.0 4.4.3 Noble Gas Dose Calculation 40.0 4.5 Radiological Environmental Monitoring Program (REHP) 40.0 4.5.1 Radiological Environmental Surveillance 40.0 4.5.2 Radiological Environmental Program Description and Sample Locations 47.0 Radioactive Effluents Monitoring Program 51.0 4.6 1
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Q PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
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Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11 Oyster Creek Offsite Dose Calculation Manual (ODCM)
Table of Contents l
Section Page i
4.6.1 Radioactive Effluent Requirements 51.0 4.6.1.1 Sections 51.0 4.6.1.2 Basis 61.0 4.6.2 Radiological Effluent Monitoring Requirements 65.0 4.6.2.1 Sections 66.0 4.6.2.2 Basis 69.0 j
4.7 Radioactive Effluent Monitoring Instrumentation 70.0 4.7.1 Radioactive Effluent Monitoring Instrument. Requirements 70.0 4.7.1.1 Sections 70.0
,e-(,)
4.7.1.2 Basis 73.0 4.7.2 Radioactive Effluent Monitoring Instrument. Surveillance 77.0 4.7.2.1 Section 77.0
- 4. 8 Reporting Requirements 78.0 4.8.1 Annual Radioactive Effluent Release Report 78.0 4.8.2 Annual Radiological Environmental Report 79.0 4.8.3 Unique Reporting Requirements 81.0 4.8.4 Basis 82.0 5.0 Responsibilities 82.0 6.0 References 83.0 H
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PROCEDURE MANUAL 2000-ADM-4532.04 NioCLEAll Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 l
LIST OF ATTACHMENTS l
Attachment Page 2000-ADM-4532.04-1 Site Boundary and Effluent Release Locations El Oyster Creek NGS 2000-ADM-4532.04-2 Distribution of Radioactive Noble Gases in Gaseous Effluent E2 2000-ADM-4532.04-3 Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-to-Dose Equivalent Rate Factors E3 l
2000-ADM-4532.04-4 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors E4 2000-ADM-4532.04-5 Air Dose Conversion Factors for Effluent Noble Gas E5 2000-ADM-4532.04-6 Locations Associated with Maximum Exposure of a Member of tne Public E6 2000-ADM-4532.04-7 Critical Receptor Noble Gas Dose Conversion Factors E7 2000-ADM-4532.04-8 The Individual Maximum Hypothetical Exposed Member of the Public at the OCNGS E8 2000-ADM-4532.04-9 Radiological Environmental Monitoring Program Monitoring l
Requirements E9 2000-ADM-4532.04-10 Detection capabilities for Environmental Sample Analysis E10 2000-ADM-4532.04-ll Reporting Levels for Radioactivity Concentrations Ell in Environmental Samples 1
2000-ADM-4532.04-12 Radioactive Liquid Effluent Monitoring Instrumentation E12 2000-ADM-4532.04-13 Radioactive Gaseous Effluent Monitoring Instrumentation E13 2000-ADM-4532.04-14 Radioactive Liquid Waste Sampling and Analysis Program E14 2000-ADM-4532.04-15 Radioactive Gaseous Waste Sampling and Analysis Program EIS 2000-ADM-4532.04-16 Radioactive Liquid Effluent Monitoring Instrumentation l
Surveillance Requirements E16 2000-ADM-4532.04-17 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Eli l
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 LIST OF EXHIBITS Exhibit Page l
2000-ADM-4532.04-1 Atmospheric Dispersion Data E18 2000-ADM-4532.04-2 Assumed Distance To OCNGS Site Boundary E19 l
l 2000-ADM-4532.04-3 (X/Q) In sec/m OCNGS Dispersion Parameters For Elevated l
Releases Stant.ard Distances E20 1
3 2000-ADM-4532.04-4 (X/Q) In sec/m OCNGS Dispersion Para.mezers For Ground Releases Standard Distances E21 2000-ADM-4532.04-5 (D/Q) In ng2 OCNGS Dispersion Parameters For Elevated i
Releases Standard Distances E22 1
2000-ADM-4532.04-6 (D/Q) In ng2 OCNGS Dispersion Parameters For Ground Releases Standard Distances E23 l
2000-ADM-4532.04-7 OCNGS Usage Factors For Individual Dose Assessment E24 2000-ADM-4532.04-8 Radionuclides In Liquid Effluent Used To Assess Compliance With Technical Specifications E25 l
2000-ADM-4532.04-9 Radionuclides In Gaseous Effluent Used To Assess l
Compliance With Technical Specifications E26 2000-ADM-4532.04-10 Exposure Pathways For Radionuclides Potentially Rt7 eased From The OCNGS E27 s
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 1
1.0 PURPOSE 1
The purpose of the Offsite Dose Calculation Manual (ODCM) is to provide information, methodology, and parameters to be used by the Oyster Creek Nuclear Generating Station (OCNGS) in the calculation of radiological doses offsite due l
to liquid and gaseous effluents. The ODCM is designed to provide computational.
methods of assessing compliance with the OCNGS Operating License and Technical Specifications related to radioactive liquid and gaseous effluents and compliance with 10CFR20, 10CFR50 Appendix I, and 40CrR190.
Besides the areas of the ODCM mentioned above, the calculational methodology for determining liquid and gaseous effluent monitoring instrumentation alarm trip setpoints is described in detail.
The pertinent information related to the Radiological Environmental Monitoring Program (REMP), including descriptions and 1
sampling locations, is also included in this manual.
2.0 APPLICABILITY / SCOPE The Offsite Dose Calculation Manual is applicable to those individuals responsible for assessing compliance with radioactive effluent and environmental
~
technical specifications he the Oyster Creek Nuclear Generating Station. This manual provides the methods used in performance of dose assessment during l
routine situations where radioactive material has been or is predicted to be released t" the environment.
3.0 DEFINITIONS 3.1 DEPOSITION (D/Q)
The direct removal of gaseous and particulate species en land or water surfaces. Deposition is expressed as a quantity of material per unit area (e.g. m*8).
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l 3.2 DOSE CONVERSION FACTOR (DCF)
A parameter calculated by the methods of internal dosimetry, which indicates the committed dose equivalent (to the whole body or organ) per unit activity inhaled or ingested. This parameter is specific to the isotope and the dose pathway. Dose conversion factors are 3
commonly tabulated in units of mrem /hr per picoeurie/m in air or water. They can be found in Reg Guide 1.109 appendices.
3.3 EFFLUENT CONCENTRATION (EC)
The liquid and air concentration levels which, if inhaled or ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem. LEC refers to liquid effluent concentration.
3.4 ELEVATED (STACK) RELEASE An airborne effluent plume whose release point is higher than twice the height of the nearest adjacent solid structure and well above any building wake effects so as to be essentially unentrained. Regulatory Guide 1.111 is the basis of the definition of an elevated release.
Elevated releases generally will not produce any significant ground level concentrations within the first few hundred yards of the source.
Elevated releases generally have less dose consequence to the public due to the greater downwind distance to the ground concentration maximum compared to ground releases. All main stack releases at the l
OCNGS are elevated releases.
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Title Revision No.
Oyster Creek offsite Dose Calculation Manual 11 3.5 FINITE PLUME MODEL Atmospheric dispersion and dose assessment model which is based on the assumption that the horizontal and vertical dimensions of an effluent plume are not necessarily large compared to the distance that ganna l
rays can travel in air.
It is more realistic than the semi-infinite plume model because it considers the finite dimensions of the plume, the radiation build-up factor, and the air attenuation of the gamma rays coming from the cloud. This model can estimate the dose to a receptor who is not submerged in the radioactive cloud. It is particularly useful in evaluating doses from an elevated plume or when the receptor is near the effluent source.
3.6 GROUND LEVEL (VENT) RELEASE An airborne effluent plume which contacts the ground essentially at the point of release either from a source actually located at ground elevation or from a source well above the ground elevation which has significant building wake effects to cause the plume to be entrained in the wake and driven to the ground elevation. Ground level releases are treated differently than elevated releases in that the X/Q calculation results in significantly higher concentrations at the ground elevation near the release point.
3.7 MEMBER OF THE PUBLIC An individual who is not occupationally associated with GPU Nuclear and who does not normally frequent the Oyster Creek site. The category does not include contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on the site,
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or for other purposes associated with plant functions. An individual is not'a member of the public during any period in which the individual receives an occupational dose.
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3.0 OCCUPATIONAL DOSE The dose received by an individual in a RESTRICTED AREA or in the course of employment in which the individual's assigned duties involve exposure to radiation and to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the l
licensee or other person. Occupational dose does not include dose i
received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public.
3.9 OFFSITE The area that is beyond the site boundary where the land is neither owned, leased nor otherwise subject to control by GPU.
Can be
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interchanged with UNRESTRICTED AREA.
3.10 RAGEMS l
l A plant system that monitors gaseous effluent releases from monitored
)
release points. There is a RAGEMS system for the main stack j
(RAGEMS I) and one for the turbine building (RAGEMS II).
They monitor i
l particulates, iodines, and noble gases.
3.11 SEMI-INFINITE PLUME MODEL Dose assessment model which is based on the assumption that the dimensions of an effluent plume are large compared to the distance that ganna rays can travel in air.
The ground is considered to be an i
infinitely large flat plate and the receptor is located at the origin I
of a hemispherical cloud of infinite radius. The radioactive cloud is I
limited to the space above the ground plane.
The send-infinite plume
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model is limited to immersion dose calculations.
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3.12 SITE BOUNDARY That perimeter line around the OCNGS beyond which the land or property is not owned, leased, or otherwise subject to control by GPU. (See 000-ADM-4532.04-1.)
3.13 SOURCE TERM j
The activity release rate, or concentration of an actual release or l
l potential release. The common units for the source term are curies, curies per second, and curies per cubic centimeter, or multiples thereof (e.g., microcuries).
3.14 UNRESTRICTED AREA The area that is beyond the site boundary where the land is neither owned, leased, nor otherwise subject to control by GPU.
Can be interchanged with OFFSITE.
3.15 X/Q - (" CHI over Q")
The dispersion factor of a gaseous release in the environment calculated by a point source gaussian dispersion model. Normal units 3
of X/Q are sec/m. The X/O is used to determine environmental atmospheric concentrations by multiplying the source term, represented by Q (in units of uCi/sec or Ci/sec). Thus, the plume dispersion, X/Q (seconds / cubic meter) multiplied by the source term, Q (uci/ seconds) l yields an environmental concentration, X (uci/m ). X/Q is a function 8
of many parameters including wind speed, stability class, release point height, building size, and release velocity.
3.16 SEEDS (Simplified Effluent Environmental Dosimetry System)
A routine ef fluent dosimetry conputer program that uses. Reg. Guides t
l.109 and 1.111 nethodologies.
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PROCEDURE MANUAL 2000-ADM-4532.04 NalCLEAR Title Revision No.
Oyster Creek offsite Dose Calculation Manual 11 4.0 PROCEDURE This section of the ODCM is divided into eight (B) sections, 4.1 Effluent Monitor Setpoints, 4.2 Radioactive Liquid Effluents, 4.3 Radioactive Gaseous Effluents, 4.4 Total Dose-Compliance with 40CFR190.10A, 4.5 Radiological Environmental Monitoring Program (REMP), 4.6 Radioactive Effluents Monitoring Program, 4.7 Radioactive Effluents Monitoring Instrumentation, and 4.8 Reporting Requirements.
4.1 EFFLUENT MONITOR SETPOINTS 4.1.1 Aqueous Effluent Radioactivity Monitor Setpoints 4.1.1.1 General Section 4.7.1.1.1.A and 4.7.1.1.1.B require radioactive liquid effluent monitors to alarm / trip in the event the limit in Section 4.6.1.1.3.A is exceeded. The Reactor Building Service Water Effluent Line monitor causes an alarm in the event its setpoint is exceeded. The Liquid l
Radwaste Effluent Line monitor and the Turbine Building Sump No. 1-5 monitor are designed to cause a trip which halts the respective effluent discharge in the event its setpoint is exceeded.
Each monitor setpoint is derived independently to enable an alarm or trip. The alarm or trip setpoints are selected to assure the Liquid Effluent Concentration (LEC) does not exceed 10 times the 10 CFR Part (20.1001 - 20.2401) Appendix B, Table 2, Column 2 value at the boundary of the OCNGS unrestricted area, i.e.,
at
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the Route 9 bridge across the discharge canal.
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 l
With prompt action to reduce the radioactive release following an alarm, GPU can be reasonably sure that radioactive material in aqueous effluent released to an unrestricted area will comply with the provisions of Section 4.6.1.1.3 and 4.6.1.1.4.
The alarm or trip setpoint of each effluent radioactivity monitor is calculated using the equation:
{10LEC Ci F2 S
=
g + EKG e
i F1 i=1 where S
= radiation monitor alarm setpoint (cpm)
Ci
= concentration of radionuclide i, in effluent g
= ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a sample of liquid (cpm per epm /ml or epm per C1/ml).
F
= flow in the batch release line (e.g. gal / min).
Value not greater than the discharge line flow alarm maximum setpoint.
F
= fl w in the discharge canal (e.g. gal / min). Value 2
not less than the discharge canal minimum flow.
BKG = Monitoring instrument background (cpm)
Ci
= concentration of radionuclide i in effluent, i.e.,
in a liquid radwaste sample tank, in reactor building service water, or in Sump no. 1-5 (pci/ml).
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l 10LEC = Ten times the unrestricted area liquid effluent
{
i l
concentration (LEC) of radionuclide i, i.e.,
10 CFR Part (20.1001 - 20.2401), Appendix B, Table 2, Column 2 quantity for radionuclide i
( Ci/ml).
In the event gross radioactivity analysis alone is used to determine the radioactivity in an effluent stream or batch, 10LEC is 1E-07.
1E-07 = Ten times the unrestricted area LEC for unidentified radionuclides (pci/ml).
If the gross activity concentration, C, is below the lower limit of detection for gross activity, the value,
-7 lx10 pCi/ml, or the equivalent counting rate (epm /ml) l may be substituted for the factor A/F10LEC:
n C1 I
= IE-07 Ci/ml 1,3 10LEC1 1
Usually, when the concentration of specific radionuclides j
is determinable in a sample (s),
i.e.,
greater than the LLD, the alarm / trip setpoint of each liquid effluent l
radioactivity monitor is based upon measurement, in i
accordance with Section 4.6.2.1.3 of radioactive paterial in a batch of liquid to be released or in a continuous aqueous discharge.
