Text

Annual Radioactive Effluent Release Report, January 1 - December 31, 2003
	ML040970240
Person / Time
Site:	Cook
Issue date:	03/24/2004
From:	Zwolinski J; Indiana Michigan Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	AEP:NRC:4691-01
	Download: ML040970240 (153)
	v • d • e

Indiana Michigan Power Company 500 Circle Drive Buchanan, MI 49107 1373 INDIANA MICHIGAN POWER March 24, 2004 AEP:NRC:4691-01 Docket Nos: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units I and 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2003 THROUGH DECEMBER 31, 2003 In accordance with Technical Specification (TS) 6.9.1.7, Indiana Michigan Power Company hereby submits the Annual Radioactive Effluent Release Report for Donald C. Cook Nuclear Plant (CNP). This report covers the period January 1, 2003 through December 31, 2003, and also contains revised fourth quarter 2002 data.

The calculations in this report were performed in accordance with the CNP Offsite Dose Calculation Manual (ODCM). Revision 17a of the ODCM was issued during the reporting period. A copy of the revision is included in Appendix 3.0 to this report to fulfill the requirements of TS 6.14.1.c.

There are no new commitments in this submittal. Should you have any questions, please contact Mr. Michael K. Scarpello, Supervisor of Nuclear Licensing, at (269) 697-5020.

Sincerely, John AZwolinski Director of Design Engineering and Regulatory Affairs DB/rdw

Attachment:

Annual Radioactive Effluent Release Report Aoci

U.S. Nuclear Regulatory Commission AEP:NRC:4691-01 Page 2 c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o attachment J. T. King, MPSC, w/o attachment MDEQ - WHMD/HWRPS, w/o attachment D. Minnaar, MDEQ NRC Resident Inspector J. F. Stang, Jr., NRC Washington, DC

ATTACHMENT TO AEP:NRC:4691-01 DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2003 THROUGH DECEMBER 31, 2003

Annual Radioactive Effluent Release Report January 1, 2003 through December 31, 2003 Z AMERICAN' ELECTRIC POWER AA4me~a'sEmw &rtner

TABLE OF CONTENTS Page Table of Contents i I. Introduction 1 II. Radioactive Releases and Radiological Impact on Man 2 Liquid Releases 2 Gaseous Releases 2 Solid Waste Disposition 3 III. Meteorological 3 IV. Offsite Dose Calculation Manual (ODCM) Changes 3 V. Total Dose ..3 VI. Radiation Monitors Inoperable Greater Than 30 Days 4 VII. Conclusion 4 LIST OF APPENDICES Appendix Title Al. 1 2003 Effluent and Waste Disposal Annual Report -

Supplemental Information Al .2 Summary of Maximum Individual Doses: First Quarter, Second Quarter, Third Quarter and Fourth Quarter 2003. Fourth Quarter 2002, Revised A2 .1 Hours at Each Wind Speed and Direction: First Quarter, 2003 A2.2 Hours at Each Wind Speed and Direction: Second Quarter, 2003 A2 .3 Hours at Each Wind Speed and Direction: Third Quarter, 2003 A2.4 Hours at Each Wind Speed and Direction: Fourth Quarter, 2003 3.0 Offsite Dose Calculation Manual (ODCM) Changes i

I. INTRODUCTION This report discusses the radioactive discharges from Unit 1 and Unit 2 of the Donald C. Cook Nuclear'Plant during 2003. This is in accordance with the requirements of Donald C. Cook Nuclear Plant Technical Specification 6.9.1.'7.

The table below summarizes the pertinent statistics concerning the Plant's operation during the'"period from January 1 to December 31, 2003. The data in this table and the descriptive information on plant operation are based upon the respective Unit's Monthly Operating Reports, 'Performance Indicators and Control Room Logs for 2003.

Parameter Unit 1 Unit 2 Gross Electrical Energy Generation 6,799,373 7,340,330 (MWH)

Unit Service Factor % 74.1 75.5 Unit Capacity Factor - MDC Net (k) 75.0 76.6 Unit 1 entered the reporting period in Mode 1 at 100 percent (%)

Rated Thermal Power (RTP). Small power adjustments were made to facilitate main turbine valve testing throughout the 'year. On 1/15/03 the unit experienced a Turbine Trip/Rx trip from 100%

RTP due.toMain Transformer fire. The transformer was replaced, the unit attained criticality on 2/4/03 and returned to'100% RTP on 2/6/03.' On 4/24/03 the unit was manually tripped due to lowering vacuum, degraded circulating water conditions caused by an alewife intrusion event.: An Alert was declared at this time due to influx of material in the screen wash system resulting in decreased Essential Service Water flow to all Emergency Diesel Generators. Alert was exited on 4/25/03. The unit'attained criticality on 5/27/03 and returned to 100% RTP on 5/30/03. On 10/18/03 the unit was shutdown and the scheduled UlC19 refueling outage commenced. The unit attained criticality on 11/25/03 and reached 100% RTP on 12/1/03. The unit exited the reporting period at 100% RTP.

Unit 2 entered the reporting period in Mode 1 at 100% RTP.

Small power adjustments were'.made to facilitate main turbine valve testing throughout'the year. On-1/26/03 the unit was manually shutdown due to. entering the Limiting Condition for Operation (LCO) associated with 2 CD Emergency Diesel' Generator being inoperable. The LCO for 2 CD Emergency Diesel Generator was exited on 1/27/03. The unit-attained criticality on 1/29/03 and achieved 100% RTP'on 1/31/03. On 2/5/03 the unit experienced a reactor trip due to feedwater/steam flow mismatch associated with loss of 24 VDC power. The power supply was replaced and the unit attained criticality'on 2/14/03 and reached 100% RTP on 2/16/03. On 4/24/03'the unit was manually tripped due to lowering vacuum,'degraded circulating water conditions caused by alewife intrusion event. An Alert was declared at this time due-to' influx of material in 'the screen wash system-resulting in decreased Essential Service Water flow to all Emergency Diesel Generators'. Alert was exited on 4/25/03. The unit entered scheduled U2C14 refueling outage from forced outage on 5/5/03. The unit attained criticality on 6/19/03 and 100% RTP was achieved on 6/26/03. On 8/13/03 the unit was manually shutdown due to a steam leak found on feedwater check valve 2-FW-118-2. The unit attained criticality on 8/28/03'and 100% RTP was achieved-on 8/30/03. On 12/14/03 1

from 10Ok power due to a low steam generator level coincident with feed flow less than steam flow, which occurred during maintenance activities. The unit exited the reporting period in Mode 3.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT ON MAN Since a number of release points are common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report. Appendices A1.l through A2.4 of this report present the information in accordance with Section 6.9.1.7 of Appendix A to the Facility Operating Licenses, as specified in the Technical Specification, Regulatory Guide 1.21 and 10 CFR Part 50, Appendix I.

The "MIDAS System" is a computer code that calculates doses due to radionuclides that were released from the Donald C. Cook Nuclear Plant.

All liquid and gaseous releases were well within Offsite Dose Calculation Manual limits and Federal Limits.

There were no abnormal liquid or gaseous releases.

Liquid Releases During 2003 there were 82 liquid batch releases. During the first quarter there were 11 liquid batch releases. During the second quarter there were 25. During the third quarter there were 20.

During the fourth quarter there were 26.

Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathways are given in Appendix 1.2 of this report.

Gaseous Releases During the first quarter of 2003 there were six batch releases from Waste Gas Decay Tanks (GDT) and 133 Containment Pressure Reliefs (CPR). During the second quarter there were six batch releases from GDT, two from containment purge and, 57 CPR. During the third quarter there were three batch releases from GDT, one from containment purge and 144 CPR. During the fourth quarter there were four batch releases from GDT, one from containment purge and 69 CPR. CPR continue to be listed as batch releases in accordance with NRC inspections 50-315/89016 (DRSS) and 50-316/8917 (DRSS). There were a total of 19 GDT, four unit purges and 403 CPR during 2003.

In calculating the dose consequences for continuous and batch gaseous releases during 2003, the meteorological data measured at the time of the release were used.

The estimated doses (in millirem) to maximally exposed individuals via the gaseous release pathways are given in Appendix 1.2 of this report.

2

Solid Waste Disposition There were 20 shipments of radioactive waste made during 2003.

This included shipments made from the site and the ' various radioactive waste processors to the ultimate disposal site.

III. METEOROLOGICAL Appendices A2.1, A2.2, A2.3, and A2.4 'of this report contain-the cumulative joint frequency distribution tables of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third and fourth quarters of 2003.

Hourly - meteorological data is available - for review and/or inspection upon request.

IV. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES The Offsite Dose Calculation Manual, PMP-6010-OSD-001, was not changed during the report period. Corrections were made to this procedure in accordance. with PMP-2010-PRC-002, Procedure Correction, Change, and .Review. The reasons for the corrections are documented on the -procedure"Review and Approval Tracking Form.

These corrections 'did not reduce the accuracy -or reliability of dose calculations or setpoint determinations. Appendix 3.0 contains the revised ODCM with corrections indicated-by marginal bars. Plant Operations Review Committee approval is not required for procedural -corrections although there is an 'evaluation and effectiveness review as well as'a'technical review performed.

V. TOTAL DOSE Section 3.2.5 of the ODCM requires that the dose 'or dose commitment to a real individual from all uranium fuel cycle sources in Berrien County be limited to no more than 25 millirem to the total body or any organ (except the thyroid, which is limited to no more than 75 millirem) over a period of 12 consecutive months to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 2003 was well within the ODCM limits. Measurements using thermoluminescent dosimeters at 11 offsite stations indicate that the dose due to direct radiation is negligible compared to preoperational doses and current background levels. This is fully evaluated in the Annual Radiological Environmental Operating Report for 2003.

The annual dose to the maximum individual will be estimated by first, summing the quarterly total body air dose, the quarterly skin air dose, the quarterly critical organ dose from iodines and particulates, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program. These quarterly values will be summed and compared to the annual limit'. The table *that follows here represents the above verbal description:

3

Dose 1"t Quarter 2nd Quarter 3rd Quarter 4th Quarter Total Body or any 1.22E-02 3.29E-02 6.51E-02 2.66E-02 organ (I&P)

Total Body (Air) 1.40E-04 5.40E-03 8.30E-04 4.30E-04 Skin (Air) 4.30E-04 2.80E-02 3.90E-03 7.90E-04 Total Body (liquid) 5.09E-03 2.15E-02 6.49E-03 1.11E-02 Maximum organ (liquid) 5.29E-03 2.39E-02 6.94E-03 1.50E-02 Direct Radiation O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Total 2.32E-02 1.12E-01 8.33E-02 5.39E-02 Cumulative Total Dose (Total Body or any other organ) mrem 2.72E-01 Annual Dose Limit (mrem) 2.50E+01 Percent of Limit 1.09E+00 For individuals that are within the site boundary, the occupancy time is sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

VI. RADIATION MONITORS INOPERABLE GREATER THAN 30 DAYS There were no radiation monitors inoperable for greater than 30 days while there was a release via that pathway.

VII. CONCLUSION Based on the information presented in this report, it is concluded that the Donald C. Cook Nuclear Plant Units 1 and 2 performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.

4

2003 Effluent and Waste Disposal Annual Report SUPPLEMENTAL INFORMATION Facility: Donald C. Cook Nuclear Plant Licensee: Indiana Michigan Power Company 1 REGULATORY LIMITS 1.1 Noble Gases The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be limited to the following:-

1.1.1 -During any'calendar quarter, to 5 5 mrad for gamma radiation and 5 10 mrad for beta radiation.

1.1.2 During any calendar year, to 5 10 mrad for gamma radiation and 5'20 mrad for beta radiation.

1.2 Iodines - Particulates The dose to a member of the public from radioiodines, radioactive materials in particulate form, and-radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas shall be limited to the following:

1.2.1 'During any calendar quarter to 5 7.5 mrem to any organ.

1.2.2 During any calendar year to

15 mrem to any organ.

1.3 Liquid Effluents The d6se or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas shall be limited to the following:

1.3.1 During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ.

1.3.2 During any calendar year to

3 mrem-to the total body and to S 10 mrem to any organ.

Al. 1-21

2003 Effluent and Waste Disposal Annual Report 1.4 Total Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to

25 mrem to the total body or any organ (except the thyroid, which is limited to

75 mrem) over a period of 12 consecutive months.

2 MAXIMUM PERMISSIBLE CONCENTRATIONS 2.1 Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

2.1.1 For noble gases:

500 mrem/yr to the total body and

3000 mrem/yr to the skin.

2.1.2 For all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days:

1500 mrem/yr to any organ.

The above limits are provided to insure that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits in 10 CFR Part 20, Appendix B, Table 2, Column 1.

2.2 Liquid Effluents The concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 .tCi/ml total activity.

Al. L-2

2003 Effluent and Waste Disposal Annual Report 3 AVERAGE ENERGY The average energy (E) of the radionuclide mixture in releases of fission and activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is not applicable because the limits used for gaseous releases are based on calculated dose to members of the public.

4 MEASUREMENTS and APPROXIMATIONS of TOTAL RADIOACTIVITY 4.1 Fission and Activation Gases Sampled and analyzed on a 4096 channel analyzer and HpGe detector. Tritium analysis is performed using liquid scintillation counter.

4.2 Iodines Sampled on iodine adsorbing media and analyzed on a 4096 channel analyzer and HpGe detector.

4.3 Particulates Sampled on a glass filter and analyzed on a 4096 channel analyzer and HpGe detector. Sr-89 and Sr-90 analyses performed by offsite vendor.

4.4 Liquid Effluents Sampled and analyzed on a 4096 channel analyzer and HpGe detector. Tritium analysis is performed using liquid scintillation counter. Fe-55,'Sr-89 and Sr-90 analyses performed by offsite vendor.

A1.1-3

2003 Effluent and Waste Disposal Annual Report 5 BATCH RELEASES 5.1 Liquid 5.1.1 Number of batch releases:

11 releases in the 1" quarter, 2003 25 releases in the 2 nd quarter, 2003 20 releases in the 3 rd quarter, 2003 26 releases in the 4th quarter, 2003 5.1.2 Total time period for batch releases:

12846 minutes 5.1.3 Maximum time for a batch release:

210 minutes 5.1.4 Average time period for batch release:

157 minutes 5.1.5 Minimum time period for a batch release:

16 minutes 5.1.6 Average stream flow during periods of release of effluent into a flowing stream:

7.36E+5 gpm circulating water Al.1-4

2003 Effluent and Waste Disposal Annual Report 5.2 Gaseous 5.2.1 Number of batch releases:

139 releases in the ilo quarter, 2003 65 releases in the 2 nd quarter, 2003 148 releases in the 3 rd quarter, 2003 74 releases in the 4er quarter, 2003 5.2.2 Total time period for batch releases:

19146 minutes 5.2.3 Maximum time for a batch release:

643 minutes 5.2.4 Average time period for batch release:

44.9 minutes 5.2.5 Minimum time period for a batch release:

10 minutes Al. 1-5

2003 Effluent and Waste Disposal Annual Report 6 ABNORMAL RELEASES 6.1 Liquid 6.1.1 Number of Releases:

1 3t Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0 0 0 6.1.2 Total activity released (Ci):

1 St Quarter 2nd Quarter 3rd Quarter 4 th Quarter 0 0 0 0 6.2 Gaseous 6.2.1 Number of Releases:

ls Quarter 2nd Quarter 3 rd Quarter 4 th Quarter 0 0 0 0 6.2.2 Total activity released (Ci):

1 S' Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0 0 0 Al.1-6

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE lNuclides Releasedl Unit I1st Quarterl 2nd Quarter! 3rd Quarterl 4th Quarterl l1. FISSION GASES I I I I I I l H3 I Ci I 2.68E+01 -I 3.65E+01 I 3.21E+01 I 3.79E+01 I l KR85 I Ci I -------- -l 1.86E+02 l -------- I -------- I l XE133 I Ci I 2.OOE+00 I 1.78E+01 l 1.32E+00 I -------- I ITotal for Period I Ci I 2.88E+01 I 2.40E+02 I 3.34E+01 I 3.79E+01 I lNuclides Releasedl Unit I1st Quarter! 2nd Quarter! 3rd Quarter! 4th Quarterl

12. IODINES I I I I I I I I131 I Ci I -------- l 2.38E-05 I -------- I 6.16E-06 I ITotal for Period I Ci I -------- I 2.38E-05 I -------- I 6.1GE-06 I l3. PARTICULATES I I I I I I I COO I Ci I -------- I 1.46E-08 I -------- I -------- -

I CS137 l Ci I -------- I 5.09E-07 I 9.56E-08 I -------- I l *AGl1OM l Ci I -------- I 1.78E-08 I -------- I -------- I ITotal for Period I Ci I -------- I 5.41E-07 I 9.56E-08 I -------- I

DENOTES SUPPLEMENTAL ISOTOPES A1.1-7

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE INUCLIDES RELEASEDI Unit I 1st Quarterl 2nd Quarterl 3rd Quarterl 4th Quarterl

11. FISSION GASES I I I I I I I H3 C ci I 1.09E-01 I 7.47E-01 I 2.33E-01 I 1.98E-01 I I AR41 I Ci I 8.78E-02 I 1.73E+00 I 1.40E-01 I 1.20E-01 I lKR85M I Ci I- - I- - I - -- I 1.13E-03 I l KR85 I Ci I 9.54E-01 I 1.67E+00 I 4.97E-01 I 3.57E-01 I I XE131M I ci C 4.32E-03 I 3.76E-03 I -------- I -------- I I XE133M I Ci I 2.76E-03 I 3.63E-03 I -------- I 5.76E-03 I I XE133 I Ci I 9.36E-01 I 2.55E+00 I 5.38E-01 I 6.20E-01 I I XE135 I Ci I 1.20E-02 I 3.61E-02 I 5.42E-02 I 1.70E-02 I ITotal for Period I Ci I 2.11E+00 I 6.75E+00 I 1.46E+00 I 1.32E+00 I

12. IODINES I I I I I I ITotal for Period I Ci I -------- I ------ -_I -------- I -------- I

13. PARTICULATES I III ITotal for Period I Ci I -------- I ----- - -_I -------- I -------- I Al.1-B

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l Units 1st I 2nd I 3rd l 4th lEst.. I IQuarter l l I Quarter I Quarter I Quarter ITotal I II I I I I I lError,%l IA.IFISSION AND I I I I I I I I lACTIVATION GASES I I I l1.lTotal Release I Ci I 3.99E+00l 2.10E+02l 2.55E+00l 1.12E+00l 33.9 l l2.lAverage release luCi/secI 5.14E-01l 2.67E+01l 3.21E-01l 1.41E-01l I I Irate for period I I I I I I I l3.-Percent of l% Gammal 4.79E-03l 1.74E-011 2.92E-01l 1.60E-021 I I lapplicable limit l Beta I 5.91E-03l 6.61E-011 5.86E-011 5.82E-031 IB.IIODINES I I I I I I I I1.lTotal I-131 I Ci I 0.00E+00l 2.38E-051 0.00E+00l 6.16E-061 16.0 l l2.lAverage release luci/seci 0.OOE+00l 3.03E-06l O.00E+00l 7.75E-071 I irate for period I I I I I I I 13.-Percent of I % I 0.00E+00l 3.19E-021 O.00E+00l 3.55E-01l I lapplicable limit I I I I I I lC.IPARTICULATES I I I I I I I ll.lParticulates withi Ci I 0.OOE+00l 5.24E-071 9.56E-08l O.OOE+00l 15.2 l I Ihalf lives>8 daysi I I I I I I l2.lAverage release luci/secl 0.OOE+00l 6.66E-081 1.20E-081 0.00E+00l I Irate for period I I I I I I 13.lPercent of I I 0.00E+00l 3.19E-021 8.68E-01l 0.OOE+00l I I lapplicable limit l I4.IGross alpha , I Ci 1<8.97E-071<8.47E-071<1.03E-061<9.02E-071 I I Iradioactivity I I I I I I I ID.ITRITIUM I I I I I I I ll.lTotal Release I Ci I 2.70E+01- 3-.73E+01l 3.23E+01l 3.80E+01l 10.6 l 12.lAverage release -luci/seci 3.47E+00l 4.74E+00l 4.06E+00l 4.78E+00l l1 I Irate for period I I I I I' I I 13.lPercent of I % I 6.05E+01l 7.94E+01l 6.23E+01l 9.19E+01I I lapplicable limit I I I I I I I Al.1-9

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE lNuclides releasedl Unit I1st Quarterl 2nd Quarterl 3rd Quarterl 4th Quarterl l H3 I Ci I 1.89E-02 I 2.63E-01 I 2.39E-02 I 1.63E-02 I BATCH MODE lNuclides releasedi Unit I1st Quarterl 2nd Quarterl 3rd Quarterl 4th Quarterl l H3 I Ci I 1.76E+02 I 5.41E+02 I 2.75E+02 I 2.52E+02 I l NA24 I Ci I 6.22E-05 I 3.23E-06 I 9.66E-05 I 1.90E-04 I I CR51 I Ci I 6.02E-05 I 4.53E-04 I 7.03E-05 I 5.10E-04 I I MN54 I Ci I 1.08E-05 I 1.04E-04 I 1.12E-04 I 1.76E-04 I I FES5 I Ci I 9.89E-04 I 8.27E-04 I 1.64E-03 I -------- I I C057 I Ci I 1.14E-06 I 3.43E-06 I 2.69E-06 I 2.01E-06 I I C058 I Ci I 1.70E-03 I 2.85E-03 I 1.47E-03 I 3.21E-03 I l C060 l Ci I 1.25E-03 I 2.12E-03 I 2.02E-03 I 3.17E-03 I l ZN65 I Ci I -------- I 7.95E-05 I 2.73E-04 I 1.OOE-04 I I ZR95 I Ci I 5.52E-05 I 7.71E-05 I 1.10E-04 I 7.60E-05 I I NB95 I Ci I 6.04E-05 I 2.73E-04 I 2.75E-04 I 1.97E-04 I l AGllOM I Ci I 3.44E-04 I 4.59E-04 I 3.09E-04 I 3.06E-04 I l SN113 I Ci I -------- I -------- I 1.45E-05 I -------- I I SB124 I Ci I 4.73E-03 I 8.56E-03 I 3.47E-03 I 6.38E-03 I I SB125 I Ci I 4.24E-03 I 7.29E-03 I 4.57E-03 I 6.76E-03 I I I131 I Ci I 2.91E-05 I _--- I_ -- I --------_I CS134 l Ci -------- 1.62E-04 l 2.31E-05 l 2.91E-04 I CS136 I Ci I -------- I -------- I -------- I 1.73E-06 I l CS137 I Ci I 5.59E-06 I 6.87E-04 I 1.62E-04 I 2.32E-03 I

AG08M Ci l 4.04E-06 l 5.33E-06 -------- 9.09E-06 l *SN117M I Ci I -------- I 3.30E-04 I 7.77E-05 I 4.43E-05 I I *SB122 I Ci I -------- I 2.93E-06 I -------- I 2.07E-04 I I *SB126 I Ci I -------- I 3.17E-05 I -------- I -------- I I *XE133 I Ci I -------- I 9.13E-06 I 1.80E-05 I 2.15E-05 I

DENOTES SUPPLEMENTAL ISOTOPES Al.1-10

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES BATCH MODE l Units 1st l 2nd I 3rd I 4th lEst. I l l IQuarter I Quarter I Quarter I Quarter ITotal I I I I I Error,tI lA.IFISSION AND I I I I lACTIVATION I IPRODUCTS I I I Il.lTotal Release I Ci 1.35E-021 2.43E-021 l.46E-021 2.40E-02l 12.1 l 12.lAverage diluted luCi/ml I 2.71E-091 2.73E-091 l.34E-09l 2.l8E-09l I I lconcentration I I I I I I I I lduring period I I I I I I I 13.-Percent of I V I 2.86E-02l 3.70E-021 1.58E-021 4.65E-02l I I lapplicable limit I I I I I I I lB.ITRITIUM I I I I I I I ll.lTotal Release I Ci I 1.76E+02l 5.41E+021 2.75E+02l 2.52E+02l 10.1 I 12.lAverage diluted luCi/ml I 3.52E-05l 6.07E-051 2.52E-05l 2.29E-05l I I lconcentration I I I lI I I I Iduring period I I I I I l3.-Percent of I II 3.52E+00l 6.07E+00l 2.52E+00l 2.29E+00l I I lapplicable limit I I I I I I I lC.IDISSOLVEDAM I I .N I I I I I lENTRAINED GASES I I I I I I I Il.lTotal Release I Ci -I 0.OOE+00l 9.13E-06l l.80E-05l 2.1SE-05l 28.9 l l2.jAverage diluted luCi/ml I 0.OOE+00l 1.02E-12I l.65E-12I l.95E-12l I I lconcentration I I I I I I I I Iduring period I I I I [ I I I3.lPercent of lI I 0.OOE+00l 5.12E-07l 8.26E-07l 9.77E-07l I lapplicable limit I I I I I I I ID.IGROSS ALPHA I Ci 1<2.80E-051<6.48E-05I<5.30E-051<9.73E-05I N/A I I IRADIOACTIVITY I I I ITOTAL RELEASE I .I lE.lVOLUME OF WASTE I Litersi 6.llE+05l l.41E+06l 1.l5E+06l 1.45E+06l 2.00 l I IRELEASED I I I I I I I IF.IVOLUME OF I Liters! 5.00E+091 8.92E+091 1.09E+10I l.10E+l0l 3.48 l l IDILUTION WATER I I I lUSED DURING I IPERIOD Al.1-11

2003 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES CONTINUOUS MODE l Units 1st l2nd I 3rd I 4th jEst. I l l Quarter l Quarter l Quarter I Quarter ITotal I lI Error,%l lA.IFISSION AND I I I I I lACTIVATION I I lPRODUCTS I ll.lTotal Release I Ci I 0.OOE+00l 0.OOE+00l 0.OOE+00l O.OOE+00l N/A I l2.lAverage diluted luCi/ml I 0.OOE+00l 0.OOE+00l 0.OOE+00l 0.OOE+00l I lconcentration I I I I I I lduring period I I I I I l3.lPercent of I t I 0.OOE+00I 0.OOE+00I 0.00E+00l 0.OOE+00l I I lapplicable limit I I I I I I I lB.ITRITIUM I I I I I I I ll.lTotal Release I Ci I 1.89E-02l 2.68E-01l 2.39E-02l 1.63E-02l 11.6 l l2.lAverage diluted luCi/ml I 4.18E-11l 9.43E-10l 3.21E-11l 4.21E-lll I I lconcentration I I I I I I lduring period I I I I I l3.-Percent of I % I 4.19E-06l 9.44E-05l 3.22E-06l 4.21E-06l I I lapplicable limit I I I I I I I lC.IDISSOLVED AND I I I lENTRAINED GASES I I ll.lTotal Release I Ci I 0.OOE+00l 0.OOE+00l 0.OOE+00l 0.OOE+00l N/A I l2.lAverage diluted luCi/ml I 0.OOE+00l 0.00E+00l 0.00E+00I 0.00E+00l I I Iconcentration I I I I lduring period I I I 13.lPercent of I I I 0.OOE+001 0.OOE+00l O.OOE+00l 0.OOE+00l I I lapplicable limit I I I I I I ID.lGROSS ALPHA I Ci 1<4.58E-031<2.16E-031<3.93E-031<4.25E-031 N/A I I IRADIOACTIVITY I I I I I I I I ITOTAL RELEASE I I I I I I lE.lVOLUME OF WASTE I Litersi 1.20E+071 4.97E+071 1.79E+07l 1.42E+071 2.00 l l IRELEASED I I I I I I I IF.lVOLUME OF I Litersl 4.51E+11l 2.84E+llI 7.43E+11l 3.87E+11l 3.48 l l IDILUTION 1IATER I I I I lUSED DURING I I I IPERIOD I I A1.1-12

Revised 2002 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE INuclides released! Unit I1st Quarterl 2nd Quarterl 3rd Quarterl 4th Quarter!

