Text

Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual
	ML101241140
Person / Time
Site:	Oyster Creek
Issue date:	04/28/2009
From:	Artz R; Exelon Nuclear
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	AD-AA-101-F-01, Rev 1, CY-AA-170-3100, RA-10-002 CY-OC-170-301, Rev 3
	Download: ML101241140 (154)
	v • d • e

Procedure Approvai Form Page 1 of 1 AD-AA-1 01 -F-01 Revision 1 Document Number: CY-OC-170-301 Revision:

3 Title: Offsite Dose Calculation Manual for Oyster Creek Generating Station 0l New Dl Cancel E] Cancel X Revision EC#: __ PCR#: PPIS#: Document Revision El Editorial (3 Batch ER#: AR#: El Supersede corporate document(s)

List: None Revision Summary: Numerous minor revisions as outlined in Attachment 1 of CY-AA-170-3100.

Attach add'l descript, if req'd Impact on Operating XLI N/A and Design Margins: Attach add'i descript, if req'd CONFIRM that no commitments (i.e., those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-AA-1 10 commitment change/deletion form and INITIAL [Preparer]:

RA Preparer:

Robert Artz 04/28/09 OC/4006 Print Date Location/Ext

!1 I Applicable BR El DR 0_Site Contacts BY E_ LA E0 Check box and PB [l OC X R. Artz provide name TMI[-] ZN [I Validation Req'd: 1@ No El Yes (attach) ,v , (Validation requirement see AD-AA-101)

'I. Print/Signature Change Management:

El HU-AA-1 101 Change Checklist Attached [I Document Level of Use: L] Level 1 -Continuous Use El Level 2 -Reference Use Approval CLD LGQ __ __ __Other E_Common Training Req'd: XNo E] Yes Site Specific Training Req'd: X No [I Yes Traveler X None Required El Level 3 -Information Use (N;Date Location/Ex:

CFAM (Standard Procedures)

Print/Sign Approval 0 C Site Document(s) to be superseded:

NIA Location: Use additional sheets as necessary.

Assure that all pehding changes are dispositioned.

[] Temp. Change El interim Change Temp or Interim Change #: Interim Change expiration:

1OCFR50.59 Applicable:

XNo E] Yes Tracking Number: Excluded per CY-AA-1 70-3100 I 10CFR72.48 Applicable:

X No [3 Yes Other Regulatory Process Applicable:

X No [3 Yes Other Regulatory Process Number: PORC Required:

[3 No X Yes PORC Number (after PORC Approved):

Environmental Review Required:

X No El Yes If "Yes" then attach completed EN-AA-103 Attachment 1.0l if superceding a document containing commitments, notify the Commitment Tracking Coordinator per LS-AA-1 10 so the CTD can be updated as appropriate.

Cross Discipline Reviews: (list below) Surveillance Coordinator Review Req'd El No [] Yes, list below Print Print Print Signature Signature Signature Date Discpline or Org.Date Oiscpline or Org.Date Discipline or Org.Temp Change Authorization Only SRO Print/Sign/Date SOR Print/Sign/Date Impl. Date Exp. Date SOR Approval indicates that all required Cross-Disciplinary reviews have been performed and the reviewers have signed this form. This procedure is technically and functionally acc ate for all tuntional reas (Refer to AD-AA-102)

SPrint/Sign Dale Discipline or Org.Site Authorization:

/LL L.*'SFAM Print/Sigr/'

-I tDate6 I I .-.rq~ired by Date ,.- /'z" .7e-T- 7e .VA)./fV a J 50.59 APPLICABILITY REVIEW FORM LS-AA- 104-1002 Revision 2 Page I of I Activity/Document Number: CY-OC- 170-310 Revision Number: 3 Address the questions below for all aspects of the Activity.

If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity.

Note that it is not unusual to have more than one process apply to a given Activity.See Section 4 of the Resource Manual (RM) for additional guidance.I. Does the proposed Activity involve a change: I. Technical Specifications or Operating License (I OCFR50.90)?

X NO __ YES See Section 4.2.1.1 of the RM 2. Conditions of License Quality Assurance program (IOCFR50.54(a))?

X_ NO -YES Security Plan (IOCFR50.54(p))?

X_ NO _ YES See Section 4.2.1.2 of the RM Emergency Plan (10CFR50.54(q))?

X_ NO __ YES 3. Codes and Standards IST Program Plan (10CFR50.55a(f))?

X_ NO __ YES IS] Program Plan (I OCFR50.55a(g))?

X_ NO _ YES 4. ECCS Acceptance Criteria (IOCFR50.46)?

X_ NO _ YES See Section 4.2.1.4 of the RM 5. Specific Exemptions (I OCFR50.12)?

X_ NO -YES See Section 4.2.1.5 of the RM 6. Radiation Protection Program (I OCFR20)? X_ NO -YES See Section 4.2.1.6 of the RM 7. Fire Protection Program (applicable UFSAR or operating license X_ NO _ YES See Section 4.2.1.7 of the RM condition)?

8. Programs controlled by the Operating License or the Technical NO X YES See Section 4.2.1.7 of the RM Specifications (such as the ODCM).9. Environmental Protection Program X_ NO -YES See Section 4.2.1.7 of the RM 10. Other programs controlled by other regulations.

X_ NO _ YES See Section 4.2.1 of the RM II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting X_ NO YES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less?Ii. Does the proposed Activity involve a change to the: I. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by NEI 96-07 X_ NO _ YES See Section 4.2.3 of the RM or NEI 98-03?2. Managerial or administrative procedures governing the conduct of facility operations (subject to the control of IOCFR50, Appendix B) X NO _ YES See Section 4.2.4 of theRM 3. Procedures for performing maintenance activities (subject to I0CFR50, X NO YES See Section 4.2.4 of the RM Appendix B)? -__4. Regulatory commitment not covered by another regulation based change X_ NO YES See Section 4.2.3/4.2.4 of the RM process (see NEI 99-04)?IV. Does the proposed Activity involve a change to the Independent Spent Fuel X NO YES See Section 4,2.6 of the RM Storage Installation (ISFSI) (subject to control by 10 CFR 72.48)Check one of the following:

If All aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordance with its governing procedure.

U If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes.

The remaining portion of the activity should be implemented in accordance with its governing procedure.

Signoff: Q 50.59 Screener/50.59 Evaluator:

7 ' i -t _ Sign: ate: (Circle One) (Print name) (Signai2 50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 2 Page I of I Station/Unit(s):

Oyster Creek Activity/Document Number: CY-OC-170-310 Revision Number: 3 Title: Off Site Dose Calculation Manual for Oyster Creek Generating Station NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:.(Provide a brief, concise description of what theproposed activity involves.)

This activity revises the ODCM CY-OC-170-tncorrforate the following changes: (I) Changes to REMP sample locations.

(2) Change the reporting level of 1- 131 to 2 pCi/L (3) Update XIQ and D/Q factors to average values from the last, five years of met data.(4) Use of the updated X/Q and D/Q factors in example dose calculations.

(5) Add a reference for a report from a vendor's hydrogeologic investigation report.(6) A complete re-write of Table E- I describing REMP sample stations.(7) Updating maps of the I-mile, I to 5-mile and greater than 5-mile rings showing REMP sample stations..

Reason for Activity: (Discuss why the proposed activity is being performed.)

This activity is being performed in accordance with CY-AA-170-3 100, "Offsite Dose Calculation Manual Revisions," a process by which changes to the ODCM are made. The changes are based upon input from various sources. The above changes affect REMP sampling and REMP sampling locations, a correction to the 1-131 reporting level and provide updates to average atmospheric dispersion and deposition values..Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)Plant operations are not affected by this activity and design bases or safety analyes as described in the UFSAR are not affected by changes to this document.Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion.

Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)

The Screening demonstrates a 50.59 Evaluation is NOT applicable to the changes outlined in the above "Description of Activity." Question 8 in the Applicability Review Form was answered YES since this is a program controlled by the"...Technical Specifications (such as the ODCM)." The document change may be implemented without prior NRC approval, as the intent of the document has not changed. However, in compliance with CY-AA-170-3 100, "Offsite Dose Calculation Manual Revisions," the revised ODCM will be forwarded to the NRC with the submission of the next Annual Radiological Effluents Release Report.Attachments:

Attach all 50.59 Review forms completed, as appropriate.(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

Forms Attached: (Check all that apply.)X Applicability Review 50.59 Screening 50.59 Screening No. OC-2009-S-0067 Rev. 0 50.59 Evaluation 50.59 Evaluation No. Rev.

50.59 SCREENING FORM LS-AA- 104-1003 Revision 2 Page I of I 50.59 Screening No. OC-2009-0067 Rev. No. 0 Activity/Document Number: CY-OC- 170-301 Revision Number:3 I L 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question)(See Section 5 of the Resource Manual (RM) for additional guidance):

I. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR described design function? (See Section 5.2.2.1 of the RM)2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)3. Does the proposed Activity involve an adverse change to an element of a UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM)4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM)5. Does the proposed Activity require a change to the Technical Specifications or Facility Operating, License? (See Section 5.2.2.5 of the RM)EYES X NO flYES X NO EYES X NO EYES X NO I[I YES X NO 11. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).

ODCM (CY-OC- 170-301), Offsite Dose Calculation Manual Revisions (CY-AA- 170-3 100), Offsite Dose Calculation Manual Administration (CY-AA- 170-2000), UFSAR.IlL Select the appropriate conditions:

X If all questions are answered NO, then a 50.59 Evaluation is not required.* E If question 1, 2, 3, or 4 is answered YES for any portion of an Activity and question 5 is answered NO, then a 50.59 Evaluation shall be performed for the affected portion of the Activity.E If question 5 is answered YES for any portion of an Activity and questions I through 4 are answered NO for the remaining portions of the Activity.

then a License Amendment is recluired prior to implementation of the portion of the Activity that requires the amendment:

however. a 50.59 Evaluation is not required for the remaining portions of the Activity.E] If question 5 is answered YES ior any portion of an Activity and question 1, 2 3, or 4 is answered YES for any of the remaining portions of the Activity.

then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment and a 50.59 Evaluation is required for the remaining affected portions of the Activity.IV. Screening Signoffs:

D 50.59 Screener:

o -e,--t ,,t ,"--Z S"(Pint name)50.59 Reviewer:

8 '2/U4 & 04r'-, -(Print name)Sign: Y (SV Sign: / (Sat 1 re )o -(Signature)

Dateo__./_.

Date: -y/l.-/I_0_9 PORC ITEM

SUMMARY

COVER SHEET

SUBJECT:

Revision I of Offsite nose (alrillatinn (OnrM)PREPARED BY: Robert Artz IS A 50.59/72.48 SAFETY EVALUATION REQUIRED?

[ Yes [X ] No ISSUE

SUMMARY

Numerous small changes are presented here for inclusion.

Revision changes are included in CY-AA-1 70-3100 Attachment 1.SAFETY IMPACT: This change does not impact any plant operations, any design bases or safety analysis as described in the UFSAR as shown by the analysis performed in Attachment 2 of CY-AA-1 70-3100..The Presentation Material is Ready for PORC Review Presenter's ig~nature of /?-8/09 Date Exelon..Nuclear CY-AA-170-3100 Revision 0 Page 1 of 4 ATTACHMENT 1 ODCM Change Summary Matrix Page 1 of 2 ODCM Changes (old) (new) Description of Change Item Rev. 2 Rev. 3 No. page No. page No.1 7 7 Clarified Figures E- I, E-2, E-3.2 II 1 Changed Amergen Energy Company to EXELON Generation.

3 48 48 Table 3.12. 1-1 For inner ring REMP sample locations, changed "16 locations" to "At least 16 locations." Also changed outer ring REMP stations from "9 locations" to "at least 14 locations." 4 49 49 Table 3.12. 1-I Changed "Three samples from Off Site locations.." to Three samples from close to SITE BOUNDARY..." Also added a clarifying footnote to "least prevalent wind direction." 5 50. 50 Table 3.12. 1 -I Changed the sampling and collection frequency from grab sample monthly to"Grab sample weekly, combine into monthly composite." 6 51 51 Table 3.12. 1- I Changed sample location from "One sample from downstream area" to "One sample from downstream area with existing or potential recreational value." 7 53 53 Table 3.12.1-1 Changed "One sample of similar broad leaf vegetation grown distant and in a low location..." to "One sample of each of the similar broad leaf vegetation grown at least 15 to 30 km (9.3-18.6 miles) distant in the least prevalent wind direction." 8 54 55 Footnote (5) in Table 3.12. 1- I clarifying circumstances under which groundwater samples are taken.9 55 55 Deleted footnote (7) of Table 3.12.1-I and substituted another footnote (7) stating: "1- 131 analysis on each composite when the dose calculated for the consumption of the water is greater than I mrem per year." 10 56 56 In Table 3.12.1-2 changed reporting level of 1- 131 from 20 to 2 pCi/L II 57 57, 59 In Table 4.12.1-1 deleted value of 3000 pCi/L for tritium's detection capabilities and replaced it with footnote (4) on page 59.12 62 62 In Section 3.12.4 changed reference from Table 3.3-3 to Table 3.12.4-1 13 69 69 In Section 3/4.12.2 added 500 ft 2 to 50 m 2 gardens.14 72 72 In Section 6.2.1 changed submission date for the ARERR from" within 60 days of January I of each year..." to "prior to May I of each year..." 15 73 73 In Section 6.2.2.9 added the words: "in the form of a complete, legible copy of the ODCM." 16 83 83 In Table 2.2.2.1 updated values of Atm. Dispersion factors to values from last five years of met data.17 85 85 Used updated values of X/Q in example calculation in Section 2.3.1.2.18 87 87 Used updated values of X/Q in example calculation in Section 2.3.1.4.19 89 89 In Table 2.3.2. 1-I changed Atm. Dispersion factors to values from last five years of met data. Also used updated values of X/Q in example calculation in Section 2.3.2.2.20 92 92 Table 2.4.1. 1-I updated values of Atm. Dispersion factors to values from last five years of met data. Also used updated values of X/Q in example calculation in Section 2.4.1.2.21 94 94 In Table 2.5-I updated D/Q deposition factors to values from last five years of met data.

