Text

2004 Annual Radioactive Effluent Release Report
	ML050870596
Person / Time
Site:	Oyster Creek
Issue date:	12/31/2004
From:	; AmerGen Energy Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
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2004 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT OYSTER CREEK GENERATING STATION AMERGEN ENERGY COMPANY

TABLE OF CONTENTS TABLE OF CONTENTS i LIST OF TABLES EXECUTIVE

SUMMARY

YEAR 2004 EVENT REPORT 4 SUPPLEMENTAL INFORMATION 5 i

LIST OF TABLES TABLE 1 Annual Offsite Doses due to Radionuclides 3 1A Gaseous Effluents - Summation of all Releases 7 IB Gaseous Effluents - Elevated Releases 8 1C Gaseous Effluents - Ground Level Releases 9 2A Liquid Effluents - Summation of all Releases 10 2B Liquid Effluents 11 3A Solid Waste and Irradiated Fuel Shipments - Summary 12 3B Solid Waste and Irradiated Fuel Shipments 13 4A Hours at each Wind Speed and Direction 23 4B Classification of Atmospheric Stability 39 11

EXECUTIVE

SUMMARY

AMERGEN ENERGY COMPANY OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2004 THROUGH DECEMBER 31, 2004 This report summarizes the radioactive liquid and gaseous effluents from the Oyster Creek Generating Station and the calculated maximum hypothetical radiation exposure to the public resulting from those effluents. This report covers the period of operation from January 1, 2004 through December 31, 2004.

Radioactive gaseous releases from the plant are monitored by radiation monitors and filtering systems installed in the plant stack and vents. If liquid releases had occurred from the Facility, representative samples would have been collected and analyzed prior to discharge. There were no radiological liquid releases during 2004. These methods accurately determine the types and quantities of radioactive materials being released to the environment.

Utilizing gaseous effluent data, the maximum hypothetical dose to any individual in the vicinity of the plant -was calculated using a mathematical model, which is based on the methods defined by the U.S. Nuclear Regulatory Commission. There was no dose attributable to liquid effluents because there were no liquid radioactive releases from the facility in 2004.

The maximum hypothetical doses (Table 1) are conservative overestimates of the actual off-site doses, which are likely to occur. For example, wet deposition due to precipitation events decreases the off-site dose, but this phenomenon is not incorporated into the mathematical dose model.

Radioactive airborne discharges from the facility during 2004 consisted of 152 curies of noble gases, 2.58E-2 (0.0258) curies of radioiodines, 1.24E-2 (0.0124) curies of particulate activity, and 62.7 curies of tritium.

Twenty-four (27) solid, low level radioactive waste shipments, totaling approximately 805 cubic meters, were shipped in Type A Containers and Strong Tight Packages from the Oyster Creek Generating Station during the reporting period. This material went to either a licensed burial site or to a waste processor for volume reduction. No solidification agent was used in any of the 27 shipments.

The maximum hypothetical calculated organ dose (Thyroid) from iodines and particulates to any individual due to gaseous effluents (0.0340 mRem/year) was approximately 2.27E-1 percent of the annual limit (Table 1). The maximum hypothetical calculated whole body dose to any individual due to gaseous effluents (1.98E-3 mRem/year) was 3.96E-4 percent of the annual limit.

I

The total maximum hypothetical organ dose (Thyroid) due to all radiological effluents of 3.55E-02 mRem/year received by any individual from gaseous effluents from the Oyster Creek Generating Station for the reporting period is over 8400 times lower than the dose the average individual in the Oyster Creek area received from natural background radiation, including that from radon (300 mRem) during the same time period. The natural background radiation dose averages approximately 300 mRem whole body per year in the Central New Jersey area, with contributions of approximately 100 mRem/year from natural background radiation and approximately 200 mRem/year from naturally occurring Radon gas.

Joint Frequency Tables of meteorological data, per Pasquill Category, as well as for all stability classes, are included. All data were collected from the on-site Meteorological Facility. Collection efficiencies for the 380-foot data and the 33-foot data were 90.4 percent and 84.9 percent, respectively. The UFSAR commits to Regulatory Guide (RG) 1.23 for Met Tower reliability. RG 1.23 requires 90% reliability over the year. Nine (9) CAPs were submitted to address Met Tower reliability issues during 2004.

Per ODCM Section 6.2.2.4, the Station eliminated two (2) land-based REMP sampling stations that were inaccessible due to lack of an overland highway. To compensate for this, the Station added five (5) sampling stations. These additional sampling stations are listed in Table E-1 and Figures E-1 and E-2 of the revised ODCM (Rev 1) which is included as part of the submittal package.

2

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OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENt RELEASE REPORT - 2004 TABLE I ANNUAL OFFSITE DOSES DUE TO RADIONUCLIDES IN EFFLUENTS January 1, 2004 through December31, 2004

. i. X-t It r3 , ,--m

--f jj-'%' ,vi ' ;r.sii,V. ,.-ItI9 .: ". ! ...6 . . .I . . I .

ODCM ODCM ODCM ODCM ODCM ODCNI ODCM ODCM 3.11.12 3.11.1.2 3.112.1 3.11.2.1 3.11.2.1 3.1122 3.11.2.2 3.11.2.3 T

Liquid Liquid Noble Gas Noble Gas H-3, lodines, & Noble Gas i

Noble Gas 1-131, 1-133, &

Total Body GI Tract Total Body Skin Particulates Gamma Dose Beta Dose Particulates Thyroid Thyroid I. ODCA1

.3.0 mrem/year 4.

mrem 10.0 rnrem/year I SW immlyear 1

Irem 4.

mrem 3000Mnrm/year 4.

mrem 1500 mnrem/yar mRad 10 mRad/year mRad 20 mRad/year mrem 15 rnrem/year N/A N/A 1 .98E-03 2.56E-03 I 3.40E-02 5.04E-03 1.69E-03 3.29E-02 -

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2004 THROUGH DECEMBER 31, 2004 YEAR 2004 EVENT REPORT LIQUID EFFLUENT RELEASES There were no liquid radioactive releases from the facility in 2004.

CHANGES TO THE OFFS1TE DOSE CALCULATION MANUAL The ODCM was revised in September 2004. The changes were: elimination of reporting requirement for type of shipping container, elimination of solidification agent, adding TLD locations, adding wording that allows for a variance from hanging TLDs in inaccessible areas, and revisions to two figures showing REMP sample locations.

EFFLUENT MONITORS OUT OF SERVICE GREATER THAN 30 DAYS No effluent monitors were out of service for greater than 30 days.

CHANGES TO THE PROCESS CONTROL PLAN There were no changes to the Process Control Plan (PCP) during 2004.

RELEASES FROM THE INDEPENDENT SPENT FUEL STORAGE FACILITY The Independent Spent Fuel Storage Facility (ISFSI) is a closed system and the only exposure would be due to direct radiation. Because it is a sealed unit, no radioactive materials were released. This includes iodines, particulates and noble gases. Therefore there is no dose from effluents from the facility.

4

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 SUPPLEMENTAL INFORMATION a Facility: Oyster Creek Generatina Station

i. Regulatory Limits

a. Fission and activation gases:

Technical Specification 3.6.E1:

Licensee: ArnerGen Enerzy Comnany. L1C.

V The gross radioactivity in noble gases discharged from the main condenser air ejector shall not exceed 021/E Cilsec after the holdup line where E is the average garnma energy (Mev per atomic transformation).

ODCM 3.112.1 The dose equivalent rate in the UNRESTRICTED AREA due to radioactive noble gas in gaseous effluent shall not exceed 500 mremlyear to the total body or 3000 nrem/year to the skin.

Note: The total body dose limit of 500 mnrem/year has been superseded by 10 CFR 20.1301.a.1 which states:

The total effective dose equivalent to individual members of the public from the licensed operation does not exceed 0.1 rem (I rillisievert) in a year, exclusive of the dose contributions from background radiation, from any medical administration itheindividual has received, from exposure to individuals administered radioactive material and released in accordance with Sec. 35.75, from voluntary participation in medical research programs, and from the licensee's disposal of radioactive material into sanitary sewerage in accordance with Section 20.2003.

ODCM 3.11.22 The air dose in the UNRESTRICTED AREA 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/calendar year due to gamnma radiation, or 20 mRad/calendar year due to beta radiation.

ODCM 3.11.4 The annual dose commitment to a MEMBER OF THE PUBUIC due to radioactive material in effluent and direct radiation from the OCNGS in the Unrestricted Area shall not exceed 75 mrem to his/her thyroid or 25 mrem to his/her total body k

,vi or to any other organ.

b. lodines ODCM 3.11.2.1.

The dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3), 1-131.1-133, 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 over no more than 31 days. [ .

M ~ODCM 3.1 1.23. A The dose to a MEMBER OF THE PUBLIC from 1-131,1-133, and from radionuclides in particulate form having half-lives of 8 days or more in gaseous effluent, in the UNRESTRICTED AREA shall not exceed 7.5 mrem to any body organ per calendar quarter or 15 mrem to any body organ per calendar year.

c. Particulates, half-lives > 8 Days:

ODCM 3.11.2.1.

e', The dose equivalent rate in the UNRESTRICTED AREA due to tritium (H-3), 1-131,1-133, 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 over no more than 31 days.

ODCM 3.11.2.3.

The dose to a MEMBER OF THE PUBLIC from 1-131.1-133, and from radionuclides in particulate form having half-lives of 8 days or more in gaseous effluent, in the UNRESTRICTED AREA shall not exceed 7.5 mrem to any body organ per calendar quarter or 15 mrem to any body organ per calendar year.

d. Liquid effluents:

ODCM 3.11.1.1.

The concentration of radioactive material, other than noble gases, in liquid effluents in the discharge canal at the U.S. Route 9 bridge 1- tshall not exceed 10 times the liquid Effluent Concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B,Table 11, Column 2.

ODCM 3.11.1.1.

The concentration of noble gases dissolved or entrained in liquid effluent in the discharge canal at the U.S. Route 9 bridge shall ,

not exceed 2.Oe4 u Ci/mL If ODCM 3.11.1.2.

The dose to a MEMBER OF THE PUBLIC due to radioactive material in liquid effluent in the UNRESTRICTED AREA shall not exceed:

1.5 mrem to the Total Body during any calendar quarter, 5.0 mrem to any body organ during any calendar quarter, 3.0 mrem to the Total Body during any calendar year, or 10.0 mrem to any body organ during any calendar year.

ODCM 3.11.A The annual dose to aMEMBER OFTHEPUBLIC due to radioactive material in effluents from the OCNGS in the Unrestricted Area shall not exceed 75 mrem to his/her thyroid or 25 mrem to his/her total body or to any other organ.

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4 ( *1 ..

OYSTER CREEK GENERATING STATION' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 SUPPLEMENTAL INFORMATION

2. Maximum Permissible Concentrations .

MPCs used in determining allowable release rates or concentrations:

a. Fission and activation gases:

Per OCGS ODCM limits, no MPCs are used to calculate allowable fission and activation gas release rates or concentrations.

b. Iodines:

Per OCGS ODCM limits, no MPCs are used to calculate allowable iodine gaseous release rates or concentrations.

c. Particulates, half-lives > 8 Days:

Per OCGS ODCM limits, no MPCs are used to calculate allowable particulate gaseous release rates or concentrations.

d. Liquidefuents:I The MPC for Tritium (H-3) is I E-3 u Ci/ml.

3. Average Energy The average energy (E) of the radionuclide mixture in releases of fission and activation gases:

First Quarter 4.79E1-0 Mev (ganuma - elevated release)

Second Quarter. 4SSE-01 Mev (gamma - elevated rekase)

Third Quarter. 3.63E-01 Mev (gamma - elevated release)

Fourth Quarter. 6.48E1-0 Mev (gamma - elevated release)

Annual: 4.97E{-I Mev (gamnma - elevated release)

4. Measurements and Approximations of Total Radioactivity 41 2 The methods used to mneasure or approximate the total radioactivity in ellbuents and the methods used to determine radionuclide composition:

a. Fission and activation gases:

1. Stack - A continuous recording of gross radioactivity and the incorporation f isotopic data obtained from a monthy grab sample analyzed using gamma spectroscopy.

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

3. Turbine Building Stack and Feedpump Room Vent - The continuous recording of gross activity and the incorporation of isotopic data obtained from a monthly grab sample analyzed using gamma spectroscopy

b. lodines:

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

2. Augmented Offgas (AOG) Vent - Filters are changed weekly and analyzed using gam spectroscopy.

c'J;aj3. Turbine Building Stack and Feedpump Room Vent - Filters are changed weekly and analyzed using gamma spectroscopy.

,-! C. Particulates:0 I. Stack - Falters are changed weekly and analyzed using a low background beta counter and gamma spectroscopy.

t" 2. Augmented Offgas (AOG) Vent - Filters are changed weekly and analyzed using ganua spectroscopy..

3. Turbine Building Stack and Feedpump Room Vent - Filters are changed weekly and analyzed using gamma spectroscopy.

cd. Liquid effluents:

Analysis per batch release using gamma spectrometry with a germanium detector. a low background beta counter. and a liquid scintillation I counter.

S. Batch Releases

a. Liquid

1. Numberofbatchrelcases: Noreleases 1 2. Total time period for batch releases: N/A

3. Maximum time period for abatch release: NIA

4. Average time period for batch releases: N/A

5. Minimum time period for a batch release: N/A

' ~~6. Averagesftram flow during periods ofreleaseof effuent into aflowingstream: NIA

b. Gaseous

1. Number of batch releases: No releases

2. Total time period for batch release: NIA

3. Maximum time period for a batch release: N/A

4. Average time period for batch releases: N/A

4. Minimum time period for abatchrelease: N/A

6. Abnormal releases

a. Liquid

1. Numberofreleases: None

2. Totalactivityreleased: N/A

's b. Gaseous

1. Numberof releases: None

2. Total activity released: N/A 2l

I. s- . I.-,>,,, -~ . ,1 icier OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I.'J."

, 0: P4, 1 1,11,, Adm..;,;,-. 1 1 I,-.T r TI,,I",

"',I,t , I

. . . . . . . s Unit I Quarter I Quarter I Quarter I Quarter I Yearly I Est. Total l

.. . 1. I

1. Total release Ci I.i6E.oi I5.72E40oi I3.05E.01 I4.55E.01 I IME.02 l 1,'l 2. Average release rate for I u Ciisec I2.36E.00 I7.28E.00 I3.84E.00 I5.72E400 I4.80E400

3. Percent of Technical Specification 1_%il J-1;, ~.i: A I I

a. 0.21/Energy (average) - gamma (elevated release only) 5.39E-04I 1.58E-03 6.62E-04I 1.76E-03 1.13E-03

b. Dose rate due to gaseous effluent -

Total Body - 500 mremlyear 3.96E-04 Skin - 3000 tfrem/year 8.53E-05

c. Air dose due to noble gas in gaseous effluent -

5 mRad/calendar quarter due to gamma radiation 2.78E-02I 4.90E.02 I 82E-MQ I 3eE-o 10 mRad/calendar quarter due to beta radiation 7M3E-03 I I.1E-02I 5.38E-03 I 6.30E-03 10 mRad/calendar year due to gamma radiation 20 mRad/calendar year due to beta radiation .

.W ee 8.45E-03

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., ,-.,-?t:_(S,5I I II-I i-- Z_,-r, -- , - ZO -

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1. Total iodine-131 Ci

-+

I 4.33E.04 *I. I2.34E-03I 2-53E-03 I ia7E-03 I7.18E-03 1-

2. Average release rate for I uCi/sec I 5.51E-05 I2.98E-04 I3.19E-04 I2.3E-04 I2.27E.04 I1_ 3. Percent of Technical Specification or! I jj, o,I, i ? .I a. Dose rate due to gaseous effluent -

V. Any body organ - 1500 znremnyear(H-3.1-131.1-133.a&reTmI>aoD) W1,r

, qI r, , -1 ij . b. Dose due to radioiodine and particulates in gaseous effluent - I I .

Any body organ per calendar quarter - 75 mrem

.I vw 4.99E.02 I2.27E-01 I .63E-olI 9xmEm Any body organ per calendar year -15 mrem

1. Particulates with half-lives> 8i SC..I 2.15E-W I 1.55E.0OI3f89E03 4.96E-03 I12E0

2. Average release rate for period u Ci/sec I 2.74E-04 I I.9E-04I 4.90E-04I 6.27E-04I 3.98E.04

.,., -- %i

3. Percent of Technical Specification , , ,! ,, t

- "P ,

a. Dose rate due to gaseous effluent - '., :'fl t;!

Any body organ - 1500 mrem/year (H-3.1-131. 1-33.& hrTm2>s D) !Pr ,

b. Dose due to radioiodine and particulates in gaseous effluent - ,," . I-V

. - 'r

.11 Any body organ per calendar quarter - 75 mrem 4.99E-MI 227E01 I IE-01I9.A-Any body organ per calendar year - 15 mrem

4. Gross alpha radioactivity Ci I9.20E-M I I.2E-065 1. OE-06 I <LLD I 3.42E-06

.. is 4 ...-. S t..:I .j.....;-

-, 1 - 3, - - i- - . ,- ... 1..W..11 . __" 4_4 , - . ; _1, .11..-. ) 11Iz D. Tritium -i .

I -r:Or, _t -

. I- - -11; .1 -. ..-, I - ., ;, -, -I 1 ,

, -'Li:,-,

i. Total Release Ci 4.98E+o0 9.93E+00 2.44E.01 I 2.4EE01 I .7

2. Average release rate for period u Ci/sec 6.33E-01 1.26E+00 3.07E+0 lE 2OT1.98E00

3. Percent of Technical Specification , '. .-

a. Dose rate due to gaseous effluent - J is..-

A tnybody organ- 15OO nrem /year(H-3.1-t31.t.33.&P.xTI/2>aD) % _______*-e _i_______m___id_ _l_ _3_l

-,.Mai -!U d-ixA-i

~ t5 ,

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OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE B13 GASEOUS EFFLUENTS - ELEVATED RELEASES Ci LLDI <LD <LLD <LD <LLD .

CS 1t9E+00 4.93E+00 1.88E+OO zt.3E+oo 1.09E+01 Ci 821E+0O Z14E+01 665E+00 1.11E+01 4.74E+01 Ci <LD <LLD <LLD 6.57E+00 6.57E+00 CG < LLD <LD <LLD < LD <CLD W

l 838E+00 2.73E+01 2.17E+O1 1.96E+01 7.70E+01 G <LLD s61E+00 Z68E-01 6.09E+00 9.97E+00 G LLD <LWD <LLD <LD <LLD E-04 W82E-04 2S3E-03 l-7E-03 5.92E-03 4.70E06 4.74E-06 1.83E-05 1.74E05 4.51 E-05

<L D <L D <L D <L D < LLD 9.11E-05 LD < LD 2.19E-05 1.13E-04 6.88E-04 9.47E-04 1.19E603 2.80E03 5.63E403 9.20607 1.07E.06 <LW <LD 1.99E-06 1.87E-04 <LMD <LD <LLD 1.87E.04

< LLD < LLD <L LD <LLD 4.83E.06 1.61E-05 3.9OE-05 t.38E-04 t.98E-04 1t.0SE04 < UD 7.31E-05 6.88E-06 l.85E-04 4.00E-05 <LD 4.09E-05 2.79E-05 1.09E-04 LLD I LLD <LLD <LD <LLD 4 a89E-03 4 4.986-03 I 1.

1.956-03 1.95E-03 F

1.55E.03 I t56E-03 I3.89E 03 4.98E-C3 It:

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE IC 6.52E-o 1.62E 2E7 6 02 1t20E-06 4.25E06 c UD LLID 619E-M6 959E-07 7,15E-06

<LUD LLUD { LLD f LLD LLD 652E-8 1.62E-47 9.0t E-06 Z16E-06 t.t4E-05 FA44111h1Y S

it'.E'1i .am *- Z 420E.07 tE.OOE4W 30&E7 &04E-07 2.28E-06

< LLD < UD 4L<D cLMD O.OOE+00 t2tE-04 <LLD LLD LLD 121E-04 4.54E-06 < LLDW LLD LLD 4.54E-06 LLD < LLD cLLD < LLD < LLD 2.45E-S LLD LLD < LLD 2.45E-05

< LLD 128E-07 10E-46 c UD 1.43E.06 dLD < UD c UD < LLD < LLD 4.69E-05 I cD ULD < LLD I4.69E-0

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

.. Unit Quarter Quarter Qualrter Quairter Yearly Est. Total I 2 3 4 Total Enfor, %

A. Fission & activation products -'i *7 r ,

1. Total release (not including tritium, gases. alpha) NOS NO F* A WA

2. Average diluted concentration during period u Cinl.

3. Percent of Technical Specification S @

The concentration of radioacicve rnaterial, other thain noble gases @jq4E!

shall not exceed 10 times the liquid effluent concentrations specified inIOCR, Part 20.1001-20.2401, AppendixB1, Table II. Column 2

b. Lri rt on Dose IDue to Liquid Efft B alue 1Coun 2%t 7j.:

Total Body - 15 nruen-icalendar quarter *

% ~

.Any Body Organ - 5.0 rnrmcalendar quarter %I*II Total Body - 3.0 mrnm/calendar year %

Any Body Organ - 10.0 injemcalendar year %

B. Tritium i1.Total release . Cis _ l__._

_ No

_._l . N.P NtA

2. Average diluted concentration during period . Ci/mL

3. percent of Technical Specification

a. Shall not exceed 10 times the liquid effluent concentrations specified in IOCFR Part 20.1001-20.2401, Appendix B.