I H3 I Ci I 5.11E-02 I 6.03E-03 I 4.55E-03 I 3.19E-02 I BATCH MODE INuclides released! Unit I 1st Quarterl 2nd Quarterl 3rd Quarterl 4th Quarterl I H3 Ci l 2.18E+02 2.28E+02 I 6.90E+01 I 1.75E+02 I l NA24 I Ci I 1.89E-04 I 1.71E-03 I -------- I -------- I l CR51 I Ci I --- -l 2.88E-04 ij--- I -------- I -------- I I MN54 I Ci I 1.54E-03 I 7.51E-04 I 1.43E-05 I 8.44E-06 I FE55 l Ci l 4.59E-04 I 1.01E-03 8.05E-04 6.49E-04 I l Coss I Ci I 2.59E-02 I 4.07E-02 I 2.82E-03 I 7.04E-04 -l C060 - Ci I .1.71E-03 I 4.93E-03 l 8.87E-04 I 9.83E-04 I ZR95 I Ci I -------- I 9.53E-05 I -------- I 1.13E-05 I l NB95 l Ci I 1.33E-05 I 2.43E-04 I 6.20E-05 I 3.01E-05 I I AGllOM I Ci I -------- I 2.84E-04 I 2.03E-04 I 1.27E-04 I l C057 I Ci I 1.09E-0-04 4.94E-06 I ---------

l SB124 I Ci I 1.40E-02 I 6.10E-02 l 2.62E-.04 I 1.29E-04 I I SB125 I Ci I 5.27E-03 I 4.71E-03 I -------- I 1.35E-04 I l TE132 I Ci I -------- I 2.76E-05 I -------- I -------- I I I131 I Ci I 1.32E 5.60E-03 I -------- I -------- I l 1132 I Ci I -------- I 4.13E-05 I -------- I -------- I l CS137 I Ci I 4.07E-05 I -------- I -------- I -------- I l *AG108M I Ci I -------- l 3.86E-05 I -------- I -------- I

SB122 I Ci I 3.82E-04 l 3.12E-03 I -------- l l *SN117M Ci l 9.18E-06 5.61E-04 4.40E-06 --------

I *SB126 I Ci I 3.06E-05 I -------- I -------- I -------- I I *XE133 I Ci I -------- I 3.92E-04 I -------- I -------- I

DENOTES SUPPLEMENTAL ISOTOPES Updated 4 th quarter FeSS values and corrected H3 transposition error.

A1.1-13

Revised 2002 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES BATCH MODE l Units 1st I 2nd I 3rd I 4th lEst. I l l Quarter I Quarter l Quarter I Quarter ITotal I I I I I lError,%l IA.IFISSION AND I IACTIVATION I IPRODUCTS ll.lTotal Release I Ci I 4.95E-021 1.25E-0ll 5.06E-031 2.78E-031 11.9 I l2.lAverage diluted luCi/ml I 7.48E-091 1.06E-081 1.01E-091 4.67E-l0l I I Iconcentration I I I I I I I Iduring period I I I I I I I 13.-Percent of I t I 6.28E-021 1.55E-011 1.04E-021 6.98E-031 I I [applicable limit Il I I I I I lB.lTRITIUM I I I I I I I ll.lTotal Release I Ci I 2.18E+021 2.28E+021 6.90E+01l 1.75E+021 10.1 I l2.lAverage diluted luCi/ml I 3.30E-05l 1.94E-051 l.38E-051 2.94E-051 I lconcentration I I I I I I I Iduring period I I I I I I 13.lPercent of I t I 3.30E+00l 1.94E+00l l.38E+00l 2.94E+00I I I lapplicable limit I I I I I IC.IDISSOLVED AND I I I I I i I JENTRAINED GASES I I I I I I I I1.ITotal Release I Ci I 0.OOE+001 3.92E-041 0.OOE+001 0.OOE+00I 28.6 l l2.lAverage diluted luCi/ml I 0.OOE+00l 3.33E-lll 0.OOE+00l 0.OOE+00l I Iconcentration I I I I I I I Iduring period I I I I I I I 13.-Percent of l I l 0.00E+00l 1.67E-051 0.OOE+00I 0.00E+001 I I lapplicable limit I I I I I I I ID.-GROSS ALPHA I Ci 1<9.28E-051<1.71E-041<4.80E-051<2.87E-051 N/A I I IRADIOACTIVITY I I I I I I I ITOTAL RELEASE I I I I I I IE.lVOLUME OF WASTE I Litersl 1.24E+061 1.45E+06l 5.63E+051 6.24E+051 2.00 l l IRELEASED I I I I I I I IF.lVOLUME OF I Litersl 6.62E+09l 1.18E+l0l 5.00E+091 5.95E+091 3.48 l l IDILUTION WATER I I I I lUSED DURING I I I IPERIOD I I 4ch quarter revised due to FeSS results and H3 transposition error.

Al.1-14

L L.

2003 Effluent and Waste Disposal Annual Report Solid Waste and Irradiated Fuel Shipments L

Solid Waste Shipped Offsite for Burial or Disposal

1) Type of Waste Unit Estimated Estimated Total Error, %

amount a) Spent resins, filters, sludge, m3 2.30E+00 1.OOE+00 evaporator bottoms, etc. Curies 3.59E+02 3.75E+00 3l b) Dry compressible waste, m3 2.63E+01 1.OOE+00 contaminated equipment, etc. Curies 3.33E+00 6.48E+00 c) Irradiated components, control Curies rods,- etc.

d) Other C Curies _________

2) Estimate of Principle Radionuclide Composition a) Cs-134 4% Ni-63 38 %

Cs-137 8% Co58 12 %

Fe-55 6% H-3 2%

Co-60 26 % Mn-54 2%

b) H-3 2% Mn-54 2%

Cs-137 2% Ni-63 19 %

Co-60 36 % Fe-55 27 %

Co-58 3% Nb/Zr-95 7%

3) Solid Waste Disposition No. of Shipments Mode of Transportation Destination 2 . Truck Barnwell, SC 18 Truck Clive, UT 4)Type of Containers used for Shipment: Containers used are strong, tight metal boxes, drums and high integrity containers.

l 5)Solidification Agent: There were no solidifications performed during this report period. I L A1.1-15 L

2003 Effluent and Waste Disposal Annual Report Yearly Release 1 I Rates l GASES Fission and Activation Gases Total Release 2.18E+02 Curies Average Release Rate 6.90E+00 jtCi/sec

% of Applicable Limits y 1.14E-02 %

r 3.66E-01 %

Iodines Total 1-131 Release 3.OOE-05 Curies Average Release Rate 9.50E-07 IiCi/sec

% of Applicable Limit 9.05E-01 %

Particulates Total Release 6.20E-07 Curies Average Release Rate 1.96E-08 ~iCi/sec

% of Applicable Limit 9.05E-01 %

LIQUIDS Fission and Activation Products Total Release 7.74E-02 Curies Average Diluted Concentration 2.16E-9 RCi/ml

% of Applicable Units Total Body 1.47E+00 %

Organ 5.11E-01 %

A1.1-16

L L The following distances were used in the calculation of the maximum individual doses:

L Sector. Direction Boundary (Meters) Nearest Residence (Meters)

A N 651 659 B NNE 617 660 C NE 789 943 D ENE 1497 1747 E E 1274 1716 F ESE 972 1643 G SE 629 1640 H SSE 594 1417 J S 594 1026 K SSW 629 942 N

Al .1-17

Summary of Maximum Individual Doses First Quarter 2003 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem) l (Toward) LIMIT QTR Liquid Total Body 5.09E-03 Child Receptor I 3.39E-01 l.51E+0 Liquid GI-Tract 5.29E-03 Child Receptor I 1.06E-01 5-.OE+0 Noble Gas Air Dose 2.40E-04 651 (N) 4.79E-03 5.OE+0 (Ganuma-mrad)

Noble Gas Air dose 5.91E-04 651 (N) 5.911E-03 l.OE+l (Beta-nrad)

Iodines and Total Body 1.22E-02 Child 660 (NNE) 1.62E-01 7.5E+0 Particulates L

L I Al.2-1

Summary of Maximum Individual Doses Second Quarter 2003 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)

(Toward) LIMIT QTR Liquid Total Body 2.15E-02 Child Receptor I 1.43E+00 1.5E+0 Liquid Liver 2.39E-02 Child Receptor I 4.78E-01 5.0E+0 Noble Gas Air Dose 8.71E-03 651 (N) 1.74E-01 5.OE+0 (Ganrma-nrad)

Noble Gas Air dose 6.6 1E-02 594 (SSE) 6.61E-01 l.0E+I (Beta-rnrad)

Iodines and Thyroid 3.19E-02 Child 1026 (S) 4.26E-01 7.5E+0 Particulates A1.2-2

Summary of Maximum Individual Doses Third Quarter 2003 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)

(Toward) LIMIT QTR Liquid Total Body 6.49E-03 Child Receptor 1 4.33E-01 1.5E+O Liquid GI-Tract 6.94E-03 Adult Receptor I 1.39E-01 5.OE+0 Noble Gas Air Dose 1.46E-03 651 (N) 2.92E-02 5.OE+0 (Gamrna-nmrad)

Noble Gas Air dose 5.86E-03 617 (NNE) 5.86E-02 1.0E+1 (Beta-murad)

Iodines and Total Body 6.51E-02 Child 659 (N) 8.68E-01 7.5E+O Particulates I

A1.2-3

Summary of Maximum Individual Doses Fourth Quarter 2003 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)

(Tooward) LIMIT QTR Liquid Total Body 1.1 E-02 Adult Receptor 1 7.42E-01 1.5E+0 Liquid Liver 1.50E-02 Child Receptor 1 3.OOE-0I 5.0E+0 Noble Gas Air Dose 8.02E-04 651 (N) 1.60E-02 5.0E+0 (Gamma-mrad)

Noble Gas Air dose 5.82E-04 651 (N) 5.82E-03 l.0E+1 (Beta-mrad) lodines and Total Body 2.66E-02 Child 659 (N) 3.55E-01 7.5E+0 Particulates Al.2-4

Summary of Maximum Individual Doses Fourth Ouarter 2002 Revised EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (I) APPLICABLE (mnrem)

. (Toward) LIMIT QTR Liquid Total Body 3.95E-03 Child Receptor 1 2.64E-01 1.5E+0 Liquid GI-Tract 4.01E-03 Child Receptor 1 8.03E-02 5.0E+0 Noble Gas Air Dose 1.68E-03 651 (N) 3.366E-02 5.0E+0 (Garnma-mnrad) oble Gas Air dose 1.41E-03 651 (N) 1.41E-02 l.0E+1 (Beta-nrad) lodines and Total Body 1.74E-02 Child 659 (N) 2.32E-01 7.5E+0 Particulates 4 th quarter revised to include Fe-55.

A1.2-5

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: A DT/DZ ELEVATION: SPEED: SP1OM DIRECTION:DIR1OM LAPSE: DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 12 10 1 0 0 25 NNE 0 8 7 0 0 0 15 NE 0 7 8 0 0 0 15 ENE 1 8 12 2 0 0 23 E 0 15 7 0 0 0 22 ESE 1 7 0 0 0 8

.0 SE 0 10 6 0 0 16 SSE 0 2 13 21 0 0 36 0

S 0 5 25 0 0 30 SSW 0 4 11 .4 0 0 19 SW 1 18 .2 0 0 35 WSW 2 20 12 .0 2 0 34 W 0 17 19 .0 0 0 36 WNW 1 27 15 0 0 0 43 NW 3 18 2 .0 0 0 23 NNW 2 31 6 0 0 0 39 TOTAL 15 216 179 9 2 0 419 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2. 1-1

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIRlOM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 2 7 1 0 0 10 NNE 0 2 2 0 0 0 4 NE 1 5 3 0 0 0 11 ENE 0 1 1 0 0 0 2 E 1 3 1 0 0 0 5 ESE 2 1 0 0 0 0 3 SE 2 0 0 0 0 0 2 SSE 3 13 3 0 0 0 19 S 1 4 4 0 0 0 9 SSW 1 3 7 0 0 0 11 SW 1 5 7 0 0 0 13 WSW 0 3 1 0 0 0 4 W 2 3 4 0 0 0 9 WNW 0 5 13 1 0 0 19 NW 2 4 0 0 0 0 6 NNW 3 12 9 1 0 0 25 TOT_____________19________________4____3____0_____0____152____

TOTAL 19 66 64 3 0 0 152 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-2

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP1OM DIRECTION: DIR1OM LAPSE: DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 7 7 3 0 0 20 NNE 2 8 0 0 0 10 NE 0 10 4 0 0 0 14 ENE 1 7 1 0 0 0 9 E 3 1 3 0 0 0 7 ESE 1 1 0 0 0 0 2 SE 2 3 1 0 0 0 6 SSE 0 8 3 0 0 0 11 S 0 5 2 1 0 0 8 SSW 1 4 16 1 0 0 22 SW 1 5 3 0 0 0 9 WSW 0 7 4 0 0 0 11 W 1 6 6 0 0 0 13 WNW 0 8 16 1 0 0 25 NW 0 3 3 0 0 0 6 NNW 1 11 12 1 0 0 25 TOTAL 16 94 81 7 0 0 198 PERIODS OF.CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-3

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP1OM DIRECTION: DIRlOM LAPSE: DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 25 17 2 0 0 56 NNE 3 22 S 0 0 0 30 NE 7 38 23 0 0 0 68 ENE 3 19 21 2 0 0 45 E 10 11 18 1 0 0 40 ESE 12 13 10 0 0 0 35 SE 14 21 10 0 0 0 45 SSE 19 28 24 1 0 0 72 S 8 26 25 2 1 0 62 SSW 7 32 50 4 0 0 93 SW 4 28 38 8 0 0 78 WSW 2 9 21 5 0 0 37 W 5 20 21 0 0 0 46 WNW 1 48 49 3 0 0 101 NW 8 65 21 1 0 0 95 NNW 8 67 25 0 0 0 100 TOTAL 123 472 378 29 1 0 1003 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-4

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP10M DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 3 0 0 0 0 3 0

NNE 4 0 0 0 0 4 0

NE 3 2 0 0 0 5 0

ENE 6 2 0 0 0 8 0

E 4 1 0 0 0 5 ESE 13 1 1 0 0 0 15 SE 20 8 0 0 0 0 28 SSE 21 25 2 0 0 0 48 S 14 30 2 0 0 0 46 SSW 5 7 0 0 0 0 12 SW 3 11 8 0 0 0 17 WSW 2 3 S O O 0 11 W 3 10 6 0 0 0 19 WNW 3 2 1 0 0 0 6 NW 3 1 0 0 0 0 4 NNW 2 2 0 0 0 0 4 TOTAL________109______105___ 0_____0_____0_____235______

TOTAL 109 105 51 0 0 0 235 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-5

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 3 2 0 0 0 0 5 ENE 5 4 0 0 0 0 9 E 7 1 0 0 0 0 8 ESE 5 0 0 0 0 0 5 SE 5 2 0 0 0 0 7 SSE 14 11 0 0 0 0 25 S 5 10 1 0 0 0 16 SSW 5 2 0 0 0 0 7 SW 2 0 0 0 0 0 2 WSW 3 0 0 0 0 0 3 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 3 0 0 0 0 0 3 NNW 0 0 0 0 0 0 0 TOTAL 58 32 1 0 0 0 91 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-6

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M IIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 0 O O 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 3 0 0 0 0 0 3 E 6 0 0 0 0 0 6 ESE 2 0 0 0 0 0 2 SE 3 4 0 0 0 0 7 SSE 13 9 0 0 0 0 22 S 1 5 0 0 0 0 6 SSW 2 0 0 0 0 0 2 SW 1 0 O O 0 0 1 WSW 3 0 0 0 0 0 3 W 0 1 0 0 0 0 1 WNW 1 0 0 0 0 0 1 NW 0 0 0 0 0 0 0 NNW 1 0 0 0 0 .0 1 TOTAL 37 19 0 0 0 0 56 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-7

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/03 - 3/31/03 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 22 46 41 7 0 0 116 NNE 9 40 14 0 0 0 63 NE 14 64 40 0 0 0 118 ENE 19 41 35 4 0 0 99 E 31 32 29 1 0 0 93 ESE 36 23 11 0 0 0 70 SE 46 48 17 0 0 0 111 SSE 72 107 53 1 0 0 233 S 29 85 59 3 1 0 177 SSW 21 52 84 9 0 0 166 SW 13 63 69 10 0 0 155 WSW 12 42 44 5 0 0 103 W 11 57 56 0 0 0 124 WNW 6 90 94 5 0 0 195 NW 19 91 26 1 0 0 137 NNW 17 123 52 2 0 0 194 TOTAL 377 1004 724 48 1 0 2154 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 5 A2.1-8

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 50 13 0 0 0 68 NNE 3 6 0 0 0 0 9 NE 3 15 0 0 0 0 18 ENE 0 7 7 2 0 0 16 E 2 19 18 0 0 0 39 ESE 1 12 4 0 0 0 17 SE 0 15 3 '0 0 0 18 SSE 3 13 15 0 0 0 31 S 1 9 8 4 0 0 22 SSW 1 2 8 1 0 0 13 SW 0 28 20 1 0 0 49 WSW 3 26 11 1 0 0 41 W 0 17 1 1 0 0 19 WNW 2 30 2 0 0 0 34 NW 4 37 5 0 0 0 46 NNW 15 140 27 0 0 0 182 TOTAL_________43_____427____ 0_____622______

TOTAL 43 427 142 10 0 0 622 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-1

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR10M LAPSE:DT6OM

______________________________________WI__D__SPEED___(MPH)_

WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 4-- 1___ 0---- 0---- 0-N 4 4 1 0 0 9 0

NNE 4 1 0 0 0 5 0

NE 0 2 0 0 0 2 0

ENE 3 0 1 0 4 0 0 E 1 0 0 0 1 0 0 ESE 0 0 0 0 0 0 0 SE 3 0 0 0 3 0 0 SSE 4 0 0 0 4 0 0 S 5 2 1 0 8 0

SSW 1 1 0 0 0 2 0

SW 1 5 2 0 0 8 0

WSW 0 2 0 1 C 3 0

W 3 2 0 0 0 5 0

WNW 1 3 0 0 0 4 0

NW 3 3 0 0 0 6 0

NNW 3 7 0 0 0 10 TOTAL____________20_______46______5_____3_____0____0_____74___

TOTAL 20 46 5 3 0 0 74 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-2

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT6OM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 5 2 0 0 0 9 NNE 1 3 0 0 0 0 4 NE 2 5 0 0 0 0 7 ENE 1 3 3 1 0 0 8 E 0 S 2 0 0 0 7 ESE 0 1 0 0 0 0 1 SE 1 2 1 0 0 0 4 SSE 3 2 1 0 0 0 6 S 0 5 1 2 0 0 8 SSW 0 2 4 1 0 0 7 SW 0 3 2 4 0 0 9 WSW '1 2 3 0 0 0 6 W 0 3 0 2 0 0 3 WNW 2 2 2 0 0 0 6 NW 6 1 0 0 0 0 7 NNW 4 6 0 0 0 0 10 TOT_____________23______50_____21___________0_____0____102____

TOTAL 23 so 21 8 0 0 102 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-3

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 20 39 1 0 0 0 60 NNE 11 15 0 0 0 0 26 NE 8 13 2 0 0 0 23 ENE 4 20 13 4 0 0 41 E 1 19 25 10 0 0 55 ESE 0 22 5 0 0 0 27 SE 3 12 3 0 0 0 18 SSE 4 7 1 0 0 0 12 S 4 6 6 0 0 0 16 SSW 4 14 8 1 0 0 27 SW 3 16 13 12 0 0 44 WSW 6 4 0 2 0 0 14 W 10 5 6 0 2 0 21 WNW 6 a 5 0 0 0 19 NW 20 14 1 0 0 0 35 NNW 18 29 5 0 0 0 52 243____ 2_____0_____490______

TOTAL 122 243 94 29 2 0 490 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-4

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIRlOM LAPSE:DT6OM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 29 14 0 0 0 0 43 NNE 14 7 0 0 0 0 21 NE 11 13 0 0 0 0 24 ENE 8 15 2 0 0 0 25 E 12 22 1 0 0 0 35 ESE 16 13 8 0 0 0 37 SE 7 9 5 0 0 0 21 SSE 11 21 3 0 0 0 35 S 11 28 15 0 0 0 54 SSW 4 8 9 1 0 0 22 SW 5 20 0 1 0 0 26 WSW 7 15 0 0~ 0 0 22 W 11 11 3 0 0 0 25 WNW 14 2 0 0 0 0 16 NW 15 1 0 0 - 0 0 16 NNW 13 12 0 0 0 0 25 TOTAL 188 211 46 2 0 0 447 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-5

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 1 0 0 0 0 10 NNE 10 1 0 0 0 0 11 NE 12 1 0 0 0 0 13 ENE 7 8 0 0 0 0 15 E 17 4 0 0 0 0 21 ESE 10 0 0 0 0 0 10 SE 4 2 0 0 0 0 6 SSE 13 3 0 0 0 0 16 S 12 7 a 0 0 0 19 SSW 3 3 0 0 0 0 6 SW 7 0 0 0 0 0 7 WSW 6 2 0 0 0 0 8 W 8 1 0 0 0 0 9 WNW 3 0 0 0 0 0 3 NW 6 0 0 0 0 0 6 NNW 9 1 0 0 0 0 10 TO______AL______136_______34______0____0____0_____0____170____

TOTAL 136 34 0 0 0 0 170 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-6

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 0 0 0 0 I0 2 NNE .5 1 0 0 0 6 0

NE 4 1 0 0 0 5 0

ENE 18 1 0 0 0 19 0

E 23 2 0 0 0 25 0

ESE 32 1 0 0 0 33 0

SE 38 1 0 0 0 39 0

SSE 41 1 0 0 0 42 0

S 17 0 0 '0 0 17 0

SSW is 0 0 0 0 15 0

SW 12 0 0 0 0 12 0

WSW 6 0 0 0 . 0 -6 W 12 1 0 0 0 13 0

WNW .9 0 0 0 0 9 0

NW 8 0 0 0 0 8 0

NNW 4 3 0 0 0 7 TOTAL 246 12 0 0 0 0 258 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-7

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/03 - 6/30/03 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 71 113 17 0 0 0 201 NNE 48 34 0 0 0 0 82 NE 40 50 2 0 0 0 92 ENE 38 57 25 8 0 0 128 E 55 72 46 10 0 0 183 ESE 59 49 17 0 0 0 125 SE 53 44 12 0 0 0 109 SSE 75 51 20 0 0 0 146 S 45 60 32 7 0 0 144 SSW 28 31 29 4 0 0 92 SW 28 72 37 18 0 0 155 WSW 29 51 14 4 2 0 100 W 44 40 10 1 0 0 95 WNW 37 45 9 0 0 0 91 NW 62 56 6 0 0 0 124 NNW 66 198 32 0 0 0 296 TOTAL 778 1023 308 52 2 0 2163 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 21 A2.2-8

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: A . DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0-N 16 101 1 0 0 118 NNE 0 0 0 11 2 0 13 0 0 0 NE 11 13 0 24 0 0 0 ENE 4 24 0 28 0 0 0 E 4 10 0 14 0 0 0 ESE 5 12 0 17 0 0 *0 SE 9 20 0 0 29 SSE 9 0 -0 24 0 33

.1 0 0

0 S 16 49 11 77 0 0 0 SSW 7 32 29 68 SW 6 0 0 63 24 0 93 WSW 0 0 4 36 10 0 50 W 0 0 14 55 7 0 76 WNW 16 0 0 31 2 0 49 NW 14 0 0 36 0 0 50 NNW 30 0 0 49 0 0 . 79 TOTAL__________17_____ 1_____0_____0_____818_____

TOTAL 176 557 84 1 0 0 818 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3-1

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 0 0 0 0 1 NNE 2 0 0 0 0 0 2 NE 0 1 0 0 0 0 1 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 2 1 0 0 0 0 3 SE 0 0 0 0 0 0 0 SSE 0 2 0 0 0 0 2 S 2 2 1 0 0 0 S SSW 0 5 2 0 0 0 7 SW 1 2 1 0 0 0 0 4 WSW 0 2 0 1 0 0 3 W 0 1 0 0 0 0 1 WNW 0 .0 0 0 0 0

0 NW 2 0 0 0 0 2

.0 NNW 3 0 0 0 0 3 TOTAL 12 18 4 1 0 0 35 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3-2

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 ,-9/30/03 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT6OM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 O* 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 1 1 0 0 0 0 2 E 2 0 0 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 4 0 .0 0 4 SSE 0 0, 0 0 0 0 0 S 4 1 1 0 0 0 6 SSW 1 4 0 0 0 0 5 SW 0 1 0 0 0 0 1 WSW 0 1 1 0 0 0 2 W 2 2 0 0 0 0 4 WNW 1 1 1 0 0 *0 3 NW 1 1 0 0 *0 0 2 NNW 0 0 0 0 0 0 0 TOTA_____________17___

TOTAL 17 12 3 0 0 0 32 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 N

A2.3-3

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR10M LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 7 0 0 0 0 16 NNE 3 2 0 0 0 0 5 NE 1 2 0 0 0 0 3 ENE 5 3 0 0 0 0 8 E 4 7 0 0 0 0 11 ESE 5 3 0 0 .0 0 8 SE 4 1 0 0 .0 0 5 SSE 9 1 0 0 0 0 10 S 13 5 4 0 0 0 22 SSW 4 12 9 0 0 0 25 SW 4 10 8 0 0 0 22 WSW 4 8 5 0 0 0 17 W 2 16 8 0 0 0 26 WNW 1 8 2 0 0 0 11 NW 2 4 0 0 0 0 6 NNW 4 3 0 0 0 0 7 TOTAL 74 92 36 0 0 0 202 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3-4

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0-- 0-N 24 13 0 0 37 NNE 0 0 15 10 0 0 25 0 19-2 0 NE 12 14 0 0_ 26 ENE 0 __ 0 11 3 0 0 14 E 0 0 0 10 1 0 0 11 ESE 0 0 0 14 3 0 0 17 SE 13 0 0 0 0 0 0 13 SSE 22 0 0 0 0 3 0 25

.0 0 0 0 S 20 48 5 73 0 0

-O 0 SSW 5 17 8 30 0 0 0 0 SW 9 20 5 34 0 0 0 0 WSW 2 6 6 0 14 W 0 0 0 3 19 4 26 0 0 WNW 5 13 2 20 NW 0 0

. 3 5 0 8 0 0 NNW 4 5 1 10 TOTA__________172______180________1_

TOTAL 172 -180 31 0 0 0 383 PERIODS' OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 N.