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l Oyster Creek Offsite Dose Calculation Manual 11 Alternatively, a radionuclide distribution that represents the distribution expected to be in the l
l effluent if the concentration were high enough to be i
detectable, i.e.,
greater than the LLD, may be assumed.
l l
The representative distribution may be based upon past measurements of the effluent stream or upon a computed 1
distribution.
4.1.1.2 Batch Release A sample of each batch of liquid radwaste is analyzed for I-131 and other principal gamma emitters or for gross beta or gross gamma activity before release. The result of the analysis is used to calculate the trip setpoint of the radioactivity monitor on the liquid radwaste effluent line to apply to release of the batch (Exhibit 2000-ADM-4532.04-8).
4.1.1.3 Continuous Release The reactor building service water effluent and the turbine building Sump no. 1-5 are each sampled and analyzed weekly for I-131 and other principal gamma emitters.
Results of analyses for the preceding week or for a period as long as the preceding 3 months are used to calculate the alarm / trip setpoint of the corresponding effluent radioactivity monitor l
in order to determine a representative value.
1 In each case, whether batch or continuous, the j
l monitor alarm / trip setpoint may be set at lower g
]
l activity concentration than the calculated setpoint.
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OYSTER CREEK POLICY AND Numb 3r PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
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Oyster Creek offsite Dose Calculation Manual 11 4.1.2 Gaseous Effluent Monitor Setpoints 4.1.2.1 General Sections 4.7.1.1.2.A and 4.7.1.1.2.B require radioactive gaseous effluent monitors to initiate an alarm in the event the dose rate beyond the site boundary due to radioactive noble gas in gaseous effluent exceeds a lindt in Section 4. 6.1.1.5. A.
With prenpt action to reduce radioactive effluent following an alarm, the unrestricted area dose provisions in 10 CFR Part 20.1301 should not be exceeded.
Each radioactive noble gas effluent monitor setpoint
(
is derived on the basis of dose equivalent rate.
The monitor may be set to cause the alarm to activate at a lower concentration than the calculated setpoint. For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:
a.
Preferably, the radionuclide distribution is obtained by ganna isotopic analysis of identifiable noble gases in effluent gas samples.
Results of the analyses of one or more samples way be averaged to obtain a representative spectrum.
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NUCLEAR Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 b.
In the event a representative distribution is unobtainable from recent measurements by the radioactive gaseous waste sampling and analysis program, it may be based upon past measurements or on a computed spectrum appearing in Attachment 2000-ADM-4532.04-2 herein, c.
Alternatively, the total activity concentration of radioactive noble gases may be assumed to be Xenon-133 as found in Reg Guide 1.97.
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l 4.1.2.2 Setpoint Based on Dose Equivalent Rate The alarm setpoint of a radioactive noble gas effluent monitor may be calculated on the basis of whole body dose equivalent rate offsite. A setpoint of a monitor of an elevated release, e.g.,
from the stack, may be calculated using the equation:
I C S
= 1.06 h
+ BKG f
I (Cf. DFS )
The setpoint of a monitor of a ground-level or split-wake
- release, e.g.,
from the turbine building vent or the AOG O
building, may be calculated with the equation:
V E C S
= 1.06 h
+ BKG fX Q
E (C DEV )
where S the alarm setpoint (epm) or (mR/hr)
=
h monitor response to activity concentration
=
of effluent being monitored, cpm or mR/hr pC1/cm5 pC1/cm8 relative concentration of noble gas C
=
g radionuclide i in effluent at the point of monitoring ( Ci/cm )
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4 Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 X/Q atmospheric dispersion from point of
=
ground-level or split-wake release to the 3
location of potential exposure (sec/m )
500 crem/ year (Sect. 4.3.1.1) 472 (conversion of cfm to ec/sec) factor converting elevated release rate of DFS
=
g radionuclide i to total body dose equivalent rate at the location of potential exposure (Attachment 2000-ADM-4532.04-3); units are:
mrem O,
yr. ECi see factor converting ground-level or DFV
=
1 splitwake release of radionuclide i to the
~
total body dose equivalent rate at the location of potential exposure (Attachment 2000-ADM-4532.04-3);
units are nxem yr uCi m3 f
flow of gaseous effluent stream being
=
monitored, i.e.,
stack flow, vent flow, etc. (ft / min).
.[
Monitoring instrument background (cpm or BKG
=
mR/hr)
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1 OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
Oyster Creek offsite Dose Calculation Manual 11 Each monitoring channel has a unique response, h, which is determined by the instrument calibration. The concentration of each noble gas radionuclide i in a gaseous effluent can be found in accordance with section 4.1.21.
The atmospheric dispersion, X/Q, and the dose conversion factor, DFS, depend upon local conditions.
For the purpose of calculating g
radioactive noble gas effluent monitor alarm setpoints appropriate for the OCNGS, the locations of maximum. potential offsite exposure and the reference atmospheric dispersion factors applicable to the derivation of setpoints are:
Discharge Point Receptor Location Atm. Dispersion Sector Distance (m)
(sec/m3)
Ground-level or vent SE 522 2.15 E-5
~
Stack SE 522 N/A The applicable dose conversion factors, DFS and DFV, for deriving g
setpoints are in Attachment 2000-ADM-4532.04-3.
l O
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Oyster Creek offsite Dose Calculation Manual 11 1
l 4.2 RADIOACTIVE LIQUID EFFLUENT 4.2.1 Radioactice Concentration in Liquid Effluent - Limits The concentration of a known mixture as a fraction of the allowable limit should be derived by determining, for each radionuclide in the mixture, the sum of the ratios of the concentration in the mixture present in the unrestricted area and 10 times the limits otherwise established in 10 CFR Part 20, (20.1001-20.2401) Appendix B, Table II, Column 2 for the specific radionuclide when not in a ndxture. The 10 times the 10 CFR Part 20 (20.1001-20.2401) value is selected as being low enough to maintain releases ALARA pursuant to 10 CFR 50 Appendix I and provides reasonable assurance that the 0.1 rem annual limit of 10 CFR 20.1301 will not be exceeded while allowing short term 0'
i operational flexibility. The following equation is used to calculate the fraction of 10 times the liquid effluent concentration (LEC) in the discharge canal at the Route 9 bridge 4
[
as required in Section 4.6.1.1.3.
n (C /10LECs)
- F / Fr F10LEC r.c I
=
t 3
i=1 where F
= flow in the discharge line (where the 3
concentration discharged is C )
(e.g. gallons / minute)*.
fl w in the discharge canal F
=
2 (e.g. gallons / minute)*.
C
= the concentration of radionuclide, i, in the liquid effluent discharged ( C1/cc),
before dilution.
[
10LEC
= Ten times the Liquid Effluent concentration of the radionuclide i in an unrestricted area according to 10 CFR 20, (20.1001-20.2401) Appendix B, Table II, Column 2.
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Oyster Creek Offsite Dose Calculation Manual 11 l
l F10LEC
= the ratio of the concentration present in i
frac the unrestricted area to 10 times the 10CFR20 Appendix B limit for the mixture of radionuclides.
4.2.2 Liquid Iffluents - 10 CFR 50 Appendix I Limits l
Radiation dose from liquid effluent may be received through the l
l ingestion of fish, shellfish, and from direct shoreline exposure.
Personal radiation exposure via other aqueous pathways is negligible at the OCNGS. The method used to assess compliance with Section 4.6.1.1.4 for exposure via fish and shellfish consumption and irradiation by shoreline deposits is described in Reference G.8, RegGuide 1.109.
The factor of dilution, incorporates a factor of 3.76 to account for recirculation of water through the intake and
/N
(
)
discharge canal (Reference 6.5.8).
A percentage of dilution of v
non-discharge water is used at each receptor.
For example, 25 percent dilution is assumed in the Barnegat Bay while one-hundred percent dilution is assumed in the Atlantic Ocean. The factor of dilution, is the ratio of the dilution to the recirculation factor.
Dilution at the U.S. Route 9 bridge is assumed to be minimal and, is simply the inverse of the recirculation factor. Liquid effluent concentration values that are less than LLD values are excluded from 1
the dose calculations.
For the purpose of assessing compliance with Section 4.6.1.1.4, the most exposed person is assumed to be a member of the public who is exposed to direct shoreline exposure and who consumes fish and shellfish taken from the canal (Attachment 2000-ADM-4532.04-8).
GPU developed software (e.g.,
" SEEDS") should be used for these calculations.
SEEDS implements the methods of Reg.
Guide 1.109.
~
I r~'s t
l l
- any suitable but identical units (vol/ time) l l
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l Oyster Creek Offsite Dose Calculation Manual 11 4.2.3 Projected Dose - Liquid When aqueous effluent is released from the liquid radwaste system without treatment during a calendar quarter, the equation used subsequently to project the radiation dose to a member of the public due to aqueous effluent is:
- PROJ"
- PREC Y
where X
the number of days
=
during the period of projection.
Y the number of days during
=
which D applies.
PREC D
the dose during a past
=
O PREC time period judged to represent anticipated releases (mrem).
The preceding time period on which the actual telease and dose is based may be the same quarter to date or may be an earlier period which is judged to represent anticipated releases.
~
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Oyster Creek Offsite Dose Calculation Manual 11 4.3 RADIOACTIVE GASEOUS EFFLUENT 4.3.1 Dose Rate - 10 CFR Part 20 1
4.3.1.1 Noble Gases The bases for monitor setpoints are the dose rates outside the restricted area resulting from radioactive noble gases in airborne effluent from the OCNGS of 500 mrem /yr to the total body and 3000 mrem /yr to skin.
The whole body dose is used as being more conservative. This value maintains effluent releases l
ALARA pursuant to 10 CFR 50 Appendix I and provides reasonable assurance that the 0.1 rem annual limit of 10 CFR 20.1301 will not be exceeded while allowing short team operational flexibility. Coupliance is monitored by radioactive gaseous effluent monitors with tneir alana setpoint set to cause automatic alarm when or before a limit in Section 4.6.1.1.5.A is exceeded, thus further calculation is not required to demonstrate compliance. The setpoint is calculated in 1
accordance with Section 4.1.2 herein. Thus further calculation is not required to demonstrate compliance l
i as long as a noble gas effluent monitor does not alarm.
l 3
m 4
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Oyster Creek Offsite Dose Calculation Manual 11 In the event a noble gas effluent monitor exceeds its alarm setting and alarum, an assessment of compliance with Section 4.6.1.1.5.A is performed by either (1) observing whether the radioactivity recorded by the noble gas monitor exceeded its derived setpoint (limit),
or
)
(2) by calculating the noble gas radiation-to-dose equivalent rate with the following equation.
- f Q i Qi -
T f ~s where Q = quantity of gas released as mecsured by r
(_-)
gross noble gas radioactivity monitor ( C1) fraction of noble gas radionuclide i within f
=
f
[
the quantity release T
averaging time of noble gas discharge (hr)
=
Gross activity, Q, measured by the noble gas effluent monitor during recording time interval, T, normally one hour, represents the quantity of noble gas released. The noble gas distribution, f, is estimated as described in Section 4.1.2.1.
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4.3.1.2 Total Body Dose Rate - The total body dose equivalent rate from radioactive noble gases discharged from an elevated point (stack above building wake) is calculated with the equation i
DG = I Q Pys f
i From a ground-level release (building vent) the total body dose equivalent rate is
)
DG = X_
E Q. Pyv j
O i
y where DG = total body dose equivalent rate due to irradiation by radioactive noble gas (mrem /hr) average discharge rate of noble gas radionuclide Q
=
i released during the averaging time (pci/hr) factor converting time integrated PyV
=
ground-level concentration of noble gas nuclide
~
\\
"#**~"
i to total body dose pCi - see See Attachment 2000-ADM-4532.04-4.
X=
atmospheric dispersion factor from the Q
OCNGS to the offsite location of interest 2
(sec/m )
factor converting unit noble gas nuclide i stack PyS
=
release to total body dose at ground level received outdoors from the overhead plume (mrem / Ci).
See Attachment 2000-ADM-4532.04-4.
Alternatively, an approved computer code (e.g.,
" SEEDS"), which implements the requirements of Reg Guide 1.109 may be used.
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U Oyster Creek Offsite Dose Calculation Manual 11 4.3.1.3 Skin Dose Rate - The dose equivalent rate to skin from radioactive noble gases is calculated by assumir.g a person at ground level is immersed in and irradiated by a semi-infinite cloud of the noble gases originating in airborne effluent.
It is calculated for each air effluent discharge point with the equation X_ IQ (SB + 1.11
- A TV )
=
i where DB dose rate to skin from radioactive noble gases
=
(mrem /hr)
X atmospheric dispersions from gaseous effluent
=
(j x
Q discharge point to ground-level location of 2
(
interest (sec/m )
Q discharge state of noble gas radionuclide 1
=
1 (pci/hr)
SB factor converting time integrated
=
ground-level concentration of noble gas radionuclide i to skin dose from beta radiation 3
mrem m
ci
- see AyV factor for converting time integrated,
=
semi-infinite concentration of noble gas radionuclide
"" ~"
i to air dose from its gansna pCi*see The dose equivalent rate due to irradiation by effluent noble gases is normally evaluated at the same location and with the same reference meteorology data as used to calculated noble gas effluent monitor setpoints (sec. 4.1.2.2).
Alternatively, meteorological dispersion data during the noble gas discharge being examined and the consequent location of most exposure may be used as the basis for evaluation.
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Oyster Creek Offsite Dose calculation Manual 11 The noble gas plume gamma-to-total body dose factors, PyS at designated locations are derived from meteorological dispersion data with the USNRC RABFIN software computer code or similar computer program implementing Reg Guide 1.109, Appendix B.
The noble gas semi-infinite cloud gamma-to-total body dose factors, PyS, are derived from Reg Guide 1.109, Revision 1, Table B-1, i
Column 5.
The noble gas beta radiation-to-skin-dose factors, SBi and the noble gas gamma-to-air dose factors, A66, are derived from Reg Guide 1.109, Revision 1, Table B-1, columns 3 and 4 respectively.
A. tabulation of these factors used to compute noble gas-to-dose p}
equivalent rate at 522 meters SE of the OCNGS is in 000-ADM-4532.04-4.
The dose equivalent rate is calculated with the following meteorological dispersion data:
Discharge Point Receptor Location Atm. Dispersion 3
Sector Distance (m)
(sec/m )
Ground Level SE 522 4.17 E-5 or vent Stack SE 522 6.04 E-9 Alternatively, an approved computer code (e.g.,
" SEEDS") which implements the requirements of Reg Guide 1.109 may be used.