CY-AA-170-3100 Revision 0 Page 2 of 4 ATTACHMENT 1 ODCM Change Summary Matrix Page 2 of 2 22 97, 98 97, 98 Used updated value of D/Q in example calculation in Section 2.5.3.2.23 99 99 Used updated value of X/Q in example calculation in Section 2.5.3.4.24 104 104 Used updated value of D/Q in example calculation in Section 2.5.4.2.25 121 122 In Table C- I -References, added reference 31 for Conestoga Rovers and Associates, Hydrogeologic Investigation Report.26 128 129 In the cover page to Appendix E, added Figure E-4 showing the site layout.27 129 to 130 to 136 134 Complete re-write of Table E- I describing REMP samplelocations.

28 135 137 Figure E- I Substituted a new map of REMP stations within a I-mile radius of the Oyster Creek Generating Station 29 136 138 Figure E-2 Substituted a new map of REMP stations within a I to 5-mile radius of the Oyster Creek Generating Station.30 139 Figure E-3 Inserted a new map of REMP stations greater than 5 miles from the Oyster Creek Generating Station.31 137 140 Moved the area plot plan of the site to Figure E-4.

CY-AA-170-3100 Revision 0 Page 3 of 4 ATTACHMENT 2 ODCM Change Determination Page 2 of 2 Station: oyster Creek ODCM Revision No. 3 Determination No.OC-2009-D-0001

.Determination Questions (Check correct response)X YES NO 1. Does the ODCM change maintain the level of radioactive effluent control required by 1OCFR20.1301?

Explain: The changes outlined in Attachment 1 do NOT affect the level of radioactive effluent control required by 10CFR20.1301.

These changes are relatively small changes that relate to hand-calculations, clarification of REMP sample locations ,and updating meteorological factors.2. Does the ODCM change maintain the level of radioactive effluent control required X YES -NO by IOCFR20.1302?

Explain: 10CFR20.1302 deals with compliance with dose limits for individual members of the public. As stated above, the changes to the ODCM do not affect dose to the public. There are subtle changes to the example calculations but these are example calculations and are not part of the actual dose to the public.)3. Does the ODCM change maintain the level of radioactive effluentcontrol required X YES -NO by 40CFR 190?Explain: 40CFR190 deals with radiation doses received by members of the public in the general environment and to radioactive materials introduced into the general environment as a result of operations that are part of the nuclear fuel cycle. The requirement is an Environmental Protection Agency regulation.

Doses to the public are not calculated by the above criteria.4. Does the ODCM change maintain the level of radioactive effluent control required X YES -NO by IOCFR50.36a?

Explain: I OCFR50.36a deals with Technical Specifications on effluents from nuclear power reactors.

The section also deals with the plant operator developing operating procedures for dealing with operating the radioactive waste system at the plant. More specifically, for radiological effluents, 50.36a also deals with the Annual Radiological Effluents Release Report (ARERR). The only change affecting the ARERR is the requirement to submit the report prior to May I of each year and in accordance with the requirements of IOCFR50.36a and Section IV.B. I of IOCFR50 Appendix I.5. Does the ODCM change maintain the level of radioactive effluent control required X YES -NO by Appendix I to IOCFR50?Explain: IOCFR50 Appendix I deals with dose limits as calculated for the Annual Radioloeical Effluents Release Reoort (ARERR). We are not chaneine the CY-AA-170-3100 Revision 0 Page 4 of 4 ATTACHMENT 2 ODCM Change Determination Page 2 of 2 affected sections to the ODCM which are Section 3.11.2.1, 3.11.2.2, 3.22.2.3 or 3.11.4. Section 3.11.2.1 spells out the limits to whole body, skin and organ dose.Section 3.11 .2.2b addresses annual air dose limits. Section 3.11.2.3 addresses dose due to radioactive iodine, tritium and particulates.

Section 3.11.4 deals with calculated organ doses and total whole body doses from effluents.

These sections are not being changed.6. Does the ODCM change maintain the accuracy or reliability of effluent, dose, or X YES -NO setpoint calculations?

Explain: Set point calculations are not changed. Furthermore, dose calculations are performed by a validated and verified computer program called SEEDS (Simplified Environmental Effluent Dosimetry System) that is controlled by Procedure CY-OC-130-501 and the changes to the ODCM as proposed do not involve any changes to these items.7. Does the ODCM change maintain the accuracy of radioactive effluent control X YES -NO required by the SAR?Explain: The UFSAR was searched and the following items were reviewed in terms of the proposed ODCM changes. In no case is the accuracy or integrity of the radioactive effluent control affected by these ODCM changes: a 1.9.24 Samplingand Analysis of Radiological Effluents from the Plant 0 2.1.1 Effluent Dose Limits , 11.2.3.3 Dilution factor for Radioactive releases o 11.5.2.2 Process Liquid Monitoring

Table 11.2.26 Population Doses from Liquid Effluents o 11.3 Gaseous Waste Management System o 11.3.12 Population Doses 1. If a. ll questions are answered YES, then complete the ODCM Change Determination and implement the Change per this procedure.

Il1. If any question is answered NO, then a change to the ODCM is not permitted IV. Signoffs:

/ /0 Determination Preparer:

Robert Artz Date:((Printed Name) (Sign re)Reviewer:

M& ?6i-f A/a4-& d J-,e. Date: ',- 07 (Printed Name) (Signature)

Exelon,.Nuclear CY-OC-170-301 Revision 3 Page 1 of 140 OFFSITE DOSE CALCULATION MANUAL FOR OYSTER CREEK GENERATING STATION Revision of this document requires PORC approval and changes are controlled by CY-AA-170-3100 040809 CY-OC-170-301 Revision 3 Page 2 of 140 TABLE OF CONTENTS INTRODUCTION PART 1 -RADIOLOGICAL EFFLUENT CONTROLS 1.0 DEFINITIONS

3.0 APPLICABILIITY

3.3 INSTRUMENTATION

3.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONTIORING INSTRUMENTATION 3.11.1 LIQUID EFFLUENTS 3.11.1.1 CONCENTRATION 3.11.1.2 DOSE 3.11.1.3 LIQUID WASTE TREATMENT SYSTEM 3.11.2 GASEOUS EFFLUENTS 3.11.2.1 DOSE RATE 3.11.2.2 DOSE NOBLE GASES 3.11.2.3 DOSE -IODINE -131, IODINE -133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 3.11.2.4 GASEOUS RADWASTE TREATMENT 3.11.3 MARK I CONTAINMENT 3.11.4 TOTAL DOSE 3.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.12.1 MONITORING PROGRAM 3.12.2 LAND USE CENSUS 3.12.3 INTERLABORATORY COMPARISON PROGRAM 3.12.4 METEOROLOGICAL MONITORING PROGRAM 040809 CY-OC-1 70-301 Revision 3 Page 3 of 140 BASES FOR SECTIONS 3.0 AND 4.0 3.3 INSTRUMENTATION 3.3.3.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3.11 RADIOACTIVE EFFLUENTS 3.11.1 LIQUID EFFLUENTS 3.11.1.1 CONCENTRATION 3.11.1.2 DOSE 3.11.1.3 LIQUID RADWASTE TREATMENT 3.11.2 GASEOUS EFFLUENTS 3.11.2.1 DOSE RATES 3.11.2.2 DOSE-NOBLE GAS 3.11.2.3 DOSE -IODINE-1 31, IODINE-1 33, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM 3.11.2.4 AUGMENTED OFFGAS TREATMENT SYSTEM 3.11.4 TOTAL DOSE 3.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3.12.1 MONITORING PROGRAM 3.12.2 LAND USE CENSUS 3.12.3 INTERLABORATORY COMPARISON PROGRAM 5.0 DESIGN FEATURES/SITE MAP 6.0 ADMINISTRATIVE CONTROLS 6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL.

OPERATING REPORT (REOR)6.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (RERR)6.3 RESPONSIBILITES 040809 CY-OC-1 70-301 Revision 3 Page 4 of 140 PART II -CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLEUNTS 1.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 1.2 LIQUID EFFLUENT MONITOR SETPOINT DETERMINATION 1.2.1 LIQUID EFFLUENT MONITORS 1.2.2 SAMPLE RESULT SETPOINTS 1.2.3 ASSUMED DISTRIBUTION SETPOINTS 1.3 BATCH RELEASES 1.4 CONTINUOUS RELEASES 1.5 LIQUID EFFLUENT DOSE CALCULATION

-10CFR50 1.5.1 MEMBER OF THE PUBLIC DOSE -LIQUID EFFLUENTS 1.5.2 SHORELINE DEPOSIT DOSE 1.5.3 SHORELINE DOSE EXAMPLE 1.5.4 INGESTION DOSE -LIQUID 1.5.5 INGESTION DOSE CALCULATION EXAMPLE 1.6 REPRESENTATIVE SAMPLES 2.0 GASEOUS EFFLUENTS 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS 2.2. GASEOUS EFFLUENT MONITOR SETPOINT DETERMINATION 2.2.1 PLANT VENT 2.2.2 OTHER RELEASE POINTS 2.2.3 RADIONUCLIDE MIX FOR SETPOINTS 2.3 GASEOUS EFFLUENT INSTANTANEOUS DOSE RATE CALCULATIONS 10CFR20 2.3.1 SITE BOUNDARY DOSE RATE -NOBLE GASES 2.3.1.1 TOTAL BODY DOSE RATE 2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE 2.3.1.3 SKIN DOSE RATE 040809 CY-OC-170-301 Revision 3 Page 5 of 140 2.3.1.4 EXAMPLE SKIN DOSE RATE 2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES 2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES 2.3.2.2 EXAMPLE IODINE AND PARTICULATES DOSE RATE CALCULATION 2.4 NOBLE GAS EFFLUENT DOSE CALCULATION

-1OCFR50 2.4.1 UNRESTRICTED AREA DOSE -NOBLE GASES 2.4.1.1 AIR DOSE METHOD 2.4.1.2 EXAMPLE NOBLE GAS AIR DOSE CALCULATION 2.4.1.3 INDIVIDUAL PLUME DOSE METHOD 2.5 RADIOIODINE PARTICULATE AND OTHER RADIONUCLIDES DOSE CALCULATIONS

-10CFR50 2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES,AND OTHER RADIONUCLIDES 2.5.2 EXAMPLE CALCULATION

-INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES 2.5.3 INGESTION OF RADIOIODINES, PARTICULATES AND OTHER RADIONUCLIDES 2.5.3.1 CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION

-OTHER THAN TRITIUM 2.5.3.2 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN ANIMAL FORAGE AND VEGETATION

-OTHER THAN TRITIUM 2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION 2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION 2.5.3.5 CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 040809 CY-OC-1 70-301 Revision 3 Page 6 of 140 2.5.3.6 EXAMPLE CALCULATION OF CONCENTRATION OF THE RADIONUCLIDE IN MILK AND MEAT 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 2.5.3.8 EXAMPLE CALCULATION

-DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES 2.5.4 GROUND PLANE DEPOSITION IRRADIATION 2.5.4.1 GROUND PLANE CONCENTRATION 2.5.4.2 EXAMPLE GROUND PLANE CONCENTRATION CALCULATION 2.5.4.3 GROUND PLANE DOSE 2.5.4.4 EXAMPLE GROUND PLANE DOSE 3.0 TOTAL DOSE TO MEMBERS OF THE PUBLIC- 40CFR190 3.1 EFFLUENT DOSE CALCULATIONS 3.2 DIRECT EXPOSURE DOSE DETERMINATION 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM APPRENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS I Table A-i: Dose Conversion Factors for Deriving Radioactive Noble Gas Radionuclide-To-Dose Equivalent Rate Factors Table A-2: Noble Gas Radionuclide-To-Dose Equivalent Rate Factors Table A-3: Air Dose Conversion Factors for Effluent Noble Gas Table A-4: Locations Associated with Maximum Exposure of a Member of The Public Table A-5: Critical Receptor Noble Gas Dose Conversion Factors APPENDIX B -MODELING PARAMETERS Table B-1 :OCGS Usage Factors for Individual Dose Assessment Table B-2: Monthly Average Absolute Humidity APPENDIX C -REFERENCES TABLE C-1: REFERENCES APPENDIX D -SYSTEM DRAWINGS 040809 CY-OC-170-301 Revision 3 Page 7 of 140 Figure D-1-la: Liquid Radwaste Treatment Chem Waste and Floor Drain System Figure D-1-lb: Liquid Radwaste Treatment

-High Purity and Equipment Drain System Figure D-1-2: Solid Radwaste Processing System Figure D-2-1: Gaseous Radwaste Treatment

-Augmented Offgas System Figure D-2-2: Ventilation System APPENDIX E -RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -SAMPLE TYPE AND LOCATION Table E-1: Figure E-1: Figure E-2: Figure E-3: REMP Sample Locations Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station.Locations of REMP Stations within a 1 to 5-mile radius of the Oyster Creek Generating Station.Locations of REMP stations greater than 5 miles from the Oyster Creek Generating Station 040809 CY-OC-1 70-301 Revision 3 Page 8 of 140 OYSTER CREEK GENERATING STATION OFF SITE DOSE CALCULATION MANUAL INTRODUCTION The Oyster Creek Off Site 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 set points; 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.040809 CY-OC-170-301 Revision 3 Page 9 of140 PART D -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.

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.040809 CY-OC-1 70-301 Revision 3 Page 10 of140 1.6 CHANNEL FUNCTIONAL TEST CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel to verify its proper response including, where applicable, alarm 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 OFF SITE 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 FREQUENCY 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 REPORABLE EVENT shall be any of those conditions specified 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.