A2.3-5

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP10M DIRECTION:DIR1OM LAPSE:DT6OM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 1 0 0 0 0 10 NNE 12 0 0 0 0 0 12 NE 20 1 0 0 0 0 21 ENE 17 0 0 0 0 0 17 E 17 1 0 0 0 0 18 ESE 45 5 0 0 0 0 50 SE 16 0 0 0 0 0 16 SSE 22 0 0 0 0 0 22 S 30 17 1 0 0 0 48 SSW 8 1 0 0 0 0 9 SW 2 5 1 0 0 0 8 WSW 5 1 0 0 0 0 6 W 3 2 1 0 0 0 6 WNW 2 0 0 0 0 0 2 NW 4 0 0 0 0 0 4 NNW 7 1 0 0 0 0 8 TOTAL 219 35 3 0 0 0 257 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3-6

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPIOM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 0 0 .0 0 0 4 NNE 1 0 0 0 0 0 1 NE 18 0 0 0 0 0 18 ENE 39 0 0 0 0 0 39 E 67 0 0 0 0 0 67 ESE 65 0 0 0 0 0 65 SE 54 0 0 0 0 0 54 SSE 64 0 0 0 0 0 64 S 76 5 0 0 0 0 81 SSW 35 4 0 0 0 0 39 SW 7 1 0 0 0 0 8 WSW 11 0 0 0 0 0 11 W 7 0 0 0 0 0 7 WNW 2 0 0 0 0 '0 2 NW 5 0 0 0 0 0 5 NNW 4 1 0 0 0 0 5 4____9____11______0____0____0____0____470____

TOTAL 459 11 0 0 0 0 470 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3-7

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/03 - 9/30/03 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP1OM DIRECTICN:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 63 123 1 0 0 0 187 NNE 44 14 0 0 0 0 58 NE 62 31 0 0 0 0 93 ENE 77 32 0 0 0 0 109 E 104 19 0 0 0 0 123 ESE 136 24 0 0 0 0 160 SE 100 21 0 0 0 0 121 SSE 126 30 0 0 0 0 156 S 161 127 23 1 0 0 312 SSW 60 75 48 0 0 0 183 SW 29 102 39 0 0 0 170 WSW 26 54 22 1 0 0 103 W 31 95 20 0 0 0 146 WNW 27 53 7 0 0 0 87 NW 31 46 0 0 0 0 77 NNW 52 59 1 0 0 0 112 TOTAL 1129 905 161 2 0 0 2197 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 11 A2.3 -8

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: A DT/DZ ELEVATION: SPEED: SPlOM DIRECTION:DIR1OM LAPSE :DT6OM

______________________________________WIND___SPEED___(MPH)_

WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1___ 0---- 0---- 0-- 23---

N 0 22 1 0 0 0 23 NNE 0 6 1 0 0 0 7 NE 0 1 0 0 0 0 1 ENE 1 3 0 0 0 0 4 E 0 6 0 0 0 0 6 ESE 1 10 1 0 0 0 12 SE 1 9 0 0 0 0 10 SSE 1 18 5 0 0 0 24 S 1 10 9 5 0 0 25 SSW 0 4 2 0 0 0 6 SW 0 8 14 0. 0 0 22 WSW 1 9 8 0 0 0 18 W 0 12 6 1 0 0 19 WNW 3 11 7 0 0 0 21 NW 1 9 6 0 0 0 16 NNW 2 19 0 0 0 0 21

___0_____6____0_____0____235_____

TOTAL 12 157 60 6 0 0 235 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-1

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIRlOM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 5 0 0 0 0 6 NNE 2 1 0 0 0 0 3 NE 0 0 0 0 0 0 0 ENE 0 3 0 0 0 0 3 E 0 3 0 0 0 0 3 ESE 2 2 0 0 0 0 4 SE 0 7 3 0 0 0 10 SSE 0 6 3 0 0 0 9 S 0 5 3 2 0 0 10 SSW 1 1 8 1 0 0 11 SW 1 4 3 0 0 0 8 WSW 1 1 1 0 0 0 3 W 1 2 0 0 0 0 3 WNW 0 7 4 0 0 0 11 NW 2 8 0 0 0 0 10 NNW 1 4 0 0 0 0 5 TOTAL____________12______59______2_______3____0_____0____99___

TOTAL 12 59 25 3 0 0 99 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-2

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0-N 1 3 1 0 0 0 5 NNE 3 1 1 0 0 5 0

NE 1 0 1 0 0 0 2 ENE 0 0 0 0 0 0 0 E 6 4 1 0 0 0 11 ESE 3 8 0 0 0 0 11 SE 0 4 1 0 0 0 5 SSE 0 3 4 0 0 0 7 S 2 4 2 1 0 0 9 SSW 2 0 4 1 0 7 0

SW 1 2 6 4 0 0 13 WSW 0 5 2 8 0 0 15 W 0 2 2 0 0 0 4 WNW 1 11 7 0 0 0 19 NW 6 20 2 0 0 0 28 NNW 2 16 2 0 0 20 0_____161_____

TOTAL 28 83 36 14 0 0 161 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-3

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF IRECORD: 10/1/03 - 12/31/03 STABILITY iCLASS: D DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 38 7 0 0 0 54 NNE 10 9 2 0 0 0 21 NE 9 7 1 0 0 0 17 ENE 7 25 4 0 0 0 36 E 11 21 3 0 0 0 35 ESE 10 48 2 0 0 0 60 SE 17 39 10 2 0 0 68 SSE 17 37 33 0 0 0 87 S 20 41 57 14 0 0 132 SSW 7 25 57 8 0 0 97 SW 8 25 33 3 0 0 69 WSW 5 18 37 11 0 0 71 W 12 23 34 2 1 0 72 WNW 8 47 18 5 0 0 78 NW 10 53 38 5 0 0 106 NNW 17 47 *16 0 0 0 80 TOTAL 177 503 352 50 1 0 1083 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-4

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0__ 14---

N 8 6 0 0 14 0 0 NNE 7 7 0 0 14 0 0.

NE 5 4 0 0 9 0 0 ENE 9 2 0 0 11 0 0 E 6 7 1 0 14 0 0 ESE 23 9 0. 0 32 0 0 SE 18 20 6 0 44 0 0 SSE .14 24 5 0 43

.9 0_ 0 S 19 28 __ 0 56 0 0 SSW 9 5 3 0 17 0 0 0,

SW 9 8 2 0 19 WSW 0 0 3 7 2 0 12 0 0 W 4 13 2 0 19 0 0 WNW - 10 10 3 0 23 0 0 NW 10 12 0 0 22 NNW 0 0 6 12 3 0 21 0 0 TOTAL 160 174 36 0 370 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 "I

A2.4-5

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0-N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 2 0 0 0 2 0 0 ENE 3 0 0 0 3 0 0 E 12 0 0 0 12 0 0 ESE 22 0 0 0 22 0

SE 16 2 0 0 0 18 0

SSE 8 3 0 0 0 0 11 0

S 13 4 0 0 0 17 0

SSW 5 0 0 0 0 5 0

SW 3 1 0 0 0 4 0

WSW 1 1 0 0 0 2 0

W 1 0 0 0 0 1 0

WNW 1 0 0 0 0 1 0

NW 1 0 0 0 0 1 NNW 1 1 0 0 0 0 2 TOTAL____________89______12______0____0_____0____0____101_____

TOTAL 89 12 0 0 0 0 101 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-6

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 0 0 0 0 0 NNE -1 0 0 0 0 0 1 NE 2 0 0 0 0 0 2 ENE 9 0. 0 0 0 0 9 E 29 0 0 0 0 0 29 ESE 27 0 0 0 0 0 27 SE 23 0 0 0 0 0 23 SSE 28 1 0. 0 0 0 29 S 27 3 0 0 0 0 30 SSW 5 0 0 o 0 0 5 SW 0 0 0 0 0 0 0 WSW 0 0 0- 0 0 0 0 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 TOTAL 151 4 0 0 0 0 155 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-7

SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/03 - 12/31/03 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP1OM DIRECTICN:DIR1OM LAPSE:DT6OM WIND SPEED (MPH)

WIND DIRECTION 1-3 4-7 8-12 13-13 19-24 >24 TOTAL N 19 74 9 0 0 102 0

NNE 23 24 4 0 0 51 0

NE 19 12 2 0 0 33 0

ENE 29 33 4 0 0 66 0

E 64 41 5 0 0 110 0

ESE 88 77 3 0 0 168 0

SE 75 81 20 2 0 178 0

SSE 68 92 50 0 0 _ 210 0

S 82 95 80 22 0 279 0

SSW 29 35 74 10 0 148 0

SW 22 48 58 7 0 135 0

WSW 11 41 50 19 0 121 0

W 18 52 44 3 1 118 0

WNW 23 86 39 5 0 153 0

NW 30 102 46 5 0 183 0

NNW 29 99 21 0 0 149 73______1___0____2204_____

TOTAL 629 992 509 73 1 0 2204 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 4 A2.4-8

OFF-SITE DOSE CALCULATION MANUAL The Off-Site Dose Calculation Manual, PMP-6010-OSD-001, was revised once during the report period. The reasons for these corrections and the Plant Operations Review Committee (PORC) approval, if required, are documented on the Review and Approval Tracking Form. This document is marginally marked. These corrections were determined to maintain the level of radioactive effluent control required by 10 CFR20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Items that are determined to be corrections, in accordance with PMP-2010-PRC-002, Procedure Correction, Change and Review, do not require PORC approval.

A3.0-l

REVIEW AND APPROVAL TRACKING FORM Number: PMP-6010-OSD-001 Rev. 17a Change: 0

Title:

Off-site Dose Calculation Manual 0Correction (Full Procedure) Q Change (Full Procedure) with Review, of Change Only oCorrection (Page Substitution) El Change'(Page Substitutdici) -K$th Review of Change Only OCancellation El New Procedure or Change with Full Review El Superseded (list superseding procedures):__________________________

Change Driver/CDI Tracking No(s).: ON/A, Cross-Discipline Reviews: Programmatic Reviews:

OChemistry Q1 Training El AL4PRA Cl Reactivity _Mgr Team O Maintenance Cl Work Control E] Component Engineering Q SPS (Safety & Health) oNDM 0 ElDesign Enginee~ring 0Srviac Scin' o3 Operations 0 . E Emerg Oper Proc Grp USystem Engineering El PAIPV

[El Reg Affairs 0

.0 '0 El Environmental IST)IIST Coordinator ElSOMS Administrator Q_______

I.

3 RPp 0 None Required 0 Performance Assurance 0None Required El Cognizant Org Review: PI , . .Date: / I 0 Technical Review: . if Dte:

El Ops Director Concurrence: IA' Date: I I Updated Revision Sux~unary-attached?~ . Y s 10 CFR 50.59 Requiremen torop t?4Tr~ .:_____0 Yes 0 N/A Implementation Plan develd d? V ( f. Step 3.4.17) El Yes O N/A Package Complete: A...iIDate: *I13io PORC Review Required: 0Yes .0No Mtg. No.-.____

Administrativ~e Hold Stats: ReleasedNo.:

Approval Authority ReviewApro Date: 5I-/p~

Expiration Date/Ending Activity M Effective Date: piL~

Periodic Review conducted? '(Data Sheet 5 Complete) 1] Yes 12 No

- t-, -A .. r- r fir-- .tr?,rrs~N FP*U U 4~j.t.F I.~ .r4Er .II0'¶ Commitment Database update requested in accordance with PMP-7100-CMP-001? [El Yes 10 N/A NDM notified of new records or changes to records that could affect record retention? E] Yes 0D N/A

REVISION

SUMMARY

Number: PMIP-6010-OSD-001 Revision: 17a Change: 0

Title:

Off-site Dose Calculation Manual Section Change/Reason For Change Correction or Step Criteria

3.3.2 Change

Corrected software reference source error. r Reason: Clarification so the correct linked item is given.

5.2.2 g Change: Added reference to CR 02150078, RRS-1000 o efficiency curve usage.

Reason: Provide reference to help implement determination of efficiencies for RRS-1000.

Att 3.4 Change: Added new flow monitor SFR-402 and attendant m recorder.

Reason: Addition of instrumentation associated with DCPs 1-DCP4214 and 2-DCP-4215. This item is associated with CR 03063062, Action 2.

Att 3.5 Change: Added new flow monitor SFR-402 to surveillance list. m Reason: Addition of instrumentation associated with DCPs 1-DCP-4214 and 2-DCP4215. This item is associated with CR 03063062, Action 2.

Att 3.19 Change: Reformatted various sample frequency boxes. k Reason: Clarification and consistency.

Att 3.19 Change: Changed sample frequency from daily to once per r calendar day for drinking and surface water samples.

Reason: Clarification associated with SA-2003-REA-001 and CR 03034020.

Att 3.19 Change: Added wording pertaining to groundwater sample r stations for the Steam Generator Storage Facility not being actual REMP samples.

Reason: Clarification associated with SA-2003-REA-001 and CR 03034020.

F.NTML !Qfllce Untorm " -, LW Wirmi;.==

0 " idI This is a free-form as called out in PNIP-2010-PRC-002. Procedure Correction, Change. and Review, Rev. la. Page Z of 3

REVISION

SUMMARY

Number: PMP-6010-OSD-001 Revision: 17a Change: 0

Title:

Off-site Dose Calculation Manual Section Change/Reason For Change Correction or Step Criteria Att 3.19 Change: Deleted specific background milk farms addresses and r added verbiage to the note associated with milk sampling.

Reason: This is to provide for consistency with the Indicator Farms. These are controlled by the Land UseCensus and are subject to change at farmer's discretion. This

.item is associated with SA-2003-REA-001 and CR 03034020.

Att 3.19 Change: Added wording pertaining to the edible portion of the r fish being the sample type to the Ingestion - Fish section.

Reason: Clarification associated with SA-2003-REA-001 and

- I! _______ CR 03034020;. ,__,___'_

Att 3.19 -Change; Added off-site (background) broadleaf vegetation r sample section to the Ingestion - Food*Producits section. Also clarified the description/location that pertains to both the grape and .broadleaf samples.

Reason: Clarification associated with SA-2003-REA-001 and CR 03034020.

Att 3.20 Change: Added clarifying words pertaining to LLD application r to actual samples.

Reason: Clarification in response to questions from Chemistry

-______ personnel.

Ir,m;g"Iil,,."Rl,lali.ruig r[16rWati6iMAp*,1,- 01YF-.N,01 _,eglr 1101-t

__ !,qgm M4 7',,,

This is a free-form as called out In PMP-201-PRC-002, Procedure Correction, '

Change, and Review, Rev. 10a. Page 3 of 3

Ap 01L

-- w l PP-610OSDao Rev. 17a lKA Pae I of 84 OFF-SITE DOSE CALCULATION MANUAL Information l l Effective Date: (oI'/C$3 Doug Foster John Carlson i Environmental Writer Owner Cognizant Organization TABLE OF CONTENTS I PURPOSE AND SCOPE .4....................................... :.. 4 2 DEFINITIONS AND ABBREVIATIONS. .......................................4 3 DETAILS.......................................... . ... 4 3.1 Calculation of Off-Site Doses .. 4 3.1.1 Gaseous Effluent Releases .4 3.1.2 Liquid Effluent Releases .10 3.2 Limits of Operation and Surveillances of the Effluent Release Points ... 13 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation . . 13 3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation . . 14 3.2.3 Liquid Effluents .. 15

a. Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge . 15

b. Concentration of Releases from the TRS Discharge .15

c. Dose .: 16

d. Liquid RadwasteTreatxment System ... ..... 16 3.2.4 Gaseous Effluents ............................. 19

a. Dose Rate .19

b. Dose-Noble Gases .19

c. Dose-Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form...................................................................................19

d. Gaseous Radwaste Treatment ............................. 20 3.2.5 Radioactive Effluents - Total Dose.22 3.3 Calculation of Alarm/riip Setpoints .. ......................... 23 3.3.1 Liquid Monitors . . . 24

a. Liquid Batch Monitor Sctpoint Methodology . . 24

b. Liquid Continuous Monitor Setpoint Methodology . .25 3.3.2 Gaseous Monitors . . . 27

a. PlantUnit Vent .. 27

b. Waste Gas Storage Tanks . .29

c. Containment Purge and Exhaust System...........................................30

d. Steam Jet Air Ejector System (SJAE) . . 31

e. Gland Seal Condenser Exhaust ................................... 31 3.4 Radioactive Effluents Total Dose ........................................ 32 3.5 Radiological Environmental Monitoring Program (REMP) . .32 3.5.1 Purpose of the REMP .................... 32 3.5.2 Conduct of the REMP .33

. ..- e P *. *... : v P uM* PMP-6010-OSD-001 Rev. 17a Page 2 of 84 L OFT-SITE DOSE CALCULATION MANUAL Information -Effective Date: 6/ /03 L Doug Foster JohnCarison Environmental Writer Owner Cogtant Organization L

3.5.3 Annual Land Use Census ................................ , 35 3.5.4 Interlaboratory Comparison Program ............................... 35 3.6 Steam Generator Storage Facility Groundwater Monitoring Program .. 36 3.6.1 Purpose ofthe Steam Generator Storage Facility Groundwater Radiological Monitoring Program .36 3.6.2 Conduct of the Steam Generator Storage Facility Groundwater Radiological Monitoring Program ............................. 36 3.7 Meteorological Model .. 36 3.8 Reporting Requirements .. 36 3.8.1. Annual Radiological Environmental Operating Report (AREOR) . 36 3.8.2 Annual Radiological Effluent Release Report (ARERR). 37 3.9 10 CFR 50.75 (g) Implementation ....................... ; 38 3.10 ReportingfManagement Review ..........................

.: 39

4 FINAL CONDITIONS .............. of........................... ...... ,......... . ... 39 5 REFERENCES . .... .... ........ .... ... ...: . ............... ;.. . . .... 39 SUPPLEMENTS Attachment 3.1 Dose Factors for Various Pathways ........................ ; Pages 42 - 45 Attachment 3.2 Radioactive Liquid Effluent Monitoring instruments. Pages 46 - 47 Attachment 3.3 Radioactive Liquid Efflueiit Monitoring Instrumentation Surveillance Requirements . Pages 48 - 49 Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation . Pages 50 - 52 L Attachment 3.5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Reurements..Pages 53 - 54 Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program . Pages 55 - 56 Attachment 3.7 Radioactive Gaseous Waste Sampling and Analysis Program .Pages 57 - 58 Attachment 3.8 Multiple Release Point Factors for Release Points .Page 59 Attachment 3.9 Liquid Effluent Release Systems ., Page 60 Attachment 3.10 Plant Liquid Effluent Parameters ................................... Page 61 L

MI f 2IO PMP-6010-OSD-001 Rev. 17a. Pagc 3 of 84 OFF-SITE DOSE CALCULATION MLANUAL Information Effective Date: (Al/03 Doug Foster John Carlson Environmental Writer Owner Cognizant Organization .11 Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors ............................ Page 62 .12 Counting Efficiency Curves for R-19, and R-24 .......... Pages 63 - 64 .13 Counting Efficiency Curve for R-20, and R-28 ..................................... Page 65 .14 Gaseous Effluent Release Systems ........................ Page 66 .15 Plant Gaseous Effluent Parameters ........................ Page 67 .16 10 Year Average of 1989-1998 Data ....... .................. Pages 68 - 69 .17 Annual Evaluation of xWQ and D/Q Values For All Sectors ................. Page 70 .18 Dose Factors ....... ; Pages.71 - 72 .19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies ...... . ................ Pages 73 -76 .20 Maximum Values for Lower Limits of DetectionsA - REMP..... Pages 77 - 78 .21 Reporting Levels for Radioactivity Concentrations in Environmental Samples .......................................... Page 79 .22 On-Site Monitoring Location - REMP ........................... Page 80 .23 Off-Site Monitoring Locations - REMN ........................... Page 81 .24 Safety Evaluation By The Office Of Nuclear Reactor Regulation...................................................................................... Pages 82 - 84

.. "..- .: ,7 . .C . .1/4 Information T PMP-6010-OSD-001 l Rev. 17a' l Page 4 of 84 OFF-SITE DOSE CAL-CULATION MANUAL

1. PURPOSE AND SCOPE NOTE: This is an Administrative procedure and only the appropriate sections need be performed per PMP 2010 PRC.003, step 3.2.7.

The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the Radioactive Effluent Controls Program (RECP), contains criteria pertaining to

-theprevious Radiological Effluent Technical SpecificAtions (RETS) as defined in NLREG-0472, and fully implements the requirements of Technical

-. Specification 6.8.4.

The ODCM contains the methodology and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.

- The ODCM provides flow diagrams detailing the treatment path and the major components'of the radioactive liquid and gaseous waste management systems.

.The ODCM presents maps of the sample locations and the meteorological model used to estimate the atmospheric dispersion and deposition parameters.

.

The ODCM specifically addresses the design characteristics of the Donald C.

Cook Nuclear Plant based on the flow diagrams containied on the "OP Drawings" and.plant "System Description" documents.

2 DEFINITIONS AND ABBREVIATIONS Term: Meaning:

S or shiftly At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D or daily At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W or weekly At least once per 7 days M or monthly At least once per 31 days Q or quarterly At least once per 92 days SA or semi-annually At least once per 184 days R At least once per 549 days..

S/U Prior to each reactor startup:

P Completed prior to each release Sampling evolution Process of changing filters or obtaining grab samples 3 DETAILS 3.1 Calculation of Off-Site Doses 3.1.1 Gaseous Effluent Releases

Information PMIP-6010-OSD-001 Rev. 17a Page 5 of 84

- OFF-SITE DOSE CALCULATION MANUAL

a. The computer program MIDAS (Meteorological Information and Dose Assessment System) performs the calculation of doses from effluent releases. The site-specific parameters associated with MIDAS reside in the following subprograms:

MIDER

MIDEX

MIDEL

MIDEG

MIDEN

b. The subprogram used to enter and edit gaseous release data is called MDIEQ (EQ). The data entered in EQ can be used to calculate the accumulation of dose to individual land based receptors based on hourly meteorology and release data. The air dose from this data is calculated via the XDAIR subprogram in MIDAS. It computes air dose results for use in Reg. Guide 1.21 reports and 10 CFR 50 Appendix I calculations based on routine releases.

c. The formula used for the calculation of the air dose is generated from site specific parameters and Reg. Guide 1.109 (Eq 7):

D,, Dœair- *X [(M, or N)

Q,* 3.17E.-8]

Where; DT DD air = the gamma or beta air dose in mrad/yr to an individual receptor X /Q = the annual average or real time atmospheric dispersion factor over land, sec/ni3 .from Attachment 3.16, 10 Year Average of 1989-1998 Data M1 = the gamma air dose factor, mrad m3 / yr pCi, from Attachment 3.18, Dose Factors N1 the beta air dose factor, mrad m3 / yr PCi, from Attachment 3.18, Dose Factors Q = the release rate of radionuclide, 'i", in gCi/yr.

3.17E-8 = number of years in a second (years/second).

d. The value for the ground average X / Q for each sector is calculated using equations shown below. Formula used for the calculation is generated from parameters contained in MIDAS Technical Manual, XDCALC (Eq 2).

~~'. . ._.

Information PMP-6010-OSD-001 ' Rev. 17a l Page 6 of 84 OFF-SITE DOSE CALCULATION MLANUAL 2.03 X/p= 203*7 Tj Where; E,. minimum of +=b.,o or x = distance downwind of the source, meters. This information is found in parameter 5 of MIDEX.

U,= wind speed for ground release, (meters/second) a, c vertical dispersion coefficient for ground release, (meters),

(Reg. Guide 1.111 Fig.1)

H, building height (meters) from parameter 28 of MIDER (Containment Building = 49.4 metdrs)

T= terrain factor (=1 for Cook Nuclear Plant) because we consider all ourxeleases to be grounid'level (see parameter S in MIEX).

2.03 = ;r 0.393 radians(22.50)

e. The dose due to gaseous releases, other than the air dose, is calculated by the MIDAS subprogram GASPRO. GASPRO computes the accumulation of dose'to individual receptors based on hourly meteorology and release data. Calculations consider the effect of each important radionuclide for each pathway, organ, age group, distance and direction.

f Calculations are based on the environmental pathwvays-to-man models in Reg. Guide 1.109. The program considers 7 pathways, 8 organs, and 4 age groups in 16 direction sectors. The distances used are taken from the

-MDEG

\ file. *. :..

Information I PMIP-6010-OSD-OD1 i Rev. 17a Page 7 of 84 OFF-SITE DOSE CALCULATION MANUAL

g. The formulas used for the following calculations are generated from site specific parameters and Reg. Guide 1.109:

1. Total Body Plume Pathway (Eq 10)

Dose (mren/year)= 3.1 7E - 8* (Q *Q

S* DFBd)

Where; S= shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy (maximum exposed individual = 0.7 per Table E-15 of Reg. Guide 1.109)

DFBi = the whole body dose factor from Table B-I of Reg. Guide 1.109, mrem - m3per piCi - yr. See Attachment 3.18, Dose Factors.

Qi = the release rate of radionuclide "i"' in jiCilyr

2. Skin Plume Pathway (Eq 11)

Dose(mremlyr) =3.17E-8 *S**[i(Q,

1.11 *DFO+E(Q, *DFS1 )]

Q Where; 1.11 = conversion factor, tissue to air, mrem/mnrad DF it = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", in rnrad m3 /p.Ci yr from Table B-1, Reg. Guide 1.109. ,See Attachment 3.18, Dose Factors.

DFSi = the beta skin dose factor for a semi-infinite cloud of radionuclide "i", in mrem m3/ACi yr from Table B-i, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.