~
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CYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Os Title Revision No.
oyster Creek Offsite Dose calculation Manual 11 4.3.1.4 Radioactive Iodines and Particulates The dose rate offsite due to the airborne release of I-131, I-133, tritium, and particulates with half-lives greater than 8 days is limited to no more than 1500 mrem /yr to any organ.
Evaluation of compliance with Section 4.6.1.1.5.B is based on the sampling and analyses specified in Attachment 2000-ADM-4532.04-15.
Since the dose rate cannot be resolved within less than the sample integration or compositing time, the contribution of each radionuclide to the calculated dose rate will be averaged no more than 3 months for H-3, Sr-89, Sr-90, D).-
k-and alpha-emitting radionuclides and no more than 31 days for other radionuclide. These are their usual sample integration or compositing times. The equation used to assess compliance of radioiodine, tritium, and radioactive particulate releases with the dose rate limit is:
n I
E TA
.-Q (X/Q)
DR
=
p eai ei e
e i=1 where:
the average dose rate to an organ *via DR
=
P exposure pathway, p (mrem /yr).
4 U
(453204/S2) 30.0
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OYSTER CREEK POLICY AND Numbar gg PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR O
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l Oyster Creek Offsite Dose Calculation Manual 11 inhalation dose factors due to intake of TA
=
g radionuclide, 1, via pathway e (mrem /yr per C1/m ) to the most restrictive age group, a (equal to the DCF..i multiplied by the breathing rate of the associated age group).
(X/Q),=
annual average relative airborne concentration at an offsite location due to a release from either the Stack or a vent, i.e.
release point, e (sec/m ).
release rate of radionuclide i from release Q
=
d point, e during the period of interest (pci/see).
The location of the maximum ground-level concentration originating from a vent release will differ from the maximum ground-level concentration from a stack release. When assessing compliance with Section 4.6.1.1.5.B for tritium, iodine, and particulate, the air dispersion (X/Q) value for a vent release is used. The appropriate location and corresponding air dispersion factors are found in Exhibit 2000-ADM-4532.04-3 and 4.
Location of Maximum Exposure Rate by Inhalation Discharge Point Receptor Location Atm. Dispersion Sector Distance (m)
(sec/m3)
~
Ground Level
['
or vent SE 522 4.17 E-5 Stack SE 522
- 6.04 E-9 1
(453204/S2) 31.0.
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OYSTER CREEK POLICY AND Numb 2r f
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Oyster Creek Offsite Dose Calculation Manual 11 l
l Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closest hypothetical individual (Attachment 2000-ADM-4532.04-8) located at:
Stack SE 966m 3.42 E-8 3
m Alternatively, an approved computer code (e.g.,
" SEEDS") which implements the methods of Reg Guide 1.109, may be used.
4.3.2 DOSE - 10CFR PART 50, APPENDIX I Doses resulting from the release of noble gases, and radiciodines and particulates must be calculated to show compliance with Appendix I of 10CFR50. Calculations will be performed at least monthly for all gaseous effluents as stated in Sections 4.6.2.1.6 and 4.6.2.1.7
/m
(
)
to verify that the dose to air is kept below the limits specified in N~
Dection 4.6.1.1.6 and the dose to members of the public is maintained below the limits specified in Section 4.6.1.1.7.
[
4.3.2.1 Noble Gases The method used to calculate the air dose at the critical location due to noble gas is described by the following equations. The limits are provided in Section 4.6.1.1.6 for air dose offsite due to gamma and beta radiations from effluent noble gas.
a)
For Gamma Radiation n
E 3.17E-8 AYV (X/Q) Q
+ AyS Dose y y
g Q,g
=
i=1
~
b)
For Beta Radiation n
Dose $
= 3.17E-8 E
E A
(X/Q),Q,1
~'
(/
e i=1 (453204/S2) 32.0
OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 where:
the gamma dose during any specified time Dose y
=
period (mrad).
the beta dose during any specified time Dose
=
period (mrad).
the air dose factor due to ground level Apri
=
gamma emissions for each identified noble gas radionuclide, i; from Reg. Guide 1.109 Table B-1 (mrad'/yr per pCi/m ).
AySi the factor for air dose at ground level due
=
to irradiation for an airborne plume resulting from a Stack release (mrad per C1), 000-ADM-4532.04-5.
A i the air dose factor due to beta emissions
=
for each identified noble gas radionuclide, i from Reg. Guide 1.109, Table B-1 (mrad /yr per pCi/m ).
X/Q,,,
the annual average relative concentration
=
for areas at or beyond the site boundary for releases from either the S, tack or ground. vent at the critical location (sec/m ),
Exhibits 2000-ADM-4532.04-3
.n' and 4.
v (453204/S2) 33.0
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PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 amoun:: of radionuclide i released from Q
=
vi vents (pci).
amount of radionuclide i released from the Q
=
si Stack (pci).
l amount of radionuclide i released from i
Q
=
ei release point e( C1).
The inverse of the number of seconds in a 3.17E-8
=
year.
Noble gases may be released from the ground level vents and Stack. The quantity of noble gas radionuclides released will be determined from the continuous noble gas monitors and periodic isotopic analyses. Noble gases discharged from either the stack or from building vents I
and dispersed by reference meteorology (Exhibits 2000-ADM-4532.04-3 and 4) produces its maximum gamma radiation p
dose-to-air offsite at 522 meters SE of the OCNGS.
U values of AyS depend upon the meteorological conditions and the location of exposure and are calculated using the NRC RABFIN code or similar one in accordance with Reg.
,~
Guide 1.109, Appendix B, Section 1.
AyV and A are derived from Reg. Guide 1.109, Table B-1 for a semi-infinite cloud, independent of meteorology or location. Values of AyS, AyV and A used to calculate the noble gas radiation dose to air at 522 meters SE of the OCNGS are in Attachment 2000-ADM-4532.04-5.
Reference atmospheric dispersion from the OCNGS to 522 I
meters SE ist Discharge Point Receptor Location Atm. Dispersion Sector Distance (m)
(sec/m3)
Ground Level SE 522 4.17 E-5 or vent Stack SE 522 6.04 E-9 Alternatively, an approved computer code (e.g.,
" SEEDS")
V-that implements the requirements of Reg Guide 1.109 may i
be used.
(453204/S2) 34.0 1
I OYSTER CREEK POLICY AND Number ll[
PROCEDURE MANUAL 2000-ADH-4532.04 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 s-4.3.2.2 Radioiodine, Particulates, and Other Radionuclides l
l The maximum dose to an individual from radiciodines and l
radioactive particulates with half-lives of greater than eight days in gaseous effluents released to unrestricted I
areas is deterndned as described in Reg Guide 1.109.
j Environmental pathways that radioiodine and particulates in airborne effluent follow to the member of the public experiencing the most confirmed exposure as determined by l
the annual land use survey and reference meteorology will be evaluated. The seasonality of exposure pathways may be considered.
For instance, if the most exposed
[}
receptor has a garden, fresh and stored vegetables are
\\~/.
assumed to be harvested and eaten during April through October.
Fresh vegetables need not be considered as an l
exposure pathway during November through March. To i
assess compliance with Section 4.6.1.1.7.A, the dose due to radioactive iodine and particulates in airborne effluent is calculated to a person residing 966 meters SE of the OCNGS where reference atmospheric dispersion and deposition factors (Exhibit 2000-ADM-4532.04-3, 4, 5, and
- 6) are:
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OYSTER CREEK POLICY AND Numbsr PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR O-Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 Discharge Point Dispersion Deposition X/O D/Q (sec/m3)
(1/m2)
Ground Level or vent 1.53E-5 1.70E-8 Stack 3.42E-8 2.40E-9 The environmental pathways of exposure to be evaluated are identified in 000-ADM-4532.04-6. Alternatively, an approved computer code (e.g.,
" SEEDS") that implements the requirements of Reg Guide 1.109 may be used.
4.3.3 Pro $ection of Doses The method used to project radiation dose from the Ground Level I
(}
Vents on releases to UNRESTRICTED AREAS during the preceding
%,)
quarter is:
- PROJ ~E*
PREC Y
where:
the number of days during the period of projection.
X
=
the number of days during which D 8PPlies.
Y
=
PREC the dose during a past time period that is judged to be D
=
PREC representative of anticipated releases (mrem).
The projection of dose is not necessary for continuous releases from the Stack because Section 4.6.1.1.2 gives guidance on operation of the Augmented Offgas System.
d (453204/S2) 36.0
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Oyster Creek Offsite Dose Calculation Manual 11 4.4 TOTAL DOSE - COMPLIANCE WITH 40 CFR 190.10a 4.4.1 General Section 4.6.1.1.8.B requires that in the event the calculated doses associated with the effluent releases exceed twice the limits of either Specification:
4.6.1.1.4 Dose due to Liquid Effluent j
4.6.1.1.6 Air dose due to Noble Gas in Gaseous Ef fluent 4.6.1.1.7 Dose due to Radiciodine and Particulates in Gaseous Effluent.
OCNGS will assess compliance with the limit on annual dose to a Member of the Public stated in Section 4.6.1.1.8. A.
To perform this assessment, the total body and organ doses resulting from liquid effluents from the OCNGS will be summed with the doses resulting from releases of radioiodines and particulates in airborne effluents. The total body dose attributable to (external) irradiation by noble gases or directly from the OCNGS will be added with the doses due to internal exposure. These dose estimates will be based on releases from the OCNGS during the calendar year to date including the calendar quarter in which twice the limit of Section 4.6.1.1.4.A, or 4.6.1.1.7.A was exceeded.
Dose estimates to assess compliance with 40 CFR Part 190.10a are also required annually by Section 4.6.2.1.8.
(Exhibit 2000-ADM-4532.04-10 shows 5xposure Pathways for Radionuclides Potentially Released from the OC':GS.)
l l
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Oyster Creek Offsite Dose Calculation Manual 11 Contributions to the dose due to liquid and gaseous effluent are calculated as described by the equations for:
a) total body and maximally exposed organ doses via shoreline exposure and eating fish and shellfish caught in the discharge canal at the Route 9 bridge as in Section 4.2.2.
b) total body and maximally exposed organ doses due to gaseous j
I effluent other than noble gases as in Section 4.3.2.2.*
c) total body and organ doses due to gaseous tritium effluent as in Section 4.4.4.
d) total body and skin doses due to noble gases are gaseous effluent as described in Section 4.4.3.
e) total body irradiation from the OCNGS, including outside storage
/(,
tanks as described in Section 4.4.2.
The dose limits of 40CRF190 are more restrictive than the 10CFR20.1301 0.1 rem / year dose limit. Therefore, showing compliance with 40CFR190 is considered to demonstrate compliance with 10CFR20.1301.
1
. Based on I-131, 'I-133, and radionuclides in particulate form having half -
lives greater than eight days, s
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Oyster Creek Offsite Dose Calculation Manual 11 The receptor of the dose is a MEMBER OF THE PUBLIC selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use survey and the minimum annual atmospheric dispersion from the OCNGS to his residence. Alternatively, the dose may be calculated to correspond l
with residence or exposure at an acceptable location where calculated exposures are unlikely to underestimate those experienced by the most exposed MEMBER OF THE PUBLIC. That is, conditions assumed in the dose assessment may be realistic or may be more conservative than actual conditions.
For the purpose of assessing compliance with Sections 4.6.1.1.8 and 4.6.2.1.8, the exposure of the most exposed member of the public is assumed to occur at the locations described in Attachment 2000-ADM-4532.04-6.
When assessing compliance with 40 CFR Part 190.10a, aqueous and atmospheric dispersion of radioactive material are based on annually-averaged conditions.
Either data trom the reference year or from the most recent calendar year are used to estimate dilution, dispersion, deposition, and elevated plume gamma exposure.
Alternatively, an approved computer code (e.g. " SEEDS") that implements the requirements of Reg Guide 1.109 may be used.
Environmental Measurements: When assessing compliance with 40 CFR 190.10a, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the OCNGS as an alternative to calculating.the concentrations from radioactive effluent measurements. The measured environmental activity levels may thus be used to supplement the evaluation of doses to a member of the public.
(453204/S2) 39.0
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OYSTER CREEK POLICY AND Numbar l
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d Oyster Creek Offsite Dose Calculation Manual 11
4.4.2 Irradiation
The dose to a member of the public due to irradiation (external gamma radiation exposure) from the OCNGS gaseous effluents will be estimated with the aid of environmental TLD's, PIC' s, or similar environmental dosimetry. This will be done by examining the annual dosimetry data for a statistical difference between measurements near the OCNGS and background measurements.
j 4.4.3 Noble Gas Dose Calculation: As an alternative to environmental 1
1 dosimetry, the gamma dose to a member of the public by irradiation by noble gases in gaseeas effluent from the OCNGS may be calculated.
In that event, the total body gamma dose is calculated as described in Section 4.3.
4.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMPl 4.5.1 Radiological Environmental Surveillance - A Radiological Environmental Monitoring Program (REMP) has been established to monitor radiation and j
i radioactive materials in the environment around the OCNGS in accordance with Section 6.8.4.b of the OCNGS Technical Specifications.
4.5.1.1 Environmental samples shall be collected and analyzed according to Attachment 2000-ADM-4532.04-9.
Analytical techniques shall be used such that the detection capabilities indicated in Attachment 2000-ADM-4532.04-10 are achieved. Locations from which radiological environmental samples are intended to be collected shall be identified in Section 4.5.2, Radiological Environmental Program Description and Sampling Locations.
d (453204/S2) 40.0
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[d Oyster Creek Offsite Dose Calculation Manual 11 4.5.1.2 Deviations are permitted from the requirements of 1
l 000-ADM-4532.04-9 if samples are unobtainable l
due to hazardous conditions, seasonal unavailability, faunal population fluctuation, malfunction of the automatic sampling equipment, or other legitimate reasons beyond the control of GPUN.
4.5.1.3 The provisions of OCNGS Technical Specifications 3.0A and
- 3. 0B, regarding Limiting Conditions for Operation, and l
6.9.2 regarding Licensee Event Reports do not apply to any l
l aspects of the Radiological Environmental Monitorir.p Program (Section 4.5) 4.5.1.4 In the event an environmental sample required by
' 000-ADM-4532.04-9 is not collected and analyzed in accordance with the provisions of the attachment, the deviation shall be documented in the Annual Radiological Environmental Report.