Table 11, Column 2

b. irnit on Dose Due to Liquid Effluent Total Body -15 mrernkalendar quarter % ll___ _

Any Body Organ -5.0 mrem/calendar quarter %

Total Body - 3.0mrem/calendaryear Any Body Organ - 10.0 nrenrlalendar year C. Dissolved and entrained gases

1. Total release l Ci l - N l No l N l N/A WA

2. Average diluted concentration during period uirLl

3. Percent of Technical Specification

a. Shall not exceed 2.0 E-4 u Ci/ml,

b. Limit on Dose Due to Liquid Effluent l .

Total Body - 1.5 rarem/calendar quarter % - I -

Any Body Organ - 5.0 mnre/calendar quarter l % l l -

Total Body - 3.0 mnrenm/calendar year % 5t Any Body Organ - 10.0 nremkcalendar year %

D). Gross alpha radioactivity 1.Total release Ct M. 6m NM. N H.mos o WP.

NP NoAas _ l A E. Volume of waste released (prior to dilution) liters lO.OOE+OO O.00E+00 OOOE+OO O.OOE+OO O.OOE+OO WA P~-.Volume of.... waNter usned-diltai-o,:sn:*r>.-lt 1 4.7E1 4.3 1E-+-1i; 4.OE1 1.82E+12

.30E+11................................

P. Volume of dilution water used i 4.31E+11 I 4.76E+11 I 4.80E+11 I 4.30E+11 I 1.82E+12

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 2B LIQUID EFFLUENTS No Flea... RD....

F Po F_

oRD. Askos. No Fl_

No Po..w.. No _d.... No . No F ... No Rd....

No R..o o Fd.... o Rd..... No Rd..... j NORd..

No Rd... N. RF_..I. P.A. I F_ N. F..I NoFd.. No td...

NoR... No RF_. J NoR...

NoFR l..NoF .I. l No FNoR...J ld.

No RF_.. No l No l NoI Rd.... I No R.W..s No Rd.. No RdF_. No Rd.. No _d.. No F No Rd No Rim.. NR, No R. No F No Rd..", No Rd... wNo~ .No Rd._. No F No R No RdF. Nm o Rs' No oF H. Rd..w.. no Rd.... No Rd.ma.. No Rd... Nol No Rd... No Rd..... No Rd.... No Rd..on.. No W. Ad..... No Rd..... No Rd..... No R.We. No F Cs No Rd.... NORd..... No Rd..... NORd..... No I NoRP.""" No Rd..... No Fd..... No Rd.... No F No Rd._ No Rd.. No RF_.... IoW _.... No F No FRd_... No Rd..... No Rd.....

I 1- No Rd..... 1- No F NoRd.....

HOP I No_ NoF

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004

. - TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS - SUMMAR Note: No solidification agent was used during the reporting period

2. Estimate of major nucear cow.position (by type otwaste) Pere

a. Iron-55 8.56 cobalt60 7.68 mnanganese-54 4.29

b. Iron-55 824

_^a- -na coualt nianganese-54_

ne h ;l34 C. , on]-

None Shipped_

izone anuppe dI iron-55 cobalt_60__

cesium-137 manganesce-54 4 Note - See attched tables i

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Motor Vehicle ALARON CORP 15 Motor Vehicle Barnwell Wastc Management Facility 9 Motor Vehicle Duratek Radwaste Processing, Inc.

I I I I Mode of Transportation Destination

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2004 TABLE3B SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Waste Stream - Summary Of All Wastes Pa"@-. r-rm^- 9 eM4 Waste Clas Volumne Shipp Actity Shipped Percent Error HilI f (Curies) (Percent)

A 2.94E+04 8.051E0 2.58E+02 4-25 B 0.0 0.0 0.00E1100 C 0.0 0.0 0.OOE+00

_ A1 r All 214E3+04 I.SE+02 258E+02

aX.

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (cont.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

ffi9~

-; IBe*~ ~f i. .w1I-~ t1ia '1'- >' ' et t'

OYSTER CREEK GENERATING STATION 1 .

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (cont.)

SOUD WASTE AND IRRADIATED FUEL SHIPMENTS I ;

I.:

Waste Stream -Spent Resins, Flters, and Falter Sludge Perked ,f Prlrnre lsl~ I 2(lA 4l...n... i~

Waste Class Volume Shipped Activity Shipped Percent Error (FTh(mh (Curies) .(Percent)

- , A 2690.0 : 762 257.0 +1-25 0.0 i 0.0 1 0.0 0.0 I 0.0 l 0.0 64~1 All 2690.0 1 7621. 461-ps-

.v- ~ ~i , w. : . ,1 -

r~-

ix MVP'i' , *i-` - - l OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (cont.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS nate or Major I I I~lterbludge

,A nt p-r -,nn d1 Nuclide Activity Percent Nuclide Activity Percent r Nuclide Activity Percent Abundanc Abundance . I Abundance (Afdccs) (Prrent) (cuies) (Percent) 'i ~Fr- (Curies) (Percent)

Vc-55 7Z2tut+UZ 5.-Ot0-9UI N N Co-60 1.98E401 7.68E+0D 0 Mn-54 1.IOE3+01 4.29E4+00 N N Cs-137 2.89E-+00 1.13E4OO0 E E Pu-241 1.02E+00 3.96E3-01 Zn-65 7.75E-01 3.011E-01 S S Ni-63 4.81E3-01 1.87E-OI1 H H Cs-13-4 3.95E-01 1-54EO-0 I I Fe-59 2-84E3-01 I.IOE3-OI p P 11-3 1.041E-01 4.00OE-02 p p CD-58 8.14E-02 3.20E-02 E E Cr-144 8.OOE-02 3.1011-02 D D I

Cm-244 6.0413-02 2.3013-02 Other 1.7213-01 7.1OE-02 -

Toal MIA N/A Nuclide Activity Percent Abundance r1C-j ,aLuLn+V4 Co-aW 1~~-V 9Sko1 7. t Mn-54 1.1013+01 4.29E3+00 Cs-137 2.8913+00 1.13E+00 Pu-241 1.02E3+00 3.96E401 Zn-65 '7.75E401 3.01E3-01 M-63 4.81E4-1 1.87E3-01 Cs-134 3.95E4-1 1.54E41 Fe-S9 2-8413-1 1.1E0E1 H-3 1.04E4-1 4.00E402 Co-58 8.14E4-2 3 sE2032 Ce-144 8.00E4-2 3.10E402 Cm-244 6.04E4-2 2.30E402 Ohler 1.72E4-1 7.10E4 Total 2.57E+02 1.0E0

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (CONT.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (cont.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS v