3. Radionuclide and Radioactive Particulate Doses (Eq 13 & 14)

The dose, Dup in mrem/yr, to an individual from radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released to unrestricted areas will be determined as follows:

DiP(mrem/year) = 3.1 7E - 8 *

W

Qu)

Where;

Information PP-6010-OSD-OO1 TRev. 17a Page 8 of 84 OFF-SITE DOSE CALCULATION MANUAL R = the most restrictive dose factor for each identified radionuclide "i",.in m2 mrem miCi sec / yr (for food and ground pathways) or mrem m 3 / yr iLCi (for inhalation pathway), for the appropriate pathway For sectors with existing pathways within five miles of the site, use the values of Ri for these real pathways, otherwise use pathways distance of five miles. See Attachment 3.1, Dose Factors for Various

Pathways, for the maximum RI values for the most

~controlling age group for selected radionucides. RI i'alues were generated by computer code PARTS, see

NUREG-0133,Appndix D.e W = the annual average or real time atmospheric dispersion parameters for estimating doses to an

- individual at the worst case location, and where W is

-further defined as:

Wj., = XIQ for the inhalation pathway, in sec/m3

-OR-W.% = 'DIQ forthe food and ground pathways in 1/m2

- QC the release rate of those radiolodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days, in tiCi/yr

h. This calculation is made for each pathway. The maximum computed dose at any receptor for each pathway is selected. These are summed together to get the dose to compare to the limits. Only the inaximnum ofthe cow milk or goat milk pathway (not both) is included in the total.

i. In addition to the above routines, the QUICKG routine of the MIDAS system is used to provide data used in the monthlyreports due to its ability to use annual average meteorological data rather than real time data, thus shortening the run time involved.

. j. Steam Generator Blowdown System (Start Up Flash Tank Vent)

1. The amount of radioiodine and other radionuclides that are released via the start up flash tank and its vent are calculated through actual sample results while the start up flash tank is in service.

2. The following calculation is peirformed to determine the amount of curies released through this pathway. (Plant established formula.)

Curies=

GPM

time on flash tank (min)

3. 785E - 3 ml

.Information l PMP-6010-OSD-001 Rev. 17a l Page 9 of 84 OFF-SITE DOSE CALCULATION MANUAL Where;' 3.785E-3 = conversion factor, ml Ci/liCi gal.

3. The flow'rate is determined from the blowdown valve position and the time on the start up tank. Chemistry Department performs the sampling and analysis of the samples.

4. This data is provided to the MIDAS computer. and dose calculations (liquid and gas) are performed to ensure compliance with Subsection 3.2, Limits of Operation and Surveillances of the Effluent Release

' Points, dose limits. MIDAS uses the formulas given in step 3.1.2, Liquid Effluent RIeleases, to calculate doses td members of the public.

NOTE: This' section provides the minimum requirements to be followed at Donald C.

Cook Nuclear Plant. -This would be used if actual sample data was not available each time the start up flash tankwas in service.

5. The radioiodine release rate must be determined in accordance with the following equation every 31 day period whenever the specific activity ofthe secondary coolant system is greater than 0.01 iCi/g dose equivalent I-131. _,

6. IF the specific activity of the secondary coolant system is less than 0.01 iCi/g dose equivalent I-131, THEN the release rate mustbe determined once every six months. Use the following plant established equation:

Q,=Ci IPF R, Where; -J Qy = the release rate of I-131 from the steam generator flash tank vent, in giCi/sec, -i Ci = the concentration (jLCi/cc) of[-131 in the secondary coolant averaged over a period not exceeding seven days IPF' the iodine partition factor for the Start Up Flash Tank, 0.05, in accordance with NUREG-0017 Rsgb = the steam generator blowdown rate to the start up flash tank, in cc/sec

7. Use the calculated release rate in monthly dose projections until the next determination to ensure compliance with'Subsection 3.2, Limits

' of Operation and Surveillances of the Effluent Release Points, dose limits. Report the release rate calculations in the Annual Radioactive Effluent Release Report.

8. Steam Generators are sparged, sampled, and drained as batches early

- in outages to facilitate cooldown for entry into the steam generator.

This is repeated prior to startup to improve steam generator chemistry for the startup.

Information PMP-6010-OSD-001 1 Rev. 17a Page 10 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.1.2 Liquid Effluent Releases

a. The calculation of doses from liquid effluent releases is also performed by the MIDAS program. The subprogram used to enter and edit liquid release data is called MDIEB (EB).

b. To calculate the individual dose (mrem), the program DS1LI (I)) is used.

It computes the individual dose forup to 5 receptors for 14 liquid pathways due to release of radioactive liquid effluents. The pathways can be selected using the MIDEL program and changing the values in parameter 1. D.C. Cook Nuclear Plant uses 3 pathways: potable water, shoreline, and aquatic foods (fresh water sport fishing).

c. The equations used are generated from site specific data and Reg. Guide 1.109. They are as follows:

1. PotableWater.(Eq 1) '

R.#,-~110O* U.,DP i-*~jAir, Mp*F*2.23E 3 L D A

'Where; Rm= the total annual dose to organ "j" to individuals of age groups "a" from all of the nuclides"i"in pathway 'p", in mrernlyear -.

1100 ='conversion factor, yr ft3 pCi I Ci sic L Up a usage factor that specifies the ex osure time or intake rate for an individual of age group "a" associated with pathway "p". Given in #29-84 of parameter 4 in MIDEL and Reg. Guide 1.109 Table E-5. .See Attachment 3.1, Dose Factors for Various Pathways.

Mp= the dilution factor at the point of exposure (or the point of withdrawal of drinking water or point ofharvest of aquatic food). Given intparanieter 5 of MIDEL as 2.6.

F = the circulation water system water flow rate; in gpm, is used for evaluating dose via these pathways as dilution flow 2.23E-3 = conversion factor, A' min / sec gal Q = the release rate ofnuclide "i" for the time period of the run input via MIDEB, Curieslyear

DAp =the dose factor, specific to a given'age group "a, radionuclide "i". pathway "p", and organ "j", which can be used to calculate the radiation dose from an intake of a radionuclide, innmrem/pCi. These values are taken from tables E-li through E-14 of Reg. Guide 1.109 and are located within the MIDAS code.

h=radioactive decay constant for Oadionuclide "i", in te hours:1

I Information PMP-6010-OSD-001 l Rev. 17a l Page 11 of 84 OFF-SITE DOSE CALCULATION MANUAL

= the average transit time required for nuclides to reach the point of exposure, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . This ailows for nuclide transport through the water purification plant and the water distribution system. For internal dose, tp is the total elapsed time between release of the nuclides and ingestion of food orwater, in hours. Given as #25 of parameter4 in MIDEL. (tp 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

2. Aquatic Foods (Eq 2)

Rpj-IOO0* Zrap B* ~pi" Mp*F*2.23E_3i, B0 DadAv it Where, -

ip= the equilibrium bioaccurnulation factor for nuclide "i" in pathway"iV", expressed as pCi L /.kg pCi. The factors are located within the MIDAS code and are taken from Table A-i of Reg. Guide 1.109. SeeAttachment 3.1, Dose Factors for Various Pathways.

tp= the average transit time required for nuclides to reach the point of exposure, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This allows for decay during transit through the food chain, as well as during food preparation. Given as #26 of paramneter 4 in MIDEL. (tp

=24 hours)'

4= the dilution factor at the point of exposure, 1.0 for Aquatic Foods. Given in parameter 5 of MIDEL as 1.0.

'N..

Information l PMP-6010-OSD-001 Rev. 17a Page 12 of 84

' OFF-SITE DOSE CALCULATON MANUAL

3. Shoreline Deposits (Eq 3)

RapJ,=1lO,00 0* M F;.E.3*XQ *

Dap 1[e~t] [i1~b

$ 2.23E -3E Fp f J>']*1-e^]

Where; W = the shoreline width factor. Given as'an input of 0.3 when running the program, based on Table A-2 in Reg. Guide 1.109.

T1 - the radioactive half-life of the nuclide, "i", in days D,,j= the dose factor for standing on contaminated ground, in mrem m2 -/ hr pCi. The values are taken from table E-6 of Reg. Guide i .109 and are located within the MIDAS code.

See Attachment 3.1, Dose Factbrs' for Various Pathways.

t = the period of time for which sediment or soil is exposed to the contaminated water, 1.31E+5 hours. Given in MEDEL as item 6 of parameter 4.

tp= the average transit time required for nuclides to reach the point'of exposure, 0 hours0 days 0 hours 0 weeks 0 months .' Give ias #28 of parameter 4 in MIDEL.

110,000 = conversion factor yr fP. pCi / Ci sec m 2 day, this accounts for proportionality constant in the sediment radioactivity model Mp the dilution factor at the point of exposure (or the point of withdrawal of drinldng water or p6int ofharvest of aquatic food). Given in parameter 5 of MIDEL as 2.6.

d. The MIDAS program uses the following plant specific parameters, which are entered by the operator.

1. Irrigation rate O

2. Fractionoftimeonpasture=0

3. Fraction of feed on pasture 0

4. Shore width factor =0.3 (from Reg. Guide 1.109, Table A-2)

e. The results of DS ILI are printed in LDRPT (LP). These results are used in the monthly report of liquid releases.

f$ In addition, the program DOSUM (DM) is used to search the results files ofDSILI to find the maximum liquid pathway individual doses. The highest exposures are then printed in a summary table. Each line is compared with the appropriate dose limit. The table provides a concise summary of off-site environmental dose calculations for inclusion in Annual Radioactive Effluent Release Reports, required by Reg. Guide 1.21.

o: 0 -

Information T PMIP-6010-OSD-001 Rev. 17a' Page 13 of 84 OFF-SITE DOSE CALCULATION MANUAL NOTE: The performance of each surveillance requirement must be within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

3.2 Limits of Operation and Surveillances of the Effluent Release Points 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation

a. The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, are operable with their alarmltrip setpoints set to ensure that the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are not exceeded. .

b. The applicability of each channel is shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments.

c. With a radioactive liquid effluent monitoring instrumentation channel alarmltrip setpoint less conservative than a value which will ensure the . ,

limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (CRS)Discharge, are met without delay, suspend the release of radioactive liquid effluents monitored by the affected channel and reset or declare the monitor inoperable.' I

d. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the applicable action shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, with a maximum allowable extension not to exceed 25% of the surveillance interval, . j excluding the initial performance. -

e. Determine the setpoints in accordance with the methodology described in step 33.1, Liquid Monitors. Record the setpoints.i

f. Dernonstrate each radioactive liquid effluent monitoring instrumentation I channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Attachment 3.3i Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

BASES-LIQUID The radioactive liquid effluent instrminentation is provided'to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments' shall be calculated in accordance with NRC approved methods in the ODCM'to ensure the alarm/trip will occir 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 specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

J

Information I PMP-6010-OSD-001 Rev. 17a Pave 14 of 84 OFF-SITE DOSE CALCULATION MANUAL '

Due to the location of the Westinghouse ESW monitors, weekly sampling is required of the ESW system for radioactivity. This is necessary to ensure monitoring of a CCW to ESW system leak and will continue until the Eberline monitors replace the Westinghouse monitors.

The Eberline monitors are in the actual ESW effluent stream so they will monitor for this leakage. [Ref 5.2.lgg] -

3.2.2 Radioactive Gaseous Effluent Monitoring instrumentation

a. The radioactive gaseous process and effluent monitoring instrumentation channels shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, are operable With their alarm/trip setpoints set to ensure that the limits of step 3.2.4a, Dose Rate, are not exceeded.

.b. The applicability of each channel is shown'in Attachment 3A, Radioactive Gaseous Effluent Monitoring Instrumentation.

c. With a radioactive gaseous process or effluent monitoring instrumentation channel alarin/trip -setpointless conservative than a value which will ensure that the limits of step 3.2.4a, Dose Rate, are met, without delay, suspend the release of radioactive gaseous effluents monitored by the

-affected channel and reset or declare the channel inoperable.

d. -With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Attachment 3.A, Radioactive Gaseous Effluent Mpnitoring Instrunentation, with a maximum allowable extension not to exceed 25%

of the surveillance interval, excluding the initial performance.

NOTE:'- This surveillance requirement does not apply to the waste gas holdup system hydrogen and oxygen monitors, as their setpoints are not addressed in this-

-document.- - '-!'

e. Determine the setpoints in accordance with the methodology as described in step 3.3.2, Gaseous Monitors. Record the setpoints.

f Demonstrate each radioactive gaseous process or effluent monitoring

'instrumentation channel is operable by performinj the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALEBRATION, and

- -CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Attachment 3.5, Radioactive Gaseous Effluent Monitoring

- Instrumentation Surveillance Requirements.

-

f. -...

. . .. *. w@

BASES - GASEOUS The radioactive gaseous effluent instruneniation is provided to monitor' and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occr 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 specified ii Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

e V _. . +

1.Z.j Liqula nmuents

a. Concentration Excluding Releases via the TurbineRoom Sump CMRS)

Dischargie ' I

1. Limit the concentration of radioactive material released via the Batch Release Tanks or Plant Continuous Releases (excluding only TRS discharge to the Absorption Pond) to unrestricted areas to the concentrations in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, limit the concentration to 2E-4 MCinli total activity. -j

2. 'With the concentration of radioactive material released from the site via the Batch Release Tanks or Plant Continuous Releases (other than the TRS to the Absorption Pond) exceeding dte above limits, without.

delay restore the concentration to within the above limits.

3. Sample and analyze radioactive liquid wastes according to the sampling and analysis program of Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

4. Use the results of radioactive analysis in accordance with the methods -

of this document to assure that all concentrations at the point of release are maintained within limits.

b. Concentration of Releases from the TRS Discharge

1. Limit releases via the TRS discharge to the on-site Absorption Pond to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2.' For dissolved or entrained noble gases, limit the concentration to 2E4 pCilml total activity.

j

2. With releases from the TRS exceeding the ab6ve limits, perform a dose projection due to liquid releases to UNRESTRICTED AREAS to determine if the limits of step 3.2.3c.1 have bden exceeded. If the dose limits have been exceeded, follow the directions in step 3.2.3c.2, as applicable.

3. Sample and analyze radioactive liquid wastes according to the program in Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

Information PMP-6010-OSD-001 Rev. 17a Page 16 of 84 OFF-SITE DOSE.CALCULATION MANUAL

4. Use the results of radioactive analysis in accordance with the methods of this document to assure that all concentrations at the point of release are maintained within the limits stated'above.

c. Dose

1. Limit the dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas during any calendar quarter to S 1.5 mrem' to the total body and to

5 mrem to any organ, and durng any calendar year to

3 rarem to the total body and to 10 Inrem to any organ.

2. With the calculated release of radioactive materials in liquid effluents exceeding ten times'any of the limits in Steps !.2.3a, 3.2.3b, or 3.2.3c.1 above, prepare and submit a Written Report, pursuant to

: 10' CFR20.2203, within 30 days after learning ofthe event. This

- report must describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:

a) Estimate of each individual's dose, b) Levels of radiation and concentration of radioactive material involved,-

c) Cause of elevated exposures, dose rates or concentrations,

. -ANd including schedule for achieving conformance with applicable i)Corctuine sthepsltaken a~emgorplmedt ansueaginst replcurrene limits These reports must be'formatted in accordance with PMP-7030.001.002, Licensee Event Reports, Special and Routine Reports, even though this is not ai LER.

3. Determine cumulative and projected dose contributions from liquid effluents in accordance with this document at least once per 31 days.

Dose may be projected based on' estimates from previous monthly projections and currentfor future plant conditions.

Ld. Liquid Radwaste Treatmnent System

1. -Use the liquid radwa'ste treatment system to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses'du6 tiothe liquid effluent from the site when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

2. Project doses due to liquid releases to UNRESTRICIED AREAS at least once per 31 days, in accordance with this document.

Information l PMP-6010-OSDOO1 Rev. 17a Page 17 of 84 OFF-SITE DOSE CALCULATION MANUAL

e. During times of primary to secondary leakage, the use of the startup flash tank should be minimized to reduce the release of curies from the secondary system and to maintain the dose to the public ALARA.

Operation of the North Boric Acid Evaporator (NBAE) should be done in a manner so as to allow the recycle of the distillate water to the Primary Water Storage Tank for reuse. This will provide a large reduction in liquid curies of tritium released to the environment, as there is approximately 40 curies of tritium released with every monitor tank of j NBAE distillate.

Drainage of high conductivity water (Component: Cooling Water and ice melt water containing sodium tetraborate) shall be evaluated to decide whether it should be drained to waste (small volumes only), the Turbine Room Sump (low activity water only) or routed without demineralization processing to a monitor tank for release. This is necessary in order to J minimi zethe detrimental affect that high conductivity water has on the radioactive wastewater demineralization system. :me standard concentration and volume equation can be utilized to determine the impact on each method and is given here. The units for concentration and volume need to be consistent across the equation:

(Ci)(Yi)+(Ca)(Va)=(C)(Vg)

Where; C, the initial concentration of the system being added to V1 = the initial volume' of the system beiuig added to C. = the concentration of the water that is being added to the system V. = the volume of the water that is being added to the system Ct = the final concentration of the system after the addition Vt = the final volume of the system after the addition The intent is to keep the:

WDS below 500 pmhos/cc.

TRS below 1E-5 tC/cc.'

MonitorTank release ALARA to members of the' public.

Wastewater leakage into the liquid waste disposal system will be monitored routinely. In the event the leak rate is determined to be over two gallons per minute (the assumed plant design'ileakage based on the original 2 gpm waste evaporator), increased scrutiny will be placed on locating inleakage, timeliness ofjob order activities, and/or activities causing increased production of waste water.

Information PMP-6010-OSD-00I Rev. 17a Page 18 of 84

. OFF-SITE DOSE CALCULATION MANUAL BASES - CONCENTRATION This specification is provided to ensure the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2. This limitatibn provides'additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures greater than 1)the Section II.A design objectives of Appendix 1, 10 CFR Part 50, to an individual and 2) the limits of 10 CFR Part 20. The concIentration limit for noble gasses is based upon the assumption that Xe-135 is the controlling radionuclide and its Effluent Concentration Unit in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commnission on Radiological Protection (ICRP) Publication 2.;

DOSE -

This specification is provided to implement the requirements of SectionsIIH.A, III.A, and IV.A of Appendix L 10 CFR Part 50. The dose limits implement 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 Ito assure the releases of radioactive material in liquid effluents will be kept "as low as is reason ably achievable".

Also, for fresh water sites with drinking water'supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of thefacility will not result in radionuclide concentrations in the finished drinking water that are in excess'of the.

requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section M.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 an individual 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, will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for'the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix r', Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix r, April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.

.This specification applies to the release of liquid effluents from each reactor at the site. The liquid effluents from the shared system are proportioned among the units sharing the system.

LQUID WASTE 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 release to the environment. The requirements that the appropriate portions of this system be used when specified provide assurance that the releases of radioactive materials in'liquid effluents will be kept "as low as is reasonably achievable'. This specification imiplemenits the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section I.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 friction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

2*.

Information l PMP-6010-OSD-001 Rev. 17- Page 19 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.2.4 Gaseous Effluents

a. Dose Rate L. Limit the dose rate due to radioactive materials released in gaseous effluents from the site to < 500 mrem/yr to the total body and.

3000 mrem/yr to the skin for noble gases. Limit the dose rate due to all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight dys to 5 1500 miem/yr to any organ.

2. With the dose rate(s) exceeding the above limits, without delay

'decrease the release rate to within the above limit(s). '

3. Determine the dose rate due to noble gases ingaseous effluents to be within the above limits in accordance with thd methods and procedures described in this document J

4. Determune the dose rate due to radioactive materials, other than noble gases, in gaseous effluents to be within the above limits in accordance with the methods and procedures of this document by obtaining -

representative samples and performing analyses in accordance with' the sampling and analysis program in Attachrent 3.7, Radioactive Gaseous Waste Sampling and Analysis Program.

b. . Dose-Noble Gases 1.' Limit the air dose in unrestricted areas due to hoble gases released in

gaseous effluents during any calendar quarter; to *5 ini5ad for gamma radiation and S 10 mrad for beta radiation and during any calendar year, to

10 mrad for gamma radiation and *'20 mrad for beta radiation. .

2. 'With the calculated air dose from radioactive noble gases in gaseous effluents exceeding ten times any of the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed -

in step 3.2.3c.2, within 30 days after'learning bf the event.

3. Determine cumulative and projected dose contributions for the total time period in accordance with this document at least on'ce every 31 days.

c. Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in' Particulate Form

1. Limit the dose to a MEMBER OF THE PUBLIC from radioiodine, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater thin eight days in gaseous effluents released to unrestricted areas (site boundary) to the following:

a) During any calendar quarter to less than or equal to 7.5 mrem to -

any organ b) During any calendar year to less than or equal to 15 mrem to any organ.

L Information l PIMP-6010-OSD;O001. - Rev. 17a . Page 20 of 84 OFF-SITE DOSE CALCULATION MANUAL L

2. With the calculated dose from the release of radioiodines,'radioactive

. materials in particulate form, or radionuclideslother than noble gases in gaseous effluents exceeding ten times any 6f the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed in step 3.2.3c.2, within 30 days after learming of the event.

3. Determine cumulative and projected dose contributions for the total time period in accordance with this document at least once every 31 days.

d. Gaseous Radwaste Treatrnent'.

1. Use the gaseous radwaste treatment system and the ventilation exhaust treatment system to reduce radioactive materials in gaseous wastes prior to their discharge when projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas 'when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. Use'the ventilation exhaust treatment system to reduce radioactive materials in gaseous waste prior td their discharge when the projected doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days would exceed 0.3 mrem to any organ.-

2. Project doses due to gaseous releases to UNRESTRICTED AREAS at

-least once per 31 days in accordance with this'docurnent.

BASES - GASEOUS EFFLUENTS -

This specificationis provided to ensure that the dose rate any time at the SITE BOUNDARY from gaseous'effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses:assaciated with the concentrations of 10 CFRPart 20, Appendix B, Table 2. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, to annual average concentrationis exceeding the limits specified in Appendix B., Table 2 of 10 CFR Part 20. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified instantaneous release rate limits restrict, at all times, the,corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to s 500 mrem/yr to

' the total body or to < 3000 mrem/yr to the skin. These instantaneous release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalationpathwayto O1500 mrem/yr.'.

This specification applies to the release of gaseous effluents from all re'actors at the site. The gaseous effluents from the shared system are proportioned among the units sharing that system.

DOSE, NOBLE GASES This specification is provided to implement the requirements of SectioAs II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits implement the guides set forth in Section 1T.B of Appendix I.

Information PIP-6010-OSD-001 Rev. 17a Page 21 of 84 OFF-SITE DOSE CALCULATION MANUAL _.

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' II.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models -

and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guidell.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix r', Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors'", Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary will be based upon the historical average atmospherical conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES .

This specification is provided to implement the requirements of Sections ILC, M.A, and IV A of Appendix L 10 CFR Part 50. The dose limits are the guides set forth in Section ILC of Appendix L .

The ACTION statements provide the required operating flexibility and!at the same time implement the guides set forth in section IV.A of Appendix Ito assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable!". The*

ODCM calculational methods specified in the surveillance requirements implement the requirements in Section I.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an -

individual through the appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendii r',

Revision 1, October 1977 and Regulatory Guide 1.1 11, 'Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled .

Reactors", Revision 1, July 1977. These equationsiiiso provide the methodology for determining the actual doses.based upon the historical average atmospheric conditions. The release rate .

specifications for radioiodines, radioactive material in particulate form; and radionuclides, other than noble gases, are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 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.

Information l . PMIP-6010-OSD-001 Rev. 17a' Page 22 of 84 OFF-SITE DOSE CALCULATION MANUAL GASEOUS WASTE TREATMENT The operability of the gaseous radwaste treatment system and the ventilation'exhaust treatment systems ensures that the systems 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 specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion Section ll.l ofthe Final SafetyAnalysis Report for the Donald C. Cook NuclearPlant, and design objective Section II.D of Appendix Ito 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guides forth in Sections IIB and I.C of Appendixi 1,0 CFR Part 50, for gaseous effluents.>

3.2.5 Radioactive Effluents - Total Dose'

a. The dose or dose'commitmnent to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total bbdy or any organ (except the thyroid, which is limited to *75 mrem) over a period of 12 consecutive months.

b. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding one half the annual limits of steps 3.2.3c (Dose), 3A2.4b (Dose -Noble Gases),or 32.24c (Dose-Iodine-131, Iodine-133, Tritium, 'and Radioactive Material in Particulate Form) during any calendar quarter, perform the following: ;

- Investigate and identify the causes for such release rates; Define and initiate a program for corrective action;

Report these actions to the NRC within 30 days from the end of the quarter during which the release occurred.

IF the estimated dose(s) exceeds the limits above, and IF the release condition resulting in violation has not already been corrected prior to violation of 40 CFR 190, THEN include in the'rep'ort a request for a variance in accordance with the provisions of4O CFR 190 and in6luding the'sp~ecified information of paragraph'l 90.1 (b). Subnittal of the report is considered a timely request, and a variance is grmated until staff action on the request is complete. The variance only relates to the limits of

- 40 CFR 190, and does not apply in anyway to the requirements for dose limitation of 10 CUR 50, as addressed in other sections of this document.

c. Determine cunulative dose contributions from liquid mid gaseous effluents in accordance with this document (including steps 32.3c [Dose),

3.2.4b [Dose - Noble Gases], or 3.2.4c [Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form]).

Information I PMIP-6010-OSD-001 I Rev. 17a3 Page 23 of 84 OFF-SITE DOSE CALCULATION MANUAL

._J BASES - TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation'andsubmittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix L For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors reiainawithiii the reporting "I,

requirement level. The Special Report will describe a course of action, which should result in the limitations of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to

I any member of the public from other uranium fuel cycle sources is negligible with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public isestimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected, in accordance with the provision of 40 CFR 190.1 1), is considered to be a timely request and fulfills the

._i requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation, which is part of the nuclear fuel cycle.

I I 3.3 Calculation of AlafxwTrip Setpoints The alarm and trip setpoints are to provide monitoring, indication, and control of liquid I i; and gaseous effluents. The setpoints are used in conjunction with sampling programs to assure that the releases are kept within the' limits of 10 CFR 20,Appendix B, Table 2.

Establish setpoints for liquid and gaseous imonitors.'Depending on the monitor function, it would be a continuous or batch monitor. The different types of monitors are subject to different setpoint methodologies. '

One variable used in setpoint calculations is the multiple release point (MRP) factor. The MRP is a factor used such that when all the releases are integrated, the applicable LIMIT I value will not be exceeded. The MRP is determined 'such that the sum of the MRP's for that effluent type (liquid or gaseous) is less than or equal to 1. The value of the MRP is .- I arbitrary, and it should be assigned based on operational perfornance. The values of the , k MRP's for each liquid release point are given in Attachment 3.S, Multiple Release Point Factors for Release Points.'

The Site' stance on instrument uncertainty is taken from HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits, which states the NRC position is the result of a valid measurement obtained by a method, which provides a reasonable demonstration of compliance. This value should be accepted and the uncertainty in that measured value need niot be considered.

_f.