4.5.1.5 If a required sample is unobtainable due to sampling equipment malfunction, every reasonable effort shall be made to complete corrective action prior to the end of the next samplirg period.
4.5.1.6 Any location specified in Section 4.5.2 from which environmental samples or dosimetry can no longer be obtained may be dropped from the surveillance program upon notifying the NRC in writing, in lieu of any other report.
GPUN shall establish a replacement sampling or dosimetry location and revise Section 4.5.2 in accordance with Specification 6.19 of the OCNGS Technical Specifications.
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4.5.1.7 If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any f
quarterly sampling period exceeds the reporting level j
given in Attachment 2000-ADM-4532.04-ll, a written report shall be submitted to the NRC within sixty days of the end of the quarter during which the licensee received confirmation that a radiological limit was exceeded. This report may include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anonalous results. If it can be demonstrated that the level is not a result of OCNGS effluent (i.e., by comparisons with control 7_s
!(_,)
station, natural radioactivity, or pre-operational data) a report need not be submitted. When more than one of the radionuclides in Attachment 2000-ADM-
~
4532.04-11 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1) concentration (2)
+
+
....... >l reporting level (1) reporting level (2) 1 A confirmatory re-analysis of the original, duplicate, or a new sample i
may be desirable as appropriate.
The results of the confirmatory analyses l
' should be completed at.the earliest time consistent with the analysis,
- but, in any case, within sixty days.
If radionuclides other than those in
,/) 000-ADM-4532.04-ll are detected and are due to OCNGS effluent, t
/
a reporting level is exceeded if the potential annual dose to an f
individual is equal to or greater than the design objectives of 10CFR50, Appendix I.
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Oyster Creek Offsite Dose Calculation Manual 11 4.5.1.8 Interlaboratory Comparison Program Specifications 4.5.1.8.1 The laboratories of the licensee and licensee's contractors which ar.alyze radiological environmental samples shall participate in an NRC-approved environmental radioactivity intercomparison program, if available.
4.5.1.8.2 In the event comparison samples are not analyzed, the reason shall be reported in the Annual Radiological Environmental Report in lieu of any other report.
4.5.1.9 Land-Use Survey Specification In accordance with Technical Specification 6.8.4.b, the Radiological Environmental Monitoring Program (REMP) is designed to account for changes in land use that may occur at and beyond the site boundary. This is necessary in order to ensure that the REMP provides representative measurements of radioactivity in the highest potential exposure locations and that calculated doses to the public, attributable to effluents from the OCNGS, will not be underestimated.
~
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Oyster Creek Offsite Dose Calculation Manual 11 4.5.1.9.1 Milk Animals - A survey will be conducted on an annual basis to determine the location of animals producing milk for human consunption in the following locations:
a) the nearest milk animal in each of the sixteen compass sectors out to a distance of 5 miles from the OCNGS, and b) all milk animals in each of the sixteen compass sectors out to a a-distance of 3 miles from the OCNGS.
f,g If the results of this surve;; demonstrate that milk animals are present at a location which yields a calculated thyroid dose at least 20 percent greater
~
.than those previously sampled, that location shall be added to the REMP and a sampling location exhibiting the lowest calculated dose may then be eliminated from the REMP. Any new sampling location shall be 1
l identified by distance and direction from the OCNGS in the Annual Radiological Environmental Report.
If I
the survey reveals that milk animals are not present or are unavailable for sampling, then broadleaf vegetation shall be sampled.
+).
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l 4.5.1.9.2 Broadleaf Vegetation Sampling - Broadleaf l
vegetation sampling will be conducted at the two locations that have historically exhibited the highest D/Q's, as determined using site-specific meteorological data (Exhibit 2000-ADM-4532.04-5).
Sampling the vegetation at the two locations where the maximum deposition of effluents from the OCNGS is calculated to occur will ensure that the REMP will not need to be modified to account for changes in agricultural land use at and beyond the site boundary. These samples will provide representative neasurements of radioactivity in the highest potential exposure locations. The calculation of radiation dose to a member of the public from the consumption of vegetation harvested at the locations experiencing the maximum D/Q will ensure that the doses are not underestimated.
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Oyster Creek Offsite Dose Calculation Manual 11 4.5.1.9.3 Garden Census - If in a given year, broadleaf vegetation cannot be obtained from the two locations with the highest D/Q's as described in Section 4.5.1.9.2, a garden census will be performed during the growing season to identify:
a) the nearest garden greater than 500 square feet, producing broadleaf vegetation, in each of the sixteen compass sectors out to a distance of 5 miles from the OCNGS, and b) all gardens greater than 500 square feet, producing broadleaf vegetation, in each of the sixteen compass sectors out to a distance of 3 miles from the OCNGS.
If the garden census identifies a location which yields a calculated thyroid dose at least 20 percent greater than those previously sampled, that location shall be added to the REMP if broadleaf vegetation is available for sampling. The new location will be identified in the Annual Radiological Environmental Report and the station having the lowest calculated I
dose may be eliminated from the REMP.
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4.5.1.10 Basis i
4.5.1.10.1 The detection capability stated in 000-ADM-4532.04-10 and the reporting levels stated in 000-ADM-4532.04-ll for j
each radionuclide in environmental samples are derived from the USNRC Branch Technical Position on nadiological Environmental Monitoring, Revision 1, Tables 2 and 4.
4.5.1.10.2 Site-specific research conducted by GPUN, which included the installation of j
a groundwater monitoring well network, i
has demonstrated that the groundwater pathway is not a potential pathway to j
man from the OCNGS.
4.5.1.10.3 The surface water into which the OCNGS discharges is a marine estuary containing saline water that is not used as drinking water or irrigation water by man.
4.5.2 Radiological Environmental Program Description and Sampling Locations 4.5.2.1 Air Particulate / Air Iodine: GPUN maintains air particulate and air iodine sampling stations as follows:
~
~3 a)
One indicator station in the SSE sector approximately 1.6 miles from the OCNGS along an azimuth of 166 degrees.
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Oyster Creek Offsite Dose Calculation Manual 11 b)
One indicator station in the SE sector approximately 0.4 miles from the OCNGS along an azimuth of 130 degrees.
c)
One indicator station in the ESE sector approximately 1.8 miles from the OCNGS along an azimuth of 108 degrees.
d)
One indicator station in the NNE sector approximately 1.8 miles from the OCNGS along an azimuth of 26 degrees.
e) One background station in the NW Sector approximately 25 miles from the OCNGS along an azimuth of 315 degrees.
D i 4.5.2.2 Thermoluminescent Dosimetry (TLD):
GPUN deploys 32 thermoluminescent dosimeters as follows:
1 a) Sixteen indicator stations, one in each of the 16
[
compass sectors, in the general area of the Site Boundary.
b) Eleven indicator stations, one per sector, within 5 miles of the site (5 sectors are over water at 5 miles).
c) Three indicator stations in areas of special interest:
Waretown and Forked River, (areas of high permanent population density), and Island Beach State Park, (as area of high seasonal population density).
d) Two background stations, located in accordance with
~
applicable distance and wind direction criteria, within p
practical constraints.
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4.5.2.3 Groundwater: One indicator station is a domestic water well located on the OCNGS site. The second indicator station is domestic water supplied from the Ocean Township Municipal Utility Authority, located in a down-gradient.
location from the OCNGS. This station is located in the SSW sector approximately 1.6 miles from the OCNGS along an azimuth of 196 degrees. The background station is domestic water supplied from the Lacey Municipal Utility Authority, located up-gradient from the OCNGS. This station is located in the NNE sector approximately 2.4 miles from the OCNGS along an azimuth of 17 degrees.
4.5.2.4 Surface Water: The indicator station for surface i
N water is located in the OCNGS discharge canal, east of the U.S.
Route 9 bridge along an azimuth of 124 m,.
degrees. The background station is in an unaffected i
~
section of the Barnegat Bay system, 19 miles SSW of
)
the OCNGS, generally along an azimuth of 196 degrees.
4.5.2.5 Aquatic Sediment: The sediment sampling locations are the same as for surface water (as described in Section 4.5.2.4).
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l 4.5.2.6 Fish: The sampling locations for fish may be affected by adverse weather, availability of fish, and other variables. Specific locations will be reported in the Annual Radiological Environmental Report. The indicator station is located in the OCNGS Discharge Canal between the condenser discharge and the US Route 9 bridge. The background station is in an unaffected section of the Barnegat
]
l Bay system, approxiscately 19 miles SSW of the OCNGS,
)
generally along an azimuth of 196 degrees.
Fish samples will consist of the edible portions of available species that are consumed by man.
Seasonal availability and naturally occurring fishery population fluctuations will determine the precise species that are sampled.
4.5.2.7 Clams: The indicator station for clams is located in Barnegat Bay, just offshore of the mouth of the OCNGS discharge canal, generally along an azimuth of 98 j
degrees. The background station is in an unaffected l
l section of the Barnegat Bay system approximately 19 miles SSW of the OCNGS, generally along an azimuth of l
196 degrees.
Samples will consist of the edible 1
portions of clams as limited by seasonal availability l
l or naturally occurring population fluctuations.
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l 4.5.2.8 Vegetation: The indicator stations for vegetation are in the two compass sectors that have historically exhibited the highest D/Q's (section 4.5.1.9.2).
The background station is located in a low D/Q sector approximately 23 miles NW of the OCNGS. Vegetation samples may consist of leafy vegetables collected from ga; dens that are greater than 500 square feet in size, or wild vegetation.
4.6 RADIOACTIVE EFFLUENTS MONITORING PROGRAM 4.6.1 Radioactive Effluent Requirements This section applies to the radioactive effluent of the facility.
It's objective is to assure that radioactive material is not j
released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released is kept as low as is reasonably achievable and, in any event, within the limits of 10CFR part 20.1301 and 40CFR Part 190.10(a).
4.6.1.1 Sections 4.6.1.1.1 Liquid Radwaste Treatment This section applies to liquid radwaste batches before discharge as aqueous effluent.
A.
Any untreated batch of liquid radwaste shall be treated (in appropriate liquid radwaste treatment equipment)' before discharge as aqueous effluent when the radioactivity concentration, exclusive of tritium and dissolved noble gases, in U-m batch exceeds 0.001 Ci/ml.
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B.
When radioactive liquid waste is 1
discharged without treatment and in excess of the above limit, in lieu of any other report, prepare and submit to the NRC within 30 days pursuant to Section 4.8.3, a Special Report that includes the following information:
l (1)
Identification of any inoperable 1
equipment or subsystems, and the l
reason for the inoperability.
(2)
Action (s) taken to restore the inoperable equipment to OPERABLE status, and a (3)
Summary e scription of action (s) taken to prevent a recurrence.
4.6.1.1.2 Condenser Offgas Treatment l
This applies whenever the main condenser air ejector system is in operation except during i
startup or shutdown with reactor power less 1
than 40 percent of rated.
In addition, the Augmented Offgas System need not be in operation during end of cycle coast-down periods when the system can no longer 1
function due to low offgas flow.
9 V
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Oyster Creek Offsite Dose Calculation Manual 11 A.
Every reasonable effort shall be made to maintain and operate charcoal absorbers in the Augmented Offgas System to treat radioactive gas from the main condenser air ejector.
B.
If gaseous effluent is released without treatment for more than 30 consecutive days and either Sections 4.6.1.1.5 or 4.6.1.1.6 exceeded, in lieu of any other report, submit a Special Report pursuant to Section 4.8.3 to the NRC within 30 O
days from the end of the quarter during which the release occurred which includes the following information:
(1) Identification of the inoperable equipment or subsystem and the reason for inoperability; and (2) Action (s) taken to restore the inoperable equipment to OPERABLE status and to prevent a recurrence.
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oyster Creek Offsite Dose Calculation Manual 11 4.6.1.1.3 Radioactivity Concentration in Liquid Effluent A.
The concentration of radioactive material, other than noble gases, in liquid (* fluent in the discharge canal at the U.S. Route 9 bridge (see 000-ADM-4532.04-1) shall not I
exceed 10 times the Liquid Effluent Concentrations specified in 10CFR Part l
l 20.1001-20.2401, Appendix B, Table II, Column 2.
B.
The concentration of noble gases dissolved or entrained in liquid s
effluent in the discharge canal at the l
U.S.
Route 9 bridge shall not
~
~
exceed 2.0E-4 Ci/nd.
C.
In the event the concentration of radioactive material in liquid effluent j
l released into the unrestricted area l
beyond the U.S.
Route 9 bridge exceeds either the concentration limit in 4.6.1.1.3.A or 4.6.1.1.3.B, reduce the release rate without delay to bring the concentration below the limit.
I 1
=
~
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N Oyster Creek Offsite Dose Calculation Manual 11 4.6.1.1.4 Limit on Dose Due to Liquid Effluent A.
The dose to a MEMBER OF THE PUBLIC due to radioactive materi'al in liquid ef fluent in the UNRESTRICTED AREA shall not exceed:
1.5 mrem to the Total Body during any calendar qtr.
5.0 mrem te any body organ during any calendar qtr.
l 3.0 mrem to the Total Body during any calendar yr.,
j or 10.0 mrem to any body organ during any calendar yr.
When the calculated dose from the release of radioactive materials in liquid effluent exceeds any of the above limits, in lieu of a Licensee Event Report, prepare and submit to the NRC within 30 days from the end of the quarter during which the release occurred, pursuant to Section 4.8.3, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines 1
'~N the corrective actions that have 1
been taken and/or will be taken.
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-Oyster Creek Offsite Dose Calculation Manual 11 4.6.1.1.s Dose Rate Due To Gaseous Effluent A.
The dose equivalent rate in the UNRESTRICTED AREA (see Attachraent 2000-ADM-4532.04-1) due to radioactive noble gas in gaseous effluent shall not exceed 500 mrem / year to the total body or 3000 mrem / year to the skin.
B.
The dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3), I-131, I-133, and to radioactive material in particulate form 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 due to H-3, Sr-89, Sr-90, and alpha-emitting radionuclides is averaged over no more than 3 months and the dose rate due to other radionuclides is averaged no more than 31 days.
~..
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k_,,iI Oyster Creek Offsite Dose Calculation Manual 11 C.
In the event the dose equivalent rate exceeds any of the limits in 4.6.1.1.5.A or 4.6.1.1.5.B, decrease the release rate without delay to comply with the limit.
If the gaseous effluent release rate cannot be reduced to meet the limits, the reactor shall be in at least SHUTDOWN CONDITION within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless corrective actions have been completed and the release rate restored to below the limit.