1.34 AUGMENTED OFF GAS SYSTEM (AOG)The AUGMENTED OFF GAS SYSTEM is designed and installed to holdup and/or process radioactive gases from the main condenser off gas system for the purpose of reducing the radioactive material content of the gases before release to the environs.1.35 MEMBER (S) OF THE PUBLIC MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with Exelon Generation 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, 040809 CY-OC-1 70-301 Revision 3 Page 11 of 140 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 OFF SITE DOSE CALCULATION MANUAL (ODCM)The OFF SITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of Off Site doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Set points, 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 Exelon Generation.

The area outside the SITE BOUNDARY is termed OFF I SITE or UNRESTRICTED AREA.1.39 OFF SITE The area that is beyond the site boundary where the land is neither owned, leased nor otherwise subject to control by Exelon Generation.

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 040809 CY-OC-170-301 Revision 3 Page 12 of 140 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 OFF SITE.1.41 DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (micro curies 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 1-135 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 10CFR Part 40 Appendix I." 1.42 DEPOSITION (D/Q)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. m 2).1.43 DOSE CONVERSION FACTOR (DCF)A parameter calculated by the methods of internal dosimetry, which indicates the committed dose equivalent (to the whole body or organ) per unit activity inhaled or ingested.

This parameter is specific to the isotope and the dose pathway. DOSE CONVERSION FACTORS are commonly tabulated in units of mrem/hr per picocurie/m3 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 1.111 is the basis of the definition of an ELEVATED RELEASE. Elevated releases generally will not produce any significant ground level concentrations within the first few hundred yards of the source.040809 CY-OC-170-301 Revision 3 Page 13 of 140 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 "OPEN DOSE" A routine effluent dosimetry computer program that uses Reg.Guides 1.109 and 1.111 methodologies.

040809 CY-OC-1 70-301 Revision 3 Page 14 of 140 1.50 RAGEMS (RADIOACTIVE 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 1) and one for the turbine building (RAGEMS II). They monitor particulates, iodine's, and noble gases.1.51 SEMI-INFINITE PLUME MODEL Dose assessment model which is based on the assumption that the travel in air. The ground is considered to be an 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.

1.52 SOURCE TERM 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., micro curies).1.53 X/Q -("CHI over Q")The dispersion factor of a gaseous release in the environment calculated by a point source Gaussian dispersion model. Normal units of X/Q are sec/m 3.The X/Q is used to determine environmental atmospheric concentrations by multiplying the source term, represented by Q (in units of pCi/sec or Ci/sec). Thus, the plume dispersion, X/Q (seconds/cubic meter) multiplied by the source term, 0 (uCi/seconds) yields an environmental concentration, X (pCi/m 3). X/Q is a function of many parameters including wind speed, stability class, release point height, building size, and release velocity.1.54 SEEDS (Simplified Effluent Environmental Dosimetry System)A routine effluent dosimetry computer program that uses Reg.Guides 1.109 and 1.111 methodologies.

040809 CY-OC-1 70-301 Revision 3 Page 15 of 140 TABLE 1.1: SURVEILLANCE FREQUENCY NOTATION *NOTATION S D W M Q SA A R 1/24 S/U P N.A.FREQUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .At least once per 7 days.At least once per 31 days.At least once per 92 days.At least once per 184 days.At least once per 366 days.At least once per 18 months (550 days).At least once per 24 months (refueling cycle)Prior to each reactor startup.Prior to each radioactive release.Not applicable.

Each surveillance requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.040809 CY-OC-1 70-301 Revision 3 Page 16 of140 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.

040809 CY-OC-1 70-301 Revision 3 Page 17 of 140 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 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.

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, hours 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.

040809 CY-OC-170-301 Revision 3 Page 18 of 140 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 set points set to ensure that the limits of CONTROL 3.11.1.1 are not exceeded.

The Alarm/Trip set points 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 set point 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 set point 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 CHANNL FUNCTIONAL TEST at the Frequencies shown in Table 4.3.3.10-1.

040809 CY-OC-1 70-301 Revision 3 Page 19 of 140 TABLE 3.3.3.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE INSTRUMENT ACTION 1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)N/A 110 N/A 114 2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Reactor Building Service Water System Effluent Line 1 112 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Effluent Line (DELETED)N/A 113 040809 CY-OC-1 70-301 Revision 3 Page 20 of 140 TABLE 3.3.3.10-1 (Continued)

TABLE NOTATIONS ACTION 110 ACTION 112 ACTION 113 ACTION 114 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 4.11.1.1.1.

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.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 1 E-6 IxCi/ml.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.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 4.11.1.1.1.

2. Qualified personnel determine and independently verify the acceptable release rate.040809 CY-OC-170-301 Revision 3 Page 21 of 140 TABLE 4.3.3.10-1:

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTSa CHANNEL SOURCE INSTRUMENT CHECK CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST 1. RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a. Liquid Radwaste Effluent Line (DELETED)b. Turbine Building Sump No. 1-5 (DELETED)N/A N/A N/A N/A N/A N/A N/A N/A 2. RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a. Reactor Building Service Water System Effluent Line D M Re od 3. FLOW RATE MEASUREMENT DEVICES a. Liquid Radwaste Effluent Line (DELETED)N/A N/A N/A N/A 040809 CY-OC-170-301 Revision 3 Page 22 of 140 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 set point.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.

040809 CY-OC-1 70-301 Revision 3 Page 23 of 140 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 set points set to ensure that the limits of CONTROL 3.11.2.1 are not exceeded.

The alarm/trip set points 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 set point 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 set point 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.

040809 CY=OC-170-301 Revision 3 Page 24 of 140 TABLE 3.3.3.11-1:

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERAE 1. DELETED 2. STACK MONITORING SYSTEM a. Radioactive Noble Gas Monitor (Low Range) 1 b. Iodine Sampler 1 c. Particulate Sampler 1 d. Effluent Flow Measuring Device 1 e. Sample Flow Measuring Device 1 3. TURBINE BUILDING VENTILATION MONITORING SYSTEM a. Radioactive Noble Gas Monitor (Low Range) 1 b. Iodine Sampler 1 c. Particulate Sampler 1 d. Effluent Flow Measuring Device 1 e. Sample Flow Measuring Device 1 3LEa APPLICABILITY ACTION b,e b,e b,e b b b b b b b-124 127 127 122 128 123 127 127 122 128 040809 CY-OC=170-301 Revision 3 Page 25 of 140 TABLE 3.3.3.11-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLEa APPLICABILITY ACTION 4. AUGMENTED OFF GAS 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 d. Sample Flow Measuring Device 1 b 128 040809 CY-OC-11 70-30 1 Revision 3 Page 26 of 140 TABLE 3.3.3.11 -1 (Continued)

TABLE NOTATIONS a. Channels shall be OPERABLE and in service as indicated except that a channel may be taken out of service for the purpose of a check,, calibration, test maintenance or sample media change without declaring the channel to be inoperable.

b. During releases via this pathway e. Monitor / sampler or an alternate shall be OPERABLE to monitor/I sample Stack effluent whenever the drywell is being purged.ACTION 122 ACTION 123 ACTION 124 ACTION 127 ACTION 128 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.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.With no channel OPERABLE, effluent releases.

via this pathway may continue provided a grab sample is taken at least once per 8 hou 'rs 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.

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).

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.040809 CY-OC-170-301 Revision 3 Page 27 of 140 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 REQUIREDa 1. DELETED 2. MAIN STACK MONITORING SYSTEM a. Radioactive Noble Gas Monitor (Low Range) D M 1/24 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 a b e. Sample Flow Measuring Device D N.A. R Q b 3. TURBINE BUILDING VENTILATION MONITORING SYSTEM a. Radioactive Noble Gas Monitor (Low Range) D M 1/2 4 f Q' 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 040809 CY-OC=170o301 Revision 3 Page 28 of 140 TABLE 4.3.3.11-1 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL INSTRUMENT CHECK SOURCE CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVIELLANCE IS REQUIRED a 4. AUGMENTED OFF GAS BUILDING EXHAUST VENTILATION MONITORING SYSTEM a. Radioactive Noble Gas Monitor D M Rf b. Iodine Sampler W N.A. N.A.c. Particulate Sampler W N.A. N.A.d. Sample Flow Measuring Device D N.A. R Q e N.A.N.A.N.A.b b b b-N 040809 CY-OC=1 70-301 Revision 3 Page 29 of 140 TABLE 4.3.3.11-1 (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.

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 set point.2. Instrument indicates a downscale failure.3. Instrument controls not set in operate mode.4. Instrument electrical power loss.f. The CHANNEL CALIBRATION shall be performed according to established calibration procedures.

h. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: 1. Instrument indicates measured levels above the alarm set point.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 cover is closed after the faceplate switches are verified in their correct positions.

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 set point.2. Instrument indicates a low count rate/monitor failure.040809 CY-OC-1 70-301 Revision 3 Page 30 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 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/mifliliter.i APPLICABILITY:

At all times.ACTION: a. In the event the concentration of radioactive material in liquid effluent released into the Off Site 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 1 E-8 IaCi/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 and 3.11.1.2.4.11.1.1.3 The alarm or trip set point of each radioactivity monitoring channel in Table 3.3.3.10-1 shall be determined on the basis of sampling and analyses results obtained according to Table 4.11.1.1.1.-1 and the set point method in ODCM Part 111.2.1 and set to alarm or trip before exceeding the limits of CONTROL 3.11.1.1.040809 CY-OC-1 70-301 Revision 3 Page 31 of 140 TABLE 4.11.1.1.1-1:

RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Sampling Minimum Type of Activity Analysis Lower Limit Frequency Analysis Detectiona (LLD)Frequency (RCi/ml)A. Batch Waste P pC Principal Gamma Emitters 5E-07 Release Tanks Each Each Batch 1-131 5E-07 Batchb p M Dissolved and Entrained 1 E-05 One Gases (Gamma Emitters)Batch/Mb P M H-3 1E-05 Each Composited Gross Alpha 1 E-07 Batchb P Q Sr-89, Sr-90 5E-08 Each Composited Fe-55 1 E-06 Batchb B. Reactor Building W W Principal Gamma Emitters 5E-07 Service Water Effluent Grab 1-131 5E-07 Samplee (note f) M H-3 1 E-05 Composite' Gross Alpha 1 E-07 (note f) Q Sr-89, Sr-90 5E-08 Compositeg Fe-55 1 E-06 040809 CY-OC-170-301 Revision 3 Page 32 of 140 TABLE 4.11.1.1-1 (CONTINUED)

TABLE NOTATIONS a. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular sample in the radioactive liquid waste sampling and analyses program.For a particular measurement system, which may include radiochemical separation:

LLD= 4.66

Sb E

V

2.22E6

Y

exp(-Azt)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-1 34, Cs-1 37; and an LLD of 1 E-5 gCi/ml should typically be achieved for Mo-99 and Ce-1 44.040809 CY-OC-1 70-301 Revision 3 Page 33 of 140 TABLE 4.11.1.1.1-1 (CONTINUED)

TABLE NOTATIONS 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-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 radionuclide.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall be identified and reported.The LLD for Mo-99 and Ce-1 44 is 1 E-5 gCi/mL whereas the LLD for the other gamma emitters is 5E-7 gCi/mL. Nuclides that 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 5E-7 gCi/mL of 1-131 and principal gamma emitters or in the event the effluent radioactivity monitor indicates more than 5E-7 4Ci/mL radioactivity in the effluent, as applicable, sample Reactor Building Service Water effluent daily until analysis confirms the activity concentration in the effluent does not exceed 5E-7 gCVmL. In addition a composite sample must be made up for further analysis for all samples taken when the activity was > 5E-7 g. A composite sample is produced combining grab samples, each having a defined volume, collected routinely from the sump or stream being sampled 040809 CY-OC-1 70-301 Revision 3 Page 34 of 140 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 II Section 1.5 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

040809 CY-OC-170-301 Revision 3 Page 35 of 140 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 RCi/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 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 4.11.1.3.1 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 Specifications 6.8.4.a.5.

4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting CONTROLS 3.11.1.1, 3.11.1.2, and 3.11.1.4.040809 CY-OC-1 70-301 Revision 3 Page 36 of 140 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 mrem/yr to any body organ.APPLICABILITY:

At all times.ACTION: a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).b. 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 II 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 are averaged over no more than 3 months and the dose rate due to other radionuclides is averaged no more than 31 days.040809 CY-OC-1 70-301 Revision 3 Page 37 of 140 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.

040809 CY-OC-1 70-301 Revision 3 Page 38 of 140 TABLE 4.11.2.1.2-1:

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Type of Activity Lower Limit Type Frequency Analysis Analysis Detectiona (LLD)Frequency (gCi/ml)Stack Q Q H-3 1 E-06 Grab Samplef Stack; Turbine M M Principal 1 E-04 Building Exhaust Grab Sample Gamma Vents; Augmented c,d,f Emittersb (Noble Off gas Building Gases)Vent Continuousf W 1-131 1E-12 Charcoal 1-133 1E-10 Sample Continuousf W Principal 1E-11 Particulate Gamma Sample Emittersb (particulates)

Continuous' Me Gross Alpha 1 E-11 Composite Particulate Sample Continuous Qe Sr-89, Sr-90 1E-11 Composite Particulate Sample Continuous Noble Gas Noble Gases 1 E-06 Monitor Gamma Radioactivity 040809 CY-OC-170-301 Revision 3 Page 39 of 140 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATIONS a. The Lower Limit of Detection (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a "real" signal.The LLD is applicable to the capability of a measurement system under typical conditions and not as a limit for the measurement of a particular sample in the radioactive liquid waste sampling and analyses program.For a particular measurement system, which may include radiochemical separation:

LLD 4.66

Sb E

V

2.22E6

Y

exp(-.Azt)

Where: LLD is the lower limit of detection as defined above (microcurie per unit mass or volume), S, is the standard deviation of thebackground 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 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-1 34, Cs-1 37, and Ce-1 41. Occasionally background fluctuations, 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 040809 CY-OC-170-301 Revision 3 Page 40 of 140 TABLE 4.11.2.1.2-1 (Continued)

TABLE NOTATIONS samples. The background count rate of a HpGe 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

b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be considered.