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (CONT.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

~~~~~~, at C4B 2 .'i.

o .-.

. }0<Ad* *n'J

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (cont.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

' ?0 tion - Irradiated Fuel 2004 through December 31, 2004 si~kiti,'.}".;.:M,>...w.,-,;..,.4ti~s,!u i W i j,:;i ; ;!o:'i h ~, 6-p

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 3B (CONT.)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I f)

Waste Stream - Other Waste i; I _

Waste Class Volume Shipped Activity Shipped Percent Error fft;b M3b (Curies) (Percent)

A 2.85E+03 i 8.07E1+01 433E-03 41-25 B 0.0 f 0.0 0.OOE+00 C 0.0 3 0.0 0.OOE+00 All i RF4fl;I fit-.a-fl 433E-03 41-25

>.a^Mt 4I's~a' e > MD,~~k~io9~r~QHAb..gSr.iaWRfSo.£-eXt W5 OYSTER CREK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004,

. ' ~TABLE 3B (cont.)*,

SOLID WASTE AND IRRDIATED FUEL SHIPMENTS *.

Estimate of Major Nudide Composition - Other NY ste **'

Period of Perforinance: January 1, 2004 through December 31, 2004*,

Waste Class: A lWkZ-f Waste C~: B llitWasteClass: C 1 Nudlide Activity l ccn ] Nudlide Activity Percent btfi#.Ncie Activity Pcrcent .

A bundancc ,7 ,- . Abunda ncc-e Ab undance4 (Curies) (Paet Curies) (Percent) (Curies) (Percent)t Fe-55 1.89E403 437E+01 qrb1gN - N '

Co-60 1.32E-03 3.C4E+01 O 0 0 Cs-137 8.28E-C4 l.91E3+01 tW9N N Mn-54 Cs-134 1.85E-04 2.71E-05 4.27E+00 6.27E-01 .,3 E fiE.

Ni-63 2.20E405 S.09E13, I S <fw Si Zn-65 1.54E4-5 3-56E-01 ii I;t-1I C0-58 5.54E-06 1.28E-01 tp P P1 Ag-110rn S.27E406 1-221341 ffP B P Cc-144 2.76E406 6.40E-02 .E . E Sr-90 2.70E406 6.20E402 0B:D T .D H-3 2.21E406 S.10E4-2 + .>4,s,.

C-14 1.85E406l 430E402 . .. $ i Other 4.22E46 9.75E4-2 ^ i tql.F Total 4.33E-03 1.00E+2114MtTta / N tAIAa TOW NfANI i

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE4A HOURS AT EACH WIND SPEED AND DIRECTIONa January 1,2004 through December 31, 2004 All PasquiU Categories 33 foot N 62 NNE 73 NE 51 ENE 41 E 29 ESE 22 SE 22 SSE 40 S 87 SSW 82 SW 119 WSW 270 W 361 WNW 207 NW ' 256 NNW 141 VARIABLE 0 TOTAL 1863 Periods of Calm (hours):

Hours of missing data CTotal):

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION

Januazy 1,2004 through Deccmber 31, 2004 Pasquill Category A 33 foot I

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: January 1,2004 through December 31. 2004 STABILITY CLASS: Pasquill Category B ELEVATION: 33 foot Wind Wind Speed (mph) at 33 foot level Direction 1-3 4-7 8-12 13-18 19-24 N 3 4 2 0 0 NNE 0 7 3 0 0

.NE 0 7 5 2 0 ENE 1 9 7 0 0 E 1 9 80 0 ESE 1 9 3 0 0 SE 1 14 5 0 0 SSE 0 8 6 0 0 S 1 4 22 2 0 SSW 0 8 16 7 0 SW 1 6 8 1 0 WSW 1 14 9 0 0 W 0 9 18 3 0 WNW 1 10 13 8 0 NW 1 11 8 2 1 NNW 0 11 6 0 0 VARIABLE 0 0 0 0 0 TOTAL 12 140 139 25 1 Periods of Calm (hours): 0 Hous Hours of missing data (Total): 1325 Hours

.Sostt'ck Vil-,?^f-Tii9.st -. +ff:,<., >.,4 - t#2X.

4,aS. .X_

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT- 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECIlONa PERIOD OF RECORD: l January 1, 2004 through December 31,2004 STABILITY CLASS: l Pasquill Category CC ELEVATION: 33 foot Wind l Wind Speed (mph) at 33 foot level Direction 1-3 4-7 8-12 13-18 19-24 N 1 3 1 0 0 NNE 1 5 0 0 0 NE 0 2 5 0 0 ENE 0 4 1 0 0 E 0 3 1 0 0 ESE 0 3 0 0 0 SE 2 4 2 0 0 SSE 0 3 1 0 0 S 0 1 5 0 0 SSW 0 5 8 3 0 SW 0 2 5 0 0 WSW 2 .9 5 0 0 W 0 5 4 0 0 WNW 1 9 5 2 0 NW 1 10 6 1 0 NNW 0 1 1 0 0 VARIABLE 0 0 0 0 0 TOTAL 8 69 50 6 0 Periods of Calm (hours): 0 Bows Hours of missing data (Total):

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: January 1, 2004 through December 31,2004 STABILITY CLASS: Pasquill Category D ELEVATION: 33 foot

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION January 1.2004 zhrough December31, 2004 Pasquill Category E 33 foot

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION January 1,2004 though December 31. 2004 Pasquill Category F 33 foot ut,!, , E-ln-v;

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004.

TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIREClION

. 00.;V Xtw M s }X S.-g0 PERIOD OF RECORD: January 1,2004 through December 31, 2004 iei STABILITY CLASS: Pasquill Category G ELEVATION: 33 foot Wind Wind Speed (mph) at 33 foot level Direction 1-3 4-7 8-12 13-18 l 1 I9-24 N 9 5 0 0 0 NNE 7 2 1 0 0 NE 4 1 0 0 0 ENE 7 2 0 0 0 E 1 2 0 0 0 ESE 1 2 0 0 0 SE 3 0 0 0 0 SSE 9 0 0 0 0 S 21 3 0* 0 0 SSW 22 1 0 0 0 SW 37 16 0 0 0 WSW 154 81 0 0 0 W 254 65 0 0 0 WNW 118 19 0 0 0 NW 133 56 0 0 0 NNW 55 23 0 0 0 VARIABLE 0 0 0 0 0 TOTAL 835278 1 0 0 Periods of Cnlm (hours): 0 Hours Hours of missing data (Total): 1325 Hours

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: Jianuay 1. 2004 uirough December 31, 2004 2 -

STABILITY CLASS: All Pasquill Categories m ELEVATION: 380 foj N 8 NNE 5 NE 7 ENE 1 E 6 ESE 8 SE 7 SSE 5 S 7 SSW 6 SW 9 WSW 9 W 7 WNW 5 NW 7 NNW 6 VARIABLE 0 TOTAL 103 Periods of Calm (hours):

Hours of missing data (Total):

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

a HOURS AT EACH WIND SPEED AND DIRECTION January 1.2004 through December31, 2004 Pasquill Category A 380 foot

, i t, :V I I 4 ,j -IT ZI ts Ij ".. ,, , ',."

63", 4r, -,

- . L! .:, . -

Wind Speed (mph) at 380 foot level 8 -12 l 13 -18 l 19 - 24 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW

, A. I W

WNW NW 1 NNW VARIABLE TOTAL Periods of Calm (hours):

Hours of missing data (Total):

I The total number of hours of each category of wind direction for the indicated period of record. stability class and elevation

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION January 1, 2004 thrugh December 31,.2004 a Pasquill Category B 380 foot

UYSTIE CUREEK UGLNERA I INGI ATICN I

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECIFONa

'ERIOD OF KECURD: January 1. 204 through LJcember 3C1, ZU04 TABILITY CLASS: Pasquill Category C IEVATION: 380 foot Wmd I Wind Speed (mph) at 380 foot level 1

l Direction I 1-3 1 - 1 8-12 1 13-18 1 19-24 1 > 24 I Total N 2 8 9 4 2 0 25 NNE 1 5 8 2 2 0 18 NE 0 3 8 10 2 3 26 ENE 0 5 7 8 7 3 30 E 1 4 12 6 1 0 24 ESE 1 4 11 2 0 0 18

SE 1 11 18 3 0 0 33 SSE 0 3 22 5 0 0 30 r 0 4 21 9 2 0 36

- SSW 0 3 9 22 8 3 45

SW 1 4 8 12 7 1 33

' WSW 1 2 15 14 5 1 38 W 0 7 10 14 9 3 43

{ WNW 1 6 9 9 9 16 50 NW 0 4 19 15 18 8 64 I NNW 0 8 12 10 0 1 31 VARIABLE 0 0 0 0 1 0 1. 0 0 TOTAL 9 81 198 145 72 39 544 I 4 + - _______ - ________ _________

Periods of Calm (hours): 0 Hours lours of missing data (Total): __839 Hours l The total number of hours of each category of wind direction for the indicated period of record, stability class and elevation

N; -Iranian, OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTIONa PERIOD OF RECORD: January 1, 2004 through December 31,204 I Pasquill Category D I 380 foot I

. - . w.

Wind Speed (mph) at 380 foot level 8-12 13-18 19-24 I > 24 l Total N 3 24 50 37 15 0 129 NNE 2 26 51 43 23 4 149 NE 5 29 70 115 75 34 328 ENE 0 19 55 59 62 27 222 E 3 17 50 53 27 3 153 ESE- 4 14 54 43 11 15 141 SE 4 23 53 35 4 5 124 SSE 2 17 51 37 9 5 121 5 2 14 66 62 10 11 165 SSW 2 12 64 149 68 25 320 SW 6 15 42 64 24 5 156 WSW 5 9 28 49 14 4 109 W 4 11 34 40 23 12 124 WNW 3 18 31 39 41 60 192 I NW . 0 23 31 52 45 51 202

., L

.5 4- 4- 4 t

4 flNNW 3 20 33 55 19 2 132 VARIABLE 0 0 0 1 0 J 0 J 0 0 I t.

.%I TOTAL 48 291 763 932 470 263 . 2767

':JI .5 L _______ L I =

Periods of Calm (hours): 0 Hours urs of missing data (Total): 839 Hors The total number of hours of each category of wind direction for the indicated period of record, stability class and clevation 35 I

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004

TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: January 1. 2004 through December 31, 2004 STABILITY CLASS: Pasquill Category E ELEVATION: 380 foot

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECllONa PERIOD OF RECORD: January 1,2004 through December31, 2004 STABIIUTY CLASS: . Pasquill Category F ELEVATION: 380 foot Wind Wind Speed (mph) at 380 foot level Direction 1-3 J 4-7 8-12 13-18 l 19-24 N0 4 17 42 13 NNE 1 3 5 29 11 NE 0 3 3 11 2 ENE 0 1 2 3 1 E 1 1 1 4 0 ESE 0 2 3 3 1 SE 1 3 0 2 0 SSE 0 7 5 4 0 S 1 6 11 9 2 SSW 2 6 14 10 9 SW 2 7 13 29 35 WSW 1 4 19 22 63 W 1 4 12 34 40 WNW 0 5 12 27 34 NW 0 3 15 39 31 NNW 0 3 17 41 37 VARIABLE 0 0 0 0 0 TOTAL 10 62 149 - 309 279 Periods of Calm (hours): 0 Hours Hours of missing data (Total): 839 Hours

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE 4A (cont.)

HOURS AT EACH WIND SPEED AND DIRECTION January 1, 2004 throughbcccmbe331. 20044l Pasquill Category G 380 foot lBu>-ge-

OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2004 TABLE4B.

CLASSIFICATION OF ATMOSPHERIC STABILITY

Stability Pasquill Sigma-eta a Termperature change * :

Classification Categories (degrees) with height (degrees-C/100m)

Extremely unstable A 25.0 <-1.9 Moderately unstable B 20.0 -1.9 to - 1.7 Slightly unstable C 15.0 -1.7 to - 1.5 Neutral D 10.0 -1.5 to-0.5 Slightly stable E 5.0 .0.5 to 1.5 Moderately stable F 2.5 1.5 to 4.0 Extremely stable G 1.7 > 4.0 a Standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to I hour. The values shown are averages for each stability classification.

Exelnm. CY-OC-1 70-301 Revision 1 Page 1 of 119 Nuclear : 1 ., '. . . .

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OFFSITE DOSE-CALCULATION MANUAL FOR.

OYSTER CREEK GENERATING STATION

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ft INTRODUCTION 6 Part I - RADIOLOGICAL EFFLUENT CONTROLS 6 Table 1.1: Surveillance Frequency Notation 11 3/4 Controls And Surveillance Requirements 12 3/4.0 APPLICABILITY 12 3/4.3 INSTRUMENTATION 14 3/ 4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 14 Table 3.3.3.10- 1: Radioactive Liquid Effluent Monitoring Instrumentation 15 Table 4.3.3.10-1: Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 17 3/4.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation 19 Table 3.3.3.11- 1: Radioactive Gaseous Effluent Monitoring Instrumentation 20 Table 4.3.3.11-1: Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 23 3/4.11.1 LIQUID EFFLUENTS 26 3/4.11.1.1 CONCENTRATION 26 Table 4.11.1.1.1-1: Radioactive Liquid Waste Sampling And Analysis Program 27 3/4.11.1.2 DOSE 30 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM 31 3/4.11.2 GASEOUS EFFLUENTS 32 3/4.11.2.1 DOSE RATE 32 Table 4.11.2.1.2-1: Radioactive Gaseous Waste Sampling And Analysis Program 33 3/4.11.2.2 DOSE - NOBLE GASES 36 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 37 3/4.11.2.4 GASEOUS RADWASTE TREATMENT 38 3/4.11.4 TOTAL DOSE 39 3/4.12 Radiological Environmental Monitoring 40 3/4.12.1 MONITORING PROGRAM 40 Table 3.12.1 - 1: Radiological Environmental Monitoring Program 42 Table 3.12.1-2: Reporting Levels For Radioactivity Concentrations In Environmental Samples -

Reporting Levels 49 Table 4.12.1-1: Detection Capabilities For Environmental Sample Analysis 50 3/4.12.2 LAND USE CENSUS 53 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 54 Bases For Sections 3.0 And 4.0 54 3/4.3 Instrumentation 54 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 54 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 55 3/4.11 RADIOACTIVE EFFLUENTS 55 3/4.11.1 LIQUID EFFLUENTS 55 3/4.11.1.1 CONCENTRATION 55 3/4.11.1.2 DOSE 55 K:\occhem\800proc 2.0

3/4.11.1.3 LIQUID RADWVASTE TREATMENT 56 3/4.11.2 GASEOUS EFFLUENTS 56 3/4.11.2.1 DOSE RATE 56 3/4.11.2.2 DOSE - NOBLE GASES 56 3/4.11.2.3 DOSE. -IODINE-131, IODINE- 133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 57 3/4.11.2.4 AUGMENTED OFFGAS TREATMENT SYSTEM 57 3/4.11.4 TOTAL DOSE 57 3/4.12 Radiological Environmental Monitoring !

58 3/4.12.1 MONITORING PROGRAM 58 3/4.12.2 LAND USE CENSUS 58 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM. 59 5.0 Design Features / Site Map 59 6.0 Administrative Controls , :I 59 6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (REOR) 59 6.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (RERR) 60 6.3 RESPONSIBILITIES 61 PART II - CALCULATIONAL METHODOLOGIES.- 62

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1.0 Liquid Effluents 62

1. RADIATION MONITORING INSTRUMENTATION AND CONTROLS 62 1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION 62 1.2.1 LIQUID EFFLUENT MONITORS 62 1.2.2 SAMPLE RESULT SETPOINTS- 63 1.2.3 ASSUMED DISTRIBUTION SETPOINTS 63 1.3 BATCH RELEASES 64 1.4 CONTINUOUS RELEASES 64 1.5 LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 64 1.5.1 MEMBER OF THE PUBLIC DOSE - LIQUID EFFLUENTS 64 Table 1.5.1-1 Liquid Pathway Dose Limits 64 1.5.2 SHORELINE DEPOSIT DOSE - 65 1.5.3 SHORELINE DOSE EXAMPLE 65 1.5.4 INGESTION DOSE - LIQUID 66 1.5.5 INGESTION DOSE CALCULATION EXAMPLE 67 1.6 REPRESENTATIVE SAMPLES I 67 2.0 Gaseous Effluents 67 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 67 2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION 68 2.2.1 PLANT VENT 68

.. i . . '. . -':

2.2.2 OTHER RELEASE POINTS . 69 Table 2.2.2-1 Receptor Locations And Dispersion For Gaseous Monitor Setpoints 70 2.2.3 RADIONUCLIDE Mix FOR SETPOINTS 70 2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS - 10 CFR 20 70 K:\occhem\800proc '3.0 k

-I If 2.3.1 SITE BOUNDARY DOSE RATE - NOBLE GASES 70 2.3. 1.1 TOTAL BODY DOSE RATE 71 2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE 71 2.3.1.3 SKIN DOSE RATE 72 Table 2.3.1.3-1 Receptor Locations And Dispersion For Site Boundary Dose Rates 72 2.3.1.4 EXAMPLE SKIN DOSE RATE 73 2.3.2 SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES 73 2.3.2.1 METHOD - SITE BOUNDARY DOSE RATE - RADIOIODINE AND PARTICULATES 73 Table 2.3.2.1-1 Location Of Maximum Exposure Rate By Inhalation 74 2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATION 74 2.4 NOBLE GAS EFFLUENT DOSE CALCULATIONS - 10 CFR 50 74 2.4.1 UNRESTRICTED AREA DOSE - NOBLE GASES 74 Table 2.4.1-1 Annual Air Dose Limits 75 2.4.1.1 AIR DOSE METHOD 75 Table 2.4.1.1-1 Receptor Locations And Dispersion For Air Dose 76 2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION 76 2.4.1.3 INDIVIDUAL PLUME DOSE METHOD 77 2.5 RADIOIODINE, PARTICULATE AND OTHER RADIONUCLIDES DOSE CALCULATIONS - 10 CFR 50 78 Table 2.5-1 Dispersion For IOCFR50 Doses 78 2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES 79 2.5.2 EXAMPLE CALCULATION - INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES 80 2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDES 80 2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION- OTHER THAN TRITIUM 80 2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHER THAN TRITIUM 81 2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION 82 2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION 83 2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 83 2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 84 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 85 2.5.3.8 EXAMPLE CALCULATION - DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 86 2.5.4 GROUND PLANE DEPOSITION IRRADIATION 86 2.5.4.1 GROUND PLANE CONCENTRATION 87 2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATION 87 2.5.4.3 GROUND PLANE DOSE 88 2.5.4.4 EXAMPLE GROUND PLANE DOSE 88 3.0 Total Dose To Members Of The Public - 40 CFR 190 88 3.1 EFFLUENT DOSE CALCULATIONS 89 3.2 DIRECT EXPOSURE DOSE DETERMINATION 89 4.0 Radiological Environmental Monitoring Program 89 K:\occhem\800proc 4.0

Appendix A - Derived Dose Factors And Receptor Locations 90 Table A-1 Dose Conversion Factors For Deriving Radioactive Noble Gas Radionuclide-To-Dose Equivalent Rate Factors , 91 Table A-2 Noble Gas Radionuclide-To-Dose Equivalent Rate Factors 92 Table A-3 Air Dose Conversion Factors For Effluent Noble Gas -93 Table A4 Locations Associated With Maximum Exposure Of A Member Of The Public 94 Table A-5 Critical Receptor Noble Gas Dose Conversion Factors 95 Appendix B - Modeling Parameters 96 Table B OCGS Usage Factors For Individual Dose Assessment 97 Table B-2 Monthly Average Absolute Humidity , 101 Appendix C - References 102 Table C-I - References 103 Appendix D-.System Drawings . ,.. 105 Figure D-1-la: Liquid Radwaste Treatment Chem Waste And Floor Drain System 106 Figure D-l-lb: Liquid Radwaste Treatrnent - High Purity And Equipment Drain System 107 Figure D-1-2: Solid Radwaste Processing -Systemr ' 108 Figure D-2-1: Gaseous Radwaste Treatment -'Augmented Offgas System' 109 Figure D-2-2: Ventilation System 110 Appendix E - Radiological Environmental Mo'nitoring Program - Sample Type And Location III Table E-1: REMP Sample Locations' 112 Figure E-1: REMP Sampling Locations Within 2 Miles 117 Figure E-2: REMP Sampling Locations Outside 2 Miles 118 Figure E-3 Area Plot Plan Of Site 119 K:\occhem\800proc 5.0

OYSTER CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL INTRODUCTION The Oyster Creek Offsite Dose Calculation Manual (ODCM) is an implementing document to the Oyster Creek Technical Specifications. The previous Limiting Conditions for Operations that were contained in the Radiological Effluent Technical Specifications (RETS) are now included in the ODCM as Radiological Effluent Controls (REC). The ODCM contains two parts: Part I - Radiological Effluent Controls, and Part II- Calculational Methodologies.

Part I includes the following:

The Radiological Effluent Controls and the Radiological Environmental Monitoring Programs required by Technical Specifications 6.8.4

Descriptions of the information that should be included in the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Operating Report required by Technical Specifications 6.9.1 .d and 6.9.1 .e, respectively.

Part II describes methodologies and parameters used for:

The calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints; and

The calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative yearly doses, and projected doses.

Part II also contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program (REMP), and the liquid and gaseous waste treatment systems.

PART I - RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these CONTROLS may be achieved.

The defined terms appear in capitalized type and are applicable throughout these CONTROLS.

1.1 OPERABLE - OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in the definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

A verification of OPERABILITY is an administrative check, by examination of appropriate plant records (logs, surveillance test records) to determine that a system, subsystem, train, component or device is not inoperable. Such verification does not preclude the demonstration (testing) of a given system, subsystem, train, component or device to determine OPERABILITY.

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1.2 ACTION ' ' .

ACTION shall be that part of a CONTROL that prescribes remedial measures required under designated conditions. : - .; . -

1.4 CHANNEL CALIBRATION, A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds, with acceptable range and accuracy, to known values of the parameter that the channel' monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including equipment actuation, alarm, or trip.

' -.~ ; ' '. ... .; ; . -

1.5 CHANNEL CHECK -

A CHANNEL CHECK shall be a qualitative determination of acceptable operability by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel with other independent 'channels measuring the same variable. '. -

1.6 CHANNEL FUNCTIONAL TEST ;-:2j '.'

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into'the channel to verify its proper response including, where applicable, alar'm and/or trip initiating actions.

1.9 CONTROL -

The Limiting Conditions for Operation (LCOs) that were contained in the Radiological Effluent Technical Specifications were transferred to the OFFSITE DOSE CALCULATION MANUAL (ODCM) and were renamed CONTROLS. This is to distinguish between those LCOs that were retained in the Technical Specifications and those LCOs or CONTROLS that were transferred to the ODCM.'

1.13 FREOUENCY NOTATION -

The FREQUENCY NOTATION specified for the' performance of Surveillance Requirements shall:

correspond to the intervals defined in Table 1.1.

1.30 REPORTABLE EVENT - ..

A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.

1.33 SOURCE CHECK SOURCE CHECK'shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

,. 4 . , :: : - i.y! ' . - '

1.34 AUGUMENTED OFFGAS SYSTEM (AOG) ; '

The AUGUMENTED OFFGAS SYSTEM is designed and installed to holdup and/or process

radioactive gases from the main condenser offgas system for the purpose of reducing the radioactive material content of the gases before release to the environs.

, ' I.' ' ,; -, g*-,.

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_ ! ~al 1.35 MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with AmerGen Energy Company, LLC and who do not normally frequent the Oyster Creek Generating Station site. This category does not include employees of the utility, its contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on site or for other purposes associated with plant functions. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. An individual is not a member of the public during any period in which the individual receives an occupational dose.

1.36 OFFSITE DOSE CALCULATION MANUAL (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radioactive Effluent Release Report AND Annual Radiological Environmental Operating Report required by Technical Specification Sections 6.9.1 .d and 6.9.1 .e, respectively.

1.37 PURGE - PURGING PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement and replacing it with air or gas.

1.38 SITE BOUNDARY The SITE BOUNDARY shall be the perimeter line around OCGS beyond which the land is neither owned, leased, nor otherwise subject to control by AmerGen Energy Company, LLC. The area outside the SITE BOUNDARY is termed OFFSITE or UNRESTRICTED AREA.

1.39 OFFSITE The area that is beyond the site boundary where the land is neither owned, leased nor otherwise subject to control by AmerGen Energy Company, LLC. Can be interchanged with UNRESTRICTED AREA.

1.40 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. Can be interchanged with OFFISTE.

1.41 DOSE EOUIVALENT 1-131 DOSE EQUIVALENT I- 13 1 shall be that concentration of I-13 1 (microcuries per gram), which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating Compliance with I OCFR Part 40 Appendix I."

1.42 DEPOSITION (D/O)

The direct removal of gaseous and particulate species on land or water surfaces. Deposition is expressed as a quantity of material per unit area (e.g. if2 ).

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1.43 DOSE CONVERSION FACTOR (DCF) ;;, i:

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 commonly tabulated in units of mrem/hr per picocurie/m 3 in air or water. They can be found in Reg Guide 1.109 appendices. . -

1.44 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.

1.45 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 1.1 11 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 OCGS are elevated releases-.;

1.46 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 gamma 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.

1.47 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.

1.48 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 licensee or other person.

Occupational dose does not include dose 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 1.49 RAGEMS (RADIOACTIVE GAS EMISSIONS MONITORING SYSTEM)

A plant system that monitors gaseous effluent releases from monitored release points. There is a RAGEMS system for the main stack (RAGEMS I) and one for the turbine building (RAGEMS II).

They monitor particulates, iodines, and noble gases.

1.50 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 gamma rays can travel in air. The ground is considered to be an K:\occhem\800proc i.9.0

_ it t

infinitely large flat plate and the receptor is located at the origin of a hemispherical cloud of infinite radius. The radioactive cloud is limited to the space above the ground plane. The semi-infinite plume model is limited to immersion dose calculations.

1.51 SOURCETERM The activity release rate, or concentration of an actual release or 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).

1.52 X/O - ("CHll over O.")

The dispersion factor of a gaseous release in the environment calculated by a point source gaussian dispersion model. Normal units of X/Q are sec/M3 . The X/Q 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) yields an environmental concentration, X (uCi/m 3 ). XIQ is a function of many parameters including wind speed, stability class, release point height, building size, and release velocity.

1.53 SEEDS (Simplified Effluent Environmental Dosimetry System)

A routine effluent dosimetry computer program that uses Reg. Guides 1.109 and 1.1 11 methodologies.

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TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION

NOTATION FREQUENCY S At least once perI 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

D At least once'per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.,.

M At least once per 31 days.

Q -- -"At least once per 92 days.

SA At least once per 184 days.

A . - At least once per 366 days. ,

-R- At least once per 18 months (550 days).

1/24 At least once per 24 months (refueling cycle)

S/U Prior to each reactor startup.

P - Prior to each radioactive release. . . . .

N.A. -Not applicable.

N.A .... .; . No; ,.,A ....

Each surveillance requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

. ............. : . -. ..... -:i . ...se.-:-....:..:;

.. ., .. , A. ..... ,,..- ;,.... .-. ,.

t q A= _ i ;

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_ 'it 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY CONTROLS 3.0.1 Compliance with the CONTROLS contained in the succeeding CONTROLS is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the CONTROL, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a CONTROL shall exist when the requirements of the CONTROL and associated ACTION requirements are not met within the specified time intervals. If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 Except as provided in the associated ACTION requirements, when a CONTROL is not met or the associated ACTION requirements cannot be satisfied, action shall be initiated to place the unit into COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.

This CONTROL is not applicable in COLD SHUTDOWN or REFUELING.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions of the CONTROLS are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual CONTROLS.

3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to CONTROL 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

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APPLICABILITY (Continued) '

SURVEILLANCEREQUIREMENTS' :; '.f, 4.'*;-

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement.

, ;,.* I'o -

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a CONTROL.

The time limits of the ACTION requirements are applicable at the time it is identified that a' Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the ACTION ' ;

requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.- ; :

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the CONTROLS have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. ' -

- ; -' . !.' :,.rx, eI I K:\occhem\800proc :;13.0

3/4.3 INSTRUMENTATION 3/ 4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.10 In accordance with Oyster Creek Technical Specifications 6.8.4.a.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.3.10-1 shall be OPERABLE with their Alarm/Trip setpoints set to ensure that the limits of CONTROL 3.1 1.1.1 are not exceeded. The Alarm/Trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM Part II section 1.2.1.

APPLICABILITY: During all liquid releases via these pathways.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip setpoint less conservative than required by the above CONTROL, immediately suspend the release of radioactive liquid effluents monitored by the 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 function(s).

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.10-1.

Make every reasonable effort to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.d why the inoperability was not corrected in a timely manner.

c. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable. Report all deviations in the Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.3.10-1.

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TABLE 3.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (DELETED) N/A 110

b. Turbine Building Sump No. 1-5 '1I 114

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE - .t,

a. Reactor Building Service Water System Effluent Line 112

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (DELETED) N/A 113 K:\occhem\800proc

TABLE 3.3.3.10-1 (Continued)

TABLE NOTATION ACTION I 10 - With no channels OPERABLE, effluent releases via this pathway may continue provided that:

a. At least two independent samples are taken, one prior to discharge and one near the completion of discharge and analyzed in accordance with SURVEILLANCE REQUIREMENT 4.1 1.1.1.1.

b. Before initiating a release, at least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 112 - With no channels OPERABLE, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during the release, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least I E-6 pCi/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 may be released provided that before initiating a release:

1. A sample is taken and analyzed in accordance with SURVEILLANCE REQUIREMENT 4.1 1.1.1.1.

2. Qualified personnel determine and independently verify the acceptable release rate.

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TABLE 4.3.3.10-1: RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS8 CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A N/A N/A

b. Turbine Building Sump No. 1-5 D M Re Qd

2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT .. . - .. ;

NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE f . . . .

- -- Ad

a. Reactor Building Service Water System Effluent Line D M iR! , w : -

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (DELETED) N/A N/A N/A N/A.

K:\occhem\800proc

_ _ __ __ _ _ _ _ _ _ __ ___ __ -II-1 TABLE 4.3.3.10-1 (Continued)

TABLE 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.

d. 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 downscale failure.

3. Instrument controls not set in operate mode.

4. Instrument electrical power loss.

e. The CHANNEL CALIBRATION shall be performed according to established calibration procedures.

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3/4.3 INSTRUMENTATION 3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.11 In accordance with Oyster Creek Technical Specifications 6.8.4.a.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.3.11-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of CONTROL 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels meeting CONTROLS 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM Part II Section 2.2.

APPLICABILITY: As shown in Table 3.3.3.11-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above CONTROL, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.3.11-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1 .d why this inoperability was not corrected in a timely manner.

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS .

4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies-shown in Table 4.3.3.11-1.

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TABLE 3.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERAF ILEa APPLICABILITY A(CTION

1. DELETED

2. STACK MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) I be 124

b. Iodine Sampler b,e 127

c. Particulate Sampler 1 b,e 127

d. Effluent Flow Measuring Device I b 122

e. Sample Flow Measuring Device I b 128

3. TURBINE BUILDING VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) I b 123

b. Iodine Sampler b 127

c. Particulate Sampler b 127

d. Effluent Flow Measuring Device I b 122

e. Sample Flow Measuring Device 1 b 128 K:\occhem\800proc

TABLE 3.3.3.1 1-I(Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLEa APPLICABILITY ACTION

4. AUGMENTED OFFGAS BUILDING EXHAUST VENTILATION MONITORING SYSTEM

a. Radioactive Noble Gas Monitor 1 b 123

b. Iodine Sampler 1 b 127

c. Particulate Sampler 1 b 127 I . . "

d. Sample Flow Measuring Device 1 b 128 II j"

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.. . . _ . A.

. . - 11

. \ .,

.. . Fv

. -. I I to3 K:\occhem\800proc

TABLE 3.3.3.11-1 (Continued)

TABLE NOTATION

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 estimated 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 sample is taken at least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months and is analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

K:\occhem\800proc 22.0

TABLE 4.3.3.11-1: RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REOUIREDa

1. DELETED

2. MAIN STACK MONITORING SYSTEM

a. Radioactive Noble Gas Monitor (Low Range) D M 1 /2 4 f Qh b

b. Iodine Sampler W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Effluent Flow Measuring Device D N.A. 1/24 Q b

. e. Sample Flow Measuring Device D N.A. R Q b

3. TURBINEIBUILDING VENTILATION MONITORING SYSTEM ; :,

a. Radioactive Noble Gas Monitor (Low Range) D M 1/24' Qi b

b. Iodine Sampler .,; W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Effluent Flow Measuring Device i D N.A. 1/24 Q b

e. Sample Flow Measuring Device D N.A. R Q b K:\occhem\800proc

TABLE 4.3.3.1 1-1 (Continued)

RADIOACTIVE GASEOUS FFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVIELLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REOJIREDa

4. AUGMENTED OFFGAS BUILDING EXHAUST VENTILATION MONITORING SYSTEM Qe

a. Radioactive Noble Gas Monitor D M b

b. Iodine Sampler W N.A. N.A. N.A. b

c. Particulate Sampler W N.A. N.A. N.A. b

d. Sample Flow Measuring Device D N.A. R N.A. b K:\occhern\800proc

TABLE 4.3.3.11-1 (Continued)

TABLE NOTATION

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. ,

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.

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.

# : ' i. r .

iX;, * -*,

h. 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.

3. Switch cover alarm shall be verified to alarm when the cover is opened; and clear when the coveris closed after the faceplate switches are verified in their correct positions.

i. 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.

K:\occhem\800proc 25.0

_ _ -_A 3/4.11 RADIOACTIVr EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.1 1.1.1 CONCENTRATION CONTROLS 3.11.1.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.2 and 3, the concentration of radioactive material, other than noble gases, in liquid effluent in the discharge canal at the Route 9 bridge (See Figure E-3) shall not exceed the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The concentration of noble gases dissolved or entrained in liquid effluent in the discharge canal at the Route 9 bridge shall not exceed 2E-4 microcuries/milliliter.

APPLICABILITY: At all times.

ACTION:

a. In the event the concentration of radioactive material in liquid effluent released into the Offsite area beyond the Route 9 bridge exceeds either of the concentration limits above, reduce the release rate without delay to bring the concentration below the limit.

b. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program in Table 4.11.1.1.1-1.

Alternately, pre-release analysis of batches(es) of radioactive liquid waste may be by gross beta or gamma counting provided a maximum concentration limit of I E-8 pICi/ml in the discharge canal at the Route 9 bridge is applied.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM Part II Section 1.2 to assure that the concentrations at the point of release are maintained within the limits of CONTROL 3.11.1.1 and3.11.1.2.

4.11.1.1.3 The alarm or trip setpoint of each radioactivity monitoring channel in Table 3.3.3.10-I shall be determined on the basis of sampling and analyses results obtained according to Table 4.11.1.1.1-1 and the setpoint method in ODCM Part 11 1.2.1 and set to alarm or trip before exceeding the limits of CONTROL 3.1 1.1.1.

K:\occhem\800proc 26.0

TABLE 4.11.1.1.1-1: RADIOACTIVE LIQUID WN'ASTE SAMPLING AND ANALYSIS

- PROGRAM Liquid Release Type Sampling Minimum Type of Activity Analysis Lower Limit Frequency

-- A'yss ' ' Detectiona (LLD)

Frequency ' (giCi/ml)

A. Batch Waste .pPc 'Principal Gamma Emitters 1E-06 Release Tanks Each Each Batch 1-131 IE-06 Batchb p M Dissolved and Entrained IE-05 One Gases (Gamma Emitters)

Batch/Mb:'-'

P M H-3 IE-05 Each Composited Gross Alpha IE-07 Batchb P Q Sr-89, Sr-90 51E-08 Each Composited Fe-55 IE-06 Batchb B. ReactorBuilding ' W W Principal Gamma Emitters 1E-06 Service Water Grab I-131 IE-06 Effluent andSape Turbine Bldg. P Sump No. 1-5 (note f) M H-3 IE-05 Compositeg 'Gross Alpha 'E-07 I (note f) -, Q Sr-89, Sr-90 51E-08 Compositeg Fe-55 IE-06 K:\occhem\800proc 27.0

TABLE 4.1 1.1.1. 1-1 (Continued)

TABLE NOTATION

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:

LLD = 4.66

Sb E

V

2.22E6

Y

exp(-AAt)

Where:

LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),

Sb 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, X 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 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; and an LLD of IE-5 liCi/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.

K:\occhem\800proc 28.0

When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the sample. The background count rate of a semiconductor detector (e.g. HPGe) 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 radioiiuclide.

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 IE-5 jCi/ml whereas the LLD for the other gamma emitters is 1E-6 hiCi/ml. 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.

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 emitters 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 l.OE-6 pjCi/ml of I-131 and principal gamma emitters or in the event the effluent radioactivity monitor indicates more than 1E-6 jiCi/ml 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.OE-6 iCi/ml. In addition a; composite sample must be made up for further analysis for all samples taken when the activity was > 1.OE-6 ICi/ml.' ';'

g. A composite sample is produced combining grab'samples, each having a'defined volume, collected routinely from the sump or stream being sampled K:\occhem\800proc 29.0 2.

3/4.11 RADIOACTIVE EFFLUENTS 3/ 4.11.1.2 DOSE CONTROLS 3.11.1.2 In accordance with Oyster Creek Technical Specifications 6.8.4.a.4 and 5, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure E-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the Total Body and to less than or equal to 5 mrem to any body organ, and

b. During any calendar year to less than or equal to 3 mrem to the Total Body and to less than or equal to 10 mrem to any body organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days from the end of the quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken and/or will be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM Part 1I Section 1.5 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

K:\occhen\SOOproc 30.0

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.3 LIQUID WASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.6, the liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce the radioactive materials in'liquid wastes prior to their discharge when the radioactivity concentration, exclusive of tritium'and dissolved noble gases, in the batch exceeds 0.001 gCi/ml.

APPLICABILITY: At all times. :

ACTION:,

a. With radioactive liquid waste being discharged without treatment and in excess of the above, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for theinoperability, - . '

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS-4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be determined at least once per 31 days in accordance with the methodology and parameters in the ODCM Part II Section 1.5 in accordance with Technical Specification 6.8.4.a.5.

4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting CONTROLS 3.111131112 and 3.11.1.' '

K-\occbem\800proc 31.0

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE CONTROLS 3.11.2.1 In accordance with the Oyster Creek Technical Specifications 6.8.4.a.5 and 7, the dose equivalent rate due to radioactive materials released in gaseous effluents in the UNRESTRICTED AREA (see Figure E-3) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mremlyr to any body organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

If the gaseous effluent release rate cannot be reduced to meet the above limits, the reactor shall be in at least SHUTDOWN CONDITION within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months unless corrective actions have been completed and the release rate restored to below the above limit.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM Part II Section 2.3.1.

4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM Part 11 Section 2.3.2 by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.

4.11.2.1.3 Dose rates due to tritium, 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.

4.11.2.1.4 Doses due to gaseous releases to UNRESTRICTED AREAS shall be determined at least once per 31 days in accordance with the methodology and parameters in the ODCM Part II Section 2.4.1 in accordance with Technical Specification 6.8.4.a.5.

K:'occhem\800proc 32.0

TABLE 4.11.2.1.2-1: RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS

-A -PROGRAM Gaseous Release Sampling ;Minimum Type of Activity Lower Limit Type Frequency Analysis Analysis Detectiona (LLD)

.Frequency - (AiCi/ml)

Stack Q , Q H-3 lE-06 Grab Sample" -:_,_.

Stack; Turbine M M Principal Gamma 1E-04 Building Exhaust Grb Sample Emitters (Noble.

Vents; Augmented c- . Gases)

Offgas Building Vent ,, .

Continuous f- W I-131 IE-12

'Charcoal Sample I-133 lE-10 Continuousf W Principal Gamma Paricate Emittersb 1E-11 Sapl . ,.(particulates)

Continuousf Me Gross Alpha 1E-11

.Composite .

Particulate Sample Continuous Qe - Sr-89, Sr-90 11-11 Composite Particulate

,,,Sample Continuous .Noble Gas Noble Gases IE-06 Monitor Gamma

.-. _ _ .. Radioactivity

. - * -- t-:.

2-..

,. , 6.1. 'I .-

. i

.... I..

K:\occhem\800proc ;33.0

-~.11 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATION

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:

LLD = 4.66

Sb E

V

2.22E6

Y

exp(-At)

Where:

LLD is the lower limit of detection as defined above (microcurie per unit mass or volume),

Sb 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, Xis 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. Occasionally background fluctuations, interfering radionuclides, or other uncontrollable circumstances may render these LLD's unachievable.

When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the samples. 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 that radionuclide K:\occhem\800proc 34.0

b. The principal gamma 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 mtean that only these nuclides are to be considered. Other gamma 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 CONTROL 3.11.2.1.

The LLD for Mo-99 and Ce-144 is lE-10 pCi/ml whereas the LLD for other principal gamma emitting particulates is IE-1 1ICi/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 taking a grab sample of effluent and analyzing it. -

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 three after factoring out the effect due to the change in reactor power, a grab sample of Stack effluent shall be collected and analyzed. 'a

e. A composite particulate sample shall include an equal fraction of at 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less, the LLD may be increased by a factor of 10.

.. I ! , I 1, 111

. I. I. .

. . f. :- . " .,!! '. , i I I . .

K:\occhem\800proc ! : 35.0

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.2 DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with the Oyster Creek Technical Specification 6.8.4.a.5 and 8, the air dose due to noble gases released in gaseous effluents in the UNRESTRICTED AREA (see Figure E-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days from the end of the quarter during which the release occurred, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM Part 11 Section 2.4.1 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

K:\occhem\800proc 36.0

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Oyster Creek Technical Specification 6.8.4.a.5 and 9, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released in the UNRESTRICTED AREA (see Figure E-3) shall be limited to the following:

a. During any calendar quarter: i Less than orequal to 7.5 mrem to any body organ and,

b. During any calendar year: Less than or equal to 15 mrem to any body organ.

APPLICABILITY: At all times. 'r. - -

ACTION:

a. With the calculated dose from the release ofiodine-131, iodine-133 and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to TechnidaltSpecification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that

-have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with them'methodology and parameters in the ODCM Part II Section 2.5 at least once per 31 days in accordance with Technical Specification6.8.4.a.5. . - '

A ;

m . 7

IC.\erchem\Rflflrnc .. . 37.0 * ':.- - :

- .__ -I---

_-II-3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2.4 GASEOUS RADWASTE TREATMENT CONTROLS 3.11.2.4 In accordance with Oyster Creek Technical Specifications 6.8.4.a.6, the AUGMENTED OFFGAS SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser steam jet air ejector is in operation except during startup or shutdown with reactor power less 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 function due to low offgas flow.

ACTION:

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 ejectors.

b. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 30 consecutive days and either CONTROL 3.11.2.1 or 3.11.2.2 exceeded, prepare and submit to the Commission within 30 days from the end of the quarter during which release occurred, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of CONTROL 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Operation of the Augmented Offgas System charcoal absorbers shall be verified by verifying the AOG System bypass valve, V-7-3 1, alignment or alignment indication closed at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the main condenser air ejector is operating.

K:\occhem\800proc 38.0

3/4.11 RADIOACTIVE EFFLUENTS : ;

3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Oyster Creek Technical Specifications 6.8.4.a.10, the annual (calendar year) dose commitment to any MEMBER OF THE PUBLIC due to radioactive material in the effluent and direct radiation from the OCGS in the UNRESTRICTED AREA shall be limited to less than or equal to 75 mrem to the thyroid or less than or equal to 25 mrem to any other organ.

APPLICABILITY: At all times ACTION: - ; --

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of CONTROLS 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3. 11.2.2b, 3.11.2.3a, or 3.11.2.3b, perform an assessment to determine whether the limits of CONTROL 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, shall include information specified in 10CFR20.2203. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with SURVEILLANCE REQUIREMENT 4.11.1.2,4.11.2.2,4.11.2.3, and in accordance with the methodology and parameters in the ODCM Part II Section 3.0 at least once per year. ' ' '

4.11.4.2 Cumulative dose contributions from direct radiation from the facility shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 3.2. This requirement-is applicable only under'coniditions set forth in 'CONTROL 3.11.4, ACTION a.

K:\occhem\800proc 39.0

- IIl-3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1. In accordance with Oyster Creek Technical Specifications 6.8.4.b, the radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1. For specific sample locations see Table E-1.

APPLICABILITY: At all times.

ACTION:

a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9. .e, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 60 days of the end of the quarter, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2) + Ž1.0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose*

to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of CONTROLS 3.11.1.2, 3.11.2.2, and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to Section 6.1.2.1

The methodology used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

K:\occhemX00proc 40.0

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)

ACTION: (Continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Document the unavailability of samples and the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

d. The provisions of CONTROLS 3.0.3, 3.0.4 and Technical Specification 6.9.2 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in Table E-1, and shall be analyzed pursuant to the requirements of Table 3.12.1-1, and the detection capabilities required by Table 4.12. 1-1.

K-\occhem\800proc 41.0

TABLE 3.12.1-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTAIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(') COLLECTION FREQUENCY OF ANALYSIS

1. DIRECT RADIATION(2) Routine monitoring Quarterly Gamma dose quarterly stations with two or more dosimeters placed as follows:

An inner ring of stations one in each meteorological sector in the general area of the SITE BOUNDARY (16 locations);

(09/04)

An outer ring of stations, one in each land-based meteorological sector in the 6- to 8-km range from the site (9 locations); and At least 5 stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

30 Indicator Stations / 2 Background stations K:\occhcm\800proc

TABLE 3.12. 1-I(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(l) COLLECTION FREOUENCY OF ANALYSIS

2. AIRBORNE Radioiodine and Samples from 5 locations: Continuous sampler Radioiodine Canister:

Particulates operation with sample 1-131 analysis weekly.

Three samples from close to collection weekly or the SITE BOUNDARY locations, more frequently if in different sectors, of the highest required by dust Particulate Sampler calculated annual average loading. Gross beta radioacti-ground-level D/Q. vity analysis follow-ing filter change(3);

One sample from the vicinity Gamma isotopic of a community having the highest analysis(4) calculated annual average ground- of composites (by level D/Q; and location) quarterly.

One sample from a control location, as'for'example'15-30 km'distant ' -

and in'the least'prevalent wind ' ' '

direction.

4 Itidicator Stations / 1 Background Station

.tt. :.i - . :..

I..

K:\occhem\800proc

TABLE 3.12.1-1 (Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(') COLLECTION FREQUENCY OF ANALYSIS

3. WATERBORNE

a. Surface One sample upstream Grab sample monthly. Gamma isotopic analy-One sample downstream sis (4) monthly.

b. Ground' 5 ) One on-site domestic water well sample Semiannually Gamma isotopic analy-One down gradient domestic water sample sis(4) and tritium One up-gradient domestic water sample -

background station.

0V K:\occhem\800proc

TABLE 3.12.1-I(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(') COLLECTION FREQUENCY OF ANALYSIS

d. Sediment One Sample from Downstream Area Semiannually Gamma isotopic analysis(4) semiannually.

One background sample from outside the influence of the facility (Sampling locations same as surface water)

.01.

K:\occhem\800proc

TABLE 3.12.I-l(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FlREQUENCY AND/OR SAMPLE SAMPLE LOCATIONSt l) COLLECTION FREQUENCY OF ANALYSIS

4. INGESTION

a. Milk (6) No milking animals Semimonthly when on pasture; Gamma isotopic (4) and If milk animals are identified: monthly at other times I-131 semimonthly when Samples from milking animals in animals are on pasture; three locations within 5km having monthly at other times the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 an 8 km distant where doses are calculated to be greater than I mrem per year. One sample 0o from milking animal at a control location 15 to 30 km distant and in the least prevalent wind direction

b. Fish One sample of available species Semiannually, Gamma isotopic consumed by man in plant when available analysis (4) discharge canal. on edible portions.

One sample of available species consumed by man not influenced by plant discharge.

K:\occhem\800proc

TABLE 3.12. l-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATH'VfAY SAMPLES AND - SAMPLING AND . TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS(l) : : COLLECTION FREOUENCY 'OF ANALYSIS

c. Clams One sample of available species' Semiannually, 'Gamma isotopic consumed by man in plant- when available analysis (4) discharge canal. on edible portions.

One sample of available species consumed by man not influenced by plant discharge.

, .1 - .: -4

d. Vegetation. Samples of broad leaf 'Monthly, -when Gamma isotopic vegetation grown nearest each available analysis (4)on of two different offsite locations of edible portion.

highest predicted annual average D/Q.

'- -One sample of similar broad leaf vegetation grown distant '

and in a low D/Q sector.

K:\occhem\800proc

TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS (I) Specific parameters of distance and direction sector from the centerline of the reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12. 1-1 and Table E- 1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.4. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Technical specification 6.19, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location(s) for obtaining samples.

(2) One or more instruments, such as pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. The number of direct radiation monitoring stations has been reduced from the NUREG 1302 recommendation due to geographical limitations; e.g., some sectors are over water and some sectors cannot be reached due to lack of highway access, therefore the number of dosimeters has been reduced accordingly.

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(5) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

(6) No milk animals have been identified within 8 km of the plant. Should the census identify milk animals, sampling would then be required at the numbers and frequencies specified.

K:'occhcm\800proc 48.0

TABLE 3.12.1-2: REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES - REPORTING LEVELS Surface and Ground' Airborne Particulate Fish Milk Vegetation Analysis Water(pCi/1) and Iodine (pCi/M 3 ) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet) 1-320000* . . .

.K Mn-54 ; 1000 . 30000 Fe-59 400 10000 Co-58 1000 30000 Co-60 300 10000 Zn-65 300 20000 Zr-Nb-95 400 1-131 20* 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 300 _ _ _ _ _ _

For a sample of water not used as a source of drinking water K:\occhem\800proc i49.0

_l - _ _ - u.

TABLE 4.12.1-1: DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS("'"" 2 -LOWVER LIMITS OF DETECTION (LLD)(')

Surface and Air Particulate Vegetation Sediment Fish and Analysis Ground Water and Air Iodine (pCi/Kg, wet) (pCi/Kg, dry) Clams (pCi/I) (pCi/M3 ) (pCi/Kg, wet)

Gross Beta 4 0.01

[1-3 2000(4) 3000(')

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 15(5) .07(6) 60 Cs-134 15 .05(7) 60 150 130 Cs-137 18 .06(7) 80 180 150 La-140 15 Ba-140 60 K:\occhcm\800proc 50.0

TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS

( This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmiental Operating Report pursuant to' CONTROL 6.1.2.3.

(2) Required detection capabilities for thermoluminescent dosimeters used for:

environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

(3) The LLD is defined, for purposes of these CONTROLS 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% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD= 4.66

Sb E

V

2.22

Y* exp(-,IAt)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec'), and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation.

K:\occhem\800proc - '51.0

TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant Technical Specification 6.9.1 .e and Control 6.1.2.6.4.

(4) For a sample of drinking water.

(5) For a sample of water not used as a source of drinking water.

(6) For the air iodine sample (7) For the air particulate sample K:\occhem\800proc 52.0

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2. In accordance with the Oyster Creek Technical Specifications 6.8.4.b, a land use census shall be conducted and shall identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 ft2 producing broad leaf vegetation. The census shall also identify within a distance of 3 miles the location in each of the 16 meteorological sectors all milk animal and all gardens greater than 500 square feet producing broadleaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in SURVEILLANCE REQUIREMENT 4.11.2.3, identify the new location(s) in the next Radioactive Effluent Release Report, pursuant to Control 6.2.2.4.

b. With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with CONTROL 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may then be deleted from this monitoring. -Pursuant to CONTROL 6.2.2.4, identify the new location(s) in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable..

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.2.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Q's in lieu of the garden census., Controls for broadleaf vegetation sampling in Table 3.12.1-1, Part 4.c shall be followed, including analysis of control samples. ,

/ . : ;'.7r. .-*

K:\occhem\800proc 153.0

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 In accordance with Oyster Creek Technical Specifications 6.8.b.3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the reason and corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3 .

b. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to CONTROL 6.1.2.6.3.

BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE: The BASES contained in the succeeding pages summarize the reasons for the CONTROLS of Sections 3.0 and 4.0, but are not considered a part of these CONTROLS.

3/4.3 INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The radioactivity monitor on the Turbine Building sump 1-5 will 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 Room when the alarm setpoint is exceeded. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is K:\occhem\8OOproc 54.0

consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR PartSO. : '

3/4.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for each of the noble gas monitors shall be calculated and adjusted in accordance with the methodology and parameters in'the ODCM. This will ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The radioactive gas'monitors for the stack effluent and the Augmented Offgas Building exhaust ventilation have alarms which report in the Reactor Control Room. The OPERABILITY-and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This CONTROL is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides'additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A desigii'6bjectives of Appendix I,10CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(a) to the population. The concentration limit for dissolved 6r entrained noble'gases'is based upon the assumption'that Xe-135 is the controlling radioisotope and its concentration limit in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