(,)
4.6.1.1.6 Air Dose Due to Noble Gas in Gaseous Effluent A.
The air dose in the UNRESTT.ICTED AREA (see Attachment 2000-ADM-4532.04-1) due to noble gas released in gaseous effluent shall not exceed:
5 mrad / calendar quarter due to gamma radiation, 10 mrad / calendar quarter due to beta radiation, 10 mrad /celendar year due.to ganna radiation, or w
20 mrad / calendar year due to f
8 t
)
beta radiation.
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Oyster Creek offsite Lose Calculation Manual 11 B.
If the calculated air dose due to
)
noble gas released in gaseous effluent exceeds any lindt in Section 4.6.1.1.6.A, prepare and submit a special Report to the NRC which identifies the cause(s) for exceeding the limit and describes the corrective action taken. The Special Report shall be pursuant to Section 4.8.3, shall be in lieu of any other report, and shall be submitted to the NRC within 30
)
days from the end of the quarter during which the release occurred.
4. 6.1.1. 7 Dose Due to Radiciodine and Particulates in Gaseous Effluent A.
The dose due to a MEMBER OF THE PUBLIC from I-131, I-133, and from radiciodines in particulate form having half-lives of B days or nere in 3
gaseous effluent, in the UNRESTRICTED AREA (See Attachment 2000-ADM-4532.04-
- 1) shall not exceed 7.5 mrem to any body organ per calendar quarter or 15 mrem to any body organ per calendar f ~s year.
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~l Oyster Creek Offsite Dose Calculation Manual 11 B.
When the calculated dose from I-131, I-133, and from radionuclides in particulate form having half-lives of B days or more in gaseous effluent exceeds any limit in Section 4.6.1.1.7.A, prepare and submit a Special Report to the NRC which identifies the cause(s) for exceeding the limit and describes the corrective action taken. The Special Report shall be pursuant to Section 4.8.3, shall be in lieu of any other report, and shall be submitted to the NRC within 30 days from the end of the quarter during which the release occurred.
4.6.1.1.8 Annual Total Dose Due to Radioactive Effluent A.
The annual dose to a MEMBER OF THE PUBLIC due to radioactive material in effluent from the OCNGS in the UNRESTRICTED AREA (See 000-ADM-4532.04-1) shall not exceed 75 mrem to his/her thyroid or 25 exem to his/her total body or to
~
'N any other organ.
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In the event the calculat-d dose due j
to radioactive material released in liquid or gaseous effluent exceeds l
twice the limits of Section 4.6.1.1.4, 4.6.1.1.6, or 4.6.1.1.7, perform an assessment of compliance with Section 4.6.1.1.8 in accordance with methodology within this ODCM.
C.
In the event an assessment shows that Section 4.6.1.1.8 to have been exceeded, prepare snd submit a Special Report to the NRC within 30 days,
(,,
pursuant to Section 4.8.3 and in lieu of any other report. The report shall include information specified in 10CFR20.2203.
If the condition causing the limit (s) to be exceeded has not been corrected, the Special Report may also state a request for a variance in accordance with the provisions of 40CFR Part 190.
In that j
event, the request is timely, a variance is granted until NRd action on the request is complete.
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Oyster Creek Offsite Dose Calculation Manual 11 4.6.1.2 Basis 4.6.1.2.1 This specification implements the requirements of 10CTR50.36a related to operation of radioactive waste treatment-equipment to keep radioactive material in effluent to unrestricted areas as low as reasonably achievable.
Radioactive liquid wastes generated at the OCNGS are controlled on a batch basis with each batch processed by a method appropriate for the quality and concentration of material present.
Below 0.001 pC1/ml, it iO is not cost-beneficial to treat a batch of aqueous waste for the purpose of reducing potential radiation exposure offsite.
Hence Section 4.6.1.1.1 implements 10CFR Part 50, Appendix I provisions for treatment of radioactive liquid waste which is sampled and analyzed for radioactivity before release to the discharge canal so that an appropriate discharge rate will be determined accounting for dilution by condenser cooling water and dilution pump discharge.
W U
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Oyster Creek Offsite Dose Calculation Manual 11 4.6.1.2.2 The operability of the AUGMENTED OFFGAS SYSTEM (AOG) charcoal absorber ensures that they will be available for use whenever main condenser offgases require treatment l
prior to release to the environment and implements 10CFR Part 50, Appendix A Criterion 60.
Operation of this system provides reasonable assurance that the releases of radioactive materials in gaseous effluent will be kept "as low as reasonably achievable". A Special Report is required in the event the Augmented O
Offgas System charcoal absorber is not operated and a concentration or dose exceeds a relevant lindt offsite.
4.6.1.2.3 The purpose of Section 4.6.1.1.3 is to require that concentrations of radioactive material in aqueous effluent to the UNRESTRICTED AREAS do not exceed 10 times the Liquid Effluent Concentrations in 10 CFR 20.1001-20.2401, Appendix B, Table 2, Columns 1 and 2.
The concentration limit for dissolved or entrained noble gas is based on assumed exposure by immersion in water containing Xe-135 (assumed to be the critical radioactive noble gas). Ten times the value for Noble Gas Effluent I
/A l -f Concentrations is applied independently of the limit for other radionuclides because
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l Oyster Creek Offsite Dose Calculation Manual 11 the exposure pathway is separate.
4.6.1.2.4 The purpose of Section 4.6.1.1.4 is to require compliance with 10CFR Part 50, Appendix I, Section IV.A to assure that I
radioactive material in liquid effluent is l
l kept as low as reasonably achievable and l
to permit operating flexibility under i
unusual operating conditions.
4.6.1.2.5 The purpose of Section 4.6.1.1.5 is to l
l require that the concentrations of radioactive material in airborne effluents to the UNRESTRICTED AREAS comply with
)
The occupancy of a l
l l
Member of the Public who may from time to time be within the RESTRICTED AREA is 4
taken to be sufficiently low to compensate for any increase in atmospheric 1
concentration within the area, thereby causing the exposure to those Members of the Public to be less than the equivalent l
l annual limit on radiation exposure to a 1
Member of the Public incurred in the UNRESTRICTED AREAS.
~
i l
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Oyster Creek Offsite Dose Calculation Manual 11 4.6.1.2.6 The purpose of Section 4.6.1.1.6 is to require compliance with 10CFR Part 50 Appendix I, Section IV.A and to provide operating flexibility under unusual conditions as permitted in 10CFR Part 50.36a.
Assessment of compliance is implemented by calculational methods specified in the ODCM provided by the Surveillance Requirements. The ODCM methodology provides for assessing compliance with dose limits at or beyond the Site boundary based on either historical average atmospheric conditions ar conditions averaged over the period of interest.
The occupancy of a Member of the Public, who may from time to time be within the SITE BOUNDARY, is taken to be sufficiently low to compensate for any increase in atmospheric concentrat ion within the area, thereby causing the exposure of those Members of the Public incurred Offsite.
4.6.1.2.7 See Basis 4.6.1.2. 6.
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Oyster Creek Offsite Dose calculation Manual 11 4.6.1.2.8 Sections 4.6.1.1.8 and 4.6.2.1.8 implement the provisions of 40 CFR 190.10a as incorporated into 10CFR Part 20.1301(d).
It is unlikely that the dose to any Member 4
of the Public will exceed the limits of 40CTR Part 190.102 as long as the exposure remains within the limits of Sections 4.6.1.1.4, 4.6.1.1.6 and 4.6.1.1.7.
Only exposure to radioactive effluent and direct ganum radiation from the OCNGS is considered in assessing compliance because the dose to a Member of the Public from fuel cycle sources other than the OCNGS is negligible since there is no other fuel cycle facility within ten miles.
4.6.2 Radiological Effluent Monitoring Requirements These requirements apply to monitoring of gaseous and liquid i
radioactive effluent of the OCNGS ouri.ng release of effluent via the monitored pathway (s).
Each Surveillance Requirement applies whenever the corresponding Specification is applicable unless otherwise stated'in an individual Surveillance Requirement.
Surveillance Requirements do not have to be performed on inoperable equipment. The objective is to measure radioactive effluent adequately to verify that radioactive effluent are as low as is reasonably achievaile and within the limit
~
p of 10CFR Part 20.1301.
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Oyster Creek offsite Dose Calculation Manual 11 4.6.2.1 Sections 4.6.2.1.1 See Sections 4.6.2.1.3.
4.6.2.1.2 Main Condenser Offgas Treatment Operation of the Augmented Offgas System charcoal absorbers shall be verified by verifying the AOG System bypass valve (V-7-31) alignment or alignment indication closed at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the main condenser air ejector is operating.
4.6.2.1.3 Radioactivity concentration in Liquid Effluent A.
Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program in 000-ADM-4532.04-14.
Alternately, pre-release analysis of batch (es) of radioactive liquid waste i
may be by gross beta or gamma counting provided a maximum concentration limit of 2E-8 pCi/nd in the discharge canal at the U.S. Route 9 bridge is applied.
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Oyster Creek Offsite Dose Calculation Manual 11 i
B.
The alarm or trip setpoint of each radioactivity monitoring channel in 000-ADM-4532.04-12 shall be determined on the basis of sampling and analyses results obtained 1
according to Attachment 2000-1 ADM-4532.04-14 and setpoint method in this document and set to alarm or trip before exceeding the limits of Section 4.6.1.1.3.
4.6.2.1.4 Dose Due to Liquid Ef fluent An assessment shall be performed in
)
accordance with this procedure at least once a month to determine compliance with j
Section 4.6.1.1.4.
1 4.6.2.1.5 Dose Rate Due To Gaseous Effluent A.
Radioactive noble gaseous effluent shall be monitored in accordance with
)
l 1
Section 4.7.1.1.2.
Radioactive noble gas monitors named in Attachment 2000-ADM-4532.04-13 shall be set to cause automatic alarm when the monitor setpoint, determined as specified in this procedure, is exceeded.
(453204/S2) 67.0.
9 OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
'N Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 B.
An assessment shall be performed in accordance with this procedure at l
least once per month to vertfy that l
l the dose equivalent rate in the l
unrestricted area from Tritium, 1-131, I-133, and radioactive naterial in particulate form having half-lives of eight days or more does not exceed any limit in Section 4.6.1.1.5.
4.6.2.1.6 Air Dose Due To Noble Gas In Gaseous Effluent An assessment shall be performed in accordance with this procedure at least once per month to verify that the air dose due to noble gases in the unrestricted area does not exceed any limit in Section 4.6.1.1.6.
4.6.2.1.7 Dose Due to Radiciodine and Particulates in Gaseous Effluent An assessment shall be performed in accordance with this procedure at least once every month to verify that the cumulative dose from I-131, I-133, and radionuclides in particulate form with half-lives of 8 days or more released in
~
gaseous effluent does not exceed any limit
\\- #
in Section 4.6.1.1.7.
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Oyster Creek Offsite Dose Calculation Manual 11 m
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4.6.2.1.8 Annual Total Dose Due to Radioactive Effluent
)
l The cumulative dose to a Member of the Public offsite contributed by liquid and gaseous effluent shall be evaluated in accordance with the methodology and parameters in this procedure at least once per year.
4.6.2.2 Basis 4.6.2.2.1 Not Used.
4.6.2.2.2 Not Used.
4.6.2.2.3 The value 2E-8 is ten times the limit for th i
4
(,)
unidentified gross gamma or beta releases as per 10 CFR 20 (20.1001-20.2401).
This provides operational flexibility while providing reasonable assurance that dose will remain less than 0.1 rem /yr.
The alarm setpoint of the monitor of a continuous, aqueous radioactive release is derived from historical, or post-release, analysis. The trip setpoint of the liquid radwaste effluent monitor is determined on the basis of pre-sampling and analysis for the batch' releases.
4.6.2.2.4 Not Used.
j,-
m (453204/S2) 69.0
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4.6.2.2.5 Not Used.
4.6.2.2.6 Not Used.
4.6.2.2.7 Not Used.
4.6.2.2.8 Not Used.
I 4.7 RADIOACTIVE EFFU ENT MONITORING INSTRUMENTATION l
4.7.1 Radioactive Effluent Monitoring Instrumentation Requirements This section applies to instrumentation whose function is to monitor aqueous and airborne radioactive effluent from the OCNGS.
Its objective is to assure that instrumentation used to monitor l
radioactive effluent is OPERABLE when effluent is discharged or that means of measuring effluent is provided.
i 4.7.1.1 Sections 4.7.1.1.1 Liquid Effluent Instrumentation A.
The radicactive effluent monitoring channels listed in
~ 000-ADM-4532.04-12 shall l
j be OPERABLE with their alarm / trip I
l setpoints set to initiate alarm / trip in the event the limit of j
specification 4.6.1.1.3.A is exceeded.
l B.
The alarm or trip setpoint of these 1
l channels shall be determined and set l
j in accordance with the method l
described in Section 4.1.
)
l l V (453204/52) 70.0
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Title Revision No.
V Oyster Creek Offsite Dose Calculation Manual 11 C.
When a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluent monitored by the l
affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative, or provide for manual initiation of the alarm / trip functions (s).
D.
When less than the minimum number of radioactive liquid effluent monitoring 1
instrumentation channels are OPERABLE, take the ACTION shown in 000-ADM-4532.04-12.
Make i
I every reasonable effort to restore the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
OU (453204/s2) 71.0 l
l
i OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NtJCLEAR
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 l
l 4.7.1.1.2 Gaseous Effluent Instrumentation A.
Each radioactive effluent noble gas monitoring channel listed in l 000-ADM-4532.04-13 shall be OPERABLE with its alarm setpoint l
set to cause automatic alarm in the 1
i event a limit of Section 4.6.1.1.5.A is exceeded.
B.
The alarm or trip setpoint of these l
channels shall be determined and set in accordance with the method described in Section 4.1.
C.
When a radioactive effluent monitoring l
instrumentation channel alarm / trip l
setpoint is less conservative than required by Section 4.7.1.1.2.A, without delay suspend the release of radioactive gaseous effluent monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably i
conservative.
1 (453204/S2) 72.0 I
1
I OYSTER CREEK POLICY AND Numbar gpg PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR O
Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 D.
When less than the minimum number of radioactive gaseous monitoring instrumentation channels are OPERABLE, take the ACTION shown in Attacht.ent 2000-ADM-4532.04-13.
Make every reasonable effort to restore the instrument to OPERABLE status within 30 days and, if unsuccessful, I
explain in the next Annual Radioactive Effluent Release Report why the
)
inoperability was not corrected in a timely manner.