Information PMP-6010-OSD-001 Rev. 17a Page 24 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.3.1 Liquid Monitors Establish liquid monitor setpoints for each monitor of the liquid effluent release systems. A schematic of the liquid effluent release systems is shown as Attachment 3.9, Liquid Effluent Release Systems. Alist of the Plant Liquid Effluent Parameters is in Attachment 3.10, Plant Liquid Effluent Parameters. The details of each system design and operation can be'found in the system descriptions. The setpoints are intended to keep releases within the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Determine setpoints using either the batch or the continuous methodology.

a. Liquid Batch Monitor Setpoint Methodology

1. There is only one monitor used on the Waste Disposal System for liquid batch releases. This monitor is identified as RRS-1000. Steam Generator Blowdown radiation monitors also can be used to monitor batch releases' while draining steam generators. The functioA of these monitors is to act as a check on the sampling program. The sainipling program determines the nuclides and concentrations of those nuclides prior to release. 'The discharge and dilution flow rates are then adjusted to keep the release within the limits of 10 CFR 20. Based on the concentrations ofnuclides in the release, the count rate on the monitor can be predicted. The high alarm setpoint can then be set above the predicted value up to the maximum setpoint of the system.

2. The radioactive concentration of each batch of radioactive liquid waste to be discharged is determined prior to each release by sampling and analysis in accordance with Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program..

3. 'The allowable release flow rates are determined in order to keep the release concentrations within the requirements of 10 CFR 20, Appendix B, Table 2, Column 2. The equation to calculate the flow rate is from Addendum AA1 of NLREG-0133:

[CI]*f

F+f L fllJ MRP Where; Cj = the concentration of nuclide "i" in itCi/rnl LIMIT 1 = the 10 CFR 20, Appendix B, Table 2, Column 2 limit of nuclide "i" in giCihnl f = the effluent flow rate in gpm (Attachment 3.10, Plant Liquid Effluent Parameters).

F the dilution water flow rate as estimated prior to release. The dilution flow rate is a multiple of 230,000 gpm depending on the number of circulation pumps Mioperation.

MRP = the multiple release point factor. A factor such that when all the release points are operating'at one time the limits of 10 CFR 20 will not be exceeded.

Information PM1P-6010-SD-001 l Rev. 17a Pa e 25 of 84 OFF-SITE DOSE CALCULATION MANUAL

4. This equation must be true during the batch release. Before the I release is started, substitute the maximum effluent flow rate and the minimum dilution flow rate for f and F, respectively. If the equation

'is true, the release can proceed with those flow' rates as the limits of operation.- If the equation is not true, the effluent flow rate can be reduced or the dilution flow rate can beincreased to make the equation true. This equation may be rearranged to solve for the maximum effluent release flow rate (f).

5. The setpoint is used as a quality check on the sampling program. The setpoint is used to stop the effluent flow when the monitor reading is greater than the predicted value from the sampiling program. The predicted value is generated by converting the effluent concentration for each gamma emitting radionuclide to counts per unit of time as per Attachment 3.11, Volumetric Detection Efficiencies for Principle 4 Gamma Emitting Radionuclides for Eberline Liquid Monitors, or Attachment 3.12, Counting Efficiency Curves for R-19, and R-24.

The sum of all the counts per unit of time is the predicted count rate..

The predicted count rate can then be multiplied by a factor to 1 detennine the high alarm setpoint that will provide a high degree of conservatism and eliminate spurious alarms.

b. Liquid Continuous Monitor Setpoint Methodology

1. There are eight monitors used as potential continuous liquid release monitors. These monitors are used in the steam generator blowdown (SGBD), blowdown treatment (BDT); and essential service water (ESW) systems.

2. The Westinghouse monitors (R) are being replaced by Eberline monitors (DRS, WRA) and are identified as:.

R-19 or DRS 3100/4100 for SGBD

. R-24 or DRS 3200/4200 for BDT

. R-20 or WRA 3500/4500 for the east ESW system

. R-28 or WRA 3600/4600 for the west ESW system The function of these monitors is to assure that releases are kept within the concentration limits of 10 CFR 20, 'Appendix B, Table 2, Column 2, entering the unrestricted area followiing dilution.

3. The monitors on steam generator blowdown aind blowdown treatment systems have trip functions associated with their setpoints. Essential service watermonitors are equipped with an alarm fimction only and monitor effluent in the' event the Containment'Spray Heat Exchangers are used or the ESW system (Eberline).

Info ation l -PMP-6010-OSD-01 Rev. 17a Page 26 of 84 OFF-SITE DOSE CALCULATION MANUAL-

4. The equation used to determine the setpoint for continuous monitors is from Addendum AAl ofNUREG-0133:

C*Eff*MRP*F*SF f

Where; Sp. = setpoint of monitor (cpm)

C - 5E-7 'LCi/ml, maximum effluent controflimit from 10 CFR 20, Appendix B, Table 2, Column 2 of a known possible nuclide in effluent stream. (The limiting nuclide shall be evaluated annually byreviewing currentnuclides

~against historical ones in order to determine if one with a more restrictive effluent concentration limit than Sr90 is found. The concentration limit shill be adjusted appropriately.)

-OR-ifamixture is to be specified,

* -.-- 2 CI

LDRITI Eff = Efficiency, this information is located in Attachment 3;11, Volumetric Detecti6n Efficiencies for Principle Gamma

' Emitting Radionuclides for Eberline Liquid Monitors,

through Attachment 3.13, Counting Efficiency Curve for

R-20, and R-28, for the specific monitors. For Eberline monitors the efficiency is nuclide specific and the calculation changes slightly to:'

(C,*Eff,)r C*Eff vC,

- ' '- -L.MrTt' MRP multiple release point factor. A factor such that when all the release points are operating at one time the limits of 10 CFR 20 will not be exceeded (Attachment 3.8, Multiple Release Point Factors for Release Points). The MRP forESW monitors is set to 1.

F = dilution water (circ water) flow rate in gpm obtained from Attachment 3.10, Plant Liquid Effluent Parameters. For routine operation, the setpointshoiild be calculated using the minimum dilution flow rate of 23 0,000 gpm.

SF Safety Factor, 0.9.

f = applicable effluent release flow rate in gpm. For routine operation, the setpoint should be calculated using maximum effluent flow rate (Attachment 3.10, Plant Liquid Effluent Parameters).

S.... *! - a Information T- PMIP-6010-OSD-001 Rev. 17a l Page 27 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.3.2 Gaseous Monitors For the purpose of implementing Step 3.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation, and Substep 3.2Aa, Dose Rate, the alarm setpoints for gaseous effluents released into unrestricted areas will be established using the following methodology. In addition, the above steps do not apply to instantaneous alarm and trip setpoints for integrating radiation monitors sampling radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. A schematic of the gaseous effluent release systems is presented in Attachment 3.14, Gaseous Effluent Release Systems: Attachment 3.15, Plant Gaseous Effluent Parameters, presents the effluent flow rate parameter(s).

Gaseous effluent monitor high alarm setpoints will routinely be established at a fraction of the maximum allowable setpoint (typically 10% of the setpoint) for ALARA purposes. Alert alarms will normally be set to provide adequate indications of small changes in radiological conditions.

a. Plant Unit Vent

1. The gaseous effluents discharged from the plant vent will be monitored by the plant vent radiation monitor low range noble gas channel [Tag No. VRS-1505 (Unit 1), VRS-2505 (Unit 2)] to assure that applicable alarms and trip actions (isolation of gaseous release) will occur prior to exceeding the limits in step!3.2.4; Gaseous Effluents. The alarm setpoint values will be established using the following unit analysis equation:

SF

MALP

DLE Sp; Fp

VQ *>(W(*DCFg)

Where; Sp= the maximum setpoint of the monitor in jtCi/cc for release point p, based on the most limiting organ SF = an administrative operation safety factor, less than 1.0 WP = a weighted multiple release point factor (* 1.0), such that when all site gaseous releases are integrated, the applicable dose will not be exceeded based on the release rate of each effluent point.

The MRP is an arbitrary value based on the ratio of the release rate or the volumetric flow rate of each effluent point to the total respective flow rate value of the plant and will be consistent with past operational experience. The MRP is computed as follows:

- Compute the average release rate, Q., (or the volumetric flow rate, fp) from each release point p.

Compute XQp (or Zfp) for all release points.

a Ratio Qp/ZQp (or fp/ZEfp) for each release point. This -4 ratio is the MRP for that specific release point

. Repeat the above bullets for each of the site's eight gaseous release points.

Information PMP-6010-OSD-001 Rev. 17a l Page 28 of 84 OFF-SITE DOSE CALCULATION MANUAL Fp= the maximum volumetric flow rate of release point "p", at the time of the release, in cc/sec. The maximum Unit Vent flow'rate, by design, is 186,600 cfn for Unit 1 and 143,400 cfm 'for Unit 2.

DLj = dose rate limit to organ "j" in an unrestricted area (mrer/yr).

Based on continuous releases, the dose rate limits, DI.,

from step 3.2.4a, Dose Rate, are as follows:

Total Body S 500 mrernryear Sldn c 3000 mrem/year

-. Any Qrgan* 1500 mremn/year' X / Q = The worst case annual average relative concentration in the applicable sector or area, in se6/m3 (see Attachment 3.16, 10 Year Average of 1989-1998 Data).

W = weighted factor for the radionuclide:

.Ck .

Where,: -

C; = concentration of the most abundant radionuclide "i"

- Ck total concentration of all identified

radionuclides in that rekase pathway. For batch releases, Uis value maybe set to I for.

-conservatism.

DCFUj =.dose conversion factor used to relate radiation.

dose to organ 'T", from exposure to radionuclide

"i" in mremm /yrpiCi; See following equations.

The dose conversion factor, DCFq1 , is dependent upon the organ of concern.

For the whole body DCfV K=

Where; I

Ki = whole body dose factor due to gamma

-emissions for each identified noble gas radionuclide in minern n 3 / yr .gCi. See Attachment 3.18, pose Factors.

For the sldn: DCFU- LI +1.lMj I . .

Where; skin dose factor due to beta emissions for

'each identified noble gas radionuclide, in mrem rn3 / yr pCi! See Attachment 3.18, Dose Factors.

1.1 = the ratio of tissue to air absorption coefficient over the energy range of photons of interest.

This ratio converts absorbed dose (mrad) to dose equivalent (mrrem).

Information PMIP-6010-OSD-001 l Rev. 17a F Page 29 of 84 OFF-SITE DOSE CALCULATION? MANUAL N i = the air dose factor'due to gamma emissions for each identified noble gas radionuclide in mrad m3 / yr ptCi. See Attachment 3.18, Dose Factors.

For the thyroid, via inhalation: DCFij = Pi Where; Pi= the dose parameter, for radionuclides other than noble gas3 for the inhalation pathway in mremin / yr LCi (and the food and ground path, as appropriate).

See Attachment 3.18, Dose Factors.

2. The plant vent radiation monitor low range noble gas high alarm channel setpoint, S., will be set such that the dose rate in unrestricted areas to the whole body, skin and thyroid (or any other organ),

whichever is most limiting, will be less than or equal to 500 mrem/yr, 3000 mrem/yr, and 1500 mrem/yr respectively.

3. The thyroid dose is'limited to the inhalation pathway only.

4. The plant vent radiation monitor low range noble gas setpoint, Sp, will be recomputed whenever gaseous releases like Containment Purge,.

Gas Decay Tanks and CVCS HUTs are discharged through the plant vent to determine the most limiting org'an.

5. The high alann setpoint, Sp, maybe established at a lower value than the lowest computed value via the setpoint eqiation.

6. Containment Pressure Reliefs will not have a recomputed high alarm setpoint, but will use the normal high alarm setpoint due to their randomness and the time constraints involved in recomputation.

7. At certain times, it may be desirable to increase the high alarm setpoint, if the vent flow rate is decreased. This may be accomplished in one of two ways.

-Max Conc (euClcc)* Max Flowrate(c*f) New Max cfin New Max Concentration(pCi/cc)

-OR-Max Conc (pCi/cc)

Max Flowrate(cfin)

.=Newv Max pCi~cc New Max Flowrate(cfim)

b. Waste Gas Storage Tanks

1. The gaseous effluents discharged from the Waste Gas System are monitored by the vent stack monitors VRS-1505 and VRS-2505.

I Information T PMP-6010-OSD-001' Il Rev. 17a I Page 30 of 84

' OFF-SITE DOSE CALCULATION MANUAL '

. - I

2. In the event of a high radiation'alann, an automatic termination of the release from the waste gas system will be initiated from the plant vent radiation monitor low range noble gas channel (VRS-1505 or VRS-2505). Therefore, for any gaseous release configuration, which includes normal operation and waste gas system gaseous discharges, the alarm sitpoint of the plant vent radiation monitor will be recomputed to determine the most limiting organ based on all gaseous effluent source terms.

Chemical and Volume Control System Hold Up Tanks (CVCS HUT), containing high gaseous oxygen concentrations, may be released under the guidance of waste gas storage tank utilizing approved Operations' procedures.

3. -It is normally prudent to allow 45 days of decay prior to releasing a Gas Decay Tank (GDT). There are extenuating, operational circumstances that may prevent this from occurring. Under these circumstances, such as high oxygen concentration creating a combustible atmosphere, it is prudent to waive the 45-day decay for safety's sake.'

c. Containment Purge' and Exhaust System

1. The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust System are monitored by the plant vent radiation monitor noble gas channels (VRS-1505 for Unit 1, VRS-2505 fo rUnit 2); and alarms and trip actions will occur prior to exceeding the limits in step 3.2.4a, Dose Rate.

2. For the Containment System, a continuous air sample from the containment atmosphere is drawn through a closed, sealed system to the radiatioinmonitors (lag No. ERS-130011400 for Unit 1 and ERS-2300/2400 for Unit 2): During purges, these monitor setpoints will give a Purge and Exhaust Isolation signal upon actuation of high alarm setpoints for particulate and noble gas channels. The sample is then returned to containment. 'Grab sample analysis is performed for a

'Containment purge before release.

3. The Upper Containment area is monitored by normal range area gammamonitors(TagNo.VRS-1I01/1201 forUnit 1 and VRS-2101/2201 'for Unit 2), which also give Purge and Exhaust Isolation Trip signals upon actuation oftheirlhigh alarm.

4. For the Containment Pressure Relief System, no sample is routinely taken prior to release, but a sample is obtained twice per month.

.. - . . . i - e .

Information I PMP-6010-OSD-001 Rev. 17a l Page 31 of 84 I

l OFF-SITE DOSE CALCULATION MANUAL -

5. The containment airborne and area monitors, upon actuation of their high alarm, will automatically initiate closure of the Containment and.

Instrument Room purge supply and exhaust duct valves and containment pressure relief system valves. Complete trip of all isolation control devices requires high alarm of one of the two Train A monitors (ERS-1300/2300 or VRS-1 101/2101) and one of the two Train B monitors'(ERS-1400/2400 or VRS-1201/2201).

d. Steam Jet Air Ejector System (SJAE)

1. The gaseous effluents from the Steam Jet Air Ejector System discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1900 for Unit 1 and SRA-2900 for Unit 2). The monitor will alarm prior to exce~ding the limits of step 3.2.4a, Dose Rate. The alarm'setpoint for the Condenser Air Ejector System monitor will be based on the maximu mi air ejector exhaust flow rate, (Attachment 3.15; Plant Gaseous Effluent Parameters).

The alarm setpoint value will be established using the following unit analysis equation: ;

SF. AUP* DL, F. *F Q **af(W,*DCFI)

Where;.

SsjAE= the maximum setpoint, based on the most limiting organ, in pCilcc and where the other terms are as previously defined

e. Gland Seal CondenserExhaust

1. The gaseous effluents from the Gland Seal CondenserExhaust discharged to the environment are continuously monitored by radiation monitor (Tag No.: SRA-1800 for Unit I and SRA-2800 for Unit 2). The radiation monitor will alarm prior to exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the GSCE mohitor will be based on the maximum condenser exhaust flow rate (1260 CFM for Unit 1, 2754 CFM each for the two Unit 2 vents). The alarm setpoint value will be established using the following unit analysis equation:

SF*MRP *DLi F.>*ZQ*(W,*DCFU)

Information I PMP-6010-OSD-001 j Rev. 17a Page 32 of 84 OFF-SITE DOSE CALCULATION MANUAL Where; SOSCE = the maximum setpoint, based on the most limiting organ, in jCi/cc and where the other terms are as previously'defined.

3.4 Radioactive Effluents Total Dose 3.4.1 The cumulative dose contrbutions from liquid and gaseous effluents will be

'determined by summinrg the cumulative doses as derived in steps 32.3c (Dose),

-3.2.4b (Dose - Noble Gases), and 3.2.4c (Dose - Iodine-13 1, Iodine-133, Tritium, and Radioactive Material in Particulate Form) 'of this procedure. Dose contribution from direct radiation exposure will be based on the results of the

--direct radiatimo nitoringdeviceslocadat the REMP monitoring stations.

See NUREG-0133, section 3.8.

3.5 Radiological Environmerital Monitoring Program (RE )

3.5.1 PurposeoftheRErvw

a. The purpose of the REM. is to:

Establish baseline radiation and radioactivity concentrations in the environs prior-to reactor operations,

' Monitor critical environmental exposure path'ays, Determine the iadiological impact, if any, caused by the operation of the Donald C. Cook Nuclear Plant uponlthe local environment

b. The first purpose of the REMP was completed pricr to the initial operation of either of the two nuclear units at the Donald C. Cook Nuclear Plant Site.

The second and third purposes of the REM are an on-going operation and

as such various environmental media and exposure pathways are examined. The various pathways and sample media used are'delineated in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies. Included is a list of the sample media, analysis required, sample stationis, and frequency requirements for both'collection and analysis. Attachment 3.19, Radiological Environmental Monitoring Program.Sample Stations, Sample Types, Sample Frequencies, defines the scope of the REM? for the Donald C. CookNuclear Plant.

. . -0 ; , ...

Information l PMP-6010-OSD-001 I Rev. 17a' I Page 33 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.5.2 Conduct of the REMP (Ref 5.2.1u]

a. Conduct sample collection and analysis for the REvP in accordance with Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, Attachment 3.20, Maximum Values for Lower Limits ofDetections" - REMP, and Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples. These are applicable at all times. The on-site monitoring locations are shown on Attachnient 3.22, On-Site Monitoring Location - REMP, and the off-site monitoring locations are shown on Attachment 3.23, Off-Site Monitoring Locations ' REMP.

1. Perform each surveillance requirement within the specified time

- interval in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, with a maximum allowable extension not to exceed 25% of the surveillance interval.

2. If an environmental sample cannot be colldcted in accordance with step 3.5.2a, submit a description of the reasons for deviation and the actions taken to prevent a reoccurrence as part of the Annual Radiological Environmental Operating Report (AREOR).

._j Deviations from the required sampling schedule are permitted if specimen's are unobtainable due to hazardous conditions, seasonal unavailability, ormalfunction of automatic sampling equipment. If the deviation from the required sampling schedule is due to the malfunction of automatic sampling equipment, make every effort to complete the corrective action prior to the end of the next sampling period.

3. If a radionuclide is detected in any sample medium exceeding the limit established in Attachment 3.21, Reportig'Levels for Radioactivity Concentrations in Environmental Samples, or if more

-than one radionuclide is detected in any sample medium and the Total Fractional Level (TEL), when averaged over the calendar quarter, is greater than or equal to 1, based on the following formula:

N1 La, co) I-C Lv)

Where; C(l) = Concentration of 1 st detected nuclide C,2) = Concentration of 2 nd detected nuclide L(E) = Reporting Level of 1st nuclide fr6m Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

L(2 ) = Reportig Level of2nd nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

Information PMP-6010-OSD-001 Rev. 17a' Page 34 of 84 OFF-SITE DOSE CALCULATION MANUAL And, if the activity is the result of plant effluents, evaluate the release conditions, environmental factors, or other aspects, which mayhave contributed to the identified levels for inclusion in the AREOR If the radioactivity was not a result of plant effluents, describe the results in the AREOR.

4. If a currently sampled milk farm location becomes unavailable, conduct a special milk farm survey within 15 days.

a) If the unavailable location Was an indicator farm, an alternate

- sample location may be established within eight miles of the Donald C. Cook Nuclear Plant, if one is available.

b) If the unavailable location was a background farm, an alternate sample location maybe established greater than 15 but less than 25 miles of the Donald C. Cook Nuclear Plint in one of the less prevalent wind direction sectors, if one is available.

.c) If a replacement farM is unobtainable and the total number of indicator farms is less than three or the background farms is less than one, perform monthly vegetation sampling in lieu of milk sampling..

BASES- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

The REMP provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the statiofi'operation. Thereby, this monitoring program supplements the radiological effluent monitoring program by verifying -the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The initially specified REMP will be effective for at least the first three years of commercial operation. 'Program changes maybe initiated based on operational experience in accordance with the requirements of technical specification 6.8.4.b.

The detection capabilities, required by Attachment 3.20, Maximum Values for'Lower Limits of Detections' - REMP, are the state-of-the-art for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as 'a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLI s will be achieved under routine analysis conditions; -Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing'factors will be identified and described in the6Annual Radiological Environmental Operating Report.

Information PMIP-6010-OSD-001 Rev. 17a Page 35 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.5.3 Annual Land Use Census [Ref 52.1u]

a. Conduct a land use census and identify the location of the nearest milk animal, the nearest residence and the nearest gardein of greater than 500 square feet producing fresh leafy vegetables in each of the ten land sectors within a distance of five miles.

b. In lieu of the garden census, grape and broad leaf vegetation sampling may be performed as close to the site boundary as possible in a land sector, containing sample media, with the highest average deposition factor (D/Q) value.

c. Conduct this land use census annually between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local agricultural authorities.

1. With a land use census identifying a location(s), which yields a calculated dose or dose commitment greater than the values currently being calculated in this document, make appropriate changes to incorporate the new location(s) within 30 days, ifpossible.

BASES - LAND USE CENSUS This is provided to ensure changes in the use of unrestricted areas are identified and modifications to the monitoring program are made in accordance with requirements of TS 6.8.4b, if required by

'the results of the census. This census satisfies the requirerients of Secti6n IV.B.3 of Appendix.I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet 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 quanitity (25 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for'consumption of a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% ofthe garden was used for growing broad leaf vegetation (that is, similar to lettuce and cabbage), and 2) a vegetation field of 2 kg/square meter.

3.5.4 Interlaboratory Comparison Program

a. inorder to comply with Reg. Guides 4.1 and 4.15, the analytical vendor participates in an Interlaboratory Comparison Program, for radioactive materials..

Address program results and identified deficiencies in the AREOR.

1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the AREOR.

BASES - INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure independent checks on the precision and accuracy ofthe measurements of radioactive.

material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.

Information PMP-6010-OSD-001 j Rev. 17a I Page 36 of 84 OFF-SITE DOSE CALCULATION MANUAL 3.6 Steam Generator Storage Facility Groundwater Monitoring Program

.- 3.6.1 Purpose of the Steam Generator Storage Facility Groundwater Radiological Monitoring Program

a. The purpose of the temporary on-site Steam Generator Storage Facility Radiological Monitoring Program is to'establish baseline radiological data for the groundwater surrounding the facility prior to the storage of the Unit 2 Steam Generator Lower Assemblies. Thereafter, the purpose is to monitor the groundwater through observation wells with locatibns as shown in Attachment 3.22, On-Site Monitoring Location - REMP, to determine the radiological impact; if any, caused by the use of the Storage Facility.

3.6.2 Conduct of the Steam Generator Storage Facility Groundwater Radiological Monitoring Priogram

a. Collect and analyze groundwater samples in accordance with Attachment 3.19, Radiological Environmental Monitoring Program,'Sample Stations, Sample Types, Sample Frequencies. Apply the values from Attachment 3.20, Maximum Values for Lower Limits of Detections"L - REMP, (excluding 1-131) and Attachment 3.21, Reporting Levels for;Radioactivity Concentrations in Environmental Samples, (excluding I-131).

_..7.

A4#eteomrn~naln 3A Modlel 3.7.1 ' Three towers are used to determine the meteorological 'condidons at Donald C.

'CookNuclearPlanL' One of the towers is located at the Lake Michigan shoreline to determine the meteorological parameters associated with unmodified shoreline air.

The data is accumulated by microprocessors at the tower sites and normally transferred to the central computer every 15 minutes.

3.7.2 'The central computer uses a meteorological softwarepfogram to provide atmospheric dispersion and deposition parameters. The meteorological model used is based on guidance provided in Reg. Guide 1.111 for routine releases. All calculations use the Gaussian plume model.'

3.8 Reporting Requirements 3.8.1 ' Annual Radiological Environmental Operating Report (AREOR)

- a. Submit routine radiological environmental operating reports covering the operation of the units during the previous calendar year prior to May 1 of each year.

b. Include in the AREOR:

Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the reporting period.'

A comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plarit operation on the environment.

Information I PMP-6010-OSD-001 I Rev. 17a I Page 37 of 84

' OFF-SITE DOSE CALCULATION MANUAL The results of the land use censuses required by step 3.5.3, Annual Land Use Census.

If harmful'effects or evidence of irreversible damage are detected by the monitoring, provide in the report an analysis of the problem 'and a planned course of action to alleviate the problem.

Summarized and tabulated results of all radiological environmental samples taken during the reporting period. In the event that some results are not available for inclusion with the report, 'submit the report noting and explaining the reasons for the missing results.i Submit the missing'data as soon as possible in a supplementary report.

A summary description of the REMP including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used.

A map of all sample locations keyed to a table giving distances and directions from one reactor.

The results of participation in the Interlaboratory Comparison Program required by step 3.5.4, Interlaboratory Companrson Program.

3.8.2 Annual Radiological Effluent Release Report (ARERR)

a. Submit routine ARERR covering the operation of the unit during the previous

' 12 months of operation within 90 days afteiaJanuary I of each year.

b. Include-in the ARERR a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Reg. Guide l.21, 'Measuring,'Evaluating and Reporting in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," wvith data summarized on a quarterly basis following the format of Appendix B, thereof.

c. -Submit in the ARERR 90 days after January 1 of each year and include a

' quarterly summary of hourly meteorological data collected during the reporting period.

This summary maybe in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, ard precipitation (if measured) on magnetic tape, or in the form ofjoint frequency distributions of wind speed, wind direction and atmospheric stability.

. Include 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.

. Include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the reporting period. Include all assumptions used in making these assessments (that is, specific activity, exposure time and location) in these reports.

Information PMP-6010-OSD-0l 7 Rev. 17a Page 38 of 84 OFF-SITE DOSE CALCULATION MANUAL

. Use the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (is'determined by sampling frequency and measuremrent) for defermining the gaseous pathway doses.

Inoperable radiation monitor periods exceeding 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence.

d. Submit the ARERR [Ref 5.2.1w] 90 days after January 1 of each year and include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Reg. Guide 1.109,Rev.1.

e. Include in the ARERR the following information for each type of solid waste shipped off-site during the report period:

Volume (cubic meters),

Total curie quantity (specify whether determined by measurement or

-' estimate),

Principle radionuclides (specify whether deteriinied by measurement or estimate),

. Type of waste (example: spent resin, compacted dry waste, evaporator bottoms),

Type of container (example: LSA, Type A, Type B, Large Quantity),

-AND- .