Other 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 1 E-10 gICi/ml whereas the LLD for other principal gamma emitting particulates is 1 E-i1 p.Ci/ml.Radionuclides which are below the LLD for the analysis should not be reported.c. The noble gas radionuclides in gaseous effluent may be identified by 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.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 10.040809 CY-OC-1 70-301 Revision 3 Page 41 of 140 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 II Section 2.4.1 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

040809 CY-OC-1 70-301 Revision 3 Page 42 of 140 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-1 31, 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: Less than or equal 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.ACTION: a. With the calculated dose from the release of iodine-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 Technical Specification 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 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for odine-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM Part II Section 2.5 at least once per 31 days in accordance with Technical Specification 6.8.4.a.5.

040809 CY-OC-1 70-301 Revision 3 Page 43 of 140 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 OFF GAS 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 OFF GAS SYSTEM need not be in operation during end of cycle coast-down periods when the system can no longer function due to low off gas flow.ACTION: a. Every reasonable effort shall be made to maintain and operate charcoal absorbers in the AUGMENTED OFF GAS 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.

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

SURVEILLANCE REQUIREMENTS 4.11.2.4 Operation of the Augmented Off gas System charcoal absorbers shall be verified by verifying the AOG System bypass valve, V-7-31, alignment or alignment indication closed at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the main condenser air ejector is operating.

040809 CY-OC-1 70-301 Revision 3 Page 44 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.3.

MARK I CONTAINMENT CONTROLS 3.11.3.1 Venting or purging of the containment Drywell may be through normal Reactor Building Ventilation if the following requirements are met: APPLICABILITY:

If the Station year-to-date radiological effluent releases (either iodine or noble gas) are less than 10% of the ODCM limit, then Standby Gas Treatment is NOT required for purging the contents of the Drywell.ACTION: If the Station year-to-date radiological effluent releases (either iodine or noble gas) are greater than 10% of the ODCM limit, then the Standby Gas Treatment System must be used for purging the contents of the Drywell.SURVEILLANCE REQUIREMENTS 4.11.3.1 The Standby Gas Treatment System is OPERABLE and available whenever the purge system is in use.040809 CY-OC-1 70-301 Revision 3 Page 45 of 140 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4.1 In accordance with Oyster Creek Technical Specifications 6.8.4.a.10, the annual (calendar year) dose commitment to any MEMBER OFTHE 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 3.11.4.1 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 1OCFR20.2203.

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 I 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 conditions set forth in CONTROL 3.11.4, ACTION a.040809 CY-OC-1 70-301 Revision 3 Page 46 of 140 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. Revisions to the non-ODCM required portions of the program may be implemented at any time. Non-ODCM samples are those taken in addition to the minimum required samples listed in Table 3.12.1-1.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 6.9.1.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) 1.0 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.040809 CY-OC-1 70-301 Revision 3 Page 47 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS (Continued)

ACTION: (Continued)

c. If garden vegetation samples are unobtainable due to any legitimate reason, it is NOT ACCEPTABLE to substitute vegetation from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

If a permanent sampling location becomes unavailable, follow Table 3.12.1-1 Table Notation (1) to replace the location.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 4.12.1-1.040809 CY-OC-170=301 Revision 3 Page 48 of 140 TABLE 3.12.1-1:

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE 1. DIRECT RADIATION(2)

NUMBER OF REPRESENTAIVE SAMPLES AND SAMPLE LOCATIONS(')

SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS Routine monitoring 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 (At least 16 locations);

Quarterly Gamma dose quarterly I An outer ring of stations, one in each land-based meteorological sector in the approximately 6- to 8-km range from the site (At least 14 locations);

and At least 8 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.I 040809 CY=OC-1 70-301 Revision 3 Page 49 of 140 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE 2. AIRBORNE Radioiodine and Particulates NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS Samples from 5 locations:

Three samples from close to the SITE BOUNDARY in different sectors of the highest calculated annual average ground-level D/Q.One sample from the vicinity of a community having the highest calculated annual average ground-level D/Q; and One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction (6).Continuous sampler operation with sample collection weekly or more frequently if required by dust loading.Radioiodine Canister: 1-131 analysis weekly.Particulate Sampler Gross beta radioacti-vity analysis follow-ing filter change (3;Gamma isotopic analysis(4) of composites (by location) quarterly.

040809 CY-OC-170-301 Revision 3 Page 50 of 140 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(')

SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY OF ANALYSIS 3. WATERBORNE

a. Surface b. Ground(5)c. Drinking One sample upstream One sample downstream Samples from one or two sources if likely to be affected.1 sample of each of 1 to 3 of the nearest water supplies that could be affected by its discharge.

Grab sample weekly, Combine into monthly composite.

Grab sample quarterly.

Grab sample weekly, combine into monthly composite.

Gamma isotopic and tritium analysis(4).Gamma isotopic and tritium analysis(4).

Gross beta, gamma isotopic and tritium analysis monthly (4)(7)One sample from a background location.040809 CY-OC-170-301 Revision 3 Page 51 of 140 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS d. Sediment One sample from downstream area with existing or potential recreational value.Semiannually Gamma isotopic analysis(4) semiannually.

040809 CY-OC-170=301 Revision 3 Page 52 of 140 TABLE 3.12.1-1(Cont'd)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS 4. INGESTION a. Milk (6)No milking animals If milk animals are identified:

Samples from milking animals in three locations within 5km having 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 1 mrem per year. One sample from milking animal at a control location 15 to 30 km distant and in the least prevalent wind direction One sample of available species consumed by man in plant discharge canal.One sample of available species consumed by man not influenced by plant discharge.

Semimonthly when on pasture;monthly at other times Semiannually, when available Gamma isotopic (4) and Iodine -131 semimonthly when animals are on pasture;monthly at other times Gamma isotopic analysis (4)on edible portions.b. Fish 040809 CY-OC170-301 Revision 3 Page 53 of 140 TABLE 3.12.1-1 (Cont'd)RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONS(1)SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS c. Clams One sample of available species consumed by man within the influence of the facility discharge.

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

3 samples of broad leaf vegetation grown nearest each of two different Off Site locations of highest predicted annual average combined elevated and ground level release D/Q Semiannually, when available Gamma isotopic analysis (4)on edible portions.d. Vegetation (8)Monthly during growing season Gamma isotopic analysis (4) and 1-131 on edible portion.One sample of each of the similar broad leaf vegetation grown at least 15 to 30 km (9.3-18.6 miles) distant in the least prevalent wind direction.

040809 CY-OC-1 70-301 Revision 3 Page 54 of 140 TABLE 3.12.1-1 (Continued)

TABLE NOTATIONS (1) 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. This applies to changes/deletions/additions of permanent sampling locations.

This does not apply to one-time deviations from the sampling schedule.

In those cases, it is NOT ACCEPTABLE to substitute sample media from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

(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 tho~on 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.040809 CY-OC-1 70-301 Revision 3 Page 55 of 140 (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.

Extensive studies of geology and groundwater in the vicinity of the OCGS (Reference 21 and 31) have demonstrated that there is no plausible pathway for effluents from the facility to contaminate offsite groundwater, including the local drinking water supplies.

Samples of groundwater, including local drinking water wells, are collected in order to provide assurance to the public that these water resources are not impacted.(6) The purpose of this sample is to obtain background information.

If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.

(7) 1-131 analysis on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per year.(8) If garden vegetation samples are unobtainable due to any legitimate reason (see (1)above), it is NOT ACCEPTABLE to substitute vegetation from other sources. The missed sample will be documented in the annual report, with no further actions necessary.

040809 CY-OC-1 70-301 Revision 3 Page 56 of 140 TABLE 3.12.1-2:

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES -REPORTING LEVELS Surface and Airborne Fish Milk Vegetation Analysis Ground Particulate (pCi/Kg, (pCi/I) (pCi/Kg, Water(pCi/l) and Iodine wet) wet)(pCi/m 3)H-3 20000*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 2** 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La- 140 200 300*For drinking water samples (this is the 40 CFR Part 141 value).If no drinking water pathway exists, a value of 30,000 pCi/L may be used.**If no drinking water pathway exists, a value of 20 pCi/L may be used.I 040809 CY-OC-170-301 Revision 3 Page 57 of 140 TABLE 4.12.1-1:

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1')(2) LOWER LIMITS OF DETECTION (LLD) (3)Surface and Air Vegetation Sediment Fish and Analysis Ground Particulate (pCi/Kg, (pCi/Kg, dry) Clams Water and Air wet) (pCi/Kg, wet)(pCi/I) Iodine (pCi/m 3)Gross Beta 4 0.01 H-3 2000(4)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 1(4) .07(-) 60 Cs-134 15 .05(6) 60 150 130 Cs-137 18 .06(6) 80 180 150 La- 140 15 Ba-140 60 040809 CY-OC-1 70-301 Revision 3 Page 58 of 140 TABLE 4.12.1-1 (Continued)

TABLE NOTATIONS (1) 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 Environmental 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(-AAt)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 Pico curie, 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.

040809 CY-OC-1 70-301 Revision 3 Page 59 of 140 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) If no drinking water pathway exists, a value of 3000 pCi/L for tritium and 15 pCi/L for iodine-1 31 may be used.(5) For the air iodine sample (6) For the air particulate sample 040809 CY-OC-1 70-301 Revision 3 Page 60 of 140 3/4.12 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 ft 2 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 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 elevated release 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.040809 CY-OC-1 70-301 Revision 3 Page 61 of 140 3/4.12 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.

040809 CY-OC-1 70-301 Revision 3 Page 62 of 140 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.4 METEOROLOGICAL MONITORING PROGRAM CONTROLS 3.12.4 The meteorological monitoring instrumentation channels shown in Table 3.12.4.-i shall be operable.APPLICABILITY:

At all times.ACTION: a. With less than the minimum required instrumentation channels OPERABLE for more than 7 days, initiate an Issue Report outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.c. The provisions of CONTROLS 3.0.3 and 3.0.4 are not applicable.

040809 CY-OC-1 70-301 Revision 3 Page 63 of 140 TABLE 3.12.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT ELEVATION MINIMUM INSTRUMENT OPERABLE 1 .Wind Speed a b.C.380 feet 150 feet 33 feet 2. Wind Direction 1 1 1 1 1 1 a.b.C.3. AT a.b.380 feet 150 feet 33 feet 380-33 150-33 1 1 040809 CY-OC=1 70-301 Revision 3 Page 64 of 140 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 reactor service water system discharge line radioactivity monitor initiates an alarm in the Control Room when the alarm set point is exceeded.

The alarm/trip set points 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 consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.3/4.3.3.11 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 set points 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 Off gas 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 50.040809 CY-OC-1 70-301 Revision 3 Page 65 of 140 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 design objectives of Appendix 1, 10 CFR 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 or entrained noble gases is based upon the assumption that Xe-1 35 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.The value 1E-8 is the limit for unidentified gross gamma or beta-releases as per 10 CFR 20 Appendix B, Table 2, Column 2 "any single radionuclide...

other than alpha or spontaneous fission ... half life 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.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 27.3/4.11.1.2 DOSE This CONTROL is provided to implement the requirements of Sections II.A, Ill.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 same 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 and 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 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 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 1.113.040809 CY-OC-170-301 Revision 3 Page 66 of 140 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 will 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 IL.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, III.A and IV.A of Appendix 1, 10 CFR Part 50. The CONTROL implements the guides set forth in Section 11.B 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 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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on 040809 CY-OC-1 70-301 Revision 3 Page 67 of 140 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 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 for 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 1, 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 of Appendix 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-1 31, iodine-1 33, tritium, and radionuclides in particulate form with half -life greater than 8 days are dependent on the e.xisting radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY.

The pathways that were examined in the development of these 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 OFF GAS TREATMENT SYSTEM The OPERABILITY of the AUGMENTED OFF GAS TREATMENT SYSTEM (AOG) ensures that the system will be available for use Whenever gaseous effluents require treatment prior to release to the environment.

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 achievable." 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 lI.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.

040809 CY-OC-1 70-301 Revision 3 Page 68 of 140 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 FR 18525. 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 the 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 exceed the dose limits of 40 CFR Part 190 if the doses remain within twice the dose design objectives of Appendix I, 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 3.11.1.1 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.040809 CY-OC-170-301 Revision 3 Page 69 of 140 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 used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m 2 (500 ft 2) 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/im 040809 CY-OC-170-301 Revision 3 Page 70 of 140 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 that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.5.0 5.0 DESIGN FEATURES I 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-4.040809 CY-OC-1 70-301 Revision 3 Page 71 of 140 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.6.1.2 The Annual Radiological Environmental Operating Reports shall include: 6.1.2.1 Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities (Radiological Environmental Monitoring Program -REMP)for the report period. This will include a comparison with preoperational studies, with operational controls (as appropriate), and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.

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 of irreversible 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 Environmental 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.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 4.12.1-1.040809 CY-OC-1 70-301 Revision 3 Page 72 of 140 6.2 ANNUAL ROUTINE RADIOACTIVE EFFLUENT RELEASE REPORT (RERR)6.2.1 Routine radioactive effluent release reports covering the operation of the unit shall be submitted prior to May 1 of each year and in accordance with the requirements of 1OCFR50.36a and section IV.B.1 of 10CFR 50 Appendix I.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 tlie 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 of joint 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 OFF SITE 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).

6.2.2.5 An assessment of radiation doses to the likely most exposed MEMBER, and 3.2.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, Environmental Radiation Protection Standards for Nuclear Power Operation.