4.7.1.2 Basis O
4.7.1.2.1 The radioactive liquid effluent instrumentation is provided to monitor and control, if applicable, the releases of radioactive materials in liquid effluent during actual or potential releases of liquid effluent. The use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part 50.
Radioactivity monitors on the liquid radwaste effluent line and in the Turbine Building Sump 1-5 initiate a trip to stop the effluent discharge pump when the trip setpoint is exceeded. The reactor service water system discharge line radioactivity
.[
monitor initiates an alarm in the Control V
Room when the alarm setpoint is exceeded.
j (453204/S2) 73.0
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Title Revision No.
l Oyster Creek Offsite Dose Calculation Manual 11 l
The alarm / trip setpoint for each of these instruments is calculated and adjusted in accordance with the methodology and parameters in Section 4.1 to ensure that the alann/ trip will occur prior to exceeding the limits of Section 4.6.1.1.3.
4.7.1.2.2 The radioactive gaseous effluent instrumentation in Attachment 2000-ADM-4532.04-13 is provided to monitor and control, as applicable, the releases of radioactive narerials in gaseous effluent during releases of gaseous effluent. The alarm / trip setpoint for each of the noble gas monitors is calculated and set in accordance with methodology and parameters in Section 4.1 to ensure that the alarm / trip will occur prior to exceeding the limits of Section 4.6.1.1.5.
The j
operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part 50.
The radioactive gas monitors for the stack effluent and the Augmented Offgas Building exhaust ventilation have alarms which report in the Reactor Control Room.
s The Stack and the Turbine Building exhaust ventilation effluent air are monitored by a (453204/S2) 74.0
OYSTER CREEK POLICY AND Numbar
-PROCEDURE MANUAL 2000-ADM-4532.04 NSICLEAR Title Revision No.
oyster Creek offsite Dose calculation Manual 11 radioactive gaseous effluent monitoring l
system. It can sample effluent for l
radioactive particulates, iodine, and noble gases.
It can measure the gross concentration of radioactive noble gases. A grab sample of the effluent will be taken at least once per month and analyzed for the l
l principal noble gas radionuclides (Reference l 000-ADM-4532.04-15).
The gross gamma activity concentration of
(
)
noble gas in Stack effluent is displayed in the Control Room. That channel also i
causes an alarm in the Control Room in the event a high activity concentration setpoint is exceeded. Low flow of sampled stack effluent would also cause an alarm in the Control Room. Although flow data may be collected by a computer, the sample flow and the sampled steam flow can also be observed at a display located near the j
l monitoring instrument (in which case the 1
l channel continues to serve its essential 1
function and remains OPERABLE). 'If the 4
noble gas' activity concentration display 1
and the associated alarm become inoperable i
~
in the Control Room, then OCNGS will perform the appropriate action according to Attachment 2000-ADM-4532.04-13.
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OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose calculation Manual 11 The gross gamma activity concentration of noble gas in Turbine Building exhaust ventilation effluent is displayed locally in the Turbine RAGEMS Building. Noble gas activity concentration, sample flow and sampled stream flow, may be collected by a computer and may also be observed on displays near the monitoring instruments I
(in which case the channels continue to l
l serve their essential functions and remain OPERABLE).
If the noble gas activity l
concentration display and the associated
)
alarm become inoperable in the Turbine RAGEMS Building, then OCNGS will perform l
the appropriate action according to
" 000-ADM-4532.04-13.
Purging i
the drywell to purify its atmosphere may l
discharge most of the air and gases in a brief time.
Hence, the drywell is purged only when the radioactive noble gas monitor in the stack monitoring system is l
operating in order to ensure measurement 1
of radioactive gases discharged.
Frequently, the drywell is vented to control its pressure.
Since the release l
rate is comparatively small, the effluent is monitored as usual and the extra requirement in (453204/S2) 76.0
OYSTER CREEK POLICY AND Numbar
(]}
PROCEDURE MANUAL 2000-ADM-4532.04 nuCLEM Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532,04-13, Action 124 that is applied during purging is not imposed during drywell venting.
4.7.2 Radioactive Effluent Monitoring Instrumentation Surveillance This section states surveillance requirements for OPERABILITY of radioactive effluent monitoring instrumentation.
Its objective is to demonstrate the OPERABILITY of radioactive effluent monitoring instrumentation.
4.7.2.1 Section 4.7.2.1.1 Liquid Effluent Instrumentation Each radioactive liquid effluent monitoring instrument channel shall be demonstrated OPERABLE by performance of the CRANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in 000-ADM-4532.04-16.
\\
(453204/S2) 77.0
(
l f
OYSTER CREEK POLICY AND Numb 2r
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PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
)
Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11 4.7.2.1.2 Gaseous Effluent Instrumentation Each radioactive gaseous effluent monitoring instrument channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in l
l 000-ADM-4532.04-17.
l 4.8 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of 10 CFR, the following identified reports shall be submitted to the Administrator of the NRC Region I office unless otherwise noted.
4.8.1 Annual Radioactive Effluent Release Report - A report of radioactive materials released from the OCNGS during the preceding year shall be submitted to the NRC within 60 days after January 1 of each year (Section 6.9.1.d of the OCNGS Tech Specs). The report shall include the i
following information:
4.8.1.1 A summary by calendar quarter and by radionuclide of the quantities of radioactive liquid and gaseous effluent from the OCNGS.
(453204/S2) 78.0
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(
)
Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11 1
4.8.1.2 A summary of radioactive solid waste shipped from the OCNGS including:
4.8.1.2.1 physical description of the waste 4.8.1.2.2 classification of the waste, per 10 CFR Part 61 4.8.1.2.3 solidification agent (if solidified) 4.8.1.2.4 total volume shipped 4.8.1.2.5 total quantity of radioactive material shipped (curies) 4.8.1.2.6 best knowledge of identity of principal radionuclides, 4.8.1.3 A description of any changes to the Process Control
/
i
( /
4.8.1.4 A summary of meteorological data collected during the year shall be included in the report. Alternatively, summary meteorological data may be retained by GPU Nuclear and made available to the NRC upon request.
4.8.2 Annual Radiological Environmental Report - A report of radiological environmental surveillance activities during each year shall be submitted before May 1 of the following year (Section 6.9.1.e of the OCNGS Tech Specs). Each report shall include the following information required in Section 4.5.
herein:
4.8.2.1 A summary description of the radiological environmental monitoring program.
[%
/
(453204/S2) 79.0
OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 uuctuan
[' }
Title Revision No.
i I
x_ '
Oyster Creek Offsite Dose calculation Manual 11 4.8.2.2 A map and a table of distances and directions 1
(compass azimuth) of locations of sampling stations from the reactor.
4.8.2.3 Results of analyses of samples and of l
radiation measurements.
(In the event some l
results are not available, the reasons shall be explained in the report.
In the event the missing results are obtained, they shall be reported to the NRC as soon as is reasonable.)
4.8.2.4 Deviation (s) from the environmental sampling l
schedule in Attachment 2000-ADM-4532.04-9.
)
4.8.2.5 Identification of environmental samples analyzed when instrumentation was not capable of meeting detection capability in
- 000-ADM-4532.04-10.
4.8.2.6 A summary of the results of the Land-Use Survey.
4.8.2.7 A summary of results of licensee participation in an NRC approved inter j
laboratory comparison program for environmental samples.
4.8.2.8 Results of dose evaluations to demonstrate compliance with 40 CFR Part 190.10a.
~
O 8
(453204/S2) 80.0
OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR O
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Oyster Creek Offsite Dose Calculation Manual 11 4.8.3 Unique Reporting R'equirements Special reports shall be submitted to the appropriate NRC office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
a)
Dose due to radioactive liquid effluent exceeding the limits in Section 4.6.1.1.4.A b) Air dose due to radioactive noble gas in gaseous effluent exceeding the lindts in Section 4.6.1.1.6.A c)
Dose due to radioiodine and particulates in gaseous
)
effluent exceeding the limits in Section 4. 6.1.1.7. A d)
Annual total dose due to radioactive effluent exceeding the limits in Section 4.6.1.1.8.A e)
Records of results of analyses required by the Radiological Environmental Monitoring Program.
(Section 4.5.1. 6) f)
Liquid radwaste batch discharge exceeding the limits in Section 4.6.1.1.1.A g) Main condenser offgas discharge without treatment 1
per the limit in Section 4.6.1.1.2.B l
i A
d v
(453204/S2) 81.0 o
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PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
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Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 s
i 4.8.4 Basis 4.8.4.1 The Annual Radiological Environmental Report
}
(section 4.8.2) includes factual data summarizing results of activities required by the surveillance program.
In order to aid interpretation of the data, GPUN may choose to submit analysis of trends and comparative non-regional radiological environmental data.
In addition, the licensee may choose to discuss previous radiological environmental data as well as the observed radiological environmental impacts of OCNGS operation (if any) on the environment.
O( )
5.0 RESPONSIBILITIES 5.1 RADIOLOGICAL CONTROLS DIRECTOR (OCNGS) - Implementing Approval of ODCM per 1000-ADM-1291.01, " Oyster Creek Review and Approval Matrix (Exhibit 2)".
5.2 PLANT RADWASTE AND CHEMISTRY (OCNGS) - Responsible for:
5.2.1 Compliance with specifications regarding routine dose i
assessment.
5.2.2 Concurring with this procedure and any Divisional procedures which address interdivisional responsibilities.
l 5.2.3 Technical Consultation and Review 1
5.3 PLANT OPERATIONS (OCNGS) - Responsible for compliance with specifications regarding operation of the OCNGS.
5.4 ENGINEERING DIVISION (OCNGS) - Responsible for compliance with specifications regarding setpoint determination and
-s b
implementation.
e (453204/S2) 82.0
)
1 l
OYSTER CREEK POLICY AND Numb 3r PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
\\~-
Oyster Creek Offsite Dose Calculation Manual 11
)
5.5 ENVIRONMENTAL AFFAIRS - (OCNGS)
Responsible for:
5.5.1 Radiological Environmental Monitoring Program.
5.5.2 Technical consultation and review.
j i
5.6 RADIOLOGICAL ENGINEERING (OCNGS) - Responsible for technical consultation and review.
6.0 REFERENCES
6.1 OCNGS Procedures 1000-ADM-1218.01, GPU Nuclear Policy, Plan and Procedure System 6.2 OCNGS Procedures 1000-ADM-1291.01, Safety Review Process 6.3 OCNGS Updated Final Safety Analysis Report 6.4 OCNGS Facility Description and Safety Analysis Report 6.5 OCNGS Operating License and Technical Specifications
?
6.6 Reg Guide 1.23 6.7 Reg Guide 1.97 6.8 Reg Guide 1.109 6.9 Reg Guide 1.111 l
6.10 Reg Guide 4.8
]
6.11 NRC Branch Technical Position 6.12 NUREG-0016 6.13 NUREG-0133 6.14 Licensing Application, Amendment 13, Meteorological l
Radiological Evaluation for the Oyster Creek Nuclear Power Station Site.
6.15 Licensing Application, Amendment 11, Question IV-8.
6.16 Evaluation of the Oyster Creek Nuclear Generating Station to Demonstrate Conformance to the Design Objectives of 10CFR50, l
\\,-
Appendix I, May, 1976, Tables 3-10.
(453204/S2) 83.0
OYSTER CREEK POLICY AND Numb 3r PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR O
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Oyster Creek Offsite Dose Calculation Manual 11 6.17 Meteorological Information and Diffusion Estimates to Conform with Appendix I Requirements: Oyster Creek, July, 1976, Table 1.3-11B.
6.18 Hydrological Information and Liquid Dilution Factors Determination to Conform with Appendix I Requirements: Oyster Creek, correspondence from T. Potter, Pickard, Lowe and Garrick, Inc. to Oyster Creek, July, 1976.
6.19 Carpenter, J. J.
" Recirculation and Effluent Distribution for Oyster Creek Site", Pritchard-Carpenter Consultants, Baltimore, Maryland, 1964.
6.20 Nuclear RegulatcIy Commission, Generic Letter 89-01,
" Implementation of Programmatic Controls for Radiological O
Ef fluent Technical Specifications in the Adadnistrative Controls Section and Relocation of the Procedural Details of RETS to tAe ODCM or PCP", January, 1989.
- 6.21 Ground Water Monitoring System (Final Report), Woodward-Clyde Consultants, March, 1984.
6.21 Meteorology and Atomic Energy, Department of Energy, 1981.
6.22 SEEDS Code Documentation through V & V of Version 98.8F (Radiological Engineering Calculation No. 2820-99-005, Dated 3/23/99) 6
+V (453204/s2) 84.0 1
OYSTER CREEK POLICY AND Numbar GPU PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
(%J~) Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532.01-1 Site Boundary and Effluent Release Locations Oyster Creek NGS N
e -d
'8 Xh '?
/
.rje cWW s
a wggy.j%op 1"
q r
v 2v
)i
",,s "Nwfdy;(3 W%
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f r-"
m e.
-- i-m ~g r. w,
l nilliti _ i.=- = >
~
- =-
ginnin f==rur $
g
((
m J
f,_
i -. - w = ~
= ;_
\\
c 9
a l.......
--. 3 7
(
ma Omrbrae Canal 7,g wye' Oyste (msk
- j
.k i...i Scale a wei OO O
(453204/S3) gi_1
OYSTER CREEK POLICY AND Numb 3r PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
' Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532.04-2 Distribution Of Radioactive Noble Gases in Gaseous Effluent Radionuclice Effluent Discharge Point Stack Turbine Buildino Vent AOG Buildino Vent (C1/ yr)
Fraction (C1/yr)
Fraction (C1/yr)
Fraction KrB3m 205 5.40E-03 Kr85m 5620 1.50E-01 68 1.90E-02 3
1'.90E-02 Kr85 140 3.70E-03 Kr87 400 1.00E-02 190 5.40E-02 3
1.90E-02 KrB0 6200 1.60E-01 230 6.60E-02 3
1.90E-02 Kr89 650 1.70E-02 Xe131m 62 1.60E-03 Xe133m 110 2.90E-03 Me133 20000 5.20E-01 280 8.00E-02 66 4.10E-01 Xe135m 760 2.00E-02 650 1.90E-01 46 2.80E-01 Xe135 1200 3.10E-02 630 1.80E-01 34 2.10E-01 Xe137 190 2.10E-02 Xe138 2000 5.20E-02 1440 4.10E-01 7
4.30E-02 Ar41 2*
6.60E-05 TOTAL 38162 3488 162
Reference:
United States Nuclear Regulatory Conunission - Off. Std. Dev.,
April 1976, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents fron. Boiling Water Reactors (BWR GALE O
Code), NUREG-0016.