. Solidification agent (example: cement).

f. Include in the ARERR unplanned release's of radioactive materials in gaseous and liquid effluent from the site to unrestricted areas on a quarterly basis.-

-g. Include in the ARERR any change to this procedure made during the reporting period.

3.9 10 CFR 50.75 (g) Implementation 3.9.1 Records of spills or other unusual occurrences involving the spread of contamination in and around the site. These records may be limited to instances when significant contamination remains after decontamination or when there is a reasonable likelihood that contaminants may have spread to inaccessible areas, as in the case of possible seepages.

3.9.2 These records shall include any known information or-identification of involved nuclides, quantities,' and concentrations.

I Information T PMIP-6010-OSD-001 I Rev. 17a l Page 39 of 84 l OFF-SITE DOSE CALCULATION MANUAL 3.9.3 This information is necessary to ensure all areas outside the radiological-restricted area are documented for surveying and reriediation during decommissioning. L There is a retention schedule file number where this information is filed in Nuclear Documents Management to ensure all required areas are listed to prevent their omission.

3.10 Reporting/Management Review 3.10.1 Incorporate any changes to this procedure in the ARERR.

3.10.2 Update this procedure when the Radiation Monitoring System, its instrunents, or the specifications of instruments are changed.

3.10.3 Review or revise this procedure as appropriate based on the results of the land use census and REMP. !

3.10.4 EB-luate any changes to this procedure for potential impact on other related Departmnent Procedures.

3.10.5 Review this procedure during the first quarter of each year and update it if necessary. Review Attachment 3.16, 10 YearAverage of 1989-1998 Data, and document using Attachment 3.17, Annual Evaluation of z/Q and D/Q Values For All Sectors.. The XIQ and D/Q values will be evaluated to ensure all data is within +/-3 standard deviations of the'10 year annual average data and documented by completing Attachment 3.17, Annual Evaluation of z/Q and D/Q Values For All Sectors, and filed in accordance with the retention schedule. '

4 FINAL CONDITIONS 4.1 None.

5 REFERENCES; 5.1 Use

References:

5.1.1 '"Inplementation of Programmatic Controls for Radiological Effluent Technical

'Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation-of Procedural Dctails'ofRETS to the Off-Site

.PDose Calculation Manual or to the Process Control Program (Generic Letter 89-01)", United States Nuclear Regulatory Cormmission, January 31, 1989 5.1.2 12-THP-6010.RPP.601, Preparation of the Annual Radioactive Effluent Release Report 5.1.3 12-THP-6010.RPP.639, Annual Radiological Environmental Operating

Report (AREOR) Preparation And Submittal 5.2 Writing

References:

5.2.1 Source

References:

a. 10CFR20,StandardsforProtectironiAgainstRadiation

b. 10 CFR 50, Domestic Licensing of Production and Utilization Facilities

c. PMI-6010, Radiation Protection Plan I

Information T PMP-6010-OSD-001 Rev. 17a l Page 40 of 84 OFF-SITE DOSE CALCULATION MANUAL

d. NUREG-0472 NUREG-0133

£ Regulatory Guide 1.109, non-listed parameters are taken from these data tables

g. Regulatory Guide 1.111

h. Regulatory Guidel.113 Final Safety Analysis Report (FSAR) 3.

Technical Specifications, Appendix A, Sections 6.8.1.e, 6.8.4.a, 6.8.4.1, 6.9.1.6, 6.9.1.7, and 6.14, Off-Site Dose Calculation Manual

k. Final Environmental Statement Donald. C. Cook Nuclear Plant, August 1973

.1. NUREGO0017 . - -- . ,

m. ODCM Sitpoints for Liquid Effluent Monitors (Bases), ENGR 107-04 8112.1 Environs Rad Monitor System

n. HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits

o. Watts - Bar Jones (WBJ) Document, R-86-C-001, The Primary Calibration of Eberlind Instrument Corporation SPING - 3/4 Low, Mid, and High Range Noble Qas Detectors

p. WBJ Document, R-86-C-003, The Primary Calibration of Eberline Instrument Corporation DAM-4 and Water Monitor;

q. 40 CFR 190, Environmental Radiation ProtectionStandaids for Nuclear Power Operations : .

r. NRC Commitment 6309 (N94083 dated 11/10/94)

s. NRC Commitment 1151

t. NRC Commitment 1217 U. NRC Commitment 3240 V. NRC Commitment 3850 W. NRC Commitment 4859 I8

x. NRC Commitment 6442 A. %Tnir r-: 3 7'e 19.U1A1UUUUVUL 0 IU0 Y.

-Z. DIT-B-00277-00, HVAC Systems Design Flows:

aa. Regulatory Guide 1.21 bb. Regulatory Guide 4.1 cc. 1-2-V3-02-Calc #4, Unit Vent Sample Flow rate for isokinetic particulates and Iodine sampling dd. H1PS N13.30-1996, Appendix A Rationalefor Methods of Determining Minimum Detectable Amount (MDA) and Minumum Testing Level (MDL II - ee. DIT-B-01971-00, Dose Factors for Radioactive Particulate Gaseous Effluents Associated with the Child by the Inhalation Pathway ff. DIT-B-01987-00, Ground Plane & Food Dose Factors Pi for Radioiodines and Radioactive Particulate Gaseous Effluents

Information l PMP-6010-OSDOO1 l Rev. 17a I Page 41 of 84 OFF-SITE DOSE CALCULATION MANUAL gg. NRC Commitment IO 10 5.2.2 General References

a. Cook Nuclear Plant Start-Up Flash Tank Flow Rate letter from D. L.

Boston dated January 21, 1997

b. Letter from B.P. Lauzau, Venting of Middle CVCS Hold-Up Tank Directly to Unit Vent, May 1, 1992

c. AEP Design Information Transmittal on Aux Building Ventilation Systems. .

d. PMP-4030.EIS.OOl, Event-Initiated Surveillance Testing

e. Environmental Position Paper, Fe Impact on Release Rates, approved 3/14/900 f Environmental Position Paper, Methodology Change from Sampling Secondary System Gaseous Effluents for Power Changes Exceeding 15%

within l hr.to Responding to Gaseous Alert Alaims, approved 4/4/00

g. CR 02150078, RRS-1000 efficiency curve usage, I: _

Information - PMP-6010-OSD-O01 Rev. 17a Page 42 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.1 ' Dose

' . Factors for Various Pathways Pages.

R; Dose Factors PATHWAY Nuclide Ground -.- Vegetable Meat Cow Milk -GoatMilk Inhalation H-3 O.OE+OO 4.OE+03 -3.3E+02 2.4E+03 -- 4.9E+03 1.3E+03 C-14 O.OE+00 3.5E+06 5.3E+05 3.2E+06 -3.2E+06 3.6E+04 Cr-51 5.4E+06 1.-E+07 - - 1.5E+06 -6.9E+06 - 8.3E+05 2.1E+04 Mn-54 1.6E+09, - 9.41E+08 - - 2.1E+07 2.9E+07 -. 3.5E+06 2.0E+06 Fe-59 3.2E+08 9.6E+08 1.7E+09 3.1E+08 - t4.OE+07 1.5E+06 Co-58 4.4E+08 - 6.0E+08 --2.9E+08 8.4E+07 ^1.OE+07. 1.3E+06 Co-60 2.5E+10 -3.2E+09 1.OE+09 2.7E+08 -- 3.2E+07 - 8.6E+06 Zn-65* 8.5E+08 -2.7E+09 9.5E+08 1.6E+10 !1.9E+09 1.2E+06 Sr-89 2.5E+04 3.5E+10 - - 3.8E+08 9.9E+09 2.1E+10 - 2.4E+06 Sr-90 O.OE+O0 '1.4E+12 - 9.6E+09 9.4E+10 - 2.0E+1 1.lE+08 Zr-95 2.9E+08 1.2E+09 -1.5E+09 9.3E+05 - .1E+05 2.7E+06 Sb-124 6.9E+08 -3.OE+09 - 4.4E+08 7.2E+08 -8.6E+07

-' 3.8E+06 I-131 1.OE+07 2.4E+10 - 2.5E+09 4.8E+1 1 5.8E+1 1.6E+07 1-133 1.5E+06 - 4.OE+08 *6.OE+01 4.4E+09 5.31E+09 3.8E+06 Cs-134 7.9E+09 2.5E+10 l.lE+09 5.OE+10 - 1.SE+1 1 - l.lE+06 Cs-136 1.7E+08 2.2E+08 4.2E+07 5.1E+09 -1.5E+10 1.9E+05 Cs-137 1.2E+10 2.5E+10 - - .OE+09 4.5E+10 1.4E+11 9.OE+05 Ba-140 2.3E+07 - 2.7E+08 5.2E+07 2.IE+08 -2.6E+07 2.0E+06 Cc-141 1.5E+07:- 53E+08 3.OE+07 8.3E+07 - :1.OE+07 6.1E+05 Ce-144 7.9E+07' 13E+10 3.6E+08 7.3E+08 -8.7E+07 113E+07 Units for atl excepti balationpathway arcm1 mr sec I yr pCi inbalatio'npathway units are mrmS /yr pCi.

Uap Values to be Used For the Maximum Exposed Individual Pathway Infant Child Teen Adult-Fruits, vegetables and grain (kg/yr) 520 630' 520 Leafy vegetables'(kg/yr) - . 26 , 42 64 Milk(IJyr) 330 330 '400 310 Meatandpoultry(kgtyr) - 41 65 110 Fish (kg/yr) - 6.9 '16 21 Drinling water (IJyr) 330 510 510 730 Shoreline recreation (hr/yr) - 14 67 12 Inhalation (m 3 lyr) . 1400 3700 8000 8000 Table E-5 ofReg. Guide 1.109.

Information PAIP-6010-OSD-001 Rev.17a Page 43 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.1 Dose Factors for Various Pathways Pages 42-45 I BipFactors for Aquatic Foods pCil /kg pCi Element Fish Invertebrate H 9.OE-1 9.OE-1

-C 4.6E3 9.1E3 Na. 1.02- 2.0E2

_P 1.0E5 2.0E4 Cr- 2.OE2 2.0E3-Mn . 4.0E2 9.0E4 Fe - 1.02- 3.2E31 Co 5.0E1 . 2.0E2-Ni - 1.022 - 1.0E2 Cu 5.0E1 *. 4.0E2 Zn 2.0E3. 1.0E4 Br 4.2E2 3.3E2 Rb - 2.0E3 1.0E3

-j Sr . 3.0E1 1.02-Y - 2.5E1 1.0L3 I zr 3.3EO 6.7EO Nb 3.0E4 1.0E2 Mo 1.0E1 1.021.

Tc 1.5E1 5.0EO Ru* 1.0E1- 3.0E2 Rh 1.OE1 3.0E2 Te 4.0E2 6.1E3 I . 1.5E1 5.OEO Cs 2.0E3 1.0W3 Ba 4.OEO 2.0E2 La 2.5E1 . 1.0L3 Ce 1.0EO 1.0E3 2.5E1 1.023 Nd 2.5E1 1.03 W 1.2E3 1.0E1 Np 1.OE1 4.0E2 Tablk A-I of Reg. Guide 1.109.

Information PMP-6010-OSD-001 l Rev. 17a Page 44 of 84 OFF-SITE DOSE CALCULATION MANUAL Pags

'Attachment 3.1 Dose Factors for Various Pathways ages:

42 -45 DIpj External Dose Factors for Standing on Contamin'ated Ground mrem mlI hr pCi Radionuclide Total Body Skin H-3 -* 0' C-14 0 0!

Na-24 2.5E-8 2.9E-8 P-32 0 0.

Cr-51 2.2E-1O 2.6E-10 Mn-54 5.8E-9 6.8E-9 Mn-56 ' .lE-8 13E'8 Fe-55 0 0:

Fe-59 8.0E-9 9.4E-9 CO-58 7.0E-9 8.2E-9 Co-60 1.7E-8 2.OE-8 Ni-63 O' ' '

Ni-65 , 3.7E-9 4.3E-9 Cu-64 1.5E-9 1.7E-9 Zn-65 4.0E-9 4.6E-9 Zn-69 .. 0

,0.

Br-83 .6.4E-1 1 9.3E-1 1 Br-84 1.2E-8 ' 1.4E&8

-Br-85 0 0-Rb-86 6.3E-10 7.2E-10 Rb-88 ' 3.5E-9 ' 4.OE-9 Rb-89 l.5E-8 1.8E-8 Sr-89 '5.6E-13 6.5E-13 Sr-91 7.1E-9 83E-9 Sr-92 9.0E-9 1.0E-8 Y-90 2.2E-12 2.6E-12 Y-91m 3.8E-9 4.4E-9 Y-91 2.4E-11 2.7E-1 I Y-92 1.6E-9 1.9E-9 Y-93 '5.7E-10 7.8E-10 Zr-95 5.OE-9 5.8B-'9 Zr-97 5.5E-9 6.4E-9 Nb-95 5.1E-9 6.0E-9 Mo-99 1.9E-9 2.2E-9 Tc-99m 9.6E-1O 1.lE-9 Tc-101 2.7E-9 3.0E-9 Ru-103 3.6E-9 4.2E-9 Ru-105 4.5E-9 5.lE-9 Ru-106 1.5E-9 1.8E-9 Ag-l1Om 1.8E-8 2.1E-8 Te-125m 3.5E-11 4.8E-1 I Te-127m 1.1E-12 1.3E-12

Information PMP-6010-OSD-001 Rev. 17a Page 45 of 84 OFF-SITE DOSE CALCULATION AMANUAL .1 Dose Factors for Various Pathways 4P2ages5 42-4 Radionuclide Total Body Skin Te-127 1.OE-1l l.lE-ll Te-129m 7.7E-10 9.0E-10 Te-129 7.1E-10 8.4E-10 Te-131m 8.4E-9 9.9E-9 Te-131 2.2E-9 2.6E-6 Te-132 1.7E-9 2.0E-9 I-130 1.4E-8 1.7E-8 I-131 2.8E-9 3.4E-9 I-132 1.7E-8 2.0E-8 I-133 *3.7E-9 4.5E-9 I-134 1.6E-8 1.9E-8 I-135 1.2E-8 1.4E-8 Cs-134 1.2E-8 1.4E-8 Cs-136 1.5E-8 1.7E-8 Cs-137 4.2E-9 4.9E-9 Cs-138 2.1E-8 2.4E-8 Ba-139 2.4E-9 2.7E-9.

Ba-140 2.1E-9. 2.4E&9 J Ba-141 4.3E-9 4.9E-9 Ba-142 7.9E-9 *9.0E-9 La-140 1.5E-8 1.7E-8 La-142 1.5E-8 1.8E-8 Ce-141 5.5E-10 6.2E-10 Ce-143 2.2E-9 2.5E-9 Ce-144 3.2E-10 3.7E-10 Pr-143 0 0_ _

Pr-144 2.0E-10 2.3E-10 Nd-147 1.OE-9 1.2E-9 W-187 3.1E-9 3.6E-9 Np-239 9.5E-10 1.1E-9 Tablc E-6 ofReg. Guide 1.109.

Information PMP-6010-OSD-OO1 -Rev. 17a Page 46 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.2

. .Pages

Radioactive Liquid Effluent Monitoring Instruments 1 46-

.:4 -4: -

Instrument Minimum Applicability Action Channels

- - . Operable' ;

1. Gross Radioactivity Monitors Providing Automatic Release Termiination

a. Liquid Radwaste (1)# At times of release 1 Effluent Line (R.S-1001) -.

b. Steam Generator (1)# At times ofrelease**- 2 Blowdown Line (R-19, DRS 3/4100 +) . _ _

c. Steam Generator . .(l)# At times ofrelease *2 Blowdown Treatment Effluent (R-24, DRS 3/4200 +) :- . _;_.

2. Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Service Water (l)per At alltimes 3 System Effluent Line(R-20, train #

R-28, WRA 3/4500 and WRA 3/4600 +) .

3. Continuous Composite . .

SamplerFlow Monitor

a. TurbineBuildingSump. (1) Atalltimes 3-Effluent Line * *_._-_.._._._._._

4.. Flow Rate Measurement Devices

a. Liquid Radwaste Line (1) At times of release 4 (R FI-285) ._._._.

b. Discharge Pipes* . (1) At allhtimes NA

.c. Steam GeneratorBlowdown (1) At times ofrclease 4 Treatment Effluent (DIFI-352) * ._ _ _

Pump curves and valve settings may be utilized to estimate flow; in such cases, Action Statement 4 is not applicable. This is primarily in reference to start up flash tank flow.'

OPERABIL1TY of RRS-l 001 includes OPERABILITY of sample flow switch RFS-1i010, which is an attendant instrument as defined by Technical Specification 1.6. This iter is also applicable for all Eberline liquid monitors (and their respective fow switches) listed here.

Since these monitors can be used for either batch or continuous release the appropriate action statement of I or2 should apply (that is, Action I if a steam generator drain is being performed in lieu of Action 2).

+ Westinghouse (R)radiation monitors are being replaced by Ebaline (DRS & WRA) midnitors. Either monitor can fulfill the

. operabilityrequirement.

a IF an RMS monitor is inoperable solely as the result of the loss of its control room alarm annutciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:

1. Collect grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2. Collect local monitor readings at a frequency equal to or greater than (more frequently tham) the action frequency.

Information PMIP-6010-OSD-OO1 Rev. 17a Page 47 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments Pages:

I 46-47

IF the RMS monitor is inoperable for reasons other than the loss of control roorii annunciation, THEN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

-TABLE NOTATION Action I With the nuiber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Sfp 3.2.3 a and;

2. At least two technically qualified members of the Facility Staff independently verify the discharge valving. Otherwise, suspend release of radioactive effluents via this pathway.

Action 2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30. days provided grab samples ame analyzed for gross radioactivity (beta or gamma) at a limit ofdetection ofat least 10-7 gCi/gram=

1. At least once per shift when the specific activity of the secondary coolant is >0.01 ,uCi/gram DOSE EQUIVALENT 1-131.

2. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is S 0.01 jiCi/gram DOSE EQUIVALENT 1-131. .

Action 3 With the number of channels OPERABLE less than required by the'Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per shift, grab samples are collected and analyzed for gross radioactivity (beta or-gamma) at a lower limit of detection of at least 10-7 pCilml. To flurther clarify this for ESW monitors the following is provided:

IF the Westinghouse monitor (R-20 andlor R-28) is fulfilling the applicability requirement, THEN grab samples are only needed if the Containment Spray Heat Exchanger is in'service since the Westinghouse ESW monitors are only used for post LOCA leak detection and have no' auto trip function associated with therm £ OR IF the Eberline monitor (WRA-3/4500 andlor WRA-3/4600) is fulfilling the applicability requirement, THEN grab sampling is required whenever the monitor is inoperable and the applicable train ofESW is in service since this monitor is located in the system'effluent.

Action 4 'With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Conqpeatory actions are governed by PMP4030.EIS.001, Event-Initiated Surveillance Testing

Information I PMP-6010-OSD-001 l Rev. 17a Page 48 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.3 l .- Radioactive Liquid Effluent Monitoring . l Pages:

lI Lnstrumentation Surv'eillance Requirements' I 48 -49 Instrument CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION FUNCTIONAL

_ _ _ _ _ ____ .T EST

1. Gross Radioactivity Monitors Providing Automatic Release Termination

a. Liquid Radwaste DP . R(3) . Q(5)

Effluent Line -

(RRS-1001) ._-_ _ _ _ _

b: Steam Generator D* M R(3): Q(1)

Blowdown Effluent Line . i .

c. Steam Generator D*. M R(3) Q(1)

Blowdo'wn Treatment Effluent Line . . -. ,_..-. . .

2. Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Service Water . D M R(3) Q(2)

.System Effluent I Line .

1. ,_.._

3. Continuous Composite Samplers - ._. _ .,_ ....

a. Turbine Building. D*- N/A N/A. N/A Surnp Effluent Line. . ........... .. .

4. Flow Rate Measurement Devices _..______,...,

a. Liquid Radwaste D(4)* N/A R Q Effluent

b. Steam Generator D(4)* N/A N/A. N/A Blowdown Treatment Line i

I

During releascs via this pathway

Information PMP-6010-OSD-001 Rev. 17a Page 49 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment33. Radioactive Liquid Instrumentation EffluentRequirements Surveillance Monitoring e Pages:

48 - 49 TABLE NOTATION

1. Demonstrate witi the CHANNEL FUNCTIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarmntriip setpoint

2. Circuit failure.*

3. Instrument indicates a downscale fihlure.*

4. Instrument control not set in operating aode.

5. Loss of sample flow. #

2. Demonstrate with the CHANNEL FUNCTIONAL TEST that control room alaim annunciation occurs if any of the following conditions exists:

1.Instrument indicates measured levels above the alarm setpoinLt

2. Circuit failure.

3. Instment indicates a downscale failure.

4. Instrument controls not set in operating mode.

5. Loss of sampleflow. # *

3. Perform the initial CHANNEL CALBRATION using one or more sources with traceability back to the National Institute of Standards and Technology (NIST). These sources pcrmit calibrating the system over its ntended range of enegy and measurement range. For subsequent CHANNEL CALIBRAT1ON, sources that have been related to the initial calibraiion'a be used.. ;

4. Verify indication of flow during periods of release with the CHANNEL CHECK. Perform the CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic or batch releases are made.

5. Demonstrate with the CHANNEL FUNCTIONAL TEST that automatic isolation of this pathway and control mom alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure*-

3. Instnruent indicates a downscale failure

4. Instrument control not set in operating mode.*

5. Loss of sample flow.

Instrument indicates, but does not provide for automatic isolation

- Instrument indicates, but does not necessarily cause automatic isolation. No credit is taken for the automatic isolation on such occurrences.

ft Applicable only to Eberline sample flow instrumentation Operations currently performs the routine channe checks and source checks. Maintenance and Radiahon Protection perform channel calibrations and channel functional tests. Cheristry perfonns the channel check on the continuous composite sampler.

These responsibilities are subject to change without revision to this document.

A

Information PMP-6010-OSD-001 Rev. 17a Page 50 of 84 OFF-SITE DOSE CALCULATION MANUAL]

Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:

50-5 Instrument (Instrument -) Operable' l linimum Action I Channels

_ _ l Action

1. CondcnserEvacuation System _ - _.

a. Noble Gas Activity , 66(1)

Monitor (SRA-1 905/2905)

b. FlowRateMonitor(SFR401, -(1) I1 5 112-MR-054 and/or SRA- 1910/2910) OR .

(SFR402 and 1/2.MR-054) - . _

2. Unit Vent. Auxiliary Building Ventilation System _

a. Noble6asActivity (1) 6 Monitor (VRS-150512S05) ._,

b. Iodine Sampler (1)

Cartridge forVRA-1503/2503

c. Particulate Sampler Filter (1) 8 forVRA-15O1/2501 '_'_._. _:

d. EffluentSystemFlowRate - ()5 Measuring Device (VFR-3 15, MR-054 and/or t VFR-151012510) . _ .

-e. SamplerFlowRate (1) . 5 Measring Device (VFS-1521/2521) :

3. Containment Purge and Containment Pressure

. Relief (Vent) . - _.,

a. Containment Noble Gas ActivityMonitor ERS-13/1405 (ERS-2312405)

(1) 1 7

b. Containment Particulate Sampler Filter

- ERS-13/1401 (ERS-2312401)

(1) t .

10.

4. Waste Gas Holdup System and CVCS HUr _

a. Noble Gas Activity (1) 1 9 Alarm and Termination of Waste Gas Releases (VRS-1505/2505)

5. Gland Seal Exhaust

a. . Noble Gas Activity Monitor (SRA-1805/2805)

b. Flow Rate Monitor (SFR-201, MR-054 or SFR-1810/2810)

At all times I I ** -* During releases via this pathway

e s Information lPMiP-6010-OSD-OO1 Rev. 17a Page 51 of 84 OFF-SITE DOSE CALCULATION MANUAL .4 Radioactive Gaseous Effluent Monitoring Instrumentation ] P o 52 TABLE NOTATIONS

1. IF an RMS monitor is inoperable solely as the result of the loss of it's control room alarm annunciation, TIEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement: -.

1. Take grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2. Take local monitor readings at a frequency equal to or greater than (more frequently than) the action frequency.

IF the RMS monitor is inoperable for reasons other than the loss of control room annunciation, THEN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

2. Consider releases as occurring "via this pathway" under the following conditions:

e *The Containment Purge System is in operation and Containment integrity is established/required,

-OR-

The Containment Purge System is in operation and is being used as the vent path for the venting of contaminated systems within the containment building prior to completing both' degas and depressurization of the RCS.

IF neither of the above are applicable, THEN the containment purge system is acting as a ventilation system and.

is covered by Item 2 of this Attachment.

-OR-

A Containment Pressure Relief (CPR) is being performed.

3. For purge (including pressure relief) purposes only. See Technical Specification table 3.3-6 for additional _

information.

4. For waste gas releases only, see Item 2 (Unit Vent, Auxiliary Buiding Venlilation System) for additional requirements.

ACTIONS S. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . After 30 days, IF the channels are not OPERABEI.r THEN continue releases with estimation of die flow rate once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

6. With the nurriber of channels OPERABLE less required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

Information PMP-6010-OSD-001 Rev. 17a Paue 52 of 84 OFF-SITE DOSE CALCULATION MANAL -

Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation... Pages:

50-52

.O5

7. With the number of channels OPERABLE less than required by-the Minimnum Channels OPERABLE requirements, immediately suspend PURGING or VENTING (CPR) of radioactivc effluents via this pathway.

S. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases via the affected pathway may continue for up to 30 days provided samples required for weekly analysis are continuously collected wvith auxiliary sampling equipment as required in Attachment 3.7, Radioactive Gaseous Waste Sampling and Analysis

Program. After 30 days, IF the channels are not OPERABLE, THEN continue releases i.rith sample collection by auliary sampling equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

Sampling evolutions are not an interruption of a continuous release or sampling period.

9. With the ninber of channels OPERABLE less than iquircd by the Minimum Channls OPERABLE requirement, thc conteats of the t (s) mayberelasedto the environmentforup to 14 daysprovided thatpriorto Initiating the rlease:

a At least two indeperndct samples of the tank's contents are analyzed and,

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineups; otherwise, suspend release of radioactive effluents via this pathway.

10. See Technical Specification 3A.6.1.

CoMPensatory actions arego~verned by PMP.4030.ES.001, Event-lnitiated Surveilance Testfing.

!I-Information PMP-6010-OSD-001 l Re. 17a Page 53 of 84 OFF-SITE DOSE CALCULATION MLANUAL Radioactive Gaseous Effluent Monitoring! Pages:

Instrumentation Surveillance Requirements 53 - 54 Instrument CHANNEL SOURCE - CHANNEL CHANNEL CHECK CHECK CALIBRATION FUNCTIONAL

._ TEST

1. Condenser Evacuation Alarm Only System - - -_ 5

a. Noble Gas ActivityMonitor MD*O R(2) Q(l)

(SRA-1905/2905) ____________ . ___________ ._ _ _ _

b. SystemEffiuentFlowRate D* NA R (SFR-401, SFR-402, MR-054, SRA-19I10910) _ .