~~~~~~~~~~- . I....; .;--;.,i:-- , :!

The value I E-8 is the limit for unidentified gross gamma or beti releas6s as per 10 CFR 20 Appendix B, Table 2, Column 2 "any single radionuclide. ..other than alpha or spontaneous fission.'. .half lifet greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ". This provides operational flexibility while providing reasonable assurance 'that dose will remain less than 0.1 rem./yr.- V ;':

The required detection capabilities for radi6active materials in liquid waste samples are'tabulated in terms of the lower limits of detection (LLDs). Detailed discussion'of the LLD, and other detection limits can be found in references 25, 26, and 27.

3/4.11.1.2 DOSE This CONTROL is provided to implement the'requirements of Sections II.A, III.A,- and IV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the s'ame time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The dose calculation methodology anid parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedure's based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The K-\occhem\800proc 55.0

equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 and Regulatory Guide 1.113.

3/4.11.1.3 LIQUID RADWASTE TREATMENT The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to their release to the environment. The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents wvil be kept "as low as is reasonably achievable". This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section 1I.A of Appendix 1, 10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This CONTROL is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the individual will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in references 25, 26 and 27.

3/4.11.2.2 DOSE - NOBLE GASES This CONTROL is provided to implement the requirements of Section II.B, ILI.A and IV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section [V.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The SURVEILLANCE REQUIREMENTS implement the requirements in Section IlI.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and K:\.occhenl\800proc K:\ochc\SO~roc56.0 56.0

parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109. and Regulatory Guide 1.111. The ODCM equations provided f6r determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. :..

3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This CONTROL is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A -ofAppendix I to assure that the releases of radioactive material in gaseous effluents to UNRERSTRICTED AREAS will be kept "as low as is reasonably achievable."

The ODCM calculational methods specified in SURVEILLANCE REQUIREMENTS implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, and Regulatory Guide 1.111. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium, and radionuclides inparticulate form with half-life greater than 8 days are dependent on the existing radionuclide pathways'to'man, in the areas at and beyond the SITE BOUNDARY.'The pathways thatwer examined'in the development offthese calculations were: 1),

individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by'man, 3) deposition onto grassy areas where milk animals' and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man..