(453204/S4)-
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OYSTER CREEK POLICY AND Numbar GPU PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR y
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Oyster Creek Offsite Dose Calculation Manual 11
( 000-ADM-4532.04-3 Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-to-D.se Equivalent Rate Factors
- Radionuclide Factor DFSi for Factor DFVi for Stack Release
- Ground-level or Split-Wake Release **
mrem-sec mrem-m' uCi-year uCi-year Kr83m 1.47E-09 7,56E-02 Kr85m 9.12E-05 1.17E+03 Kr85 1.47E-06 1.61E+01 Kr87 4.80E-04 5.92E+03 7.
f i
\\/
Kr88 1.18E-03 1.47E+04
~-
Kr89 1.17E-03 1.66E+04 Kr90 1.56E+04
~
Xe131m 2.10E-05 9.15E+01 Xei33m 1.64E-05 2.51E+02 Xe133 1.57E-05 2.94E+02 Xe135m 2.77E-04 3.12E+03 Xe135 1.51E-04 1.81E+03 Xe137 1.06E-04 1.42E+03 Xe138 7.63E-04 8.83E+03 Xe139 1.44E-04 5.02E+03 Ar41 9.11E-04 8.84E+03
[
- Based on reference meteorology applicable at 522 meters SE of stack.
For exposure to a semi-infinite cloud of noble gase.
%_J (453204/SS)
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OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
' Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532.04-4 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors
- Radionuclide PySi++
Pyvi + *
- AWi+ *
- SBi***
mrem mrem-m3 mrad-m3 mrem-m3 uCi uCi-sec uCi-sec uCi-sec Kr83m 4.66E-17 2.40E-09 6.13E-07 Kr85m 2.91E-12 3.71E-05 3.90E-05 4.63E-05 Kr85 4.66E-14 5.11E-07 5.46E-07 4.25E-05 Kr87 1.52E-11 1.88E-04 1.96E-04 3.09E Kr88 3.73E-11 4.67E-04 4.83E-04 7.52E-05 Kr89 3.70E-11 5.27E-04 5.49E-04 3.21E-04 Kr90 4.95E-04 5.17E-04 2.31E-04 X513J'm 6.65E-13 2.90E-06 4.95E-06 1.51E-05 Xe133m 5.20E-13 7.97E-06 1.04E-05 3.16E-05 Xe133 4.97E-13 9.33E-06 1.12E-05 9.71E-06 Xe135m 8.78E-12 9.90E-05 1.07E-04 2.26E-05 Xe135 4.78E-12 5.75E-05 6.10E-05 5.90E-05 Xe137 3.36E-12 4.51E-05 4.79E-05 3.87E-04 Xe138 2.42E-11 2.80E-04 2.92E-04 1.31E-04 Xe139 4.56E-12 Ar41-2.89E-11 2.81E-04 2.95E-04 8.54E-05
- All of these dose f actors apply cut-of-doors.
~
Based on reference meteorology st 522 meters SE of effluent stack.
- *
- Derived from Reg ' Guide 1.109, Revision 1, Table B-1.
-(453204/S6).
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I OYSTER CREEK POLICY AND Numb 3r PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR p
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g Oyster Creek Offsite Dose Calculation Manual 11 I 000-ADM-4532.04-5 Air Dose Conversion Factors for Effluent Noble Gas
- Radionuclid.
AySi *
- AyVi * *
- ABi***
mrad mrad-m3 mrad-m3 uCi uCi-sec uCi-sec Kr83m 9.35E-15 6.13E-07 9.14E-06 Kr85m 3.03E-12 3.90E-05 6.25E-05 Kr85 4.94E-14 5.46E-07 6.19E-05 l
Kr87 1.60E-11 1.96E-04 3.27E-04 Kr88 3.93E-11 4.83E-04 9.30E-05 l
Kr89 3.90E-11 5.49E-04 3.37E-04 l
l Kr90 5.17E-04 2.49E-04 Xe131m 7.26E-13 4.95E-06 3.52E-05 l
.6133m 5.86E-13 1.04E-05 4.70E-05 Xe133 5.45E-13 1.12E-05 3.33E-05 Xe135m 9.32E-12 1.07E-04 2.35E-05 Xe135 6.18E-12 6.10E-05 7.81E-05 Xe137 3.55E-12 4.79E-05 4.03E-04 Xe138 2.54E-11 2.92E-04 1.51E-04 Xe139 4.82E-12 Ar41.
3.03E-11 2.95E-04 1.04E-04
- To balance time units,. when using AyVi or ABi from the above table, omit the 3.17E-B time conversion from the associated formulae.
~
~ ** Based on reference meteorology at $22 meters SE of effluent stack.
- *
- Derived from Reg Guide 1.109, Revision 1, Table B-1.
-(453204/S7)
E5-1
r OYSTER CREEK POLICY AND NumbIr
$pS PROCEDURE MANUAL 2000-ADM-4532.04 i
NUCLEAR Title Revision No.
(
)
Oyster Creek Offsite Dose Calculation Manual 11 L/
1 l 000-ADM-4532.04-6 Locations Associated with Maximum Exposure of a Member of the Public*
Effluent Location Distance Direction (meters)
(to) l Liquid U.S. Route 9 Bridge at Discharge Canal Airborne Iodine and Particulates 966 SE Tritium 966 SE i
Noble Gases 966 SE Irradiation by OCNGS Site Boundary All
-s I
w/
Note: the nearby resident experiencing the maximum exposure to airborne effluent and to gamma radiation directly from the Station is located 966 meters SE of the OCNGS.
The-most exposed member of the public is assumed to be exposed by irradiation from the OCNGS, by inhaling airborne effluent, by irradiation by the airborne effluent, by irradiation by the airborne plume of the noble gas, by radionuclides deposited onto the ground, by irradiation by shoreline deposits, and by eating fish and shellfish caught in the discharge canal.
l
- The age group of the most exposed member of the public is based on Reg.
Guide 1.109, Revision 1.
l l
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OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 MUCLEAR l
i Title Revision No.
(
Oyster Creek Offsite Dose calculation Manual 11 000-ADM-4532.04-7 l.
Critical Receptor Noble Gas Dose Conversion Factors
- Rtdionuclide PySi *
- PyVi* *
- AYVi* *
- AySi*
- SBi***
mrem mrem-m3 mrad-m3 mrad mrem-m3 uCi uC1-sec uCi-sec uC1 uCi-sec I
Kr83m 3.76E-17 2.40E-09 6.13E-07 9.66E-15 I
Kr85m 1.68E-12 3.71E-05 3.90E-05 1.75E-12 4.63E-05 Kr85 2.60E-14 5.11E-07 5.46E-07 2.75E-14 4.25E-05 Kr87 8.37E-12 1.88E-04 1.96E-04 8.81E-12 3.' 09E-0 4
(
4Kr88 2.08E-11 4'. 67 E- 04 4.83E-04 2.18E-11 7.52E-05 Kr89 1.83E-11 5.27E-04 5.49E-04 1.93E-11 3.21E-04 Kr90 4.95E-04 5.17E 04 2.31E-04
?.elaiim,~
3.99E-13 2.90E-06 4.95E-06 4.44E-13 1.51E-05 Xe133m 3.10E-13 7.97E-06 1.04E-05 3.58E-13 3.16E-05 Xe133 3.11E-13 9.33E-06 1.12E-05 3.42E-13 9.71E-06 Xe135m 4.71E-12 9.90E-05 1.07E-04 5.01E-12 2.26E-05 Xe135 2.73E-12 5.75E-05 6.10E-05 2.87E-12 5.90E-05 Xe137 1.65E-12 4.51E-05 4.'79E-05 1.75E-12 3.87E-04 Xe138-1.33E-11 2.80E-04 2.92E-04 1.40E-11 1.31E-04 i
Xe139 1.61E-12 Ar41 1.58E-11 2.81E-04 2.95E-04 1.66E-11 8.54E-05 11 of these dose -factors apply out-of-doors.
Based on reference meteorology at 522 meters SE of effluent stack.
i I
- Derived from Reg Guide 1.109, Revision 1, Tab 1? B-1
.(453204/59)
E7-1
I-OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.01 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose calculation Manual 11 000-ADM-4532.04-8 The Individual Maximum Hypothetical Exposed Member of the Public at the OCNGS Effluent Location Distance Direction (meters)
(to)
Liquid U.S. Route 9 Bridge at Discharge Canal Noble Gas Y-Air Dose Site Boundary All Noble Gas B-Air Dose 966 SE Iodine and Particulates 966 SE Notet,The Beta Air Dose, Noble Gas and Iodine and Particulate receptor is dependent on the highest annuel-average X/Q values as described in this ODCM.
For liquids, the maximum pathway is via consumption of fish and shellfish from the OCNGS: Discharge Canal and direct shoreline exposure. The nearest individual resident is 956 meters to the SE of the OCNGS for assessing compliance with Sections 4.6.1.1.5, 4.6.1.1.6 and 4.6.1.1.7.
.e (453204/S10)
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f OYSTER CREEK POLICY AND Numbar g%
PROCEDURE MANUAL 2000-ADM-4532.04 NUCLCA2 Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532.04-10 (continued)
The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only five percent probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular environmental sample.
For a particular measurement system, which may include radiochemical separation:
LLD =
4.66*Sb E*V* 2. 2 2 *y* exp (-AAt )
where LLD is the lower limit of detection (picoeuries per unit
(
mass or volume) l So is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)
E is the counting efficiency (counts per disintegration)
V is the sample size (mass or volume) 2.22 is the number of disintegrations per minute per picoeurie y is the fractional radiochemical yield, when applicable A is the radioactive decay constant for the particular radionuclide At for environmental samples is the elapsed time between sample collection, or end of the sample collection' period, and time of counting j
l Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions. Occasionally, background fluctuations, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report pursuant to OCNGS Technical Specification 6.9.1.e and Section 4.8.2 herein.
b)
(,,
For a sample of drinking water. See Section 4.5.1.10.3 For a sample of water not used as a source of drinking water.
See section 4.5.1.10.4.
(453204/S13)
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OYSTER CREEK POLICY AND Numb 3r g%
PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR g-s Title Revision No.
(
)
Oycter Creek Offsite Dose Calculation Manual 11 ATTACHMENT 2000-ADM-4532.04-12 NOTATIONS a.
Instrument channels shall be OPERABLE, and in service as indicated except that a channel may be taken out of service for the purpose of j
a check, calibration, test, or maintenance without declaring the channel to be inoperable, b.
During releases via this pathway.
)
ACTION 110 With no channel OPERABLE, effluent may be released provided that:
(
l.
At least two independent samples are taken, one prior to discharge and one near the completion of discharge. These will be analyzed per Section 4.6.2.1.3.A, and 2.
Before initiating a release, qualified personnel must determine the acceptable release rate and proper discharge valving and other qualified personnel independently verify that the release rate and discharge valving are acceptable.
otherwise, suspend release of radioactive effluent via this pathway.
\\--
ACTION 112 With no channel OPERABLE, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the release, grab samples are collected and analyzed for gross radioactivity (beta 1
or gamma) at a limit of detection of at least lE-6 uci/ml.
ACTION 113 With no channel OPERABLE, effluent releases via the affected pathway may continue provided the flow is estimated with the pump curve or change in tank level, at least once per batch during a release.
ACTION 114 With no channel OPERABLE, effluent umy be released provided that before initiating a release:
1.
A sample is taken and analyzed in accordance with Section 4.6.2.1.3.A.
2.
Qualified personnel determine and independently verify the acceptable release rate.
l
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OYSTER CREEK POLICY AND Numb 3r (l[
PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR.
Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 V,
ATTACHMENT 2000-ADM-4532.04-13 NOTATIONS a.
Channels shall be OPERABLE and in service as indicated except that a channel may be taken out of service for the purpose of a check, calibration, test maintenance or sample media change without declaring the channel to be inoperable.
b.
During releases via this pathway.
e.
Monitor / sampler or an alternate shall be OPERABLE to monitor / sample Stack effluent whenever the drywell is being purged.
ACTION 122 With no channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estinated whenever the exhaust fan combination in this system is changed.
ACTION 123 With no channel OPERABLE, effluent releases via this pathway may continue provided a grab 7-g sample is taken at least once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and is analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter or provided an alternate monitoring system with local display is utilized.
, ACTION 124 With no channel OPERABLE, effluent releases via this pathway may continue provided a grab sample is taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed for gross radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or provided an alternate monitoring system with local display is utilized.
Drywell purge is permitted only when the radioactive noble gas monitor is operating.
ACTION 127 With no channel OPERABLE, effluent releases via this pathway may continue provided the required sampling is initiated with auxiliary sampling equipment as soon as reasonable after discovery of inoperable primary sampler (s).
' ACTION 128 With no channel OPERABLE, effluent releases via the sampled pathway may continue provided the sampler air flow is estimated and recorded at least once per day.
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OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NLICLEAR
- O Title Revision No.
Oyster Creek offsite Dose Calculation Manual 11 000-ADM-4532.04-14 NOTATIONS a.
The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular sample in the radioactive liquid waste sampling and analyses program.
For a particular measurement system, which may include radiochemical separation:
4.66S.
LLD =
E*V*2.22E+6*Y*exp(-AAt)
Where:
O.
LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),
S. is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
,' E~is the counting efficiency, V is the sample size (units of mass or volume),
2.22E+6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and A t is the elapsed time between the end of the sample collection and the time of counting.
Analyses shall be performed in such a manner that the stated LLDs will be
' achieved under routine conditions with typical values of E, V, Y, and t'for the radionuclides Mn-54, Fe-59, co-58, Co-60, Zn-65, Ce-141, Cs-134, Cs-137; i
and~ an LLD of lE-5 pCi/ud should typically be achieved for Mo-99 and Ce-144.
. Occasionally, background fluctuations, interfering-radionuclides, or other i
uncontrollable. circumstances may render these LLD's unachievable.
AD (453204/S20)
E14 r
OYSTER CREEK POLICY AND Numb 3r GPU PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
/j Title Revision No.