The assessment of radiation doses shall be performed in accordance with this OFF SITE DOSE CALCULATION MANUAL (ODCM) Part II Sections 1.5, 2.4, 2.5 040809 CY-OC-1 70-301 Revision 3 Page 74 of 140 PART I1 -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 (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-1-la and D-1-1 b.1.2 LIQUID EFFLUENT MONITOR SET POINT DETERMINATION Per the requirements of CONTROL 3.3.3.10, alarm set points shall be established for the liquid monitoring instrumentation to ensure that the release concentration limits of CONTROL 3.11.1.1 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 pCi/ml for dissolved or entrained noble gases).1.2.1 LIQUID EFFLUENT MONITORS The set points for the liquid effluent monitors at the Oyster Creek Generating Station are determined by the following equation: A4 F2 S A g -+ BKG FLEC F I Where: S = radiation monitor alarm set point (cpm)A = activity concentration (pLCi/ml) of sample in laboratory:

A = XC 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 gICi/mL).Fi = flow in the batch release line (e.g. gal/min).

Value not greater than the discharge line flow alarm maximum set point.040809 CY-OC-170-301 Revision 3 Page 73 of 140 6.2.2.6 The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by 10 CFR Part 61)shipped Off Site during the report period (see Figure D-1-2): a. Total volume shipped 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 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 OFF SITE DOSE CALCULATION MANUAL (ODCM) in the form of a complete, legible copy of the ODCM.6.3 RESPONSIBILITIES:

-6.3.1 Chemistry

/ 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 compliance with specifications regarding set point determination and implementation 6.3.4 Radiological Engineering

-Responsible for technical consultation and review.040809 CY-OC-1 70-301 Revision 3 Page 75 of 140 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 pCi/mL. If the concentration in a expected release is 6E-6 gCi/mL; then FLEC is 6E-6/3E-6

= 2.The term AL represents the count rate of a solution having the same nuclide FLEC 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 (jaCi/mL).

LECG = 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 (pCi/mL).In the event gross radioactivity analysis alone is used to determine the radioactivity in an effluent stream or batch, FLEC is C/1 E-8 (see 4.11.1.1.1), Where: C = The gross radioactivity concentration in effluent (jiCi/mL).

1 E-8 = The unrestricted area LEC for unidentified radionuclides (gCi/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, 1 E-8 liCi/mL, or the equivalent counting rate (cpm/mL) may be substituted for the factor A FLEC A =1E-8 iCi/mL FLEC 1.2.2 SAMPLE RESULT SET POINTS Usually, when the concentration of specific radionuclides is determinable in a sample(s), i.e., greater than the LLD, the alarm/trip set point 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 SET POINTS 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 040809 CY-OC-170-301 Revision 3 Page 76 of 140 based upon past measurements of the effluent stream or upon a computed distribution.

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 set point 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 is 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 set point of the corresponding effluent radioactivity monitor in order to determine a representative value. In each case, whether batch or continuous, the monitor alarm/trip set point may be set at lower activity concentration than the calculated set point.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 1 OCFR50. Calculations will be performed at least monthly for all liquid effluents as stated in SURVEILLANCE REQUIREMENT 4.11.1.2 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.040809 CY-OC-1 70-301 Revision 3 Page 77 of 140 1.5.1 MEMBER OF THE 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 Quarter 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-4.1.5.2 SHORELINE DEPOSIT DOSE The shoreline exposure pathway dose is calculated generally in the form (based on Reg. Guide 1.109): Rapj = 1 1 0 0 0 0 UapWM QiTiDaipj(l

-exp(-kiTb))

F Where: 110000 = a constant that accounts for time and 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 040809 CY-OC-1 70-301 Revision 3 Page 78 of 140 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, and 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-6 through E-1 4 ki = the decay constant of the ith isotope in years Tb = the long term buildup time, assumed to be 30 years Note: Xi and Tb 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 liquid dose calculation:

Initial parameters:

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

Release: 10,000 gallons of water at 1 E-3 pCi/ml Co-60 Problem: calculate shoreline whole body dose Uap = 67 (teenager) hours W =0.1 M =.3.76 F = 2228 [1 E6 gpm *3785 ml / gal / (60 sec/min

28316 ml/ft 3) = 2228 CFS]Qi = 0.03785 Ci [1 E-3uCi/ml

1 0000gal

3785ml/gal

= 0.03785 Ci]Ti = 1930 (5.27 years*365.25days/yr

= 1.93E3 days)= 1.31 E-1 [0.693 / (5.27 yrs)]Tb = 30 years Daipj = 1.7E-8 mrem/hr / pCi/m 2 Gamma dose factor Calculate Rapj for a = Teen, j = total body, p = shoreline dose for one isotope 67 *0. 1* 3.76 Rapj = 11006 I 0.1L: *37 0.03785" 1930

1.7E -8 * (I -exp(-1.3E

-1 *30))2228 Rapj =1.5E -3 mrem: teen: wholebody 040809 CY-OC-170-301 Revision 3 Page 79 of 140 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 Z 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-1 4. 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-I.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.

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

Initial parameters:

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

Release: 10000 gallons of water at 1 E-3 gCi/mLl Co-60 Problem: calculate teen whole body dose from saltwater fish ingestion Rapj = 1100 UapM QiBipDaipj F Uap = 16 (teenager)

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

28316 ml/ft 3) = 2228 CFS]Qi = 0.03785 Ci [1 E-3uCi/mL

10000

3785 = 0.03785 Ci]Bip = 100 Daipj = 6.33E-6 mrem / pCi 040809 CY-OC-1 70-301 Revision 3 Page 80 of 140 Calculate Rapj for a = Teen, j = total body, p = fish ingestion dose for one isotope 16 *3. 76 Rapj = 1100 0.03785

100

6.33 E -6 2228 0 Rapj = 7.12 E -4mrem : teen : wholebody 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.

040809 CY-OC-1 70-301 Revision 3 Page 81 of 140 2.0 GASEOUS EFFLUENTS 2.1 RADIATION MONITORING INSTRUMENTATION AND CONTROLS The gaseous effluent monitoring instrumentation and controls at Oyster Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent CONTROLS are summarized as follows: (1) Main Stack The main stack receives normal ventilation flow from the reactor building, new radwaste, old radwaste, process discharge flow from the augmented off gas system (AOG), condenser off gas 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.

Off gas flow is processed through AOG or through a 30-minute delay pipe prior to release. Flow from the 'new' and 'old' radwaste buildings is HEPA filtered.Releases through the main stack are monitored for noble gases using the RAGEMS I 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 II. 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 Gas Building Vent Off gas Building HVAC is released through a ground level release from the building.Off Gas process flow is not released through the building ventilation, but is routed To the stack plant. A ventilation monitoring system monitors for noble gas and samples for particulate and iodine.040809 CY-OC-1 70-301 Revision 3 Page 82 of 140 (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 SET POINT DETERMINATION 2.2.1 PLANT VENT Per the requirements of CONTROL 3.3.3.11, alarm set points 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, Off gas process flow, etc.), the radiation monitoring alarm set points may be established by the following calculation methods. A set point of a monitor of an elevated release, e.g., from the stack, may be calculated using the equation: S = 1.06 Bkg f (CiD~i) +k where: S = the alarm set point (cpm)h = primary conversion factor of the instrument

-monitor response to activity concentration of effluent being monitored, cpm/(gCi/cm 3). 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 (pCi/cm 3)1.06 = 500 mrem/year

/472 (conversion of cfm to cc/sec)DFSi = factor converting elevated release rate of radionuclide i to total body dose equivalent rate at the location of potential exposure.

Units are: mrem/(yr(pCi/sec)).

From Table A-I.f = flow of gaseous effluent stream being monitored, i.e., stack flow, vent flow, etc.(ft 3/min)040809 CY-OC-1 70-301 Revision 3 Page 83 of 140 BKG = Monitoring instrument background (cpm or mR/hr)2.2.2 OTHER RELEASE POINTS The set point of a monitor of a ground-level or split-wake release, e.g., from the turbine building vent or the AOG building, may be calculated with the equation: S=1. h ___Ci S = 1.06 (CiDFVi) + Bkg Where: DFVi = factor converting ground-level or split wake release of radionuclide i to the total body dose equivalent rate .at the location of potential exposure.

Units are: mrem/(yr(lgCi/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/m 3) from Table 2.2.2-4.The atmospheric dispersion, X/O, and the dose conversion factor, DFSi, depend upon local conditions.

For the purpose of calculating radioactive noble gas effluent monitor alarm set points appropriate for the OCGS, the locations of maximum potential Off Site exposure and the reference atmospheric dispersion factors applicable to the derivation of set points are given in Table 2.2.2-1.TABLE 2.2.2-1 RECEPTOR LOCATIONS AND DISPERSION FOR GASEOUS MONITOR SET POINTS.Discharge Point Receptor Location Atm. Dispersion Sector Distance(m) (sec/m 3)Ground-level or vent SE 522 1.36 E-5 Stack SE 522 1.09 E-8 2.2.3 RADIONUCLIDE MIX FOR SET POINTS For the purpose of deriving a set point, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways: 040809 CY-OC-1 70-301 Revision 3 Page 84 of 140 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-1 33 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 3.11.2.1a 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 set points are established to ensure that these release limits are not exceeded.

In the event any gaseous releases from the station results in an alarm set point (as determined in Section 2.2) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed.

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= ZQiP2Si From a ground-level release (building vent) the total body dose equivalent rate is: x DG = jQiP /i QV t 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 (gCi/hr)PyVi = factor converting time integrated ground-level concentration of noble gas nuclide i to total body dose mrem -m3. See Table A-2.gCi -sec 040809 CY-OC-1 70-301 Revision 3 Page 85 of 140= atmospheric dispersion factor from the OCGS to the Off Site location of interest Qv (sec/m 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/gCi).

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 1, Table B-1, Column 5.2.3.1.2 EXAMPLE TOTAL BODY DOSE RATE Calculate the dose from a release of 100 Ci of Xe133 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release DG = -QiP Vi Qv X/Qv = 1.36E-5 sec/m3 (Table 2.3.1.3-1)

Qi =lE8gICi/hr

[100Ci*1E6.tCi/Ci]

PyVi = 9.33E-6 mrem-m 3 / IgCi-sec DG =1.36E-5Z1E8*9.33E-6 DG=0.013 mrem/hr 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: Q X where: DB = dose rate to skin from radioactive noble gases (mrem/hr)X-= Atmospheric dispersions from gaseous effluent discharge point to ground-level location o of interest (sec/m3) from Table 2.3.1.3-1.

040809 CY-OC-1 70-301 Revision 3 Page 86 of 140 0i = discharge rate of noble gas radionuclide i (jiCi/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.pCi

sec AyVi = factor for converting time integrated, semi-infinite concentration of noble gas radionuclide mrad -m3 i to air dose from its gamma mra -Sm from Table A-2.jiCi

sec The noble gas beta radiation-to-skin-dose factors, SBi and the noble gas gamma-to-air dose factors, AyV 1 , 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.

040809 CY-OC-1 70-301 Revision 3 Page 87 of 140 TABLE 2.3.1.3-1 RECEPTOR LOCATIONS AND DISPERSION FOR SITE BOUNDARY DOSE RATES Discharge Point Receptor Location Atm. Dispersion Sector Distance (W) (sec/m 3)Ground Level SE 522 1.36 E-5 or Vent Stack SE 522 1.09 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") 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.2.3.1.4 EXAMPLE SKIN DOSE RATE Calculate the skin dose from a release of 100 Ci of Xe133 in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from a ground level release: DB = -x Qi ( SBi + l1.11 A ;yVi)QI X/Q = 1.36 E-5 sec/m3 Qi = 1 SBi = 9.71 E-6 AyVi = 1.12E-5 DB = 1.36E- 5 -5Z 1E8(9.71E

-6 + 1. 1 *1.12E -5)DB = O.O030mrad

/hr 2.3.2 SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES 2.3.2.1 METHOD -SITE BOUNDARY DOSE RATE -RADIOIODINE AND PARTICULATES The dose rate Off Site due to the airborne release of 1-131, 1-133, 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 3.11.2.1 b is based on the sampling and 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 contribution 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 040809 CY-OC-1 70-301 Revision 3 Page 88 of 140 integration or compositing times. The equation used to assess compliance of radioiodine, tritium, and radioactive particulate releases with the dose rate limit is: DRp = 1E6Y I RaDFAijaQe i-e i Qe where: 1 E6 = conversion pCi/pCi DRp = the average dose rate to an organ via exposure pathway, p (mrem/yr).

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 dependent inhalation respiratory rate (usage factor) m 3/yr from Table B-1 Y X- annual average relative airborne concentration at an Off Site location due to a release Oe from either the Stack or a Vent, i.e. release point, e (sec/mr) from Table 2.3.2.1-1.

Qei = release rate of radionuclide i from release point, e during the period of interest (p.Ci/sec).

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 3.11.2.1b for tritium, iodine, and particulate, the air dispersion (X/Q) values are provided in Table 2.3.2.1-1.

040809 CY-OC-170-301 Revision 3 Page 89 of 140 TABLE 2.3.2.1-1 LOCATION OF MAXIMUM EXPOSURE RE BY INHALATION Discharge Point Receptor Location Atm. Dispersion Sector Distance (m) (sec/m3)Ground Level or Vent SE 522 1.36 E-5 Stack SE 522 1.09 E-8 Alternatively, inhalation exposure to effluent from the stack may be evaluated at the closest hypothetical individual located at: Stack SE 966m 1.19 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") 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 gCi/hr of 1131 from a ground level release: n DRp = 1E67.- Y RaDFAijaQei--

Qe Ra 3700 m 3/yr DFAija= 4.39E-3 Qei = 0.028 jiCi/sec [1 OO1Ci/hr /3600 sec/hr = 0.02778]X/Qe = 1.36 E-5 DRp = 1E6- 3700

4.39E -3* 0.028

1.36E -5 DRp = 6.2mrem / 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 10CFR50. 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 2.4.1-1.040809 CY-OC-1 70-301 Revision 3 Page 90 of 140 TABLE 2.4.1-1 ANNUAL AIR DOSE LIMITS During any calendar quarter During any calendar year_ 5 mad gamma-air 10 mad gamma-air_ 10 mad beta-air 20 mad 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 Off Site due to gamma and beta radiations from effluent noble gas.2.4.1.1 AIR DOSE METHOD a: For Gamma Radiation:

n x Dose A i A -vQvi + A AiQsi i=I Q b: For Beta Radiation Dose/i I 1 A/-X--eQei where: Dose y =the gamma dose during any specified time period (mrem).Dose fP=the beta dose during any specified time period (mrad).AyV 1 = the air dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per gCi/m 3). Table A-2 AySj = the factor for air dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per gCi), Table A-3.Ap3i = the air dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per gCi/m 3). Table A-3 or x =the annual average relative concentration for areas at or beyondthe site-e Q Q .boundary for releases from either the Stack or ground vent at the critical location (sec/m 3), Table 2.4.1.1-1 Qvi = amount of radionuclide i released from vents (40Ci).Qsi = amount of radionuclide i released from the Stack (gCi).040809 CY-OC-170-301 Revision 3 Page 91 of 140 Qei = amount of radionuclide i released from release point e(gCi).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 Off Site 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. AyVi and ABi are derived from Reg. Guide 1.109, Table B-1 for a semi-infinite cloud, independent of meteorology or location.