3/4.11.2.4 AUGMENTED OFFGAS TREATMENT SYSTEM' The OPERABILITY of the AUGMENTED OFFGAS TREATMENT SYSTEM (AOG) ensures that the system will be 'available for use Whenever. gaseous effluents require treatment prior to release to the en'vironment.' The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achi6vable." This CONTROL implements the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part'50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix IA10 CFR-Part 6, for gaseous effluents.;

3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have now been incorporated into 10 CFR Part 20 by.46 FR1 18.525.',The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses'from plant radioactive effluents exceed 25 mrem to the total body or any organ, except t e thyroid, which shall be limited to less than or equal to 75 mrem. It is'highly unlikely'that the resultant dose'to a MEMBER OF THE PUBLIC will K:\occhem\800proc . 57.0

exceed the dose limits of 40 CFR Part 190 if the doses remain within twice the dose design objectives of Appendix 1,and if direct radiation doses from the unit, including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190 and 10 CFR Part 20, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.1 1.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological environmental monitoring program required by this CONTROL provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Position on Environmental Monitoring, Revision 1, November 1979.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12. 1-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits can be found in references 25, 26, and 27.

Site-specific research, which included the installation of a groundwater monitoring well network, has demonstrated that the groundwater pathway is not a potential pathway to man from the OCGS. The surface water into which the OCGS discharges is a marine estuary containing saline water that is not used as drinking water or irrigation water by man.

3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey, from visual survey or consulting with local agricultural authorities shall be K:\occhem\800proc 58.0

used. This census satisfies the requirements of Section IV.B.3 of Appendix Ito 10 CFR Part 50.

Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To 'determine this minimum garden 'size, the following assumptions were made: 1) 20% of the garden was used for growing broad leaf vegetation (i.e.,

similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/rn.

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING, BASES -

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate thatthe'results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

5.0 DESIGN FEATURES / SITE MAP (Provided FOR INFORMATION ONLY. 'Technical Specifications are'controlling.)

5.1 Site map which will allow identification of structures and release points shall be as shown in Figure E-3.

6.0 ADMINISTRATIVE CONTROLS -

6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (REOR) 6.1.1 In accordance with Oyster Creek Technical Specifications 6.9.1.e, a routine radiological environmental operating report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of the following year.

i- i t6* ' - ' ;

6.1.2 The Annual Radiological Environnmental Operating Reports shall include:'

6.1.2.1 Summaries, interpretations, anhd an' analysis of trends of the'results of the radiological environmental surveillance activities (Radiological Environmental Monitoring Program -

REMP) for the report period. JThis will include a comparison with preoperational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and

'an assessment of the observed im pats 'of the plant operation 6ntheehvironment."

6.1.2.2 The reports shall also include the results of land use censuses required by CONTROL 3.12.2.-

If harmful effects or evidence oftifre!ersible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

6.1.2.3 The Annual Radiological Enviroimiental Operating Reports shall include summarized and tabulated results similar in format to that in Regulatory Guide 4.8, December 1975 of all the radiological environmental samples taken during the report period.

K:\occhem\800proc 5.9.0

' 5

6.1.2.4 Deviations from the sampling program identified in CONTROL 3.12.1 shall be reported.

6.1.2.5 In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

6.1.2.6 The reports shall also include the following:

6.1.2.6.1 A summary description of the radiological environmental monitoring program; 6.1.2.6.2 Map(s), covering sampling locations, keyed to a table giving distances and directions from the reactor; 6.1.2.6.3 The results of licensee participation in the Inter-laboratory Comparison Program, as required by CONTROL 3.12.3; 6.1.2.6.4 Identification of environmental samples analyzed when the analysis instrumentation was not capable of meeting the detection capabilities in Table 4.12.1-1.

6.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (RERR) 6.2.1 In accordance with Oyster Creek Technical Specifications 6.9. .d, routine radioactive effluent release reports covering the operation of the unit shall be submitted within 60 days of January I of each year and in accordance with the requirements of IOCFR50.36a and section IV.B. I of 10CFR 50 Appendix 1.

6.2.2 The Radioactive Effluent Release Report shall include:

6.2.2.1 A summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21. "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

6.2.2.2 An annual summary of hourly meteorological data collected over the previous year. This annual summary may be in the form ofjoint frequency distributions of wind speed, wind direction, and atmospheric stability. Alternatively, summary meteorological data may be retained and made available to the NRC upon request.

6.2.2.3 An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. The historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this OFFSITE DOSE CALCULATION MANUAL (ODCM).

6.2.2.4 Identify those radiological environmental sample parameters and locations where it is not possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In addition, the cause of the unavailability of samples for the pathway and the new location(s) for obtaining replacement samples should be identified. The report should also include a revised figure(s) and table(s) for the ODCM reflecting the new location(s).

K-:occhcm\800proc 60.0

6.2.2.5 An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190,'Environinental Radiation Protection Standards for Nuclear Power Operation. The assessment of radiation doses shall be performed in accordance with this OFFSITE DOSE CALCULATION MANUAL (ODCM) Part II Sections 1.5,2.4,.'

2.5, and 3.2.

6.2.2.6 The Radioactive Effluent Release Rep0its'shall include the following information for each class of solid waste (as defined by 10 CFR Part 61) shipped offsite during the report period (see Figure]D-1-2): " .

a. Total volume shipped x -'Y*

i; ..

b. Total curie quantity (specify whether determined by measurement or estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),

6.2.2.7 Unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in (09/04) gaseous and liquid effluents on a quarterly basis.

6.2.2.8 Changes to the PROCESS CONTROL PROGRAM (PCP) 6.2.2.9 Changes to the OFFSITE DOSE CALCULATION MANUAL (ODCM)

6.3 RESPONSIBILITIES

^

6.3.1Chemistry/ Radwaste-Responsible for ;

6.3.1.1 Implementing approval. ; ;

6.3.1.2 Compliance with specifications regarding routine dose assessment.

6.3.1.3 Radiological Environmental Monitoring Program 6.3.1.4 Technical consultation and review !

6.3.2 Operations - Responsible for compliance with specifications regarding operation of the OCGS.

6.3.3 Engineering - Responsible for coimpliance with specifications regarding setpoint determination and implementation 6.3.4 Radiological Engineering - Responsible for technical consultation'and review.'

K...c,8. . . .... ,-.I.-,8 K:\occhem\800proc .61.0

- -1L PART 11 - CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENTS 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS The liquid effluent monitoring instrumentation and controls at Oyster Creek for controlling and monitoring normal radioactive material releases in accordance with the Oyster Creek Radiological Effluent Technical Specifications are summarized as follows:

(1) Alarm (and Automatic Tenmination) - Turbine Building 1-5 Sump Monitor provides the alanm and automatic tennination of liquid radioactive material releases from the 1-5 sump.

(2) Alarm (Only) - The Reactor Building Service Water Effluent Line Monitor provides an Alarm function only for releases into the environment.

Liquid radioactive waste flow diagrams are presented in Figures D-l-la and D-l-lb.

1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION Per the requirements of CONTROL 3.3.3.10, alarm setpoints shall be established for the liquid monitoring instrumentation to ensure that the release concentration limits of CONTROL 3.1 1.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS at the U.S. route 9 bridge over the discharge canal shall not exceed the concentrations specified in 10 CFR 20 Appendix B.

Table 2, Column 2, for radionuclides and 2.OE-04 jiCi/ml for dissolved or entrained noble gases).

1.2.1 LIQUID EFFLUENT MONITORS The setpoints for the liquid effluent monitors at the Oyster Creek Generating Station are detennined by the following equation:

A F2 S = g -+ BKG FLEC FI Where:

S = radiation monitor alarm setpoint (cpm)

A = activity concentration (giCi/ml) of sample in laboratory: A = 5C1 g = the primary conversion factor for the instrument - the ratio of effluent radiation monitor counting rate to laboratory activity concentration in a sample of liquid (cpm per 40Ci/mL).

Fi = flow in the batch release line (e.g. gaUrnin). Value not greater than the discharge line flow alann maximum setpoint.

K:\occhem\SOOproc 62.0

F2 = flow in the discharge canal (e.g. gal/min). Value not less than the discharge canal minimum flow.

BKG = Monitoring instrument background (cpm)

FLEC= fraction or multiple of unrestricted area LEC in aqueous effluent based on sample analysis.

FLEC is the ratio between the LECi and Ci. FLEC is unitless. For example: LEC for Co-60 is 3E-6 gCi/ml. If the concentration in a expected release is 6E-6'[jCi/ml; then FLEC is 6E-6/3E-6 = 2.

The term A represents.the 'count rate. of a solution having the same nuclide distribution as the sample and the LEC of that mixture.

Ci concentration of radionuclide i in'effluent, i.e.,' in a liquid radwaste sample tank, in reactor building service water, or iii Suinp No. 1-5 (jiCi/mL).

LECj= The unrestricted area liquid effluent concentration (LEC) of radionuclide i, i.e., 10 CFR 20, Appendix B, Table 2, Column 2 quantity for radionuclide i (gCi/mL).

In the event gross radioactivity analysis alone is used'to determine the radioactivity in an effluent stream or batch, FLEC is C/1E-8 (see 4.1 14-.'1.i),

Where:

C the gross radioactivity concentration in effluent (giCi/mL).

1E-8 - The unrestricted area LEC for unidentified radionuclides (jCi/mL) from 4.11.1.1.1.

If the gross activity concentration, C, is below the lower limit of detection for gross activity, the value, 1E-8 gCi/ml, or the equivalent counting rate (cpm/ml) may be substituted for the factor A

- Am FLEC A =1E-8jtCi/mlI FLEC -.

1.2.2 SAMPLE RESULT SETPOINTS Usually, when the concentration of specific radionuclides is determinable in a sample(s),

i.e., greater than the LLD, the alarm/trip setpoint of each liquid effluent radioactivity monitor is based upon the measurement of radioactive material in a batch of liquid to be released or in a continuous aqueous discharge.

1.2.3 ASSUMED DISTRIBUTION SETPOINTS Alternatively, a radionuclide distribution that represents the distribution expected to be in the effluent if the concentration were high enough to be detectable, i.e., greater than the LLD, may be assumed. The representative distribution may be based upon past measurements of the effluent stream or'upon' a computed distribution.

,~~ ..-..-., 1 .,:,..;.:

K-\occhem\800proc :'.:63.0

il .

1.3 BATCH RELEASES A sample of each batch of liquid radwaste is analyzed for 1-131 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.

1.4 CONTINUOUS RELEASES The Reactor Building Service Water Effluent and the Turbine Building 1-5 Sump are each sampled and analyzed weekly for 1-131 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 in order to detennine a representative value. In each case, whether batch or continuous, the monitor alarn/trip setpoint may be set at lower activity concentration than the calculated setpoint.

1.5 LIQUID EFFLUENT DOSE CALCULATION - 10 CFR 50 Doses resulting from the release of radioiodines and particulates must be calculated to show compliance with Appendix I of 10CFR50. Calculations will be perfonned at least monthly for all liquid effluents as stated in SURVEILLANCE REQUIREMENT4.11.1.2 and SURVEILLANCE REQUIREMENT 4.11.1.3.1 to verify that the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.1.2 The maximum dose to an individual from radioiodines, tritium, and radioactive particulates with half-lives of greater than eight days in liquid effluents released to unrestricted areas is determined as described in Reg. Guide 1.109. Environmental pathways that radioiodine, tritium, and particulates in liquid effluent follow to the maximally exposed MEMBER OF THE PUBLIC are assumed to be: exposure to shoreline deposits, ingestion of fish, and ingestion of shellfish. To assess compliance with CONTROL 3.11.1.2, the dose due to radioactive iodine, tritium, and particulates in liquid effluent is calculated to a person at the Route 9 bridge who consumes fish and shellfish harvested at that location.

1.5.1 MEMBER OF THIE PUBLIC DOSE - LIQUID EFFLUENTS CONTROL 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Oyster Creek Generating Station to those listed in Table 1.5.1-1.

TABLE 1.5.1-1 LIQUID PATHWAY DOSE LIMITS During Any Calendar Ouarter During Any Calendar Year

< 1.5 mrem to total body < 3.0 mrem to total body

< 5.0 mrem to any organ < 10.0 mrem to any organ Per the SURVEILLANCE REQUIREMENTS of 4.11.1.2, the following calculation methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Oyster Creek. Applicable liquid pathways to man for Oyster Creek include shoreline exposure, and ingestion of saltwater fish and shellfish. The receptor location is provided in Table A-4.

K:\occhem\8O0proc 64.0

1.5.2 SHORELINE DEPOSIT DOSE -,

The shoreline exposure pathway dose is calculated generally in the form (based on Reg.

Guide 1.109): . -

Rap] =110000 UapWM ZQiTiDaipj(I- exp(-iTb))

F Where: -

110000 = a constant that accounts for time aand flow conversions Rapj = the annual dose to organ j (including the total body), through pathway p, to age group a Uap = the age dependent usage factor for the specific pathway. Usage factors for shoreline exposure are residence time on the shoreline (hours). Usage factors are provided in Reg. Guide 1.109 Table E- 5. Usage factors specifically selected for Oyster Creek are presented in Table B-i.

W the shore width factor. This adjusts the infinite plane gamma or beta dose factors for the finite size and shape of the shoreline. Different factors apply to different bodies of water. A factor of 0.1 is used for OC for 'discharge canal bank'.

M = the recirculation factor. The recirculation factor is a multiplier of 3.76 to account for recirculation of discharge water back into the intake. Although this occurs infrequently, it is assumed to occur for each liquid release.

F = the flow rate in the discharge canal in cubic feet per second Qi = the activity of the ith isotope in the release in curies Ti = the half life of the ith isotope in days Daipj = the age a, isotope i; pathway p, aid organ j, specific 'dose conversion factor. Pathway, isotope, age, and organ specific dose factors are obtained from Regulatory Guide 1.109 Appendix E, Tables E-7 through E-14 i - = the decay constant of the ith isotope in years Th = the long term buildup time,iassumed to bd' 15 years Note: Xi and Th can use any time units as long as they are both the same.

No transit delay (Tp from Reg. 'Guide 1.109) is assumed.

1.5.3 SHORELINE DOSE EXAMPLE.

The following provides an'example of the liquicd'dose calculation:

Initial parameters:

K-\occhem%800proc ', '65.0

Canal flow rate I E6 gpm (typical of normal full power operation)

Release: 10000 gallons of water at I E-3 gCi/ml Co-60 Problem: calculate shoreline whole body dose Uap = 67 (teenager) hours W =0.1 M = 3.76 F = 2228 [I E6 gpm *3785 ml / gal / (60 sec/min

28316 ml/ft') = 2228 CFS]

Qi = 0.03785 Ci [IE-3uCi/ml

10000gal

3785ml/gal = 0.03785 Ci]

Ti = 1930 [5.27 years*365.25days/yr = 1.93E3 days)

XI = 1.31E-1 [0.693 / (5.27 yrs)]

Tb = 15 years Daipj = 1.7E-8 mremlhr / pCi/rn 2 Gamma dose factor Calculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope Rapj= 1000067 0- I 3- 7 6 0.03785* 1930* 1.7E -8 * (1-exp(-1.3E-1

15))

2228 Rapj = I.3E - 3mren : teen: wvlholebody 1.5.4 INGESTION DOSE - LIQUID Ingestion dose pathway calculations are similar to those for the shoreline dose, with minor changes in constants, removal of the shore width factor, and inclusion of the bioaccumulation factor:

Rapj = 1100 Uapm QiBipDaipj F

Where:

Bip = the stable element bioaccumulation factor for pathway p for the ith isotope No transit delay is assumed Pathway, isotope, age, and organ specific dose factors are obtained from Regulatory Guide 1.109 Appendix E Tables E-7 through E-14. Bioaccumulation factors are provided in Reg.

Guide 1.109 Table A-I . Usage factors are provided in Reg. Guide 1.109 Table E-5. Usage factors specifically selected for Oyster Creek are presented in Table B-l.

The radionuclides included in the periodic dose assessment per the requirements of CONTROL 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of CONTROL 3/4.11.1.1, Table 4.11.1.1.1-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Table 4.11.1.1.1-1.

K:\occhem'800proc 66.0

1.5.5 INGESTION DOSE CALCULATION EXAMPLE The following provides an example of the liquid'dose calculation:

Initial parameters:

Canal flow rate 1E6 gpm (typical of normal full power operation)

Release: 10000 gallons of water at IE-3 gtCi/ml Co-60 Problem: calculate teen whole body dose from'saltwater fish ingestion Rapj = 1io. UapM A QiBipDazj F.-

Uap = 16 (teenager) Kg M = 3.76 F = 2228 [1E6 gpm *3785 ml / gal /(60 sec/min

28316 m/fl3 ) = 2228 CFS]

Qi = 0.03785 Ci [lE-3uCi/ml

10000

3785 = 0.03785 Ci]

Bip =100;- - -

Daipj = 6.33E-6 mrem /pCi .. - .1 '

Calculate Rapj for a Teen, j = total body, p = fish ingestion dose for one isotope Rap] 1100 16* 3.76 0.03785 *100 *6.33E - 6 2228 Rap] 7.12EE - 4mrem teen ivholebody 1.6 REPRESENTATIVE SAMPLES; -

A sample should be representative of the bulk stream or volume of effluent from which it is taken. Prior to sampling, large volumes of liquid waste should be mixed in as short a time interval as practicable to assure that any sediments or particulate solids are distributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks (collection or sample test tanks) should be capable of recirculating at a rate of not less than two tank volumes in eight hours. Minimum recirculation times and methods of recirculation are controlled by specific plant procedures.::-

2.0 GASEOUS EFFLUENTS 2.1 RADIATION MONITORING INSTRUMENTATON AND CON'TROLS The gaseous effluent monitoring instrumentation and controls at Oyster Creek for controlling and monitorinig noirmal ifadiioactive' iaterial releases in accordance with the Radiological Effluent CONTROLS are summarized as follows:

(I) Main Stack K:\occhem\800proc ;. 67.0

The main stack receives nornal ventilation flow from the reactor building, new radwaste, old radwaste, process discharge flow from the augmented offgas system (AOG), condenser offgas flow if AOG is not in service, and normal ventilation flow from portions of the turbine building, predominantly the condenser bay area. Reactor building and turbine building flow is not normally processed or filtered. Reactor Building flow may be manually or automatically directed through the Standby Gas Treatment System (SBGTS) which has particulate and charcoal filtration. Offgas flow is processed through AOG or through a 30 minute delay pipe prior to release. Flow from the 'new' and 'old' radwaste buildings is IIEPA filtered. Releases through the main stack are monitored for noble gases using the RAGEMS [ system and sampled for iodine, particulates and tritium. The plant stack is considered to be a true elevated release point.

(2) Turbine Building Vent The Turbine building vent is monitored for noble gases by the RAGEMS II system and sampled for iodine, particulates and tritium. It discharges on the west side of the turbine building approximately at roof height and is considered to be a ground level release. It ventilates the turbine floor and other areas of the turbine building. Flow through this release point is not filtered.

(3) Feed Pump Room Vent The feed pump room vent is monitored by RAGEMS 11. It discharges on the east side of the turbine building below roof height and is considered to be a ground level release. It ventilates the reactor feed pump room. Flow through this release point is not filtered.

(4) Augmented Off'as Building Vent Offgas Building HIVAC is released through a ground level release from the building. Offgas process flow is not released through the building ventilation, but is routed to the plant stack. A ventilation monitoring system monitors for noble gas and samples for particulate and iodine.

(5) Isolation Condensers The isolation condensers are a ground level release. The predominant isotope through this potential release point is tritium as a consequence of the forced evaporation of'condensate transfer water when the isolation condensers are initiated. Releases are neither monitored nor is the release process flow sampled.

Releases of tritium are evaluated based on liquid samples of the input and the volume used.

Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation controls are presented in Figures D-2-1 and D-2-2.

2.2 GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION 2.2.1 PLANT VENT K:\occhcm\800proc 68.0

Per the requirements of CONTROL 3.3.3.11, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of CONTROL 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem/year to the total body or 3000 mrem/year to the skin.

Based on a grab sample analysis of the applicable release (i.e., of the Stack, Offgas:

process flow, etc.), the radiation monitoring alarm setpoints may be established by the following calculation methods. A setpoint of a monitor of an elevated release, e.g., from the stack, may be calculated using the equation:

-S- = 106 h EC + Bkg

- (CiDFSi) where:

S = the alarm setpoint (cpm) h = primary conversion factor of the instrument - monitor response to activity concentration of effluent being'nionitored, cpn/(p.Ci/cm2 ). Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Ci = relative concentration of noble gas radionuclide i in effluent at the'point of monitoring (jiCi/cm3 )

1.06 = 500 mrem/year /472 (conversion of cfm to cc/sec)

DFSi = factor converting elevated release rate of ra'dionuclide i to total body dose equivalent rate at the location of potential exposure. Units are: mrem/(yr(iCi/sec)); From Table A-l. ' -;

f = flow of gaseous effluent stream being monitored, i.e., stack flow, vent flow, etc. '(ft3/min)

BKG = Monitoring instrument background (cpm or mR/hr)

- A'-t . - .- ..

2.2.2 OTHER RELEASE POINTS The setpoint of a monitorr of a-grouind-level or split-wake release,' e.g., from the turbine'e building vent or the'AOG building, may be calculated with the equation:

S.= 1.06 + Bkg

.E(CiPDFVi)

K:\occhem\800proc i,., 69.0

- IL Where:

DFVi = factor converting ground-level or splitwake release of radionuclide i to the total body dose equivalent rate at the location of potential exposure. Units are: mrem/(yr(gCi/m 3 )). From Table A-I.