'( _ /
Oyster Creek Offsite Dose Calculation Manual 11 Attachment.2000-ADM-4532.04-14 NOTATIONS When calculating the LLD for a radionuclide determined by ganna ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the sample. The background count rate of a GeLi detector is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for the radionuclide.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Mn-54, Fe-59, co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. The LLD for Mo-99 and Ce-144 is lE-5 KC1/ml whereas the LLD for the other gamma emitters is lE-6 Ci/nd. Nuclides which are below the LLD for the analysis should not be reported.
b.
A batch release is the discharge of liquid wastes of a discrete volume.
Before sampling for analysis, each batch should be thoroughly mixed.
I
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c.
In the event a gross radioactivity analysis is performed in lieu of an isotopic analysis before a batch is discharged, a sample will be analyzed for principal gamma emitter afterwards.
d.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
e.
Analysis may be performed after release.
f.
In the event a grab sample contains more than 1.0E-6 pCi/ml of I-131 and principal gamma emitters or in the event the effluent radioactivity monitor indicates more than 1E-6 Ci/nd radioactivity in the effluent, as applicable, sample Reactor Building Service Water effluent daily or sample Turbine Building Sump 1-5 each discharge until analysis confirms the activity concentration in the effluent does not exceed 1.0E-6 pCi/ml.
In addition a composite sample must be made up for further analysis for all samples taken when the activity was > 1.0E-6 pCi/ml.
g.
A composite sample is produced combining grab samples, each having a defined volume, collected routinely from the sump or stream being sampled.
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OYSTER CREEK POLICY AND Numb 2r i
PROCEDURE MANUAL 2000-ADM-4532.04 CUCL"A2 l
Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 000-ADM-4532.04-15 NOTATIONS a.
The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is applicable to the capability of a measurement 1
l system under typical conditions and not as a limit for the l
measurement of a particular sample in the radioactive liquid waste sampling and analyses program.
For a particular measurement system, which may include radiochemical separation:
4.66S3 LLD =
E*V* 2. 22 E+ 6
- Y* exp (- AAt)
Where O
LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),
S, is the standard deviation of the background counting rate or of l
i the counting rate of a blank sample as appropriate (counts per minute),
\\
E is the counting efficiency, V is the sample size (units of mass or volume),
2.22E+6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between the end of the sample collection and the time of counting.
Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions with typical values of E, V, Y, and t for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, Cs-137, and Ce-141; an LLD of IE-5 Ci/ml should typically be achieved for Mo-99 and Ce-144.
Occasionally background fluctuations, interfering radionuclides, or other uncontrollable circumstances may render these LLD's unachievable.
~
When calculating th'e LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other
,Q radionuclides normally present in the samples. The background count rate of V-a GeLi detector is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for that radionuclide.
(453204/S22)
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I OYSTER CREEK POLICY AND Numbar GPU PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAD Title Revision No.
(~')
Oyster Creek Offsite Dose Calculation Manual 11 x
/
Lr 000-ADM-4532.04-15 NOTATIONS (continued) b.
The principal ganum emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other ganum peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report consistent with section 4.6.1.1.5.B.
The LLD for Mo-99 and Ce-144 is 1E-10 Ci/ml whereas the LLD for other principal gamma emitting particulates is 1E-11 Ci/ml.
Radionuclides which are below the LLD for the analysis should not be reported.
c.
The noble gas radionuclides in gaseous effluent may be identified by either on-line (gamma spectrum) analysis of a flowing sample of effluent or by taking a grab sample of effluent and analyzing
/~~'s it.
N~-l j
d.
In the event the reactor power level increases more than 15 percent in one hour and the Stack noble gas radioactivity monitor shows an activity increase of more than a factor of j
three after factoring out the effect due to the change in
- reactor power, an on-line analysis for noble gas radionuclides in Stack effluent shall be performed or a grab sample of Stack effluent shall be collected and analyzed.
e.
A composite particulate sample shall include an equal fraction of a least one particulate sample collected during each week of the compositing period.
f.
In the event a sample is collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, the LLD may be increased by a factor of 10.
d b
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PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
~'s Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11 l 000-ADM-4532.04-16 NOTATIONS a.
Instrumentation shall be OPERABLE and in service except that a channel may be taken out of service for the purpose of a check, calibration, test or maintenance without declaring it to be inoperable, b.
During releases via this pathway.
- c..The CHANNEL TUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and alarm annunciation in the Radwaste Control Room occur if the instrument indicates measured levels above the alarm setpoint.
d.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions i
exists:
1 1.
Instrument indicates measured levels above the alarm setpoint.
2.
Instrument indicates a downscale failure.
3.
Instrument controls not set in operate mode.
4.
Instrument electrical power loss.
e.
The CHANNEL CALIBRATION shall be performed according to i
established calibration procedures, i
f.
On any day during which a release is made, a SOURCE CHECK shall be made at least once per day, before the first release.
l g.
A CHANNEL CHECK shall consist of verifying indication of flow during effluent release. A CHANNEL CHECK shall be made at least once during any day on which a release is made.
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f--
Title Revision No.
( )g 1
Oyster Creek Offsite Dose Calculation Manual 11 m 000-ADM-4532.04-17 NOTATIONS a.
Instrumentation shall be OPERABLE and in service except that a channel umy be taken out of service for the purpose of a check calibration, test or unintenance without declaring it to be inoperable.
b.
During releases via this pathway.
e.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
1.
Instrument indicates measured levels above the alarm setpoint.
l 2.
Instrument indicates a downscale failure.
3.
Instrument controls not set in operate mode.
4.
Instrument electrical power loss.
f.
The CHANNEL CALIBRATION shall be performed according to established calibration procedures.
h.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control
)
room alarm annunciation occurs if any of the following conditions
>kd exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Instrument indicates a low count rate / monitor failure.
3.
Switch cover alarm shall be verified to alarm when the cover l
~
is opened; and clear when the cover is closed after the faceplate switches are verified in their correct positions.
l l
1.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Instrument indicates a low count rate / monitor failure.
I I
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-(453204/S26)
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r OYSTER CREEK POLICY AND Numb r GM PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
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Oyster Creek Offsite Dose Calculation Manual 11
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EXHIBIT 2000-ADM-4532.04-1 ATMOSPHERIC DISPERSION DATA Centerline X/Q and D/Q values were obtained for a sector width of 22.5 degrees. On-site meteorological data for the period January 1, 1989 through Decerser 31, 1990 were used.
Data were collected and atmospheric and stability classes were defined on the basis of vertical temperature difference methodology in conformance with Reg Guide 1.23.
METEOROLOGICAL ANALYSES Exhibit 2000-ADM-4532.04-2 Assumed Distance to OCNGS Site Boundary in each Sector Exhibie 2000-ADM-4532.04-3 OCNGS Dispersion Parameters (X/Q) for l (" \\
\\,-
Elevated Releases l
Exhibit 2000-ADM-4532.04-4 OCNGS Dispersion Parameters (X/Q) for Ground Releases
~ Exhibit 2000-ADM-4532.04-5 OCNGS Dispersion Parameters (D/Q) for Elevated Releases Exhibit 2000-ADM-4532.04-6 OCNGS Dispersion Parameters (D/Q) for Ground Releases 6
v (453204/S27)
E18-1
7.
OYSTER CREEK POLICY AND Number PROCEDURE MANUAL 2000-ALM-4532.04 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 EXHIBIT 2000-ADM-4532.04-2 Assumed Distance to OCNGS Site Boundary In Each Sector
- Direction Sector Distance (Meters)
N 640 NNE 460 NE 410 ENE 400 E
1900 WNW 980 0
NW 617 NNW 519
~'
- Distances are measured from a point equidistant from the reactor building and the stack. The distance between the two is 16 meters.
(453204/S28)
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OYSTER CREEK POLICY AND Numbar g%
PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Revision No.
O '
Title Oyster Creek Offsite Dose calculation Manual 11 EXHIBIT 2000-ADM-4532 04-7 OCNGS Usage Factors For Individual Dose Assessment
- Effluent Ingestion Parameters Usage Factor Fraction Of Produce From Local Garden 7.6E-1 Soil Density In Plow Layer (Kg/m )
2.4E+2 Fraction Of Deposited Activity Retained on Vegetation 2.5E-1 l
Shielding Factor For Residential Structures 7.0E-1 1
Period Of Buildup Of Activity In Soil (hr) 1.31E+5 Period of Pasture Grass Exposure to Activity (hr) 7.2E+2 Period Of Crop Exposure to Activity (hr) 1.44E+3 Delay Time For Ingestion Of Stored Feed By Animals (hr) 2.16E+3 Delay Time For Ingestion Of Leafy Vegetables By Man (br) 2.4E+1 Delay Time For Ingestion Of Other Vegetables By Man (hr) 1.44E+3 Transport Time Milk-Man (hr) 4.8E&l Time Between Slaughter and consumption of Meat Animal (hr) 4.8E+2 Gr' ass ~ Yield Wet Weight (Kg/m )
7.0E-1 i
l Other Vegetation Yield Wet-Weight (Kg/m )
2.0 Weathering Rate Constant For Activity on Veg. (hr~ )
2.lE-3 Milk Cow Feed Consumption Rate (Kg/ day) 5.0E+1 l
Goat Feed Consumption Rate (Kg/ day) 6.0 l
l Beef Cattle Feed Consumption Rate (Kg/ day) 5.0E+1 l
Milk Cow Water Consumption Rate (L/ day) 6.0E+1 Goat Water Consumption Rate (L/ day) 8.0 1
Beef Cattle Water Consumption Rate (L/ day) 5.0E+1 Environmental Transit Time For Water Ingestion (hr) 1.2E+1
[ Environmental Transit Time For Fish Ingestion (hr) 2.4E+1 Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1
(
From USNRC Reg. Guide 1.109, Tables E-5, E-3 and E-15.
(453204/S33)
E24-1
)
r OYSTER CREEK POLICY AND Numbar gpg PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR p-Title Revision No.
I l (_)
Oyster Creek Offsite Dose Calculation Manual 11 l
l EXHIBIT 2000-ADM-4532.04-7 (Continued)
OCNGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor l
Environmental Transit Time For Shore Exposure (hr) 0 Water Ingestion (L/yr) a.
Adult 7.3E+2 b.
Teen 5.lE+2 c.
Child 5.1E+2 d.
Infant 3.3E+2 Shore Exposure (hr/yr) a.
Adult 1.2E+1 b.
Teen 6.7E+1 c.
Child 1.4E+1 d.
Infant 0
Salt Water Sport Fish Ingestion (Kg/yr) a.
Adult 2.lE+1 b.
Teen 1.6E+1 c.
Child 6.9 O
d.
Infant 0
Salt Water Commercial Fish Ingestion (Kg/yr) a.
Adult 2.1E+1 b.
Teen 1.6E+1 c.
Child 6.9
.~
d.
Infant 0
Salt Water Invertebrate Ingestion (Kg/yr) a.
Adult 5.0 b.
Teen 3.8 c.
Child 1.7 d.
Infant 0
Irrigated Leafy Vegetable Ingestion (Kg/yr) a.
Adult 6.4E+1 b.
Teen 4.2E+1 c.
Child 2.6E+1 d.
Infant 0
Irrigated Other Vegetable Ingestion (Kg/yr) a.
Adult 5.2E+2 b.
Teen 6.3E+2 c.
Child 5.2E+2 d.
Infant 9
Irrigated Root Vegetable Ingestion (Kg/yr) a.
Adult 5.2E+2
\\~
b.
Teen 6.3E+2 c.
Child 5.2E+2 d.
Infant 0
(453204/S33)
E24-2
i OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Revision No.
O Title Oyster Creek Offsite Dose Calculation Manual 11 EXHIBIT 2000-ADM-4532.04-7 (Continued)
OCNGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Irrigated Cow and Goat Milk Ingestion (L/yr) a.
Adult 3.1E+2 b.
Teen 4.0E+2 c.
Child 3.3E+2 d.
Infant 3.3E+2 Irrigated Beef Ingestion (Kg/yr) a.
Adult 1.1E+2 b.
Teen 6.5E+1 c.
Child 4.1E+1 d.
Infant 0
0 1
i
~
(453204/533)
E24-3 J
l OYSTER CREEK POLICY AND Numbar GPU PROCEDURE MANUAL 2000-ADM-4532.04
)
NUCLEAR r~x Title Revision No.
i
)
Oyster Creek Offsite Dose Calculation Manual 11 i
EXHIBIT 2000-ADM-4532.04-8
)
RADIONUCLIDES IN LIQUID EFFLUENT USED TO ASSESS COMPLIANCE WITH TECHNICAL SPECIFICATIONS, H-3 Ru-103 Kr-85m Ru-106 Xe-131m Ag-110m Xe-133m Sb-124 Xe-133 Sb-125 Xe-135
.Te-132 Cr-51 I-131 Mn-54 I-133 r 's Fe-59 I-135
)
(,
Co-58 Cs-134 Co-60 Cc-136 l
En-65 Cs-137 i
Sr-89 Ba-140 Sr-90 La-140 Nb-95 Ce-141 Zr-95 Ce-143 Mo-99 Ce-144 Np-239 l
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(453204/S34)
E25-1
OYSTER CREEK POLICY AND Numbar PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR
-Title Revision No.
O i
Oyster Creek Offsite Dose Calculation Manual 11 q
EXHIBIT 2000-ADM-4532.04-9 RADIONUCLIDES IN GASEOUS EFFLUENT USED TO ASSESS COMPLIANCE WITH TECHNICAL SPECIFICATIONS 1
Kr-85m co-58 Kr-85 Co-60 i-I Kr-87 Zn-65 Kr-88 Sr-89 Kr-89 Sr-90 Xe-131m Zr-95 Xe-133m Ru-103 Xe-133 Ru-106 Xe-135m Ag-110m i
Xe-135 Sb-124 1
Xe-137 Sb-125
~
'Xe-138-Cs-134 H-3 Cs-136 I-131 Cs-137 I-133 Ba-140 Mn-54 Ce-141 Fe-59 Ce-144 (453204/S35)
E26-1 I
i f
OYSTER CREEK POLICY AND Numbar (gpg PROCEDURE MANUAL 2000-ADM-4532.04 NUCLEAR Title Revision No.
Oyster Creek Offsite Dose Calculation Manual 11 Exhibit 2000-ADM-4532.04-10 EXPOSURE PATHWAYS FOR RADIONUCLIDES POTENTIALLYRELEASED FROM THE OCNGS Caseons EfDuents Oyster Creek Nuclear Genenting Staden Tualsa Bul341=s l
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E27-1