2. Auxiliary Building Unit Alarm Only Ventilation Systemr :, * ;

a. Noble Gas Activity Monitor - D M R(2) Q(l)

(VRS-1505t2505) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

b. Iodine Sampler Wo NA NA NA (For VRA-1503/203). ' . ,;

c. Particulate Sampler W NA NA NA (ForVRA-1501/2501) I

d. SystemEffluentFlowRate D NA R, Q Measurement Device (VFR-3 15, MR-054, VRS-1510/2510)

e. Sampler Flow Rate Measuring D4 N/A R'Q

.Device (VFS-152112521) . . . ._.

3. Containment Purge System and Alarm and Trip Containment Pressure Relief

a. Containment Noble Gas SO* P R(2) Q Activity Monitor (ERS-13/1405 and ERS-23/2405) _

b. Containment Particulate S** NA R Q Sampler (ERS-13/1401 and ERS-23/2401) . i .

4. Waste Gas Holdup System Alarn and Trip Including CVCS HUT _

a. Noble Gas Activity Monitor P** P R(2) Q(3)

Providing Alarm and Termination . .

(VRS-1505/2505) .:

5. Gland Seal Exhaust

.a. Noble Gas Activity (SRA-1805/2805)

b. SystemEffluentFlow Rate (SFR-201, MR-054, SRA-1810/2810)

At all times

- During releases via this pathway

Information T PMP-6010-OSD-001 Rev. 17a Page 54 of 84 OFF-SITE DOSE CALCULATION MANUAL ttac ment 3.5 Radioactive Gaseous Effluent Monitoring; Pages:

Attchmnt .5Instrumentation Surv'ei11ance Re'quirementsl I 53 -54 TABLE NOTATIONS

1. Demonstrate with the CHANNEL FUNCTIONAL TEST that control room alanzn annunciation occurs if any of the following conditions exists:

1.- Instrmment indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure. ;

4. Instrument controls not set in operate mode.

2. Perform the initial CHANNEL CALIBRATION using one or more sources with traceability-back to the NIST.

These sources permit calibrating the system over its intended range of energi and measurement range. For

. .subsequent CHANNEL CALIBRATION, sources that have bcen related to the initial calibration may be used.

3. Demonstrate with the CHANNEL FUNCTIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates mi'easured levels above the alarm/trip setpoint

2. Circuit failure.'*

3. Instrument indicates a downscale failure.'

4. . Instrument controls not set in operate mode.*

Instrument indicates, but does not provide automatic isolation. -

Operations currently performs the routine channel checks, and source checks. Maintenance and Radiation Protection perforn charnel calibrations and charmen finctional tests. These rcsponsibilities are subject to change without revision to this document

5 N

i:

Information PMP-6010-OSD-001 Rev. 17a Page 55 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.6 lRadioactive Liquid Waste Sampling and Analysis Program T P~ages:

r er 5.2.1si - _-_-_-_-_-_._. -. _

LIQUID SAMPLING MINIMUM TYPE OF LOWER RELEASE FREQUENCY ANALYSIS ACTIVITY LIMIT OF TYPE FREQUENCY ANALYSIS DETECTION (LLD)

.___. ._ _._ (C nlm l)

A. Batch Waste P P PrincipalGamma 5x10-7 Release Tanks' Each Batch Each Batch Emitters' 1-131 1xlO p P Dissolved and h c E B Entrained Gases Each Batch .'Each Batch (Gamma IX10-s

._ _. Emitters_

P M1 H-3 lxlO 5

.Each Batch CoWnpositeb Gross Alpha lxlO 7

. Sr-89, Sr-90 5x1O-1 Each Batch Compositeb .

. ._._._._._Fe-55 lxi1 5 B. Plant W PrincipalGamma, Continuous Daily Compositeb Emitters 5x10 7 .

Releases* d

-131 1x10l Ga Sp Dissolved and Grab Sample Entrained Gases 10-5 (Gamma

. Emitters)'

Daily Compositeb __________

Gross Alpha 1x1O-7 Q Sr-89, Sr-90 5xlO Daily Compositeb ._:

Fe-55 1x1O Durizig releases via this pathway Ij

Information PMP-6010-OSD-001 Rev. 17a l Page-56of84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis programi P5ges:

TABLE NOTATION

a. The lower limit ofdetection (LLD) is defined in Table Notation A.of Attachment 32o, Maximum Values for Lower Limnits of DetectionsAB - REMP.

b. '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.

c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, isolate, recirculate or sparge each batch to ensure thorough mixing.

d. A continuous release is the discharge of liquid ofianon-discrete volunme eg. from a volume of system that has an input flow during the continuous release.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. his list does not mean that only these nuclides are to be detected and reported. Identify and report other peaks, which are measurable and identifiable together with the above nuclides.

II Information PMIP-6010-OSD-OO1 Rev. 17a Page 57 of 84 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Waste Sampling and Pages:

Analysis Program . 57 - 58 Gaseous Release Type Frequency Minimum Tyjbe of Lower Limit Analysis Activity of Detection

- Frequency Anilysis (plCi/nl)'

a. Waste Gas Storage Tanks P Principal Gamma and CVCS HUgs Each Tank EachTank Emitters d 1x14 Grab Sample

. .H-3 ; lx104

b. Containment Purge P P Principal Gamma Each Purge Each Purge Emitters d IX Grab Sample CPR(vent)** Twiceper Twice per Month Month ._ ._ .

. H-3 ;x10 4

c. Condenser Evacuation WorAl Al Principal Gamma Systein Grab Sample Particulatr Sample Emittersd Ix 10 Gland Seal Exhaust' Al H-3 _1,

.W Principle Gamima I x 104 Noble Gas Emitters d

M 1-131 Iodine Adsorbing Ix 10 12 Media Continuous W Noble Gases Noble Gas Monitor 1 x 104

d. Auxiliary BuildingUnit Continuous' Wb 1-131 Vent Iodine Adsorbing 1x 104'

'Media Continuous *W b Principal Gamma Particulate Sample Emitters I x 10' Continuouso M Gross Alpha Composite Particulate I x 1041 Sample w W H-3 Grab Sa'mple H-3 Sample I x 104 4

W Principle Gamma Ix IO Noble Gas Emitters d Continuous' Q Sr-89, Sr-90 Composite Particulate I x 10T" Sample

- Continuous' Noble Gas Monitor Noble Gases 1x 104

e. Incinerated Oil P p Principal Gamma EachBatcht Each Batchf Emittersd 5xl1

Durng releases via this pathway "Only a twice per month sampling program for containment noble gases and H. is required

Information PMP-6010-OSD-OO1 l Rev. 17a F Page 58 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.7 Radioactive Gaseous Waste Sampling and - Pages:

I Analysis Program ; I 57 - 58.

TABLE NOTATION

a. lhe lower lirit ofdetection (ILD) is defined in Table Notation A. of Attachment 3.20, Maxi'MU Values for Lower Limits of DetectionsA,B - REMP.

b. Change samples at least once per 7 days and complete analyses within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months afeichanging. Perform analyses at least once per 24 bours for 7 days following each shutdown, startup or THERMAL POWER change> 15% perhour ofRATED THERMAL POWER. WHEN samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed. THEN the corresponding LLDs may be increased by a factor of

10. This requiremeent does not apply IF (l) analysis shows that DOSEQ 11 31 concentration in the RCS has not increased more than a factor of 3; and (2) the noble gas monitor shows that efiluent activityhas not increased more than a factor of 3. ptee sziyj

c. Know the ratio of the sample flow rate to the sampled strearn flow rate for'the time period covered by each dose or dose rate calculation made in accordance with steps 32.4a, 3.2Ab, and 3.2Ac of this document Sampling evolutions are not an Interruption of a continuous release or sampling period.

d. The principal ganrmn emitters for which the LLD specification applies exclusively are the following radionuclides Kr-87, Kr-88B Xe-l33, Xe-133M, Xc-135 and Xe-138 for gaseous emissions and Mn-54, Fe-S9, Co-S8, Co-60, Zn65,Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides tre to be detected and reported.

Identify and report other peaks, which are measuable and identifiable, together viththe abovcnuclides.

e. Releases from incinerated ol are discharged through the Auxiliary Boiler Systen; Account for releases based on pre-release grab sample data.

f Collect samples f waste oil to be incinerated from the container in which 'he waste oil is stored (examnple: waste oil storage taiks,

, 55 gal. drmis) prior to transfer to the AuxiliaryBoiler SystemL Ensure samples are representative of cortainer contcnts.

g. Obtain and analyze a gas marinelli grab sampie weeldy for noble gases efiluent quantfication.

h. Take tritium grab sasples at least once per 24 hou'rs when the refueling cavity is flooded.

L Grab sampling of the Gland Seal Exhaust pathway need not be performed if the RMS, lowr ange channel (SRA-1 805f280S) readings are less than IE-6 pC/cc. Attach the RMS daily averages in lieu of sampling. This is based on opcrating 'xperience indicating no activity is deected in the Gland Seal Exhaust below this value. Compensatory szpling for out of service monitor is still required in the event 180512805 is inoperable.

, . . w.

Information PMP-6010-OSD-001 Rev. 17a Page 59 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.8 Multiple Release Point p Factors for Release e Points Page:

59 Liquid Factors Monitor Description Monitor Number MRP #

U I SG Blowdown IR19124, DRS 3100/43200* 0.35 U 2 SG Blowdoavn 2R19/24, DRS 410014200* 0.35 U I & 2 Liquid-Waste Discharge RRS-1000 0.30 Gaseous Factors Monitor Description MonitorNumber Flow Rate (cfin) 'MR #

Unit I Unit Vent VRS-1500 186,600 0.54 Gland Seal Vent SRA-1800 1,260 . 0.00363 Steam let Air Ejector SRA-1900 . 3,600D(b) 0.01 Start Up FT Vent 1,536 0.004 Total 192,996 Unit2 UnitVent VRS-2500 143,400 0.41 Gland Seal Vent SRA-2800 5,508 (a) 0.02 Steam Jet Air Ejector SRA-2900 3,6000(b) 0.01 StartUpFI Vent 1,536.. 0.004 Total 154,044 .'

EitherR-19, 24,DRS 314100 or 3/4200 can be used for blowdown nmonitoring as the Eberline mornitors (DRS) are replacing the Westinghouse (E)monitors.

Nominal Values a Two rtlease points of 2,754 cfmn each are totaled for this value.

b Ihis is the total design m aximum of the Start Up Air Ejectors. This is a conservative value for unit 1.

I Information l PMP-6010-OSD-OO1 - I-Rev. 17a l Pa e 60 bf 84 OFF-SITE DOSE CALCULATION MANUAL Attaclunent 3.9 Liquid Effluent Release Systems l Page

.60 6

ik Information PMP-6010-OSD-001 Rev. 17i Page 61 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment3.10 Attahmet Plant Pt 3.0 Liquid Effluent Parameters I Page:

61 J

SYSTEM COMPONENTS CAPACITY FLOW RATE

. TANKS PUMPS (EACH) (EACII)*

I Waste Disposal System I

+ Chemical Drain Tank 1 1 600 GAL. 20 GPM

+ Laundry & Hot Shower Tanks . 2 I 600.GAL- 20 GPM

+Monitor Tanks 4 2 21,600 GAL. 150 GPM

+ Waste Holdup Tanks 2 25,000 GAL.

+ Waste Evaporators 3 _ _ . 30 GPM

+ Waste Evaporator Condensate 2 2 6,450 GAL 150 GPM T anks_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

II Steam Generator Blowdown and Blowdown Treatment.

Systems

+ Start-up Flash Tank (Vented)9

+ Nornal Flash Tank (Not Vented) -

I 1 j 1,800 GAL.

525 GAL. .

580 GPM.

100 GPM

+ Blowdown Treatment System 1 0 G 60 GPM HI Essential Service Water System . i :

. + WaterPumps 4 10,000 GPM

+ Containment Spray Heat 4 3,300 GPM Exchanger Outlet . _

IV Circulating Water Pumps Unit41 3. . 230,000 GPM Unit 2 4 . . 230,000 GPM Nominal Values The 580 gpm value is calculated from the Estimatcd Steam Generator Blowdown Flow vs. DRV Valve Position letter prepared by M. J. OfKeefc, dated 9/27/93. This is 830 gpm tirmcs the 70% that remains as liquid while the other 30% flashes to steam and exhausts out the flash tank vent i

Information PMP-6010-OSD-001 Rev. 17a Page 62 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.11 Volumetric Detection Efficiencies for Principle Gamma Page:

me , Emitting Radionuclides for Eberline Liquid Monitors 62 This includes the following monitors: RRS-1000, DRS 3100, DRS 3200,'DRS 4100, DRS 4200, WRA 3500, WRA 3600, WRA 4500 and WRA 4600. [Ref. 5.2.1p]

NUCLIDE EFICIENCY 1-131 3.78 E7 Cs-137 3.00 E7 Cs-134 7.93 E7 Co-60 5.75 E7 Co-5B 4.58 E7 Cr-Sl 3.60E6 Mn-54 3.30 E7 Zn-65 1.5SE7 :

Ag-IIOM 9.93 E7 Ba-133 4.85 E7 Ba-140 1.92 E7 Cd-109 9.58 E5 Ce-139 3.28 E7 Ce-141 1.92 E8 Cc-144 4.83 E6 Co-57 3.80E7 Cs-136 1.07 E8 Fe-59 .2.83 E7 i Sb-124 5.93 E7 1-133 3.40 E7 1-134 -7.23 E7 1-135 3.95 E7 Mo-99 8.68 E6 Na-24 4.45 E7 Nb-95 3.28 E7 Nb-97 3.50 E7 Rb-89 5.00 E7 Ru-103 3.48 E7

.Ru-106 1.23 E7 i Sb-122 2.5S E7 i

I Sb-125 3.15 E7 Sn-1 13 7.33 ES Sr-85 3.70 E7 N1 Sr-899 2.88 E3 Sr-92 3.67 E7 Tc-99M 3.60 E7 Y-88 525 E7 Zr-95 . 338 E7 Zr-97 3.10 E7l Kr-85 * *156 E5 Kr-85M 353 E7 Kr-88 4.10 E7 Xe-131M 8.15 E5 Xe-133 7.78 E6 Xe-133M 5.75 E6 Xe-135 3.83 E7

Information PMP-6010-OSD-001 l ev. 1a Page 63 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.12 l Counting Efficiency Curves for R-19, and R-24 l Pages-Couting Efficiency Curve for R1-19 Effiiency FactDr - 4.2 E6 cprn:iCir (B&W audc ral dc1 Wm dziradurg s i ma-137)

%i la U

.0.

U 1.00E+OO 9 9 9 8 w Uw w 0* 9 C9 MIaCurDbIS/Ml I l I l. .1 L-. ' l L - L-. L- L.. L L.. L L 1 . I- L-

V77- F7 f . r7 E

Information PMP-6010-OSD-001 Rev. 17a Page 64 of 84 OFF-SITE DOSE CALCULATION MANUAL Pages:

63-64 .12 Counting Efficiency Curves for R-19, and R-24 Cou.ting Effideny Curve for R-24.

Effidcery Factr - 75E6 InbAd

. )

1.00E+07 1.OOE4O6 1.D0E+05

,1.00E405 C

0 ' .WOE+04

-o

£1 1.00E+03

.0.

U l.OOE+02 1.DOE+01 1.00E400 Sn C.

9 C> 9 9 LLI 0 0 To 0 0

. .. II. V

-. - : mlcrocutolslml .- :

. T , ,

Information I PMP-6010-OSD-001 . I Rev. 17a I Page 65 of 84 OFF-SITE DOSE CALCULATION MANUAL 3CPage:

A~cmn.3Counting Efficiency Curve for R-20, and R-28 65

/ Countin5Efficaenq Curve for R-20 and n-28 Efficiency. Factor - 4.3 E6 cpmniCiftl (sud c m&zIc3I dasa aLgdpt*opnlonkswi&Co-58 1.00E506 1.00E*05 t0 oo

.a1

'a A 1.OOE03 5

1.00E*02 1.00E+01 l.U 9U C?

9 9 8 0

q 4 o. o w 0*, w mlcrocurlsiml I- - L . _ L. l: I -.. - .. I ..( L .... t I. -.. l . L. . l - I ., . .. l 1.- L. I,.- - - C-..

Information PMP-6010-OSD-001 T- Rev. 17a T Page 66 of 84 OFF-SITE DOSE CALCULATION MLANAL Attachment 3.14 Gaseous Effluent Release Systems Page:

66 ELEASE I I POINTSI

-! , , _- II Ib**'

I

. C~ A"- - W. ,.

7 ~_- _'_

h b*.-* -

E: "I3. ,2 , i I .1 , , ,, ,-

IBra

'1-Codi byM is ~~

.. rni _ ' ' :

'-4 Information PMP-6010-OSV-001 Rev. 17a Page 67 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.15 Plant Gaseous Effluent Parameters Page:

n .u 67 SYSTEM UNIT EXHAUST CAPACITY FLOW RATE (CFM) __

PLANTAUXILIARYBUILDING 1 186,600 max. -

UNIT VENT 2 143,400 max' WASTE GAS DECAY TANKS (8)AND 1 125 '4082 FT' 100 psig CHEMICAL & VOLUME CONTROL 28,741 ft3 max SYSTEM HOLD UP TANKS (3) ., @ 8#, 0 level

+ AUXILIARY BUILDING 1 72,660 EXHAUST 2 59,400

+ ENG. SAFETY FEATURES 1&2 50,000 VENT __.

+ FUEL HANDLINGAREA VENT. 1 30,000 -4 SYSTEM '_.___

CONTAINMENT PURGE SYSTEM 1 &2 .32,000 .; _._. _ .

CONTAINMENT PRESSURE 1&2 1,000 RELIEF SYSTEM -- ;

INSTRUMENT ROOM PURGE 1&2 1,000 -j SYSTEM . . .

II CONDENSER AIR EJECTOR 2 Release Points __j SYSTEM One for Each Unit NORMALSTEAMJETAIR 1&2 230 EJECTORS START UP STEAM JET AIR 1& 2 3,600 EJECTORS - * .

III TURBINE SEALS SYSTEM 1 1,260 . _.

2 5,508 2 Release Points

. forUnit 2 IV STARTUPFLASHTANKVENT 1 1,536

.2 1,536.

+ Designates total flow for all fans.

i

Information l PMP-6010-OSD-001 Rev. 17a Page 68 of 84 OFF-SITE DOSE CALCULATION MANUAL Attaclhment 3.16 l 10 Year Average of 1989-1998 Data X/Q GROUND AVERAGE (sec/m3 )

DIRECTION DISTANCE (IETERS)

(NV'D FROM) 594 2416 . 4020 5630 - 7240 N 3.50E-06 4.23E-07 1.97E-07 1.16E-07 8.13E-08 NNE 2.69E-06 322E-07 1.53E-07 9.16E-08 6.44E-08 NE 3.64E-06 4.51E-07 2.20E-07 - 1.33E-07 9A3E-08 ENE - - 5.94E-06 6.70E-07 3.35E-07 2.07E-07 - -1.A8E-07 E 8.68E-06 9.50E-07 4.84E-07 3.03E-07 2.17E-07 ESE 8 A5E-06 9;36E-07 4.75E-07 2.96E-07 2.12E-07 SE - 9.71E-06 I.OSE-06 5.38E-07 3.37E-07 2.42E-07 SSE 1.09E-05 1.20E-06 6.14E-07 3.86E-07 2.77E-07 S .1.16E-OS *1.30E-06 6.53E-07 4.05E-07 2.89E-07 SSW 5.87E-06 6.70E-07 3.30E-07 2.01E-07 1A3E-07 SW 3.66E-06 4.26E-07 2.04E-07 1.23E-07 8.64E-08 WSW 2.84E-06 .3.14E-07 1.50E-07 ' 1.57E-07 6.32E-08 W 3.29E-06 3.69E-07 1.75E-07 1.04E-07 7.32E-08 WNW 3.20E-06 3.61E-07 1.69E-07 1.01E-07 7.0SE-08 NW 2.98E-06 3.33E-07 1.58E-07 9.44E-08 6.61E-08 NNW --- 3.41E-06 3.81E-07 1.78E-07 - 1.06E-07 7.41E-08 DIRECTION DISTANCE (METERS)-

(WIND FROM) 12067 24135 - 40225 56315 80500 N *4.03E-08 1.55E-08 7.71E-09 - 4.93E-09 3.09E-09 NNE 3.23E-08 1.26E-08 - 6.27E-09 4.01E-09 2.52E-09 NE 4.78E-08 1.91E-08 9.52E-0, 6.11E-09 -3.88E-09 ENE 7.59E-08 3.08E-08 1.5SE-08 9.95E-09 6.37E-09 E - 1.12E-07 4.62E-08 2.33E-08 1.50E-08 9.64E-09 ESE - 1.1OE-07 4.50E-08 2.27E-08 1.46E-08 9.38E-09 SE 1.26E-07 5.20E-08 2.62E-08 1.55E 1.09E-08 SSE - 1.44E-07 5.94E-08 2.99E-08 1.93E-08 - 1.24E-08 S 1.50E-07 6.09E-08 3.06E-08 [.97E-08 - 1.26E-08 SSW 7.3 1E-08 2.94E-08 1.47E-08 9.39E-09 5.97E-09 SW 4.35E-08 1.72E-08 8.56E-09 S.48E-09 3.A7E-09 WSW 3.18E-08 *1.2E-08 6.22E-09 3.99E-09 2.53E-09 W 3.66E-08 - 1.43E-08 7.07E-09 4.55E-09 2.85E-09 WNW 3.50E-08 .1.35E-08 6.70E-09 4.28E-09 2.69E-09

. NW 3.3 OE-08 1.28E-08 6.38E-09 4.09E-09 2.57E-09 NNW 3.68E-08 1.43E-08 7.08E-09 4.54E-09 2.85E-09 DlRECTI'ON - SECITOR I N - *-A - E E S =aNJ W NNE B - ESE F SSW -=K .WNW =P NE -- C SE -G SW L ! NW = Q ENE =D SSE -H WSW M NNW R Worst Case Z/Q = 1.65E-05 sec/rm in Sector A 2001

Information PiMP-6010-OSD-OO1 Rev. 17a Page 69 of 84 OFF-SITE DOSE CALCULATION MIANUAL Attachment 3.16 10 Year Average of 1989-1998 Data I Pages:

68-69

.-j DIQ DEPOSMTION (1/m2)

DIRECION DISTANCE (NIETERS)

VINDFROM 594 2416 1 4020 15630 17240 N 2.46E-08 2.38E-09 1.082-09 S.66E-10 3.62E-10 NNE 1.06E-08 1.02E-09 4.62E-10 2A3E-10 1.55E-10 NE 1.3 1E-08 1.27E-09 5.75E-10 3.02E-10 1.93E-10 ENE 1.62E-08 1.56E-09 7.09B-10 3.72E-10 2.37E-10 E 1.92E-08 1.85E-09 8.39E-10 4.4E-10 2.81E-10 ESE 1.82E-08-- 1.76E-09 7.98E-10 4.19E-10 2.67E-10 SE 1.85E-08 1.79E-09 8.09E-10 4.25E-10 2.71E-10 SSE 2.24E-08 2.17E-09 9.84E-10 5.15-10 3.29E-10 S 3.5E-08 338E-09 1.53E-09 8.03E-10 5.13E-10 SSW 2.31E-08 2.24E-09 1.01E-09 531E-10 3.39E-10 -J SW 2.14E-08 2.07E-09 9.38E-10 4.91E-10 3.14E-10 WSW 2.08E-08 2.01E-09 9.12E-10 4.78E-10 3.0SE-10 W 2.13E-08 2.06E-09 9.33E-10 4.9E-10 3.13E-10 -j WNW 1.95E-08 1.89E-09 8.54E-10 4.48E-10 2.86E-10 NW 1.62E-08 1.57E-09 7.11E-10

3.73E-10 2.38E-10 NNW 2.18E-08 2.11E-09 9.56E-10 5.01E-10 3.2E-10

-- DI T N E ( E E . S I DIRECTION ... I . DISTANCE (METERSY (WIND FROM) 12067 I24135 T 4022S 56315. 80500 N 1.51E-10 4.91E-11 .1.81E-11 9.65E-12 4.84E-12 NNE 6.78E-11 2.1E-11 7.75E-12 . 4.13E-12 2.07E-12 NE 8.18E-11 2.62E-11 9.64E-12 5.15E-12 -

2.58E-12 ENE 9.95E-11 3.23E-11 I.19E-11 6.34E-12 3.18E-12 E - . 1.16E-10 - 3.82E-11 1.41E-11 7.5E 3.76E-12 ESE

1.12E-10 3.64E-11 1.34E-11 7.14E-12 3.58E-12 SE - - 1.13E-10 3.68E-11. 1.36E-11 7.24E-12 3.63E-12 SSE 1.37E-10 4.47E-11 1.65E-11 8.79E-12 4.41E-12 S . 2.14E-10 6.97E-11 2.57E-11 1.37E-11 6.87E-12 SSW 1.42E-10 4.61E-11 1.7E-11 9.06E-12 4.54E-12 SW 1.31E-10 4.27E-1 I 1.57E-11 8.38E-12 4.21E-12 WSW 1.27E-10 4.15E-1 1 1.53E-11 8.16E-12 4.09E-12 -4 W 1.3E-10 4.25E-1 I 1.56E-11 1.73E-1 1 4.19E-12 WNW 1.192-10 3.89E-11 1.43E-11 7.64E-12 3.83E-12 NW 1.78E-10 3.24E-11 1.19E-11 6.36E-12 3.19E-12 NNW 1.34E-10 4.35E-11 1.6E-11 8.55E-12 4.29E-12 DIRECTION-SECTOR N A E -E S J* J W - N NNE -B ESE -- F SSW - K WNW P NE -C SE G SW -L NW Q ENE =D SSE H WSW - M N4W -R I Worst Casc D/Q - 4.46E-08 1/rn in Sector A 2001 I

Information - PMP-6010-OSD-01 l Rev. 17a Page 70 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.17 - Annual Evaluation of X/Q and D/Q Values For l Page:

I All Sectors 70

1. Performed or received annual update of z/Q and D/Q values. Provide a description of what has been received..

Signature Date Environmental Department II . (print name, title)

. 2

. 2. Worst X/Q and D/Q value and sector determined. PMP-6010.OSD.00l has been updated,

ifnecessary. Provide an evaluation.

. . ,_ ./

Signature Date

- -Environmental Department (print name, title)

3. Review nuclide mix for gaseous and liquid release paths to determbine if the dose conversion

- factor of total body is still applicable. Provide ah evaluation. -

. . , ./

I Signature - -- Date Environmental Department

- (print name, title)

.2 Approved and verified by-..