X/Q = atmospheric dispersion from point of ground-level or split-wake release to the location of potential exposure (sec/mn3 ) from Table 2.2.2-1.

The atmospheric dispersion, X/Q, and the dose conversion factor, DFSi, depend upon local conditions. For the purpose of calculating radioactive noble gas effluent monitor alarm setpoints appropriate for the OCGS, the locations of maximum potential offsite exposure and the reference atmospheric dispersion factors applicable to the derivation of setpoints are given in Table 2.2.2-1.

TABLE 2.2.2-1 RECEPTOR LOCATIONS AND DISPERSION FOR GASEOUS MONITOR SETPOINTS Discharge Point Receptor Location Atm. Dispersion Sector Distance(m) (sec/mr3 )

Ground-level or vent SE 522 2.15 E-5 Stack SE 522 N/A 2.2.3 RADIONUCLIDE MIX FOR SETPOINTS 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:

2.2.3.1.1 Preferably, the radionuclide distribution is obtained by gamma isotopic analysis of identifiable noble gases in effluent gas samples. Results of the analyses of one or more samples may be averaged to obtain a representative spectrum.

2.2.3.2 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.

2.2.3.3 Alternatively, the total activity concentration of radioactive noble gases may be assumed to be Xenon-133 as found in Reg Guide 1.97.

2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS - 10 CFR 20 2.3.1 SITE BOUNDARY DOSE RATE - NOBLE GASES CONTROL 3.1 1.2.1a limits the dose rate at the SITE BOUNDARY due to noble gas releases to < 500 mrem/yr, total body and < 3000 mrem/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station results in an alarm setpoint (as determined in Section 2.2) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed.

K:\occhem\SOOproc 70.0

2.3.1.1 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:

DG=zQiP6i From a ground-level release (building vent) the total body dose equivalent rate is:

DG; X DG=-~QiP7Vi Qg Qv 1 where:

DG = total body dose equivalent rate due to irradiation by radioactive noble gas (mrem/hr)

Qi average discharge rate of noble gas radionuclide i released during the averaging time (ptCi/hr) . .1 PyVi factor converting time integrated ground-level concentration of noble gas nuclide mrm 3 ito total body dos mrem - m See Table A-2.

pCi - sec QX _ atmospheric dispersion factor from the OCGS to 'the offsite location of interest (sec/i 3 )

from Table 2.3.1.3-1 PySi factor converting unit noble gas nuclide i stack release to total body dose at ground level received outdoors from the overhead plume (mrem/ICi). See Table A-2 The noble gas plume gamma-to-total body dose factors, PySi 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, PySi, are derived from Reg Guide 1.109, Revision l, Table B-i, Column 5.'

2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE Calculate the dose from a release of 100 Ci of Xel 33 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release DG DG =- X QiP YVi

,.,; Qv , -

X/Qv = 4.17E-5 sec/m3 (Table 2.3.1.3-1)

Qi - = 1E8 plCi/hr [lOOCi*1E6 pCi/Ci]

PyVi = 9.33E-6 mrem-m 3 / pCi-hr -

DG =4.17E -5Z E8*9.33E -6 DG - 0.039mnrenI hr/

K:\occhem\800proc 71.0

2.3.1.3 SKIN DOSE RATE The dose equivalent rate to skin from radioactive noble gases is calculated by assuming 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:

DB DB =- x Qi(SBi+1.IIAyVi) where:

DI3 = dose rate to skin from radioactive noble gases (mremlhr)

- = atmospheric dispersions from gaseous effluent discharge point to ground-level location of interest (sec/mr3 ) from Table 2.3.1.3-1.

Qi = discharge rate of noble gas radionuclide i (gtCi/hr)

SBi = factor converting time integrated ground-level concentration of noble gas radionuclide i to skin dose from beta radiation mrem - m3 from Table A-2.

jiCi

sec AyVi = factor for converting time integrated, semi-infinite concentration of noble gas radionuclide i to air dose from its gammna mrad - m from Table A-2.

goci

sec The noble gas beta radiation-to-skin-dose factors, SBi and the noble gas gamma-to-air dose factors, A7Vj, are derived from Reg Guide 1.109, Revision 1, Table B-I, columns 3 and 4 respectively. A tabulation of these factors used to compute noble gas-to-dose equivalent rate at 522 meters SE of the OCGS is in Table A-2.

The dose equivalent rate is calculated with the meteorological dispersion data given in Table 2.3.1.3-1.

TABLE 2.3.1.3-1 RECEPTOR LOCATIONS AND DISPERSION FOR SITE BOUNDARY DOSE RATES 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") that implements the requirements of Regulatory Guide 1.109 may be used.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented above may be used for evaluating the gaseous effluent dose rate.

K:\occhcm\800proc 72.0

2.3.1.4 EXAMPLE SKIN DOSE RATE ' im no .:

Calculate the skin dose from a release of 100 Ci of Xel33 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release:

DB = Z3Qi(SBi +l.llArVi)

QIZ X/Q =4.17E-5sec/m3 , ;-;-

'Qi = 1E8 Ci/hr ;.-

SBi = 9.7 1E-6 i' , -

A~yVi =1.12E-5 DB = 4.1 7E - 5Z IE8(9.7 1E-6 + 1. 1*1.1 2E -5)

DB= 0.092mrad/ hr 2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES 2.3.2.1 METHOD - SITE BOUNDARY DOSE RATE - RADIQIODINE 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 in CONTROL 3.11.2.1b.. Evaluation of compliance with CONTROL 3.11.2.lb is based on the sampling'gand analyses'specified in TABLE 4.11.2.1.2-1. Since the dose rate cannot be resolved within less than the sample integration or compositing time,'the contribiition'of each radionuclide to the calculated dose rate will be averaged no more than 3 months for H-3, Sr-89, Sr-90, and alpha-emitting radionuclides and no more than 31 days for other radionuclides' These are their usual sample integration'or coipositing times. The equation used to assess compliance of radioiodine, tritium, and radioactive particulate releases with the dose rate limit is:

n>r DRp =1E6Z, E RaDFAijaQe i Qe where: 3 .; -'

IE6 = conversion pCi/4Ci DR = the average dose rate to an organ via exposure pathway, p (mrem/yr).

p p Y DFAija= inhalation dose factors due to intake of radionuclide i, to organ j age group a (mrem/pCi) from Reg. Guide 1.109 Appendix E. ' ,

Ra - age group ent inhalation respiratory rate (usage 'factor) matyr from Table B-i

' ; : ! _ . ' '33

1 .- .. . - .U . : .

-__ = annual average relative airborne concentration at an offsite location due to a release from Qe either the Stack or a vent, i.e. releasepoint,"'e (sec/m3 ) from Table 2.3.2.'1-1.

ei ' = release'rate of radionuclide i fron'rel pbint,'e during the period of interest (p.Ci/sec).

pbse K:\occhem\800proc :73.0

--- -1 .

For real-time meteorology and on an annual average basis, 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 CONTROL 3.11.2.1 b for tritium, iodine, and particulate, the air dispersion (X/Q) values are provided in Table 2.3.2.1-1.

TABLE 2.3.2.1-1 LOCATION OF MNI MXIMUNI EXPOSURE RLAI'E BY INHALATION Discharge Point Receptor Location Atm. Dispersion Sector Distance (m) (sec/mY)

Ground Level or Vent SE 522 4.17 E-5 Stack SE 522 6.04 E-9 Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closest hypothetical individual (Table A-6) located at:

Stack SE 966m 3.42 E-8 Alternatively, an approved computer code (e.g., "SEEDS") that implements the methods of Regulatory Guide 1.109, may be used.

2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATION Calculate the child thyroid dose rate from a release of 100 ACi/hr of 1131 from a ground level release:

n v DRp = IE6Z Z RaDFA ijaQeiQ e Qe Ra =3700 m 3/yr DFAija= 4.39E-3 Qei = 0.028 pCi/sec [I OOpCi/hr /3600 sec/hr = 0.02778]

X/Qe = 4.17E-5 sec /m3 DRp =1 E6Z 3700

4.39E - 3

0.028

4.1 7E -5 DRp = 19inrem / yr 2.4 NOBLE GAS EFFLUENT DOSE CALCULATIONS - 10 CFR 50 Doses resulting from the release of noble gases must be calculated to show compliance with Appendix I of IOCFR50. Calculations will be performed at least monthly for all gaseous effluents as stated in SURVEILLANCE REQUIREMENT 4.11.2.2 to verify that the dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.

2.4.1 UNRESTRICTED AREA DOSE - NOBLE GASES CONTROL 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly air dose limits shown in Table 2.4.1 -1.

K:\occhem\800proc 74.0

TABLE 2.4.1-1 ANNUAL AIR DOSE LIMITS During any calendar quarter ! ': During any calendar vear

< 5 mradgamma-air.- - -<10mradgaminma-air

< 10 mrad beta-air '20 mrad beta-air 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 CONTROL 3.11.2.2 for air dose offsite due to gamma and beta radiations from effluent n6ble gas.

2.4.1.1 AIRDOSEMETHOD:

a: For Gamma Radiation:

Dose y = A P '-vQvi + A 7SiQsi

- =1 .. 9 b: For Beta Radiation DoseI =>L. 3A/i-eQei e i=1 Q where:

Dose -y=the gamma dose during any specified time period (mrem).

Dose P=the beta dose'during any specified time'period (mrad).

AyVi = the air dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per jCi/m3 ). Table A-2 AzyS = the factor for air dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per giCi), Table A-3.;

Ai= the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per pCi/m3 ). Table A-3 Xor =the

- annual average relative concentration for areas at or beyond the site boundary for Q -

releases from either the Stack or ground vent at the critical location (sec/m3 ), Table 2.4.1.1-1 Qvi = amount of radionuclide i released from vents '(Ci).

Qsi = amount of radionuclide i released from the Stack (jiCi).

K:\occhem\800proc 75.0

Qei = amount of radionuclide i released from release point e([uCi).

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. The maximum offsite gamma radiation dose rate to air from noble gases discharged from either the stack or from building vents occurs at 522 meters SE of the OCGS.

Values of AySi 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. A7Vi and ABi are derived from Reg. Guide 1.109, Table B- I for a semi-infinite cloud, independent of meteorology or location. Values of AySi, AyVi and ABi used to calculate the noble gas radiation dose to air at 522 meters SE of the OCGS are in Table A-3. Reference atmospheric dispersion from the OCGS to 522 meters SE is given in Table 2.4.1.1-1.

TABLE 2.4.1.1-1 RECEPTOR LOCATIONS AND DISPERSION FOR AIR DOSE 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") that implements the requirements of Reg. Guide 1.109 may be used.

2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION Calculate the gamma air dose from a release of I Ci per hour of Xe 133 for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release and I0OCi per hour for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from an elevated release:

it Dosey = A, yVi-vQvi + A ySiQsi 11 Q AyVi = 1.12E-5 mrad - m 3 /tCi - sec X/Q = 4.17E-5 sec /m3 Qvi = IE7 pCi [ICi/hr*lOhrs*IE6 pCi/Cil AySi = 5.45E-13 mrad / pCi Qsi = IE9 pCi [I0OCi/hr* IOhrs* IE6 gCi/Ciu Dosey=Z1.12E-5 *4.17E-5*1E7+5.45E-13*1E9 i=I n

Doser=Z4.67E-3+5.45E-4 j=I Dosey = 5.2 E-3mrad Note how the ground level portion has a higher dose contribution per unit activity than the elevated portion.

K:\occhem'800proc 76.0

2.4.1.3 INDIVIDUAL PLUME DOSE METHOD The method for dose to an individual from noble gases is essentially identical with the air dose method except that different dose factors apply.- Also, since dose to the skin combines the.

contribution from gamma and beta emissions, the gamma dose mu-st be added to the beta dose to obtain a total skin dose.

~~ ~~.-., . hi .,......

a: - ForTotal Body:

Dost= P2'V-vQvi+P Doset= 2SiQsi Lis b: For Skin Doses = A-, S,/i-eQei + Doset where: - - '

Doset = the total body dose during any specified time period (mrem).

Doses = the skin dose during any specified time period (mrad).

PyV; = the plume dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per pCi/m 3 ). Table A-5 PyS = the factor for plume dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per gCi), Table A-5.

S,-= the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per pCi/m 3 ) from Table A-5.

X X or -v X = the annual average relative concentration for areas at or beyond the site boundary for Q

releases from either the Stack or ground vent at the critical location (sec/m 3 ) from Table 2.5.1. . i; Qvi ='amount of radionuclide i released from. ve.nts (Ci Qi= amount of radionuclide i released from thenStack (pCi).

Qei = amount of radionuclide i released from release point e (pCi).

K:\occhem\800proc 7*

~.77.0

II-2.5 RADIOIODINE, PARTICULATE AND OTHER RADIONUCLIDES DOSE CALCULATIONS

- 10 CFR 50 Doses resulting from the release of radioiodines 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 SURVEILLANCE REQUIREMENT 4.11.2.2 and SURVEILLANCE REQUIREMENT 4.11.2.3 to verify that the dose to air is kept below the limits specified in CONTROL 3.11.2.2 and the dose to MEMBERS OF THE PUBLIC is maintained below the limits specified in CONTROL 3.11.2.3.

The maximum dose to an individual from radioiodines, tritium, and radioactive particulates with half-lives of greater than eight days in gaseous effluents released to unrestricted areas is determined as described in Reg. Guide 1.109. Environmental pathways that radioiodine, tritium, and particulates in airborne effluent follow to the maximally exposed MEMBER OF TIHE PUBLIC as determined by 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 exposure pathway during November through March. To assess compliance with CONTROL 3.11.2.3, the dose due to radioactive iodine, tritium, and particulates in airborne effluent is calculated to a person residing 966 meters SE of the OCGS. Reference atmospheric dispersion and deposition factors are given in Table 2.5-1.

TABLE 2.5-1 DISPERSION FOR 10CFR50 DOSES Discharge Point Dispersion Deposition XIQ (sec/mi3 ) D/0(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: inhalation, irradiation from ground deposition, and ingestion of milk (cow and goat are treated separately), meat, and vegetables. Eight organs are considered: Bone, Liver, Total Body, Thyroid, Kidney, Lung, GI-LLI (Gastro-Intestinal tract / Lower Large Intestine), and Skin. Four different age groups are considered: Infants, Children, Teens, and Adults. Doses are calculated to a 'receptor' - a person who inhales the airborne activity and resides in a location with ground deposition, and eats and drinks the foodstuffs produced. The maximally exposed individual is conservatively assumed to reside at the location of the highest sum of the inhalation and ground plane doses, while eating and drinking foodstuffs transported from the locations that are highest for those pathways. Receptor locations are provided in Table A-4.

Alternatively, an approved computer code (e.g., "SEEDS") that implements the requirements of Reg Guide 1.109 may be used.

K:"occhem\OOproc 78.0

2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES : , ,

Dose from the inhalation pathway is generally in the form:

Dja-= RaT->9QiDF4ijaExp(-AiTr)

Where:

Dja = the dose to the organj (of eight) 'of age' grou'p a '(of four)

Ra = the respiration rate for age group a from Table B-i T = the duration of the release in fraction of a year X = The atmospheric dispersion to the point of interest (the 'receptor') in sec/M3 from Table 2.5-1

- ,Q ,

Qi = The release rate of radionuclide i (pCi/sec)

DFAija= The inhalation dose conversion factor (mrem per pCi) for radionuclide ito organj of age group a fromReg. Guide 1.109 Appendix E.'

Xi = 'decay constant of isotope i: 0.693/ Half life in years Tr plume transit time from release to receptor in years Xi and Tr may be in any time units as long as they are the same Note that a 'depleted X/Q' (dQ)is applicableto particulates only, which accounts for the natural settling and lack of surface reflection of particulates to estimate the downwind concentration accounting for these removal processes. Depleted X/Q will be slightly smaller than the X/Q. This, is, not used 'in the ODCM for simplicity. Using'the:X/Q is therefore slightly conservative compared to the dX/Q.

K:\occhem\800proc - -79.0

2.5.2 EXAMPLE CALCULATION - INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTIIER RADIONUCLIDES Calculate the dose to child lung from inhalation from a ground level release of 100 jiCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-XiTr)=I).

DjaX Dja = RaTZ -QiDFA Ua Dja = the dose to the organ j (of eight) of age group a (of four)

Ra = 3700 m 3 /yr T = 0.001 14 yrs [10 hrs / 8760 hrs /yr]

X = 1.53 E-5 sec/in 3 Q

Qi = 2.78E3 pCi/sec [100 tlCi

IE6 pCi/tCi / (10 hrs*3600 sec / hr)]

DFAija=1.91E-3 rnrem / pCi Dja=3700*0.001 14*1.53E -5*2.78E3*l.91E - 3 Dja = 3.4E - 4mrein 2.5.3 INGESTION OF RADIOTODINES, PARTICULATES AND OTHER RADIONUCLIDES Dose from the ingestion pathways is more complex and is broken out here into multiple steps:

2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHIER THAN TRITIUM The concentration of a radionuclide in a foodstuff (other than tritium - see section 2.5.3.3 for tritium) is dependent on the atmospheric deposition, the biological uptake into the food, various decay times (plume travel, harvest to table, etc.) and is generally of the form:

D .r(1 - EXP(-2EiTe)) Biv(1 - EXP(-AiTb))]

Civ = QY2Ei+ 1 EXP(-2dTh)EXP(-2iTr)

Where:

Civ = the concentration (pCi/kg) of radionuclide i in vegetation Qi = the release rate of isotope i in pCi/hr D2

- = The atmospheric deposition to the point of interest (the 'receptor') in I/m2 from Table 2.5-1.

r = the retention coefficient for deposition onto vegetation surfaces (1.0 for iodines, 0.2 for particulates) xi = the decay constant of radionuclide i; 0.693/half life in hours K:\occhem\800proc 80.0

XEi = the effective removal constant which is the sum of Xi + Xw where Xw is the weathering constant, 0.0021/hr Te = duration of crop exposure during the growing season in hours. This is not the entire duration of the growing season, and is different 'for leafy vegetable and fruit/grain/vegetables. Provided in Table E-15 of Reg. Guide 1.109'or'Table B-1.

Yv = agricultural yield Kg of vegetation per m2 , typically 0.7 kg/M2 Biv soil uptake concentration factor for transfer of the radionuclide i from the soil to the vegetation through normal root uptake processes in pCi/kg in vegetation per pCi/Kg in soil. Values are provided in Reg. Guide 1.109 Table E-1.'

Th = the length of time the soil is exposed to 'cntaminated inputs - nominally 15 years (131000hr)

P = effective soil density'in kg/rm 2 normnally 240 kg/rm2 Th = holdup time, the time the foodstuff is in trahsit between harvest and consumption in hours Tr = plume tra'nsit tim'e from release to receptor in hours 2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION - OTHER THAN TRITIUM Calculate the forage and vegetation concentration from a ground level release of 100 pCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (plume transit time is'ignored Tr=0, EXP(-XiTr)=l):

Civ = Qi{r(1-EXP(-AEiTe)) Bi-v - EXP(-AiTh))}ExP(ITh)ExP(./iT)

D/Q = 1.7E-8 /m2 Qi = 1E7 pCi/hr[IOOgCi 1E6 pCi/Ci/ 10 hr]

r = 0.2 Xi = 1.5E-S/hr [0.693 / (5.27yr

8760 hr/yr)] .

XEi = 2.1E-3 /hr [1.5E-5 + 0.0021]

Te = 720 hr [grass-cow-milk-manpathwayvalue].

Yv = 0.7 kg/m Biv = 9.4E-3 Tb -131000 .. ;.

P =240 kg/m2 ,

Th - 'hr (consumption of pasture grass directiy byanimals) 0.2*(1-EXP(-2.1E-3*720)) +

Civ = 1.7E - 8*1E7 .7*2.1E3EXP(-1.5E - 5 0) 9.4E - 3 * (I - EXP(-1 .5E - 5

13 1000))

240*1.5E-5 K-\occhem\800proc ~'.81.0

U1 F0.2 * (1- EXP(-1 .52)) +

Civ = 1.7E -8* lE7 1.47E-3 }EXP(-O) 9.4E - 3 *(I - EXP(- 1.965))

3.6E-3 Civ = 1.7 E -1I{ }*1 2.245 Civ = 18.4 pCi / Kg 2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION Since tritium is assumed to be released as tritiated water ([ITO), the concentration of tritium in a foodstuff is dependent on atmospheric dispersion like a gas, rather than particulate deposition as for other radionuclides for foodstuff uptake. Further, the concentration of tritium in food is assumed to be based on equilibrium between the concentration of the tritium in the atmospheric water and the concentration of tritium in the water in the food. Concentration of tritium in vegetation can be calculated generally in the form (a plume transit decay term: EXP(-XiTr) is ignored since plume travel times are very short compared to the half life):

Ctv = I0Qt X

0.75

0.5 Q H Where:

Ctv = the concentration (pCi/kg) of tritium in vegetation 1000 = gm per kg Qt = the release rate of the tritium in pCi/ sec X/Q = the atmospheric dispersion at the vegetation point, sec/M 3 from Table 2.5-1 0.75 = the fraction of vegetation that is water 0.5 = the effective ratio between the atmospheric water concentration and the vegetation concentration

[1 = the absolute humidity gm / m3 . Absolute humidity is seasonally dependent, varying from as little as I in the winter to as much as 20 in the summer. Monthly average values derived from historical data are provided in Table B-2.