Values of AySi, ATVi 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.

040809 CY-OC-1 70-301 Revision 3 Page 92 of 140 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 1.36 E-5 or Vent Stack SE 522 1.09 E-8 Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") 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 1 Ci per hour of Xe133 for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from a ground level release and 10OCi per hour for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months from an elevated release: Dose y =A Wj-vQvi + A ýSiQsi= 1.12E-5 mrad -m 3/gCi -sec X/Q = 1.36 E-5 Qvi = 1E7 1.Ci [lCi/hr*10hrs*lE6

[Ci/Ci]A7Si = 5.45E-1 3 mrad / pCi Qsi = 1 E9 iCi [10Ci/hr*l 0hrs*l E6 jCi/Ci]n i=1 Dosey= Y1.63E-3-3+5.45E-4 i=1 Dosey = 2.2E -3mrad Note how the ground level portion has a higher dose contribution per unit activity than the elevated portion.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 must be added to the beta dose to obtain a total skin dose.040809 CY-OC-170-301 Revision 3 Page 93 of 140 a: For Total Body: Doset=

P)SiQsi i=1 Q b: For Skin Doses = S/ik-eQei

+ Doset e i=where: Doset = the total body dose during any specified time period (mrem), Doses= the skin dose during any specified time period (mrad).PyVi = the plume dose factor due to ground level gamma emissions for each identified noble gas radionuclide, i; (mrad/yr per liCi/m 3). Table A-5 PyS 1 = the factor for plume dose at ground level due to irradiation for an airborne plume resulting from a Stack release (mrad per giCi), Table A-5.SP = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i (mrad/yr per gCi/m 3) from Table A-5.-oX = the annual average relative concentration for areas at or beyond the site X or -V--e e Q boundary for releases from either the Stack or ground vent at the critical location (sec/m 3) from Table 2.5.1.Qvi = amount of radionuclide i released from vents (pCi).Qsi = amount of radionuclide i released from the Stack (gtCi).Qei = amount of radionuclide i released from release point e (90Ci).040809 CY-OC-1 70-301 Revision 3 Page 94 of 140 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 1 OCFR50. 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 THE 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 X/Q (sec/m 3) D/Q(1/m 2)Ground Level or Vent 4.86 E-6 1.41 E-8 Stack 1.19 E-8 1.74 E-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 highesf for those pathways.

Receptor locations are provided in Table A-4.Alternatively, an approved computer code (e.g., "SEEDS" or "Open EMS") that implements the requirements of Reg Guide 1.109 may be used.040809 CY-OC-170-301 Revision 3 Page 95 of 140 2.5.1 INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES.

Dose from the inhalation pathway is generally in the form: Dja = RaT>i iQ Where: Dja = the dose to the organ j (of eight) of age group a (of four)Ra = the respiration rate for age group a from Table B-1 T = the duration of the release in fraction of a year x/X = The atmospheric dispersion-to the point of interest (the 'receptor')

in sec/m 3 from Q -Table 2.5-1 Qi = The release rate of radionuclide i (pCi/sec)DFAija= The inhalation dose conversion factor (mrem per pCi) for radionuclide i to organ j of age group a from Reg. 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' (dX/Q) is applicable to 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.040809 CY-OC-1 70-301 Revision 3 Page 96 of 140 2.5.2 EXAMPLE CALCULATION

-INHALATION OF RADIOIODINES, TRITIUM, PARTICULATES, AND OTHER RADIONUCLIDES Calculate the dose to child lung from inhalation from a ground level release of 100 gCi 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(-]3iTr)=1).

Dja =3700*0.00114*

1.53E -5

2.78E3 *1.91E-3 Dja = 3.4E- 4mrem Dja= RaTZ---QiDFAija i Q Dja = the dose to the organ j (of eight) of age group a (of four)Ra = 3700 m 3/yr T = 0.00114 yrs [10 hrs/8760 hrs / yr]X- = 1.53 E-5 sec/m 3 Qi = 2.78E3 pCi/sec [100 Ci* 1 E6 pCi/gCi / (10 hrs*3600 sec / hr)]DFAija=1.91 E-3 mrem / pCi 2.5.3 INGESTION OF RADIOIODINES, 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

-OTHER 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: Where: Civ = the concentration (pCi/kg) of radionuclide i in vegetation Qi = the release rate of isotope i in pCi/hr D = The atmospheric deposition to the point of interest (the 'receptor')

in 1/M 2 from Q Table 2.5-1.040809 CY-OC-1 70-301 Revision 3 Page 97 of 140 Civ D Qi { (Z (-ETe))Yv+Ei Biv(1 -EXP(-AiTb))

EXP(-AiTh)EXP(-AiTr)

Q YvA~iPAi 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 XEi = the effective removal constant which is the sum of Xi + Xw where ýw 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-1 5 of Reg. Guide 1.109 or Table B-1.Yv = agricultural yield Kg of vegetation per M 2 , typically 0.7 kg/m 2 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.Tb = the length of time the soil is exposed to contaminated inputs -nominally 30 years (2.63E5 hr)P = effective soil density in kg/m 2 normally 240 kg/m 2 Th = holdup time, the time the foodstuff is in transit between harvest and consumption in hours Tr = plume transit time 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 [0Ci 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=O, EXP(-XiTr)=1):

D/Q = 1.41E-8m 2 Qi = 1 E7 pCi/hr [1 OOtCi

1 E6 pCi/jtCi / 10 hr]r = 0.2 Mi = 1.5E-5/hr

[0.693 / (5.27yr

8760 hr/yr)]XEi = 2.1E-3/hr

[1.5E-5 + 0.0021]Te = 720 hr [grass-cow-milk-man pathway value]Yv = 0.7 kg/m 2 Biv = 9.4E-3 040809 CY-OC-1 70-301 Revision 3 Page 98 of 140 Civ=QQi r(1 -EXP(-2EiTe))

+ Biv(1 -EXP(-2iTb))

EXP(_A.Th)EXP(_2iTr)

Civ = 1.41E-8*1E7j

¢, 0.2 * (1 -EXP(-2. 1E -3

720)) +0.7*2.1E-3 9.4E- 3 * (1- EXP(-1.5E-5

2.63E5))-5*0)240*1.5E-5 Civ = 1.41E-8*1E7{

0.2 * (1- EXP(-1.52))

+1.47E -3 9.4E -3 * (1- EXP(-3.95))

}EXP(-O)3.6E -3 Civ = 1.41E -1 {2056 Civ = 15.3 pCi / Kg Tb = 2.63E5 hr P = 240 kg/m2 Th = 0 hr (consumption of pasture grass directly by animals)2.5.3.3 CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION Since tritium is assumed to be released as tritiated water (HTO), 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(-DiTr) is ignored since plume travel times are very short compared to the half life): Ctv = 1000Qt x-* 0.75

0.5 Q H Where: 'Ctv = the concentration (pCi/kg) of tritium in vegetation 040809 CY-OC-1 70-301 Revision 3 Page 99 of 140 1000= g 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 H = the absolute humidity g/m 3.Absolute humidity is seasonally dependent, varying from as little as 1 in the winter to as much as 20 in the summer. Monthly average values derived from historical data are provided in Table B-2.2.5.3.4 EXAMPLE CALCULATION OF CONCENTRATION OF TRITIUM IN ANIMAL FORAGE AND VEGETATION.

Calculate the forage and vegetation concentration from a ground level release of 100 piCi 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(-XiTr)=1):

Ctv -= Ioooatx * .75 ,* ..5 Q H Ot = 2778 pCi/sec [100uCi

1EGpCi/uCi

/ (10hrs*3600sec/hr)]

X/Q = 4.86E-6 sec/m 3 H = 5 g/m 3 (assumed for this example)Ctv = 2778

1000

4.86E -6

0.75* 0.5 5 Ctv= 1.OpCi/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(1 -Fs) + CipFs(1 -Fp)040809 CY-OC-170-301 Revision 3 Page 100 of 140 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-1 or Exhibit E-15 from Reg. Guide 1.109.Cip = the concentration in the fresh pasture feed (Civ from section 2.5.3.2 with Th = 0 for immediate consumption)

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 = FmCivQfEXP

(-AiTf)Where;Cim = the concentration in milk pCi/I Fm = the transfer coefficient of intake to concentration in the milk (d/1) from Reg. Guide 1.109 Table E-1.Qf = feed intake rate Kg/d from Reg. Guide 1.109 Table E-3.Xi = radionuclide i decay constant in 1/days Tf = transport time from milk production to consumption (2 days for milk)The Goat milk pathway may be similarly evaluated:

Cim = FgCivQfEXP

(-2iTf)Where Fg = the transfer coefficient of intake to concentration in the milk (d/1) for goats from Reg. Guide 1.109 Table E-2.And for meat: Cif = FfCivQfEXP

(-AiTs)Where: Ff = the transfer coefficient of intake to concentration in the meat d/kg from Reg.Guide 1.109 Table E-1.Ts = The transport time from slaughter to consumption (20 days)040809

, CY-OC-170-301 Revision 3 Page 101 of 140 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 gCi 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)=l):

Civ = FpCis + (1 -Fp)Cis(1 -Fs) + CipFs(l -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.!pCil kg The concentration in milk is given by: Cim = FmCivQfEXP

(-2iTf)Fm =1.OE-3 d/I Of = 50 Kg/d xi = 3.6E-4/d [0.693 / (5.27yrs*365.25days/yr)]

Cim= 1.0E- 3 *18.1*50*

EXP(-3.6E-4* 2)Cim = 0.9OpCi/ I The concentration in meat given by: Cif = FfCivQfEXP

(-AiTf)Ff =1.3E-2 d/kg Of = 50 Kg/d Ai = 3.6E-4/d Cif = .3E- 2

18.1

50

EXF(-3.6E

-.4

20)Cif = 11.7 pCi / kg 040809 CY-OC-170-301 Revision 3 Page 102 of 140 2.5.3.7 DOSE FROM CONSUMPTION OF MILK, MEAT, AND VEGETABLES The environmental pathway ingestion dose is the sum of the milk, meat, and vegetation ingestion pathways.

There are two separate pathways for 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 = T DFlija[UavFgCiv+

UamCim+ UafCif + UalFlCiI]Where: Dja = the dose to organ j of age group a -mrem T = fraction of year of release duration DFlija = the ingestion dose factor for isotope i to organ j for age group a -mrem/pCi from Reg.Guide 1.109 Appendix E 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 Table B-I.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.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.Uaf = the ingestion rate for meat for age group a: from Table B-1 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-1 or Reg.Guide 1.109 Table E-5.040809 CY-OC-170-301 Revision 3 Page 103 of 140 Fl the fraction of annual leafy vegetable ingestion from the location of interest : 1.0 in Reg. Guide 1.109.Cil Civ= concentration of isotope i in the leafy vegetables for direct human consumption:

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)=l):

Dja = Tj DFIija[UavFgCiv+

UamCim+ UafCif + UaFlCit]T = .00114 [1Ohrs / 8760 hrs/yr)DFlija= 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 =1 Cil = 18.4 Dja =.00114-1.56E-5[520*0.76*18+

330*0.9+ 41*11.7 + 26*1 *18.4]Dja= .0011411.56E-5[7114+

297+ 480+478]Dja = 1.5E -4mrem: child: wholebody 2.5.4 GROUND PLANE DEPOSITION IRRADIATION Dose from ground plane deposition is estimated by determining the surface activity resulting from the release.2.5.4.1 GROUND PLANE CONCENTRATION The ground surface activity is estimated as: Cig = D (1 -EXP(-AiTb))

QWee Where: 040809 CY-OC-1 70-301 Revision 3 Page 104 of 140 Cig ground plane concentration of radionuclide i in pCi/mr 2 D = local atmosphieric release deposition factor in 1/M 2 from Table 2.5-1 Q Qi = release rate in pCi/sec Xi = radiological decay constant in 1/sec Tb = long term buildup time 30 years (9.46E8 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 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.Cig = D Qi (- EXP(-iTb))

D =1.41 E-8/m 2 Q Qi = 2778 pCi/sec [100gC i/10hrs/3600sec/hrJ Xi = 4.17E-9/sec

[0.693/(5.27yr*8760hr/yr*3600sec/hr)]

Tb = 9.46E8 sec Cig = 1.41E -8 2778 (1- EXP(-4.17E

-9

9.46E8))4.17E-9 Cig=141E-82778 Cig = 1.41E -8 2778 , (1 -EXP(-4.17 E -9

9.46E8))Cig = 1.1lE4pCi/m2 2.5.4.3 GROUND PLANE DOSE Annual dose from the ground plane deposition is of the form: Djg = 8760*T

Sf CigDFGij Where: Djg = the annual dose (mrem) from ground plane pathway (g) to the total body or skin (j)8760 = hours in a year 040809 CY-OC-1 70-301 Revision 3 Page 105 of 140 T = fraction of year release is in progress Sf = shielding factor accounting for shielding from dwelling from Table B-1 DFGij = Ground plane dose factor for skin or total body (j) 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 gCi 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*SfjCigDFGij T = 0.00114 [10/8760]Sf =0.7 DFGij 1.7E-8 Djg = 8760*0.00114*0.7Z9729*J.7E-8 Djg = 1.15E -3mremTotalBody 3.0 TOTAL DOSE TO MEMBERS OF THE PUBLIC -40 CFR 190 The Radiological Environmental Monitoring Report (REMP) submitted by May 1st of each year shall include an assessment of the radiation dose to the likely most exposed MEMBER OF THE 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.As appropriate for demonstrating/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 040809 CY-OC-1 70-301 Revision 3 Page 106 of 140 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) may be 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.040809 CY-OC-170-301 Revision 3 Page 107 of 140 APPENDIX A -DERIVED DOSE FACTORS AND RECEPTOR LOCATIONS 040809 CY-OC-170-301 Revision 3.Page 108 of 140 Table A-1 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 gCi-year gCi-year* Based on reference meteorology applicable at 522 meters SE of stack.** For exposure to a semi-infinite cloud of noble gas.040809 CY-OC-1 70-301 Revision 3 Page 109 of 140 I Table A-2 Noble Gas Radionuclide-to-Dose Equivalent Rate Factors* I Radionuclide PSi** PVi*** AYVi*** SBi***mrem mrem-m 3 mrad-m 3 mrem-m 3 gCi pCi-sec (Ki) pCi-sec (M) pCi-sec (Li)Kr83m 4.66E-17 2.40E-09 6.13E-07 Kr85m 2.91E-12 3.71E-05 3.90E-05 4.63E-05 Kr85 4.66E-14 5.11E-07 5.46E-07 4.25E-05 Kr87 1.52E-1 1 1.88E-04 1.96E-04 3.09E-04 Kr88 3.73E-1 1 4.67E-04 4.83E-04 7.52E-05 Kr89 3.70E-11 5.27E-04 5.49E-04 3.21E-04 Kr90 4.95E-04 5.17E-04 2.31E-04 Xe131m 6.65E-13 2.90E-06 4.95E-06 1.51 E-05 XeI33m 5.20E-13 7.97E-06 1.04E-05 3.16E-05 Xe133 4.97E-13 9.33E-06 1.12E-05 9.71E-06 Xe135m 8.78E-12 9.90E-05 1.07E-04 2.26E-05 Xe135 4.78E-12 5.75E-05 6.1OE-05 5.90E-05 Xe137 3.36E-12 4.51E-05 4.79E-05 3.87E-04 Xe138 2.42E-11 2.80E-04 2.92E-04 1.31 E-04 Xe139 4.56E-12 --Ar4l 2.89E-1 1 2.81 E-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-1.040809 CY-OC-1 70-301 Revision 3 Page 110 of 140 Table A-3 Air Dose Conversion Factors for Effluent Noble Gas Radionuclide AySi** AyVi*** Ai***mrad mrad-m3 mrad-m3 gCi 1 tCi-sec(Mi) pCi-sec (Ni)** Based on reference meteorology at 522 meters SE of effluent stack.*** Derived from Reg Guide 1.109, Revision 1, Table B-1.040809 CY-OC-170-301 Revision 3 Page 111 of 140 Table A-4 Locations Associated with Maximum Exposure of a Member of the Public*Liquid U.S. Route 9 Bridge at Discharge Canal Airborne Iodine and Particulates Tritium 966 966 966 Noble Gases SE SE SE All All SE Irradiation by OCGS Noble Gas g Air Dose Noble Gas B Air Dose Site Boundary Site Boundary 966 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 1.040809 CY-OC-1 70-301 Revision 3 Page 112 of 140 Table A-5 Critical Receptor Noble Gas Dose Conversion Factors*Radionuclide PTSi** PyTi*** AYVi*** AYSi** SBi***mrem mrem-m 3 mrad-m 3 mrad mrem-m 3 RCi ýtCi-sec(Ki) gCi-sec(Mi) ltCi gtCi-sec(Li)

Kr83m 3.76E- 17 2.40E-09 6.13E-07 9.66E- 15 -Kr85m 1.68E-12 3.71E-05 3.90E-05 1.75E-12 4.63E-05 Kr85 2.60E-14 5.11E-07 5.46E-07 2.75E-14 4.25E-05 Kr87 8.37E-12 1.88E-04 1.96E-04 8.81E-12 3.09E-04 Kr88 2.08E-11, 4.67E-04 4.83E-04 2.18E-11 7.52E-05 Kr89 1.83E-1 1 5.27E-04 5.49E-04 1.93E-1 1 3.21 E-04 Kr9O 4.95E-04 5.17E-04 -2.31E-04 Xel31 m 3.99E-13 2.90E-06 4.95E-06 4.44E-13 1.51 E-05 Xe133m 3.1OE-13 7.97E-06 1.04E-05 3.58E-13 3.16E-05 Xe133 3.11E-13 9.33E-06 1.12E-05 3.42E-13 9.71E-06 Xe135m 4.71E-12 9.90E-05 1.07E-04 5.01E-12 2.26E-05 Xe135 2.73E-12 5.75E-05 6.1OE-05 2.87E-12 5.90E-05 Xe137 1.65E-12 4.51E-05 4.79E-05 1.75E-12 3.87E-04 Xe138 1.33E-1 1 2.80E-04 2.92E-04 1.40E-1 1 1.31 E-04 Xe139 --1.61E-12 -Ar4l 1.58E-1 1 2.81 E-04 2.95E-04 1.66E-1 1 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-1 040809 CY-OC-170-301 Revision 3 Page 113 of 140 APPENDIX B -MODELING PARAMETERS 040809 I CY-OC-1 70-301 Revision 3 Page 114 of 140 Table B-1 -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/m2 ) 2.4E+2 Fraction Of Deposited Activity Retained On Vegetation 2.5E-1 Shielding Factor For Residential Structures 7.OE-1 Period Of Buildup Of Activity In Soil (hr) 1.31 E+5 Period of Pasture Grass Exposure to Activity (hr) 7.2E+2 Period Of Crop Exposure to Activity (hr) 1.44E+3 Delay Time For Ingestion Of Stored Feed By Animals (hr) 2.16E+3 Delay Time For Ingestion Of Leafy Vegetables By Man (hr) 2.4E+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/m2) 7.0E-1 Other Vegetation Yield Wet-Weight (Kg/m2) 2.0 Weathering Rate Constant For Activity on Veg. (hr" 1) 2.1 E-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 (L/day) 6.0E+1 Goat Water Consumption Rate (Llday) 8.0 Beef Cattle Water Consumption Rate (L/day) 5.0E+1 Environmental Transit Time For Water Ingestion (hr) 1.2E+1 Environmental Transit Time For Fish Ingestion (hr) 2.4E+1 Environmental Transit Time For Shore Exposure (hr) 0 Environmental Transit Time For Invertebrate Ingestion (hr) 2.4E+1 040809 CY-OC-1 70-301 Revision 3 Page 115 of 140 Table B-1 (Continued)

OCGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Water Ingestion (L/yr)a. Adult 7.3E+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+1 b. Teen 6.7E+1 c. Child 1.4E+1 d. Infant 0 Salt Water Sport Fish Ingestion (Kg/yr)a. Adult 2.1 E+1 b. Teen 1.6E+1 c. Child 6.9 d. Infant 0 Salt Water Commercial Fish Ingestion (Kg/yr)a. Adult 2.1E+1 b. Teen 1.6E+1 c. Child 6.9 d. Infant 0 Salt Water Invertebrate Ingestion (Kg/yr)a. Adult 5.0 b. Teen 3.8 c. Child 1.7 d. Infant 0 Irrigated Leafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1 b. Teen 4.2E+1 c. Child 2.6E+1 d. Infant 0 040809 CY-OC-1 70-301 Revision 3 Page 116 of 140 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 5.2E+2 d. Infant 0 Irrigated Cow and Goat Milk Ingestion (Uyr)a. Adrilt 3.1E+2 b. Teen 4.0E+2 c. Child 3.3E+2 d. Infant 3.3E+2 Irrigated Beef Ingestion (Kg/yr)a. Adult 1.1 E+2 b. Teen 6.5E+1 c. Child 4.1E+1 d. Infant 0 Inhalation (m 3/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 3.1E+2 b. Teen 4.OE+2 c. Child 3.3E+2 d. Infant 3.3E+2 Meat Ingestion (Kg/yr)a. Adult 1.1 E+2 b. Teen 6.5E+1 c. Child 4.1E+1 d. Infant 0 040809 CY-OC-1 70-301 Revision 3 Page 117 of 140 Table B-1 (Continued)

OCGS Usage Factors For Individual Dose Assessment Effluent Ingestion Parameters Usage Factor Leafy Vegetable Ingestion (Kg/yr)a. Adult 6.4E+1 b. Teen 4.2E+1 c. Child 2.6E+1 d. Infant 0 Fruits, Grains, & Other Vegetable Ingestion (Kg/yr)a. Adult 5.2E+2 b. Teen 6.3E+2 c. Child 5.2E+2 d. Infant 0 040809 CY-OC-1 70-301 Revision 3 Page 118 of 140 Table B-2 Monthly Average Absolute Humidity g/m 3 (derived from historical climatological data)Average Absolute Month Humidity (q/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 040809 CY-OC-1 70-301 Revision 3 Page 119 of 140 APPENDIX C -REFERENCES 040809 CY-OC-170-301 Revision 3 Page 120 of 140 Table C-1 -REFERENCES

1) Oyster Creek Updated Final Safety Analysis Report 2) Oyster Creek Facility Description and Safety Analysis Report 3) Oyster Creek Operating License and Technical Specifications

4) NUREG 1302 "Off Site Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors" -Generic Letter 89-10, Supplement No.1,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 10CFR50, Appendix I, May, 1976, Tables 3-10 040809 CY-OC-170-301 Revision 3 Page 121 of 140 17) XOQDOQ Output Files for Oyster Creek Meteorology, Murray and Trettle, Inc.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 99.25) 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 30) 1 OCFR20, Appendix B, Table 2, Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage 040809 CY-OC-170-301 Revision 3 Page 122 of 140 31) Conestoga Rovers and Associates, Hydrogeologic Investigation Report, Fleet wide Assessment, Oyster Creek Generating Station, Forked River, New Jersey, Ref. No.045136(18), September, 2006.040809 CY-OC-170-301 Revision 3 Page 123 of 140 APPENDIX D -SYSTEM DRAWINGS 040809 CY-OC-1 70-301 Revision 3 Page 124 of 140 FIGURE D-1-la: LIQUID RADWASTE TREATMENT CHEM WASTE AND FLOOR DRAIN SYSTEM.0 0.E wu W, 11 co, 040809 CY-OC-1 70-301 Revision 3 Page 125 of 140 FIGURE D-1-1 b: LIQUID RADWASTE TREATMENT

-HIGH PURITY AND EQUIPMENT DRAIN SYSTEM LU 0r 0 W cr o .r m~ mmN 00E 7(L 0- CLV.C C U))C4)0..(L.00 zO a.co E '040809 CY-OC-170-301 Revision 3 Page 126 of 140 FIGURE D-1-2: SOLID RADWASTE PROCESSING SYSTEM FIGURE D- 1 -2: SOLID RADWASTE PROCESSING SYSTEM A/B/C Filter Sludge 040809 CY-OC-170-301 Revision 3 Page 127 of 140 FIGURE D-2-1: GASEOUS RADWASTE TREATMENT