K:\occhem\SOOproc 82.0

2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION Calculate the forage and vegetation concentration from a ground level release of 100 pCi of H-3 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time'is ignored (exp(-kiTr)=l):

-'~ X 0.5 Ctv =lOOOQt-* 0.75 *-

16Q H Qt = 2778 pCi/sec [lOuCi I E6 pCi/uCi / (l0hrs*3600sec/hr)]

X/Q = 1.53E-5 sec/r 3 H = 5 gm/M3 (assumed for this example)

Ctv -2778 *1000 *-1.53E -5

0.75

5 5

iCtv=3.2pCi/kg 2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT Meat and milk animals are assumed to eat both pasture grass and stored feed. During a fraction of the year, they may be assumed to be exclusively on stored feed, outside of the growing season. If using annual average release, the fraction of stored and fresh feed must be accounted for with fractions, otherwise (as in this ODCM), the fresh pasture pathway is turned on or off depending

'on the growing season.

The concentration of a radionuclide in the animal feed is calculated as follows:

Civ = FpCis+ (1- Fp)Cis(I- Fs) + CipFs(I- Fp)

Where: - -- -

Fp = the growing season pasture factor: 1 if not growing season, 0 if in growing season Fs = the fraction of the daily feed from fresh pasture from Table B-I or Exhibit E-15 from Reg.

Guide 1.109.

Cip' = the concentration in the fre'sh pasture feed (Civ from'section 2.5.3.2 with Th - 0 for immediate consumption) - ii:i.'> ! . .

Cis = the concentration in stored feed (Civ from section'2.5.3.2 with Th -90 days)

The concentration in the milk is then based on this feed concentration:

Cim FmCivQJEXP(-P )

Where; Cim = the concentration in milk pCi/l Fm = the transfer coefficient of intake to concentration in the milk (d/l) from Reg. Guide 1.109 Table E-1.

Qf = feed intake rate Kg/d from Reg. Guide 1.109 Table E-3.

pr. ,: 83.0

,,cce.m-.. ..

KC.occhem\800proc ' 83.0

Ul-ki = radionuclide i decay constant in I/days Tf = transport time from milk production to consumption (2 days for milk)

The Goat milk pathway may be similarly evaluated:

Cirn = FgCivQJEXP (-AiTf)

Where Fg = the transfer coefficient of intake to concentration in the milk (dII) for goats from Reg. Guide 1.109 Table E-2.

And for meat:

Cif = FfCivQJEXP(-AiTs)

Where:

Ff = the transfer coefficient of intake to concentration in the meat d/kg from Reg. Guide 1.109 Table E-l.

Ts = The transport time from slaughter to consumption (20 days) 2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT Calculate the concentration in cow milk from a ground level release of 100 jICi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-XiTr)=1):

Civ = FpCis+ (I - Fp)Cis(l- Fs)+ CipFs(I- Fp) assume animals are on pasture and receive half of their food from stored feed.

Cip = 18.4 pCi/kg as previously calculated in section 2.5.3.2 Fp =0 Fs = 0.5 Cis is calculated by applying a 90 day decay term to the Cip value previously calculated, since the previous decay correction was for 0 time as shown in 2.5.3.2.

Cis = 18.4 * (exp(-0. 693

90 /(5.27

365.25)))

Cis = 17.8 pCi/kg Civ is then:

Civ = 0*17.8+ (1- 0.5)17.8 * (1 -0) +18.4 *.5* (1 -0)

Civ= 18. IpCi/ kg The concentration in milk is given by:

Cin = FonCivQfEXP(-AiTf)

Fm =I.OE-3 d/l Qf = 50 Kg/d Li = 3.6E-4/d [0.693 / (5.27yrs*365.25days/yr)]

K:\occhem\800proc 84.0

Cirn=1.OE-3*18.1*50*EXP(-3.6E-4*2)

Cim='O.9OpCi/l The concentration in meat given by:

Cf = FfCivQJEXP(-2iTf)

Ff =1.3E-2 d/kg' Qf =50Kg/d Xi = 3.6E-4/d COf= 1.3E -2

18.1

50*EX (-3.6E -. 4* 20)

COf =11.7pCilkg 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES The environmental pathway ingestion dos is'thesum of the milk; meat, and vegetation ingestion pathways. There are two separate patliways'foi'vegetation: 'fresh leafy vegetables and a combination of fruits, non-leafy vegetables, and grains. These differ only in the decay and buildup processes applied to account for the environmental exposure, and transportation delay decay represented by Te and Th as shown in section 2.5.3.1.'For long half-life isotopes (e.g. Co-60) the decay differences have little impact on the dose.

Dose from the environmental ingestion pathways is generally of the form:

Dja = TZ DFIifa[UavFgCiv+Uam Cin + UafCif + UalFlCil]

Where:

Dja = the dose to organ j of age group a - mrem T = fraction of year of release duration DFIija = the ingestion dose factor for isotope i to organ j for age group a - mremlpCi from Reg. Guide 1.109AppendixE. '

Uav = Ingestion rate (usage factor) for non-leafy vegetables, grains, and fruits for age group a from Reg. Guide 1.109 Table E-5 or'Tabl6 B `' '

Fg the fraction of vegetables, grains, and fruits from' the location' of interest: 0.76 in Reg. Guide 1.109.

Civ the concentration of isotope i in the vegetables, fruits, and grains calculated from section 2.5.3.2. 8-; * ; o a;*

Uam =Ingestion rate (usage factor) for milk for age group a: from Table B-1 or Reg. Guide 1.109 Table E-5.

Cim = the concentration of isotope i in milk calculated from section 2.5.3.5.

K:\occhem\S800proc ' -e85.0

1i Uaf = the ingestion rate for meat for age group a: from Table B- I or Reg. Guide 1.109 Table E-5.

Cif = the concentration of isotope i in meat calculated from section 2.5.3.2.

Ual = the ingestion rate for leafy vegetables for age group a: from Table B- I or Reg. Guide 1.109 Table E-5.

Fl = the fraction of annual leafy vegetable ingestion from the location of interest: 1.0 in Reg.

Guide 1.109.

CiH = concentration of isotope i in the leafy vegetables for direct human consumption: Civ calculated from section 2.5.3.2 with Th=0.

2.5.3.8 EXAMPLE CALCULATION - DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES Calculate the ingestion dose to child whole body from a ground level release of 100 jiCi of Co-60 in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Plume transit decay time is ignored (exp(-XiTr)=1):

Dja = TY DFHja[UavFgCiv+Uamn Cirn+ UafCif+ UalFlCiI]

T = .00114 [IOhrs /8760 hrs/yr)

DFIija = 1.56E-5 mrem/pCi Uav = 520 Fg = 0.76 Civ = 18.0 [1 8.4*EXP(-X*60) using 60 day delay for ingestion]

Uam = 330 Cim = 0.9 Uaf =41 Cif = 11.7 Ual = 26 Fl = I CiH = 18.4 Dja=.001 14E1.56E-5[520*0.76*18+330*0.9+41*1 1.7+26*1*18.4]

Dja =.001 14Zl.56E-5[71 14+297+480+478]

Dja = 1.5E - 4nmrem: child: wvholebody 2.5.4 GROUND PLANE DEPOSITION IRRADIATION Dose from ground plane deposition is estimated by determining the surface activity resulting from the release.

K:\occhem\800proc 86.0

2.5.4.1 GROUND PLANE CONCENTRATION The ground surface activity is estimated as: -.

Cig DQi 0 -- (Q A (1-EXP(-AiTh))

Where:

Cig = ground plane concentration of radionuclide i in pCi/m2 D = local atmospheric release deposition factor in /rM2 from Table 2.5-1 Qi = release rate in pCi/sec Xi = radiological decay constant in 1/sec -

Th long term buildup time typically 15 years (4.7E8 sec)

Note: Qi, Xi and Tb can utilize any time units as long as they are all the same 2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATION Calculate the ground plane concentration from a 100 p.Ci release of Co-60 over 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release point. -

Cig = - (I -EXP(-Ai T))

QA

- =1.7E-8/m 2 Q

Qi = 2778 pCi/sec [100I Ci/1 Ohrs/3600sec/hr]

Xi = 4.1 7E-9/sec [0.693/(5.27yr*8760hr/yr*3 600sec/hr)]

Tb = 4.7E8 sec Cig =1.7E-8 2778 (1I-EXP(-4.17E-9*4.7E8))

4.17E-9 2778 Cig =1.7E-8 (I EXP(-4.17E-9*4.7E8))

-'4.17E-79.

-. Cg = 9729pCi/m2 K:\occhem\800proc 87.0

2.5.4.3 GROUND PLANE DOSE Annual (lose from the ground plane deposition is of the fonn:

Djg = 8760

T

Sf CigDFGij Where:

Djg = the annual dose (mrem) from ground plane pathway (g) to the total body or skin ()

8760 = hours in a year T = fraction of year release is in progress Sf = shielding factor accounting for shielding from dwelling from Table B-I DFGij = Ground plane dose factor for skin or total body (I) for radionuclide i from Table E-6 of Reg.

Guide 1.109 in mrem/hr / pCi/m 2 .

2.5.4.4 EXAMPLE GROUND PLANE DOSE Calculate the ground plane Total Body dose from a 100 pCi release of Co-60 over 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release point.

Given: Djg = 8760

T

Sf E CgDFGU T = 0.00114 [10/8760]

Sf = 0.7 DFGij = 1.7E-8 Djg = 8760 *0.001 14 *0.7Z 9729

1.7E - 8 Djg = 1.15E - 3 nirentTotalBocly 3.0 TOTAL DOSE TO IMIEMNIBERS OF TIHE PUBLIC - 40 CFR 190 The Radiological Environmental Monitoring Report (REMP) submitted by May Ist of each year shall include an assessment of the radiation dose to the likely most exposed MEMBER OF THlE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contributions from effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Oyster Creek, the sources of exposure need only consider the Oyster Creek Generating Station. No other fuel cycle facilities would contribute significantly to the MEMBER OF THE PUBLIC dose for the Oyster Creek vicinity, however, both plant operation and ISFSI sources must be included in the dose assessment.

To assess compliance with CONTROL 3.11.4, calculated organ and total body doses from effluents from liquid pathways and atmospheric releases as well as any dose from direct radiation will be summed.

K:\occhcm\800proc 88.0

As appropriate for demonstraiting/evaluating compliance with'the limits of CONTROL 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radiation and / or radioactive material and resultant dose to the MEMBER OF THE PUBLIC in the actual pathways of exposure.

3.1 EFFLUENT DOSE CALCULATIONS For purposes of implementing the surveillance requirements of CONTROL 3/4.11.4 and the reporting requirements of Technical Specification 6.9.1 .d (RERR), dose calculations for the Oyster Creek Generating Station may be performed using the calculation methods contained within the ODCM; the conservative controlling pathways and locations from the ODCM or the actual pathways and locations as identified by the land use census (CONTROL 3/4.12.1) maybe used. -Average annual meteorological dispersion parameters provided herein or meteorological conditions concurrent with the release period under evaluation may be used.

3.2 DIRECT EXPOSURE DOSE DETERMINATION Any potentially significant direct exposure contribution to off-site individual doses may be evaluated based on the results of environmental measurements (e.g., TLD) and/or by the use of radiation transport and shielding calculation methodologies.

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of CONTROL 3.12.1. The objectives of the program are:

- To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Oyster Creek

- To determine if the operation of the Oyster Creek Generating Station has resulted in any increase in the inventory of long lived radionuclides in the environment;

- To detect any changes in the ambient gamma radiation levels; and

- To verify that OCGS operations have no detrimental effects on the health and safety of the public or on the environment.

The REMP sample locations are presented in Appendix E.

NOTE: No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid effluents discharged from Oyster Creek Generating Station.

K:\occhem\800proc :89.0

- - t APPENDIX A - DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS K:'occhcm.800proc 90.0

l Table A-l Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-to-Dose Equivalent Rate Factors*

Radionuclide , Factor DFSi for Factor DFVi for Stack Release* Ground-level or Split-Wake Release**

mrem-sec mrem-m3 Ci-year-- , pCi-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 Kr88 - 1;18E:03 1.47E+04 Kr89 1.17E-03' 1.66E+04 Kr9O - I ' '- 1.56E+04 Xel31m 2.1OE-05' 9.15E+01 Xel33m 1,.64E 2.51E+02 Xel33 1.57E-05 2.94E+02 Xel35m 2;77E1-04 3.12E+03 Xel35 ' - 1;51 E-04 - -.. 1.81E+03 Xel37 1.06E-04' 1.42E+03 Xel38 7.63E-04 8.83E+03 Xel39 1.44E-04' 5.02E+03 Ar441 9.1 lE-04 8.84E+03 .

Based on reference meteorology applicable at 522 meters SE of stack. '- I-

- For exposure to a semi-infinite cloud of h6ble gas. It ' ' -* . '

K:\occhem\800proc .".91.0 9O

- U

'rable A-2 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors* I Radionuclidle 1',tSi** PYvi*** A7Vi** SBi***

mremn mrem-mn3 mrad-nlll mrem-m 3 Pci gCi-sec glCi-sec PlCi-sec Kr83m 4.66E-17 2.40E-09 6.13E-07 -

Kr85m 2.9113-12 3.71 E-05 3.90E-05 4.63E-05 Kr85 4.66E-14 5.1 1E-07 5.4613-07 4.25E-05 Kr87 1.5213-11 1.88E-04 1.96E-04 3.09E-04 Kr88 3.73 E-11 4.67E-04 4.83E-04 7.52E-05 Kr89 3.7013-11 5.27E-04 5.49E-04 3.21 E-04 Kr9O - 4.9513-04 5.17E-04 2.31 E-04 Xel3ln 6.65E-13 2.90E-06 4.95E-06 1.51 E-05 Xel33m 5.20E-13 7.97E-06 1.04E-05 3.1613-05 Xe133 4.97E- 13 9.33E-06 1.12E-05 9.71 E-06 Xel35m 8.78E-12 9.90E-05 1.07E-04 2.2613-05 Xel35 4.78E-12 5.75E-05 6.1OE-05 5.90E-05 Xe137 3.36E-12 4.51 E-05 4.79E-05 3.87E-04 Xe138 2.42E- 11 2.8013-04 2.92E-04 1.31 E-04 Xel39 4.5613-12 Ar41 2.891E-11 2.811E-04 2.95E-04 8.54E-05

All of these dose factors apply out-of-doors.

- Based on reference meteorology at 522 meters SE of effluent stack.

- - Derived from Reg Guide 1.109, Revision 1, Table B-i.

K:\occhem\,00proc 92.0

Table A-3 Air Dose Conversion Factors for Effluent Noble Gas Radionuclide AySi** AyVi*** Api***

mrad . mrad-m3 mrad-m3 -.

I - ptCi pCi-sec gCi-sec

-.. 3E0 .1E0 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 Kr87 1.60E-11I 1.96E-04 3.27E-04 Kr88 3.93E-11I 4.83E-04 9.30E-05 Kr89 3.90E-1 I 5.49E-04 3.37E-04 Kr9O 5.17E-04 2.49E-04 Xel3 lr m 7.26E-13 4.95E-06 3.52E-05 Xel33r n : ' 5.86E-13, 1.04E-05 4.70E-05 Xe133 5.45E-13 1.12E-05 3.33E-05 Xel35r m 9.32E-12 1.07E-04 2.35E-05 Xe135 6.18E-12 6.1OE--

7.81IE-05 Xel37

3.55E-12 4.79E-05, .4.03E-04 Xel38 -. -. . ). -2.54E-11 2.92E-04 -1.51E-04' Xel39 - --4.82E-12 Ar41 3.03E-1 I 2.95E-04 1.04E-04

- Based on reference meteorology at 522 meters SE of effluent stack.

- - Derived from Reg Guide 1.109, Revision 1, Table B-1.

K:\occhem\800proc *-, 93.0

U-Table A4 Locations Associated with Maximum Exposure of a Member of the Public*

Effluent Location Distance Direction (meters) (to)

Liquid U.S. Route 9 Bridge at Discharge Canal Airborne Iodine and Particulates 966 SE Tritium 966 SE Noble Gases 966 SE Irradiation by OCGS Site Boundary All Noble Gas g Air Dose Site Boundary All Noble Gas B Air Dose 966 SE 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 OCGS. The most exposed member of the public is assumed to be exposed by irradiation from the OCGS, 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.

The age group of the most exposed member of the public is based on Reg. Guide 1.109, Revision 1.

K:\occhcm\800proc Page 94

Table A-5 Critical Receptor Noble Gas Dose Conversion Factors*

Radionuclide PYSi** PYVi*** AyVi*** AySi** SBi***

- mrem mrem-m3 mrad-m3 mrad mrem-m3 ACi [iCi-sec piCi-sec pCi pCi-sec Kr83m 3.76E-17 2.40E-09 6.13E-07 9.66E-15 Kr85m 1.6813-12 -3.71E1 05, . .3.90E-05 1.75E-12 4.63E-05 Kr85 2.60E-14 5.111E-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-04 Kr88 2.08E-1 1 4.67E-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 Kr9O 4.95E-04 5.17E-04 2.3 1E-04 Xel31m 3.99E-13 2.90E-06 4.95E-06 4.44E-13 1.51E-05 Xel33m 3.1OE-13 7.97E-06 1.04E-05 3.58E-13 3.16E-05 Xel33 3.1 lE-13 9.33E-06 1.12E-05 3.42E-13 9.71E-06 Xel35m 4.71E-12 9.90E-05 1.07E-04 5.01E-12 2.26E-05 Xel35 2.73E-12 5.75E-05 6. 1 OE-05 2.87E-12 5.90E-05 Xel37 1.65E-12 4.5 lE-05 4.79E-05 1.75E-12 3.87E-04 Xel38 1.33E-1 1 2.80E-04 2.92E-04 1.40E-1 1 1E-04 1.3 Xe139 1.61E-12 Ar4l 1.58E-1 1 2.81E-04 2.95E-04 2.9513-04 1.66E-l 1.6613-11I 8.54E-05 8.5413-05

Al l of these dose factors appiy out-of-doors.

- Based on reference meteorology at 522 meters SE of effluent stack.