-AUGMENTED OFF GAS SYSTEM 040809 CY-OC-1 70-301 Revision 3 Page 128 of 140 FIGURE D-2-2: VENTILATION SYSTEM 040809 CY-OC-1 70-301 Revision 3 Page 129 of 140 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, E-2 and E-3 show the locations of sampling stations with respect to the site. Figure E-4 shows the site layout.040809 CY-OC-170-301 Revision 3 Page 130 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (1)Sample Medium Station Code Distance (miles)Azimuth (degrees)Description TLD DW APT, AIO, TLD TLD TLD TLD TLD TLD APT, AIO, TLD 1 0.4 219 SW of site at OCGS Fire Pond, Forked River, NJ (Inner Ring)1 0.1 209 On-site southern domestic well at OCGS, Forked River, NJ 0.2 349 On-site northern domestic well at OCGS, Forked River, NJ Either the southern or northern well is sampled.3 6.0 97 East of site, near old Coast Guard Station, Island Beach State Park TLD -Special Interest Area 4 4.6 213 SSW of Site, Garden State Parkway and Route 554, Barnegat, NJ (Outer Ring)5 4.2 353 North of Site, Garden State Parkway Rest Area, Forked River, NJ (Outer Ring)6 2.1 13 NNE of site, Lane Place, behind St. Pius Church, Forked River, NJ (Outer Ring)8 2.3 177 South of site, Route 9 at the Waretown Substation, Waretown, NJ (Outer Ring)9 2.0 230 SW of site, where Route 532 and the Garden State Parkway meet, Waretown, NJ (Outer Ring)C 24.7 313 NW of site, JCP&L office in rear parking lot, Cookstown, NJ (Background Station)11 8.2 152 SSE of site, 80th and Anchor Streets, Harvey Cedars, NJ (Special Interest Area)14 20.8 2 North of site, Larrabee Substation on Randolph Road, Lakewood, NJ (Background Station)20 0.7 95 East of site, on Finninger Farm on south side of access road, Forked River, NJ 22 1.6 145 SE of site, on Long John Silver Way, Skippers Cove, Waretown, NJ (Outer Ring)23 3.6 64 ENE of site, Barnegat Bay off Stouts Creek, 040809 TLD TLD APT, AIO TLD SWA, CLAM, CY-OC-1 70-301 Revision 3 Page 131 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (1)Sample Medium Station Distance Code (miles)Azimuth (degrees)Descrip~tion AQS SWA, CLAM, AQS SWA, AQS, FISH 24 2.1 33 0.4 VEG VEG DW DW DW TLD TLD TLD TLD TLD TLD 35 0.4 36 23.1 37 2.2 38 1.6 39 3.5 46 5.6 47 4.6 48 4.5 51 0.4 52 0.3 53 0.3 approximately 400 yards SE of "Flashing Light 1'" 101 East of site, Barnegat Bay, approximately 250 yards SE of "Flashing Light 3" 123 ESE of site, east of Route 9 Bridge in OCGS Discharge Canal 111 ESE of site, east of Route 9 and north of the OCGS Discharge Canal, Forked River, NJ 319 NW of site, at "U-Pick" Farm, New Egypt, NJ (Background Station)18 NNE of Site, off Boox Road at Lacey MUA Pumping Station, Forked River, NJ (Background Station)197 SSW of Site, on Route 532, at Ocean Township MUA Pumping Station, Waretown, NJ 353 N of Site, Trenton Ave. off Lacey Road Lacey Twp., MUA Pump Station, Forked River, NJ (Background Station)323 NW of Site, on Lacey Road adjacent to Utility Pole BT 259 65 (Outer Ring)26 NNE of Site, Route 9 and Harbor Inn Road, Berkeley Township, NJ (Outer Ring)189 South of Site, Intersection of Brook and School Streets, Barnegat, NJ (Outer Ring)358 North of site, on the access road to Forked River Site, Forked River, NJ (Inner Ring)333 NNW of site, on the access road to Forked River Site, Forked River, NJ (Inner Ring)309 NW of site, at sewage lift station on the access road to the Forked River Site, 040809 CY-OC-1 70-301 Revision 3 Page 132 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (1)Sample Medium Station Code Distance Azimuth (miles) (degrees)Description TLD TLD TLD TLD TLD TLD TLD TLD TLD 54 0.3 55 0.3 56 0.3 57 0.2 58 0.2 59 0.3 61 0.3 62 0.2 63 0.2 64 0.3 Forked River, NJ (Inner Ring)288 WNW of site, on the access road to Forked River Site, Forked River, NJ (Inner Ring)263 West of site, on Southern Area Stores security fence, west of OCGS Switchyard, Forked River, NJ (Inner Ring)249 WSW of site, on utility pole east of Southern Area Stores, west of the OCGS Switchyard, Forked River, NJ (Inner Ring)206 SSW of site, on Southern Area Stores access road, Forked River, NJ (TLD -ODCM Required -Inner Ring)188 South of site, on Southern Area Stores access road, Forked River, NJ (Inner Ring)166 SSE of site, on Southern Area Stores access road, Waretown, NJ (Inner Ring)104 ESE of site, on Route 9 south of OCGS Main Entrance, Forked River, NJ (Inner Ring)83 East of site, on Route 9 at access road to OCGS Main Gate, Forked River, NJ (Inner Ring)70 ENE of site, on Route 9, between main gate and OCGS North Gate access road, Forked River, NJ (Inner Ring)42 NE of site, on Route 9 North at entrance to Finninger Farm, Forked River, NJ (Inner Ring)TLD 040809 CY-OC-1 70-301 Revision 3 Page 133 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (Continued)

Sample Medium TLD APT, AIO, TLD, VEG Station Code 65 Distance (miles)0.4 66 0.4 TLD 68 1.3 APT, AIO, TLD 71 1.6 APT, AIO, TLD APT, AIO, TLD TLD TLD TLD TLD TLD 72 1.9 73 1.8 74 1.8 75 2.0 78 1.8 79 2.9 81 3.5 Azimuth (degrees)

Description 19 NNE of site, on Route 9 at Intake Canal Bridge, Forked River, NJ (Inner Ring)133 SE of site, east of Route 9 and south of the OCGS Discharge Canal, inside fence, Waretown, NJ (TLD -Inner Ring)266 West of site, on Garden State Parkway North at mile marker 71.7, Lacey Township, NJ (Outer Ring)164 SSE of site, on Route 532 at the Waretown Municipal Building, Waretown, NJ (TLD -Special Interest Area)25 NNE of site, on Lacey Road at Knights of Columbus Hall, Forked River, NJ (TLD -Special Interest Area)108 ESE of site, on Bay Parkway, Sands Point Harbor, Waretown, NJ (TLD -Outer Ring)88 East of site, Orlando Drive and Penguin Court, Forked River, NJ (Outer Ring)71 ENE of site, Beach Blvd. and Maui Drive, Forked River, NJ (Outer Ring)2 North of site, 1514 Arient Road, Forked River, NJ (Outer Ring)160 SSE of site, Hightide Drive and Bonita Drive, Waretown, NJ (Outer Ring)201 SSW of site, on Rose Hill Road at intersection with Barnegat Boulevard, Barnegat, NJ( Special Interest Area)040809 CY-OC-170-301 Revision 3 Page 134 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (Continued)

Sample Medium Station Code Distance (miles)Azimuth[degrees)

Description TLD TLD TLD TLD TLD TLD TLD 82 4.4 84 4.4 85 3.9 86 5.0 88 6.6 89 6.1 90 6.3 92 9.0 93 0.1 94 20.0 36 NE of site, Bay Way and Clairmore Avenue, Lanoka Harbor, NJ (Outer Ring)332 NNW of site, on Lacey Road, 1.3 miles west of the Garden State Parkway on siren pole, Lacey Township, NJ (Outer Ring)250 WSW of site, on Route 532, just east of Wells Mills Park, Waretown, NJ (Outer Ring)224 SW of site, on Route 554, 1 mile west of the Garden State Parkway, Barnegat, NJ (Outer Ring)125 SE of site, eastern end of 3 rd Street, Barnegat Light, NJ (Special Interest Area)108 ESE of site, Job Francis residence, Island Beach State Park (Special Interest Area)75 ENE of site, parking lot A-5, Island Beach State Park (Special Interest Area)46 NE of site, at Guard Shack/Toll Booth, Island Beach State Park (Special Interest Area)242 WSW of site, OCGS Discharge Canal between Pump Discharges and Route 9, Forked River, NJ 198 SSW of site, in Great Bay/Little Egg Harbor (Background Station)TLD FISH, CRAB SWA, AQS, CLAM, FISH TLD 98 1.6 318 NW of site, on Garden State Parkway at mile marker 73.0, Lacey Township, NJ (Outer Ring)040809 CY-OC-1 70-301 Revision 3 Page 135 of 140 TABLE E-1: REMP SAMPLE LOCATIONS (Continued)

Sample Medium Station Code Distance (miles)Azimuth (degrees)Description TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 99 100 101 102 103 104 105 106 107 109 110 111 112 113 1.5 310 NW of site, on Garden State Parkway at mile marker 72.8, Lacey Township, NJ (Outer Ring)1.4 43 NE of site, Yacht Basin Plaza South off Lakdeside Dr., Lacey Township, NJ (Outer Ring)1.7 49 NE of site, end of Lacey Rd., East, Lacey Township, NJ (Outer Ring)1.6 344 NNW of site, end of Sheffield Dr., Barnegat Pines, Lacey Township, NJ (Outer Ring)2.4 337 NNW of site, Llewellyn Parkway, Barnegat Pines, Lacey Township, NJ (Outer Ring)1.8 221 SW of site, Rt. 532 West, before Garden State Parkway, Ocean Township, NJ (Outer Ring)2.8 222 SW of site, Garden State Parkway North, beside mile marker 69.6, Ocean Township, NJ (Outer Ring)1.2 288 NW of site, Garden State Parkway North, beside mile marker 72.2 Lacey Township, NJ (Outer Ring)1.3 301 NW of Site, Garden State Parkway North, beside mile marker 72.5, Lacey Township, NJ (Outer Ring)1.2 141 SE of site, Lighthouse Dr., Waretown, Ocean Township, NJ (Outer Ring)1.5 127 SE of site, Tiller Drive and Admiral Way, Waretown, Ocean Township, NJ (Outer Ring)0.3 64 ENE of site, Finninger Farm property along access road, Lacey Township, NJ 0.2 178 S of site, along Southern access road, Lacey Township, NJ (Inner Ring)0.3 90 E of site, along Rt. 9 North, Lacey Township, NJ (Inner Ring)0.4 219 SW of site, at OCGS Fire Pond, Lacey Township, NJ (Inner Ring)0.4 112 ESE of site on Finninger Farm adjacent to Station 35, Lacey Township, NJ APT, AIO TLD TLD TLD GW Ti W-3C 040809 CY-OC-170-301 Revision 3 Page 136 of 140 GW MW-24-3A 0.8 97 E of site on Finninger Farm on South side of access road, Lacey Township, NJ SAMPLE MEDIUM IDENTIFICATION KEY APT = Air Particulate AIO = Air Iodine VEG = Vegetables SWA = Surface Water AQS = Aquatic Sediment CLAM = Clams DW = Drinking Water TLD = Thermoluminescent Dosimeter FISH = Fish CRAB =Crab GW = Ground Water (1) Samples may not be collected from some locations listed in this table, as long as the minimum number of samples listed in Table 3.12.1-1 is collected.

040809 CY-OC-1 70-301 Revision 3 Page 137 of 140 FIGURE E-1 Figure E-1.Locations of REMP Stations within a 1-mile radius of the Oyster Creek Generating Station 040809 CY-OC-1 70-301 Revision 3 Page 138 of 140 FIGURE E-2 Figure E-2.Locations of REMP Stations within a I to 5-mile radius of the Oyster Creek Generating Station 040809 CY-OC-1 70-301 Revision 3 Page 139 of 140 FIGURE E-3 Figure E-3.Locations of REMP Stations greater than 5 miles from the Oyster Creek Generating Station 040809 CY-OC-170-301 Revision 3 Page 140 of 140 FIGURE E-4 AREA PLOT PLAN OF SITE SITE MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS 040809 ATTACHMENT 3 CORRECTED 2006 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT OYSTER CREEK NUCLEAR GENERATING STATION The maximum hypothetical calculated organ dose (thyroid) from iodines and particulates to any individual due to gaseous effluents (0.0218 mRem/year) was approximately 0.15 percent of the annual limit (Table 1). The maximum hypothetical calculated whole body dose to any individual due to gaseous effluents (7.96E-4 mRem/year) was 1.59E-4 percent of the annual limit.The total maximum hypothetical organ dose (thyroid) due to all radiological effluents from the Oyster Creek Generating Station of 2.25E-02 mRem/year received by any individual for the reporting period is over 13,000 times lower than the dose the average individual in the Oyster Creek area received from background radiation, including that from radon (200 mRem) during the same time period. The background radiation dose averages approximately 300 mRem whole body per year in the Central New Jersey area, which is made up of contributions of approximately 100 mRem/year from 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 reliabilities for the 380-foot data and the 33-foot data were 98.63 percent and 97.6 percent, respectively.

The UFSAR commits to Regulatory Guide (RG) 1.23 for Met Tower reliability.

RG 1.23 requires 90%reliability over the year.2 OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -2006 TABLE I.!,.ANNUAL OFFSITE DOSES DUE TO RADIONUCLIDES IN EFFLUENTS ianuary 1. 2006 through December 31, 2006 Reference ODCM ODCM ODCM ODCM ODCM ODCM ODCM ODCM 3.11.1.2 3.11.1.2 3.11.2.1 3.11.2.1 3.11.2.1 3.11.2.2 3.11.2.2 3.11.2.3 Liquid Liquid Noble Gas Noble Gas H-3, Iodines, & Noble Gas Noble Gas 1-131, 1-133, &Total Body Liver Total Body Skin Particulates Gamma Dose Beta Dose Particulates Thyroid Thyroid mrcm mrern mrcm imrem nmrem mRad mRad mrem ODCM :...ODM 3.0 mrmm/ycar 10.0 mremdycar 500 mrvm/year 3000 torro/ycar 1500 mrem/year 10 mRad/year 20 mRad/year 15 torero/year Limit _ _ ,.._3.53E-04 6.97E-04 7.96E-04 1.03E-03 2.18r.02 1.80E-03 4.04E-04 2.1BE.02 2006 Dose mren I rMrenm mrem mrem rarem mRad mRad mrem Percent Percent 1.18E-02 6.97E-03 1.59E-04 3.43E-05 1.45E-03 1.BOE-02 2.02E-03 1.45E-01 of" Llmit Percent Percent Percent Percent Percent Percent Percent Percentý ý -....,... ,: : ::ý ::.. ., ;: .w .: ..:' ' :ý:: ...:. ... :-4.ý:'- "ý;-- '.., .ý , ..,!%ý:-,::..

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ATTACHMENT 4 CORRECTED 2007 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT OYSTER CREEK NUCLEAR GENERATING STATION OYSTER CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -2007 TABLE I ANNUAL OFFSITE DOSES DUE TO RADIONUCLIDES IN EFFLUENTS January I. 2007 through December 31, 2007 Reference ODCM ODCM ODCM ODCM ODCM ODCM ODCM ODCM 3.11.1.2 3.11.1.2 3.11.2.1 3.11.2,1 3.11.2.1 3.11.2.2 3.11.2.2 3.11.2.3 Liquid Liquid Noble Gas Noble Gas H-3, Iodines, & Noble Gas Noble Gas 1-13 i, I- 133, &Total Body Liver ,Total Body Skin Particulates Gamma Dose Beta Dose Particulates Thyroid Thyroid nwem rnlrcm ll mrem mrem n-re mRad mRad rnrem OLCml 3.0 mren/year 10.0 mrem/year 500 mrenilyear 3000 mremlyear 1500 miremlyear 10 niRadlyear 20 mRadlyear 15 mrerndyear 20Doe 0.OOE+00 O.00E+00 1.65E-04 3.63E-04 1.34E-02 7.79E-0)4 9.64E-04 1.33E-02 nirem narem mntrnm mremn mrem nmRad mRad rnreni Pecnt 000E+O0 0.OOE+00 3.30E-05 1.21E-05 "8.93E-04 7.79E-03 4.822-03 8.87E-02 of Limit Perceat Percent. Percent Percent Percent Percent Percent Percent C : .;-ý:ý:-+.

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RA-10-002, Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual

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RA-10-002, Oyster Creek, CY-OC-170-301, Revision 3, Offsite Dose Calculation Manual

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