Derived from Reg Guide 1.109, Revision 1, Table B-I IK:\occhem\800proc - Page 95

-- - Il APPENDIX B - MODELING PARAMETERS K:\occhern\800proc Page 96

Table B OCGS 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/mr) 2 2.4E+2 Fraction Of Deposited Activity Retained On Vegetation 2.5E-1 Shielding Factor For Residential Structures 7.0E-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) 2.166E+3 Delay Time For Ingestion Of Leafy Vegetables By Man (hr) 2.4E1+1 Delay Time For Ingestion Of Other Vegetables By Man (hr) 1.44E+3 Transport Time Milk-Man (hr) 4.8E+1 Time Between Slaughter and Consumption of Meat Animal (hr) 4.8E+2 Grass Yield Wet Weight (Kg/mr) 2 7.0E-I 2

Other Vegetation Yield Wet-Weight (Kg/mr) 2.0 Weathering Rate Constant For Activity on Veg. (hr ) 2.11E-3 Milk Cow Feed Consumption Rate (Kg/day) 5.0E+1 Goat Feed Consumption Rate (Kg/day) 6.0 Beef Cattle Feed Consumption Rate (Kg/day) 5.0E+1 Milk Cow Water Consumption Rate (Iiday) ;6.0E+I Goat Water Consumption Rate (L/day) .8.0 Beef Cattle Water Consumption Rate (Iiday) 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 Shore Exposure (hr) 0 Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1 K:\occhem\800proc "!, 4. Pg997 Page

Table B- I (Continued)

OCGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Water Ingestion (L/yr)

a. Adult 7.3 E+2

b. Teen 5.1 E+2

c. Child 5. 1E+2

d. Infant 3.3E+2 Shore Exposure (hr/yr)

a. Adult 1.2E+l

b. Teen 6.7E+ I

c. Child 1.4E+1

d. Infant 0 Salt Water Sport Fish Ingestion (Kg/yr)

a. Adult 2.1 E+I

b. Teen 1.6E+I

c. Child 6.9

d. Infant 0 Salt Water Commercial Fish Ingestion (Kg/yr)

a. Adult 2.1 E+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+I

b. Teen 4.2E+I

c. Child 2.6E+ I

d. Infant 0 K:\occhcm\800proc Pagc 98

Table B-1 (Continued)

OCGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Irrigated Other Vegetable Ingestion (Kg/yr)

a. Adult 5.2E+2

b. Teen 6.3E+2

c. Child 5.2E+2

d. Infant 0 Irrigated Root Vegetable Ingestion (Kg/yr)

a. Adult 5.2E+2

b. Teen 6.3E+2

c. Child 5.21E+2

d. Infant 0 Irrigated Cow and Goat Milk Ingestion (L/yr)

a. Adult 3.11E+2

b. Teen 4.OE+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+l

d. Infant 0 Inhalation (m3 /yr)

a. Adult 8.0E+3

b. Teen 8.OE+3

c. Child 3.7E+3

d. Infant 1.4E+3 Cow and Goat Milk Ingestion (L/yr)

a. Adult 3.11E+2

b. Teen 4.OE+2

c. Child 3.3E+2

d. Infant 3.3E+2 Meat Ingestion (Kg/yr)

a. Adult l.1E+2

b. Teen 6.5E+1

c. Child 4.11E+1

d. Infant 0 K:\occhem\800proc Page 99

II Table B-1 (Continued)

OCGS Usaize Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Leafy Vegetable Ingestion (Kg/yr)

a. Adult 6.41E+1

b. Teen 4.2 E+ I

c. Child 2.6 E+ I

d. Infant 0 Fruits, Grains, & Other Vegetable Ingestion (Kg/yr)

a. Adult 5.21E+2

b. Teen 6.3 E+2

c. Child 5.2E+2

d. Infant 0 K:\occhen\8OOproc Pagc I100

Table B-2 Monthly Average Absolute Humidity g/m 3 (derived from historical climatological data)

Average Absolute Month Humidity (g/m 3 )

January 3.3 February 3.3 March 4.5 April 6.1 May 9.4 June 12.8 July 15.2 August 15.6 September 12.4 October 7.9 November 5.9 December 3.8 K:\occhem\800proc Page 101

APPENDIX C - REFERENCES K:\occhem\800proc Page 102

Table C-1i-REFERENCES

1) Oyster Creek Updated Final Safety Analysis Report

2) Oyster Creek Facility Description and Safety Analysis Report

3) Oyste'r Creek Operating License and Technical Specifications

4) NUREG 1302 "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors" - Generic Letter 89-10, Supplement No. I,April 1991

5) Reg Guide 1.21 "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants" Rev. 1, June 1974

6) Reg Guide 1.23

7) Reg Guide 1.97

8) Reg Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR 50, Appendix I", Rev 1, October, 1977

9) Reg Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors", Rev.1, July, 1977

10) Reg Guide 4.8 " Environmental Technical Specifications for Nuclear Power Plants"

11) NRC Radiological Assessment Branch Technical Position, Rev 1, November 1979 (Appendix A to NUREG1302)

12) NUREG-0016

13) NUREG-0133

14) Licensing Application, Amendment 13, Meteorological Radiological Evaluation for the Oyster Creek Nuclear Power Station Site.

15) Licensing Application, Amendment 11, Question IV-8.

16) Evaluation of the Oyster Creek Nuclear Generating Station to Demonstrate Conformance to the Design Objectives of I0CFR5O, Appendix I, May, 1976, Tables 3-10

17) Meteorological Information and Diffusion Estimates to Conform with Appendix I Requirements: Oyster Creek, July, 1976, Table 1.3-1 l1B.

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.

19) Carpenter, J. J. "Recirculation and Effluent Distribution for Oyster Creek Site",

Pritchard-Carpenter Consultants, Baltimore, Maryland, 1964.

20) Nuclear Regulatory Commission, Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section and Relocation of the Procedural Details of RETS to the ODCM or PCP", January, 1989.

21) Ground Water Monitoring System (Final Report), Woodward-Clyde Consultants, March, 1984.

22) Meteorology and Atomic Energy, Department of Energy, 1981.

23) SEEDS Code Documentation through V & V of Version 98.8F (Radiological Engineering Calculation No. 2820-99-005, Dated 3/23/99)

24) Lynch, Giuliano, and Associates, Inc., Drawing Entitled, "Minor Subdivision, Lots 4 and 4.01 Block 1001", signed 13 Sep 99.

K:\occhem\800proc Page 103

25) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements".

26) NUREG/CR-4007 (September 1984).

27) HASL Procedures Manual, HASL-300 (revised annually)..

28) Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of Implementing Appendix I," April 1977

29) Reg. Guide 4.13 K:\occhem\800proc Page 104

APPENDIX D - SYSTEM DRAWINGS

--I . . . . . .

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K:\occhem\800proc -.: : e\ r Page 105

C I -

14,000 gal ea 1 Prefitration i -' IN VVC-D-1 A, I B.,0 -

WFT-1 A 53 ft 2 ea 30gpm 3eRCS

-30 gpmWC-T-3 iWC-.T-1 B.W,-A W1Ar;l ORW_

o *

WCPs Af A WCIFD HEADER 0~ 10 High Purity <> :W Cond > 50 pS/cm Cod-0pSc S WCP2Bm S = Sample Point WC-TC WCP-1 Sz 175 GPM

0 0

0 U

C) 00 01 0

. 25,000 gal ea i 'Prefiltration =coo1 . . -. -.

.34,300 gal HP-D-1A, 1B

.INSERIES' P-T-1A 150 ft 3 ea

, HP-P-1A S HP-F-IA f

.75 GPM..:

IV 103 f ea IP-P-2B.

Ca 0

-j ORW - i

.-. TIz 30,000 gal HP-T-1 B HP-P-1B s ILEAKAGE OR CBEM WASTE Off Spec Recycle CONDENSATE PUMP SUCTION I

S = Sample Point z

FIGURE D-1-2: SOLID RADNWASTE PROCESSING SYSTEM RADWASTE PROCESS

.FLOWPATH

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Blocide .

Injection Skid Blocide Storage K-\occhem\800proc Page 108

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APPENDIX E - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - SAMPLE TYPE AND LOCATION All sampling locations and specific information about the individual locations are given in Table E-1.

Figures E-1 and E-2 show the locations of sampling stations with respect to the site. Figure E-3 shows the site layout.

~ ..

. I

., i .k I - .

K:\occhem\800proc Page III

TABLE E-1: REMP SAMPLE LOCATIONS Sample Station Distance Azimuth Medium Code (miles) (degrees) Description TLD I 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ (TLD - ODCM Required - Inner Ring)

WWA I 0.1 209 On-site southern domestic well at OCGS, Forked River, NJ (WWA - ODCM 0.2 349 Required - One Location)

On-site northern domestic well at OCGS, Forked River, NJ (WWA - ODCM Required - One Location)

APT, AIO, TLD 3 6.0 97 East of site, near old Coast Guard Station, Island Beach State Park (APT, AIO, & TLD - Non-ODCM Required)

TLD 4 4.6 213 SSW of Site, Garden State Parkway and Route 554, Barnegat, NJ (TLD - ODCM Required - Outer Ring)

TLD S 4.2 353 North of Site, Garden State Parkway Rest (09/04)

Area, Forked River, NJ (TLD - ODCM Required - Outer Ring)

TLD 6 2.1 13 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ (TLD - Non-ODCM Required)

TLD 8 2.3 177 South of site, Route 9 at the Waretown Substation, Waretown, NJ (TLD - Non-ODCM Required)

TLD 9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, Waretown, NJ (TLD - Non-ODCM Required)

APT, AIO, TLD C 24.7 313 NW of site, GPU Energy office in rear parking lot, Cookstown, NJ APT, AIO, & TLD- ODCM Required Background Station)

TLD 11 8.2 152 SSE of site, 80h and Anchor Streets, Harvey Cedars, NJ (TLD - ODCM Required - Special Interest Area)

TLD 14 20.8 2 North of site, Larrabee Substation on Randolph Road, Lakewood, NJ (TLD - ODCM Required Background Station)

APT, AIO 20 0.7 95 East of site, on Finninger Farm on south side of access road, Forked River, NJ (APT, AIO - Non-ODCM Required)

K:\occhem\800proc Page 112

TLD 22: - ;- 1.6 -145 SE of site; on-Long John Silver Way, Skippers Cove, Waretown, NJ 3 3 .. (TLD - Non-ODCM Required)

SWA, CLAM, 23 - - 3.6 64 ENE of site, Barnegat Bay off Stouts Creek, AQS approximately 400 yards SE of "Flashing Light 1" (SWA, CLAM, AQS - Non-ODCM Required)

SWA, CLAM, 24 . 2.1. 101 East of site, Barnegat Bay, approximately AQS 250 yards SE of "Flashing Light 3" (CLAM - ODCM Required, SWA, AQS -

Non-ODCM Required)

SWA, AQS, 33 0.4. 123 ESE of site, east of Route 9 Bridge in FISH OCGS Discharge Canal (SWA, AQS - ODCM Required, Fish -

Non-ODCM Required)

-VEG 35 0.4 111 ESE of site, east of Route 9 and north of the OCGS Discharge Canal, Forked River, NJ (VEG - ODCM Required)

VEG 36 23.1- 319 NW of site, at "U-Pick" Farm, New Egypt,

- NJ (VEG - ODCM Required)

WWA .37 2.2 18 NNE of Site, off Boox Road at Lacey MUA Pumping Station, Forked River, NJ (WWA - ODCM Required)

. WWA 38: .6 197 SSW of Site, on Route 532, at Ocean Township MUA Pumping Station, Waretown, NJ (WWA - ODCM Required)

TLD 46 5.6 323 NW of Site, on Lacey Road adjacent to Utility Pole BT 259 65 (TLD - ODCM Required - Outer Ring)

TLD 47 4.6 26 NNE of Site, Route 9 and Harbor Inn road, Iii Berkeley Township, NJ (TLD - ODCM Required - Outer Ring) (09/04)

TLD 48 4.5- 189 South of Site, Intersection of Brook and School Streets, Barnegat, NJ (TLD - ODCM Required - Outer Ring)

TLD 51 0.4-: 358 North of site, on the access road to Forked River site, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 52 - 0.3 333 NNW of site, on the access road to Forked River site, Forked River, NJ - -

(TLD - ODCM Required - Inner Ring)

TLD ;53 ; 0.3 309 NW of site, at sewage lift station on the access road to the Forked River site, Forked River, NJ -

(TLD - ODCM Required - Inner Ring)

TLD ' 154 - 0.3 288 WNW of site, on the access road to Forked

1 1 River site, Forked River, NJ (TLD - ODCM Required - Inner Ring)

K-.occhem\800proc I c m80oc* Page 113

TLD 55 0.3 263 West of site, on Southern Area Stores security fence, west of OCGS Switchyard, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 56 0.3 249 WSW of site, on utility pole east of Southern Area Stores, west of the OCGS Switchyard, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 57 0.2 206 SSW of site, on Southern Area Stores access road, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 58 0.2 188 South of site, on Southern Area Stores access road, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 59 0.3 166 SSE of site, on Southern Area Stores access road, Waretown, NJ (TLD - ODCM Required - Inner Ring)

TLD 61 0.3 104 ESE of site, on Route 9 south of OCGS Main Entrance, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 62 0.2 83 East of site, on Route 9 at access road to OCGS Main Gate, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 63 0.2 70 ENE of site, on Route 9, between main gate and OCGS North Gate access road, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 64 0.3 48 NE of site, on Route 9 at entrance to Finninger Farm, Forked River, NJ (TLD - ODCM Required - Inner Ring)

TLD 65 0.4 19 NNE of site, on Route 9 at Intake Canal Bridge, Forked River, NJ (TLD - ODCM Required - Inner Ring)

APT, AIO, 66 0.4 133 SE of site, east of Route 9 and south of the TLD, OCGS Discharge Canal, inside fence, VEG Waretown, NJ (APT, AIO, TLD, & VEG - ODCM Required. TLD - Inner ring)

TLD 68 1.3 265 West of site, on Garden State Parkway at mile marker 71.7, Lacey Township, NJ (TLD - Non-ODCM Required)

APT, AIO, TLD 71 1.6 164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ (APT, AIO, TLD - ODCM Required. TLD

- Special Interest Area)

APT, AIO, TLD 72 1.9 25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ (APT, AIO, TLD - ODCM Required. TLD

- Special Interest Area)

K:\occhem\800proc Page 114

APT,AIO,TLD 73. if1.8 :108 ESE of site, on Bay Parkway; Sands Point Harbor, Waretown, NJ (APT, AIO - ODCM Required. TLD - Non-ODCM Required)

TLD 74 1.8 88 East of site, Orlando Drive and Penguin Court, Forked River, NJ (TLD - Non-ODCM Required)

TLD 75 i2.0 71 ENE of site, Beach Blvd. and Maui Drive, Forked River, NJ (TLD - Non-ODCM Required)

TLD 78. 1L8 2 North of site, 1514 Arient Road, Forked River, NJ (TLD - Non-ODCM Required)

TLD 79 :2.9 160 SSE of site, Hightide Drive and Bonita Drive, Waretown, NJ (TLD - Non-ODCM Required)

TLD'

81 3.5 201 SSW of site, on Rose Hill Road at intersection with Barnegat Boulevard, Bamegat, NJ

'..1; :r,-(TLD - ODCM Required - Special Interest Area)

TLD: 82 4.4 -- -36 NE of site, Bay Way and Clairmore Avenue, Lanoka Harbor, NJ (TLD - ODCM Required - Outer Ring)

TLD 84 4.4 332 NNW of site, on Lacey Road, 1.3 miles west of the Garden State Parkway on siren pole, Lacey Township, NJ (TLD - ODCM Required - Outer Ring)

TLD 85 3.9 250 WSW of site, on Route 532, just east of Wells Mills Park, Waretown, NJ (TLD - ODCM Required - Outer Ring)

TLD 86 5.0 224 SW of site, on Route 554, 1 mile west of the Garden State Parkway, Barnegat, NJ (TLD - ODCM Required - Outer Ring)

TLD 88 6.6 125 SE of site, eastern end Of 3 rd Street, Barnegat Light, NJ (TLD - Non-ODCM Required)

TLD 89 6.1 108 ESE of site, Job Francis residence, Island Beach State Park (TLD - Non-ODCM Required)

TLD 90 6.3 75 ENE of site, parking lot A-5, Island Beach State Park (TLD - ODCM Required - Special Interest Area)

TLD 92 9.0 46 NE of site, at Guard Shack/Toll Booth, Island Beach State Park (TLD - Non-ODCM Required)

K:\occhem\800proc K\.cr Page 115

FISH, CRAB 93 0.1 242 WSW of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ (FISH - ODCM Required, CRAB - Non-ODCM Required)

SWA, AQS, 94 20.0 198 SSW of site, in Great Bay/Little Egg Harbor CLAM, (SWA, AQS, CLAM, FISH - ODCM FISH Required)

TLD 98 1.3 292 WNW of site, on Garden State Parkway at mile marker 72.3, Lacey Township, NJ (TLD - Non-ODCM Required)

TLD 99 1.5 310 NW of site, on Garden State Parkway at mile marker 72.8, Lacey Township, NJ (TLD - Non-ODCM Required)

TLD Ti 0.4 219 SW of site, at OCGS Fire Pond, Forked River, NJ (TLD - Non-ODCM Required)

SAMPLE MEDIUM IDENTIFICATION KEY APT = Air Particulate SWA = Surface Water TLD = Thermoluminescent Dosimeter AIO = Air Iodine. AQS = Aquatic Sediment FISH = Fish WWA = XVell Water CLAM = Clams CRAB = Crab VEG = Vegetables K:\occhem\800proc Page 116

--FIGURE E-1 SAMPLING LOCATIONS WITHIN 2 MILES

1 I..;'

dmaTht 711 .':'

I- 'A I I: Z'A I . , .

i 11

ll.

't I "I

- - V- ru~k~ luo S

~m nnmmwwm~wmnmcmvn

.. .." . . :.I -; . ,; , .

I II :' , m ;: i.- *,: Is. ..

K:\occbem\800proc ;ocr , Page 117

FIGURE E-2 SAMPLING LOCATIONS OUTSIDE 2 MILES (09/04)

Oyster Creek Generating Station (OCOS)

Locations of Radiologlcal Emirontental MoEitoriJ Prognm (REIIN')

Stations geater than 2 miles fiom the OCGS K:\occhem\800proc Page 118

FIGURE E-3 AREA PLOT PLAN OF SITE SITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS K:\occhem\800proc Page 119

PORC Meeting 04-37 Page1 of 16 PORC MEETING (04-37) REPORT

- - -- PORCQUORUM: -- C. Wilson (C), M Button (P)- T;-Powell-(P)-W.-Tritt (A);-

G. Waldrep (P) Items 1,2,3 only, P. Cervenka (A) Item 4 only (C) - Chamiran, (P) - Priary Member. (A) = Altemate Member OTHER PARTICIPANTS: D. Fawcett (Presenter - Item 1),

R. Artz (Presenter - Item 3),

M. Godknecht (Presenter - Item 4)

R. Milos (PORC Coordinator)

Meeting 04-37 of the Oyster Creek Plant Operations Review Committee (PORC) was convened at 2:00 PM on Thursday, September 30,2004. The Chairman verified that a quorum was present The PORO members reviewing item 4 were qualified to review 10CFR50.59 Evaluations. Four items were on the agenda for PORC meeting 04-37:

(1) LER 2004-004 Operation In Excess of Thermal Power Urmit LER 2004-004-00 addressed exceeding the licensed maximum thermal power limit due to plant computer isolator power supply degradation affecting input values to the heat balance calculation. The Issue Summary and Safety Significance are described in the attached copy of LER 2004-004-00. Most questions were adequately answered during the meeting; however, several PORC comments/recommendations (see Attachment A) required follow-up.

The Chairman polled the voting members. All voting members agreed that thre were no technical or safety concerns preventing approval of the LER, provided PORC comments were adequately addressed. The PORC disposition is: Approval Recommended with Conditions.

Following the PORC meeting, the Chairman determined that the PORC comments were adequately addressed. No open items remain.

(2) Prompt Investigation Report - Heat Balance Inaccuracies - 08/29/04 PORO reviewed the Prompt Investigation Report"Heat Balance Inaccuracies -08/29/04."

This report investigated the same event covered by LER 2004-004-00, which is discussed above as Item 1. PORC was not asked to recommend approval of the supplied documentation.

Instead, PORC was asked to perform an Independent review of the Prompt Investigation Report and provide comments to the Originator. The primary focus of PORFCs review is to assure that no unrecognized safety issues exist and that there is consistency between the Prompt Investigation Report and LER-2004-004-00. All PORC questions were adequately answered at the meeting and there are no open issues. The PORC disposition is Review Only.

(3) CY-OC-170-301, Oyster Creek Offsite Dose Calculation Manual, Rev. 1 PORC reviewed Revision 1 to CY-OC-170-301, Oyster Creek Offsite Dose Calculation Manual.

The revision deleted the requirements for reporting both the type of shipping container as well as the identification of solidifying agent in the Annual Radioactive Effluent Release Report. The ODCM revision also included some TLD relocations. This revision to the ODOM was originally presented to PORC on 09/23/04 (PORC Meeting 04-36), but was remanded because the ODCM revisions were not processed in accordance with the ODCM change procedure, CY-AA-170-

PORC Meeting 04-37 Page 2 of 16 3100. The issue Summary, Safety Significance, and Significant PORC Questions I Comments from today's meeting are provided in Attachment B to this report. Most PORC questions /

comments were addressed at the meeting, however, several PORC comments required follow-up (see attached Meeting Notes). The Chairman polled the voting members. All voting merrbers-agreed that'there were no technical or safety concerns preventing approval of Revision

-1to-CY't70:30t; provided PORC comments were adequatey-ddressed.-The PORC disposition is: Approval Recommended with Conditions.

Subsequent to the meeting, the Chairman determined that the responses to PORC's comments were adequate. There are no open issues.

(4) 50.59 Eval OC-2004-E-O006. Rev. 0- UFSAR Revision re Aux Flash Tank Drain Pump This 10CFR50.59 Evaluation applies to the disabling of the auto-start function of the Aux Flash Tank Large Drain Pump to allow manual control of pump operation. This action will reduce/eliminate wear/damage to the drain pump and system components due to cycling that occurs when the Aux Flash Tank experiences high level transients. A copy of the 50.59 Evaluation, OC-2004-E-0006. Rev. 0, Is attached to this report. Revision 0 to OC-2004-E-0006 was originally presented to PORC on 07/15/04 (PORC Meeting 04-26) as Revision 1to O0 2004-E-0005, but was remanded for several reasons delineated in that PORC Report. The Issue Summary, Safety Significance. and Significant PORC Questions / Comments from today's meeting are provided in Attachment C to this report Most PORC questions / comments were addressed at the meeting, however, several PORC comments required follow-up (see attached Meeting Notes). The Chairman polled the voting members. All voting members agreed that there were no technical or safety concerns preventing approval of Revision 0 to OC-2004-E-0006, provided PORC comments were adequately addressed. The PORC disposition is:

Approval Recommended with Conditions.

Subsequent to the meeting, the Chairman determined that the responses to PORC's comments were adequate. There are no open issues.

Submitted: R. Milos, PORC Coordinator Minutes Approved: C. Wilson, PORC Chairrn Recommendation Approved: M. Massaro, Plant Manager

ML050870596

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