, SI Signature Date Environmental Department (print name, title)

5. Copy to NS&A for information.

S u D

Signature Date Environmental Department (print name, title)

I

Information PMP-6010-OSD-001 Rev. 17a l Page 71 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.18 Dose Factors Pages:

DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

TOTALBODY SKINDOSE GAMMA AIR BETAAIR DOSE FACTOR FACTOR DOSE FACTOR DOSE FACTOR K (DFB,) L1 (DFS,) Ml (DFI, N1 (DFV mrem m' (mrem,m 3 (mrad m3 RADIONUCLIDE per liCi yr) per liCi yr) per jiCi yr) per liCi yr)

Kr-83m 7.56E-02 -- 1.93E+:01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72Et:01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 -j Kr-89 1.66E+04 1.01E+.04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 ' 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.5 1E+02 9.94E+02*- , '3.27E+02 .1.48E+03' Xc-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 -j Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+,03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Te listeddose factors arc forradionuclidesthat maybedetectcd in gaseouseffluents, fromReg. Guide 1.109, Table B.l.

Information PMP-6010-OSD-OO Rev. 17a Page 72 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.18 'Dose Factors'--I P gs I 1 71 -72 DOSE FACTORS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE,

- - IN GASEOUS EFFLUENTS FOR CILD* R£ S.21ec and ff

.. p. .P 1 -,

.HALATION FOOD & GROUND PATHWAY. PATHWAY (mrem m' - (mrem n 2 sec RADIONUCLIDE - - per PCI yr) per pCi yr)

H-3 1.12E+03 1.57E+03' P-32 2.60E+06 7.76E+10 Cr-Si 1.70E+04 - 1.20E+07 Mn-54 ,1.58E+06 1.12E+09 Fe-59 -- 1.27E+06 5.92E+'08

' Co-58 1.11E+06 5.97E+O08

- Co-60 7.07E+06 4.63E+09

- Zn-65 9.95E+05 1.17E+10 Rb-86 ' 1.98E+05 8.78E+09

- Sr-89 2.16E+06

6.62E+09.

Sr-90 1.OlE+08 1.12E+ 1.

Y-91 2.63E+06 6.72E+06 -

Zr-95 . 2.23E+06 . 3.44E+08 I Nb-95 ' 6.14E+05 4.24E+08

- Ru-:103 6.62E+05 1.55E+08 Ru-106 1.43E+07 3.01E+08 Ag-R11Om 5.48E+06 1.99E+10

I-131 1.62E+07 4.34E+l I

-- 1 132 - 1.94E+05 - 1.78E+06 1-133 3.85E+06 3.95E+09

' .1-135 7.92E+05 - 1.22E+07 Cs-134 .OlEIE+06 4.OOE+10

-Cs-136 - - 1.71E+05 -3.00E+09 Cs237 9.07E+O5 3.34E+10O Ba-140 - 1.74E+06 1.46E+08 Ce-141 5.44E+05 3.3 1E+07 -

Ce-144 1.20E+07.- 1.91E+08

As Sr-90, Ru-106 and 1-131 anslyse arc performcd, THEN use Pi given in P.32 (ornmlisted ridionuclides.

'The units for boath 13 fctors are the same, nvem rn per pCi yr '

Information PMP-6010-OSD-001 Rev. 17a Pa e 73 of 84 OFF-SITE DOSE CALCULATION MLANUAL Attachment 3.19 Radiological Environmental Monitoring PrcHgram Pages:

Sample Stations, Sample Types, Sample Frequencies 73 - 76 R cf. 5.2.lv. S.2.lx. S.2.ltl -_ _ _ _ __ _ _ __-_ _ _ __ _ _ _ _ -_

SAMPLE DESCRIPTION/ SAhSPLE SAMPLE I ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY . TYPE FREQUENCY ON-SITE AIRBORNE AND DIRECT RADIATION (TLD) STATIONS ONS-I Cr-M) 1945 ft@ I fromPbntAxis Airborne Palrticulate Weekly Gross Beta Weekly Airborne Radioiodine TLD Quarterly Weekly Ganra Isotopic

1-131 Direct Radiation

Gross Beta Quar Crnp.

Weekly Quarly Weekly i J ONS-2 (-2) 233S ft 48 frcmPlantAxis Airborne Particulate Airborne Radioiodine TLD Quarterly tGarrna Isotopic 1-131

Direct Radiation Quart Comp.

Wekly Quarey I

ONS-3 (r-3) 2407 ft @90 from PlantAxis Airbcme Particulate Weekly Gross Beta Weekly TLD

_._Garnrna Airborne Radioiodine Quarterly 1-131 Isotopic

.Direct Radiation Quan Corn.

Weekly Q-terly I

ONS-4 (r-4) 1852 Qi 113 frorn Plant Axis Airborne Particulate Weekly - Gross Beta Weekly, ONS-5 (T-5) 1895 ft

@ 189 fromPlantAxis Airborne Radiolodine TLD AirbcrParticulate Quarterl y Weekly

-Garruna Isotopic 1-131 Direct Radiaton Gross Beta Quart Cornp.

Weekly Quanrtyer Weekly I

Airborne Radioiodine TLD

_1-131 Quarterly Gumna Isotopic

Direct Radiation Quart CorniP Weekly Quartery I

ONS-6 (T-6) 1917 ft@210- fromPlantAxis Airborne Particulate Weekly Gross Beta Weekly Airborne Riadfoodine.

TLD

Ganuna Isotopic IQuarterly 1-131 Direct Radiation Quart, Comp.

Weekly Quarterly I.-j T-7 2103 ft 36 from Plant Axis TLD QutYeiiy Direct Radiation- Quarterly T-S 2208 ft ( 82 firm Plant Axis TLD Qtiteiy - Diret Radiation Quarterly T-9 1368 ft @ 1490 rom PlantAxis TLD Quartery Direct Radiation Quarterly T-10 1390 ft (a 1270 fom Plant Axis TLD Quarterly- Direct Radiation Ouarterly T-1 I 1969 ft @ 1Il from Plant Axis TLD Quarterly Direct Radiation Quarterly -j T-12 2292 fta 63 from PlantAxis TLD Quarterly Direct Radiation Quarterly CONTROL AIRBORNE AND DIRECT RADIATION (TID) STATIONS ;_._ l NBF 15.6 rniles SSW Arboe Particulate Weekly Gross Beta Wa ly SBN New Buffalo, M1 26.2 miles Se.

SouthBend, IN Airborne Radioiodine TLD Airborne Particulate Qutnly Weekly Ganua Isotopic 113t Direct Radiation Gross Beta -

Gatrrna Isotopic-Quart. Comp.

Weekly Quarterly Weekly Quat Corp.

.I Airborne Radioiodine 1-13.1 Weekly TLD arterly Direct Radiation DOW 24.3 miles ENE Airborne Particulate Wee y Gross Beta - Weekly Dowagiac, Ml Gnmma Isotopic Quart Conp.

Airborne Radioiodmne 1-131 ; - Weekly TLD Quarterly Direct Radiation Quarterly COL 189 miles NNE Airborne Particulate - Weekly Gross Beta Weekly Colon MI Ganmna hotopi Quart. Comp.

Airborne Radiojodine 1.131 Weekly TLD Quarterly Direct Radiatin I Quarty i

I

-4j

Information l PMP-6010-OSD-001 -l Rev. 17a l Page 74 of 84 OFF-SITE DOSE CALCULATION MANUAL A 3 Radiological Environmental Monitoring Program - Pages:

Sample Stations, Sample Types, Sample Frequencies 73 - 76.

SAMIPLE DESCRIPTION/ SAMPLE SAMPLE . ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY 1 TYPE FREQUENCY OFF-SITE DIRECT RADIATION (TLD) STACIONS - ,_ ._._.

OFT-I1 4.5 miles NE, Pole #B294-44 TLD Quaterly Direct Radiation Quay OFP-2 3.6 mies, NE, Strensvill - TLD - Quarterly Direct Radiation Quarterly Substation - - -

OFT-3 5.1 miles NE, Pole #B296-13 TLD . ;Direct Radiation rly OFr-4 4.1 miles, E. Pole #B350-72 1TLD Qu*nzrly Direct Radiation Qua1y OFT-S 4.2 miles ESE, Pole #B387-32 TLD Quarterly Direct Radiation QUalTlY OFI-6 4.9 mnies SE. Pole #B426-1 TLD - Quanerl Direct Radiation Quanerlr OFT-7 2.5 miles S. Bridgtrun Substation TLD Quately tDirect Radiation Quanaly OFT-S 4.0 miles S. Pole #B424-20 TLD QuarDerly

irect Radiation Quarterly OFT-9 4A miles ESE, Pole #B369-214 TLD . 4uarly -Direct Radiation Quarterly OFT-I0 3.8 miles S. Pole #B422-99 TLD QUrlY Direct Radiation Quarterly OFT-1I 3.S miles S, Pole #B423-12 TLD Quartnly Direct Radiation Quarerly GROUNDWATER (WEILL WATER) SAMPLE STATIONS ; ._*_ ._ l W;1 1969 ft I I" friomPlant Axis Groundwater Quarterly Gamma Isotopic Quarterly

._ .. ._.._..._..: _ ITritiurn Quarterly W-2 2302 ft @ 63 from Plant Axis . Groundwater Quarterly. Ganra Isotopic Quarterly

. . .Tritium : Quarterly W-3 3279 ftn 107 from Plant Axis Groundwater Quarterly *0Gamm Isotopic Quarterly

.. TrriTum -_Qu__ _er_

W-4 41S ftn 301 from Plant Axis Groundwater ;Qmy ana Isotopic* Quarterly

._ _ ._._._-_._..*'Tridlum r

.W-S 404 ft 290' from.Plant Axis Groundwater Quarterly Garima Isotopic Quarterly 1'

i!.

_-_-_. .Tritium Quarterly W-6 424 ft 27V3from Plant Axis Groundwater Quarterly- Gamriza Isotopic Quarterly

. .. . . : . . . . .Tritiumr Quartcrhr II W.7 1895 ft@ 189' from Plant Axis Groundwater Quarterly Gam=a Isotopic Quarterly

. .Tritium . Qutrly W48 1274 ft @ 54' firom Plant Axis Groundwater Quarterly. Garma Isotopic Quarterly

. ._._._._.._ Tritium Quarly W-9 1447 ft 22- from Plant Axis Groundwater Quarterly Gamma Isotopic Quarialy

. .. Tritium __urtcrlu W-10 4216 ft 129' from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly

.Tritium Q W-l 3206 ft 1530 from Plant Axis Groundwater Quarterly Ganma Isotopic Quarterly Tritium

u W-12 2631 ft @ 162' from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly

. Tritium QuarterlY W-13 2152 ft 1820 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Ti Ttium . uarterly W-14 1780 f r 1640 from Plant Axis Groundwater Quarterly Gamrna Isotopic Quarterly dritium Quarterly SAMPLE l DESCRIPTIONI SAMPLE 1 SAMPLE l ANALYSIS l ANALYSIS

.STATION LOCATION l TYPE FREQUENCY TYPE FREQUENCY DRINKING WATER .

STJ St. Joseph Public Intake St. Drinking water Once per calendar Gross Beta 14 day Comp.

9 mi. NE Day Gamma Isotopic 14 day Comp.

1-131 14 day Comp.

. Tritium Quart. Cornp.

LTW Like Twp. Public Intake Sta. Drinking water Once per calendar Gross Beta 14 day Cornp.

0.6 mi. S Day Garnma Isotopic 14 day Comp.

1-131 I4 da Con.

. Tritium Quart Comp

Information PMP-6010-OSD-OO1 Rev. 17a Page 75 of 84 OFF-SITE DOSE CALCULATION MANUAL Attahment 3.19 Radiological Environmental Monitoring Program Pages:

Sample Stations, Sample Types, Sample Frequiencies 73 - 76 i

SURFACE WATER -

SWL-l Condenser Circulating Water Surface Water Once per calendar Gamma Isotopic Month. Conp.

0nta.es o Day .Tritium Quart Co SWL-Z Plant Site Boundary - South Surface Water Once per calendar Gamma Isotopic Month. Conp.

- 500 ft. south of Plwit Centerlinc Day .Tritium Quart. Compa SWL-3 Plant Site Boundary - North Surface Water Once per calendar Gamma Isotopic Month. Comp.

I - 500 ft. north of Plant Centerline I Day ititumn Quatt Comp. .I SEDIMENT SIA2 Plant Site Boundary - South Sediment Sceni-Ann.. - :Ganma Isotopic Semi-Annual

-500 tt. south of Plant Ccntcrline . -

SLP3 Plant Site Boundary - North Sediment Semi-Ann. .Gamma Isotopic Seti-Annual

-500 fL north of Plant Centerline :

SL-4 Plant Site Boundary - South Sediment Quarterly Gamma Isotopic Quarterly

. South storm drain culvert to lake . *_ _ _ _

SL-S Plant Sitc Boundary -North Sediment Quarterly Gamma Isotopic Quarterly North storn drain culvert to lake - .

SL t& 5 are data collection points only not actual REMP samples GROUNDWATER (STEAM GENERATOR STORAGE FACLTy) SAMPLE STATIONS SG-I . g mi.@ 95 from PlantAxis Groundwater Quartely Gross Alpha Quartely Gross Beta . Quirerly I

. Ganma Isotopic Quarterly SG-2 0.7 mi. 92' from Plant Axis Groundwater Quarterly Gross Alpha Quarterly Gross Beta

. Gamma Isotopic Quarterly SG-4 0.7 rni @ 93' from Plant Ais Groundwater Quaterly Gross Alpha Qurterty Gross Beta Quartel

_ Gamma Isotopic QusnErX SG-5 0.7 rid. 0 92P fom Plant Axis Groundwater Quarterly Gross Alpha Quarterly Gross Beta Qutrly Gas Isotopic Quartsly -a rSG-I, 2,4 and 5 are data collection points onlynot actual REMP samples I.

INGESTION - MILK Indicator Farms I

2 t

i:~ .:

Information l PMP-6010-OSD-001 Rev. 17a Page 76 of 84 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring Program Pages:

Attachment 3.19 Sample Stations, Sample Types, Sample Frequencies 73 - 76.

SAMPLE DESCRIPTION/ SAMPLE -SAMPLE ANALYSIS l ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY lNGESllON - MIX 13aclcground Farms - - * -

. Milk Once every 131

.1 is days

Ganurn Iscotopic Iper sairple

. . Milk Once every - 1-131 persample N . - . 15 days Ganmna Isotopic persample llON* F.I* i ONS-N 0.3 mrile N. Lake Michigan Fish-edible portion 2year

Gammn Isotonic per sample ONS-S 0.4 nile S,.lakc Michigan . Fish - edible portion 2yar Ganm Isotopic persanmple OFS-N 3.5 rnile NLike Michigan . Fish -edible portion 2/ir _ num Isotopic per saxple OFS4; S.0 mle S. Lke Michfgan Fish - edible portion 2 r Gamma Isotopic per sanple INGESTION - FOOD PRODUCTS ._-_;___.___*

On Site ONS-G Nearest sample to Plant in the i Grpes At tine of Ganiu Isotopic At time of i

highest D/Q land sector . harvest harvest

'containing media I I

ONS-V Broadleaf Bei. At time of jGamma Isotopic At time of --

i- . veretation harvest I harvest Off Site

.- . 4 OFS-G .In a land sector containing Grapes At time of - Gamma Isotopic At time of grapes, apprdimately 20 miles _ harvest - harvest h.. -

-:fromthe plant, in one bf the . . .

. less prevalent DIQ land sectors 2 . - I_

OFS-V Broadleaf At time of Gamra Isotopic 1 At time of vegetation harvest 1- harvest INGESTION - BROADLEAF IN LIEU OF MIL t _l 3 indicator samples of broad leaf vegetation Bseadleaf I Monthly Gamma Isotopic Monthly collected at different locations, within eight vegetation when available 1131 when available miles of the plant In the highest minmual averageD/Q land sector.

1 background sample of similar vegetation Broadleaf Monthly Gamma isotopic Monthly grown 15-25 miles distant In oneof vegetation when available. 1131 when available the less prevalent wind directions.

Collect composite samples of Drinking and Surface water at least daily. Analyze particulate sample filters frgros a activity 24 ormorc hours following filterremoval. 7bis will allow for radon and thoron daughter decay. If gross beta activity in air or water is gratcr than 10 times the yearly mean of control samples for any medium, perform gamma isotopic analysis on the Individual sanplcs.

If at least three indicator milk samples and one background nilk sample cannotbe obtained, three Indicator broad leaf samples will be collected at different locations, within eight miles of the plant, in the land sector with the highest D/Q (refers to the highest annual average D/Q). Also, ne background broad leaf sample will be collected 15 to 25 miles from the plant in one of the less prevalent D/Q land sectors.

The three rnilc indicator and two background farms will be determined by the Annual Land Use Census and those that arc willing to paiticipate.

IF it is determined that the milk animals arc fcd stored feed. THEN monthly sampling is appropriate for that tsne peiod.

Information PMP-6010-OSD-O01l Rev. 17a l Page 77 of 84 OFF-SITE DOSE CALCULATION MANUAL

. Pages:

Attachment 3.20 Maximum Values for Lower Limits of DetectionsA3 - REMP 77 ge78 eL5.2.1v Radionuclides. Food Product Water Milk Air Filter Fish Sediment

. pCi/kg, wet pCiII pCiI pCi/r 3 pCi/kg, wet pCi/kg, dry Gross Beta . 4. 0.01 H-3 _2000 _

Ba-140 - 60 60 La-140 15 15 . : . .

.Cs-134 60 15 15 0.06 130 150 Cs-137 60 18. -:18 0.06- ;150 180 Zr-95 ;30 - : -d Nb-95 15s .

Mn 15 .130 Fe-59 30 . . .<260 Zn-65 30 260 Co-58 15 . 1.30 Co-60 - _._. _ 15 i 130 I-131 60 1 .1 0.07 - .

lbis Data is directly from our plant-spccific Technical Specification. t I

I LLD for drinking water L

i i

II

I Information lPMP-6010-OSD-001 .Rev. 17a Page 78 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.20 Maximum Values for Lower Limits of Deteciions REMPIPages:

77-78.

NOTES A. be Lower Limit ofDetection (LLD) is dcfined as the smallest concentation ofradioactive matcrial in a sample that will be detected with 95% probability and 5%probability of falsely concluding that ablank observation represents a reat" signal..-

For a panicularr.nerment system (which may include radiochemnical separation), the LLD is given by the equation:

II .-

LLD z =r as4.66" 4.66u*S *5 E*V* 2.22*Y*e(A~)

-.- Whcrc LID is the a i' lower limit of detectibn as defined above '(as pCi per unit nass or volume). Perform analysis in such a manner that the stated ITLns will be achieved under routine conditions Occasionally background fluctuations, unavoidably small'sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable. It should be further clarified that the LD represents the capability of aneasurement system and not as an after the fact limit for a particular Measurenent.

S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate

.(as counts per mrinute).

E is the counting efficiency of the detection equipment as counts per transfornatibn (that is, disintegration)

I V is the sample size inappropriate mms or volume units I 2.22 is the conversion factor from picocuries (pCi) to transformations (disintegrations) per minute Y is the fractional radiochemical yield as appropriate X. is the radioactive decay constant for the particular radionuclide At is the elapsed time between the midpoint of sample collection (or end of sample collection period) and time of counting.

B. Identify and report other peaks which are rneasurable and Identifiable, together with the radionuclides listed in Attachment 3.20, MaximumrValues for Lower Limits of DetectionsA&B - REMP.

a A 2.71 value maybe added to the equation to provide correction fordeviations in thePoissodistbution at low count rates, that is,2.71 + 4.66 x S.

. I .

Information PMP-6010-OSD-001 Rev. 17a Page 79 of 84 OFF-SITE DOSE CALCULATION MANUAL Reporting Levels for Radioactivity Concentratons Page:

achmen . in Environmental Samples l 79 Radionuclides Food Product Water Milk Air Filter Fish pCilkg, wet pCi/l pCill pCiOW 3 pClkg, wet H-3 20000 . .

Ba-140 . 200 300 .

La-140 200 300 _

Cs-134 1000 30 60 10 1000 Cs-137 2000 50 70 20 2000 Zr-95 . 400 . . . i Nb-95 _ _: _ ._ 400 30000 Mn-54 _ 1000 30000 Fe-59 400 . 10000 Zn-65 X__ 300 . 20000 Co-58 _ 1000 . 30000 Co-60 - 300 . 10000 I-131 100 2 3 090 __

-J i

I i

I

Information l PMP-6010-OSD-001 Rev. 17a Page 80 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachinent 3.22 3.22 On-Site Monit oring Location - RENT O-Site Page:

. : . . -. '. i, ..

. I: . .

. . .. t AI..

UCiLUaa 4it.1 vSODAM?VA..-)

.- wf L W -M ML ILJJ Cc.

M-3.

ONS-1 -

-LEGEND ONS-6: Air SanmpIing Station T-01 T.12:. TLD Sampling Station W-1 W-1 4: REMP TIS Oroundwater Wells SG-1, SG-2, SG-4, SO-S: REMP Non T/S Groundwater Wells SWL-1.2.3: Surface WaterSarniplingStations SLI2.SL-3: SedimentSamnpling Stations

Information I PMP-6010-OSD-OO1 I Rev. 17a I Page 81 of 84 OFF-SITE DOSE CALCULATION MANUAL .23 l Off-Site Monitoring Locations - RE Page:

I 81

<, X-J

... . J I,.

e _

A . . .. -. -

,,s **,',* ',, . .. ' :_

l at .. . .

, SY i -- fA<

D, ', . , ........................

Information PMP-6010-OSD-O01 - Rev. 17a Page 82 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.24 . Safety Evaluation . ByThe Office Of Nucleai - -Pages:

I Reactor Regulation ,82 - 84 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO DISPOSAL OF SLIGHTLY CONTAMINATED SLUDGE INDLANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKETNOS. 50-315 AND 50-316 [Ref. 5.2.1r]

(Ihis is a 10 CR 50.75 (g) item)':

1. INTRODUCTION : .-.-

By letters dated.October 9, 1991, October 23, 1991, Scptember 3, 1993, and September 29, 1993, Indiana Michigan Power Company (I&M) requested spproval pursuant to 10 CFR20.2002 for the on-site disposal 'of licensed rnaterial not previously considered in the Donald C. Cook NuclearPlant Final Environrmental Statement dated August 1973. Specifically, this request

- addresses actions taken in 1982 in which approximately 942 cubic meters of slightly contaminated sludge were removed from the turbine room sumpo absorption pond and purnped to the upper parking lot located within 'theexclusion area of the Donald C Cook Nuclear Plant. The contaminated sludge was spread over an area ofapproximnately 4.7 acres. The sludge contained a

total radionuclide inventory of 8.89 rnillicuries (rnCi) of Cesium-137, Cesium-136, Cesium-134, Cobalt-60 and Iodine-13 1.

In its submittal, the' licensce addressed spcfie information requested in accordance withx IO C;R 20.2002(a), provided a

detaed

descripdon of the licensed material, thoroughly aLalyzed and evaluated information pertinent to the impacts n he envitronment of the proposed disposal of licensed material,, and committed to follow specicfi procedures to minimize the risk of

. expos s aexpected s f . o t . c 1

2. DESCRIPTION OF WASTE -

The turbine room surnp absorption pond ls'a collection place for water released from the plant's turbine room sump. The contamination was caused by a primary-to-secondary steam generator leak that entered the pond from the turbine building sunmp, a recognized rclease paftway. Sludge, consisting mainlyefleaves and roots mixed wit sand, built up in the pond. As a result, the licensee dredged the pond In 1982. 'The radioactive sludge removed by the dredging activities was punped to a

containment arei located within the exclusion area. The total volume of 942 cubic teters of the radioactive Sudge that was dredged from the bottom of the turbine room absorption pond was subsequently spread and'made into a graveled road over the upper paring lot area of approximately 4.7 acres.'

The principal radionuclides identified in the dredged material are listed below. . .

TABLE 1 NUCLIDE AC71VITY (mCI) 'ACTVITY (mCi) i~ialf-Iife) . : .1982 . - 1991 36 Cs (13.2 d) 0.03 . NA*

34 Cs(2.1y) 2234 . . 0.18 i

13 "Cs (30.2 y) 5.59 -4.57

_ Co (5.6 y) . 0.90 - 0.27 13 t (8.04 d) 0.03 ; -NA*

TOTAL: 8.89 i 5.02 0 NA: not applicable due to decay

Information PAIP-6010-OSD-001 Rev. 17a Page 83 of 84 OFF-SITE DOSE CALCULATION MANUAL Attachment3.24 l Safety Evaluation By The Office Of Nuclear Pages:

I Reactor Regulation 822-84'

3. RADIOLOGICAL IMPACTS The licensee in 1982 evaluated the following potential exposure pathways to members of the general public from the -

radionuclides in the sludge' (I) external exposure caused by groundshine from the disposal site; (2) internal exposure caused by inhalation of re suspended radionuclide-,

-AND-(3) internal exposure from ingesting ground water.

The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NUREG-II01, "Onsite Disposal of Radioactive Waste," Volumes I and 2, November 1986 and Febrary 1987, respectively.

The staff finds the assessment methodology acceptable. Table 2 lists the doses calculated by the licensee for the maximally exposed member ofthe public based on a total activity of 8.89 mCi disposed in that year.

TABLE2 .

Pathway Whole Body IDose Received by

.* .Miximaly Exposed Individual (mreni/year)

Groundshine 0.94 Inhalation . 0.94 Groundwater Ingestion . :.; . 0.73 Total . 2.61 On July 5, 1991, the Hcemsee re-sampled the onsite disposal area to sssire that no significant Impacts and adverse effects had occurred. A counting procedure based on the appropriate environmental low-level doses was used by the licensee; however, no activity was detected during the re-sampling'. This is consistent with the original activity of the material and the decay time.

The 1991 re-sanpling process used by the licensee confirms that the environmental impact of the 1982 disposal was very smalL The staff finds the licensee's methodology acceptable' 4 ENVIRONMENTAL FINDING AND CONCLUSION The staff has evaluated the environmental impact of the proposal to leave in place approxiisately 942 cubic meters of slightly contaminated sludge underneath the upper parking lot on the Donald C. Cook Nuclear Plant bite.

In 1982, the licensee evaluated the potential exposure to members of the general public fronithe radionuclides in the sludge and calculated the potential dose to the maximally exposed member of the public, based on a total activity of 8.89 mCi disposed in that year, to be 2.61 mrtrilyr. The staff has reviewed the licensee's calculational methods and assumptions and found that they are consistent with NUREG-1101, Onsite Disposal of Radioactive Waste, Volumes I and 2, November 1986 and Febcuary 1987, respectively. The staff finds the assessment methodology acceptable. For comparison, the radiation from the naturally occurring radionuclides in soils and rocks plus cosmic radiation gives a person in Michigan i whole-body dose rate of about 89 mrern per year outdoors. Subsequent licensee sampling in 1991 identified no detectable activity. The staff evaluated the licensee's sampling and analysis methodology and finds it acceptable. The results, of the 1991 re-sampling by the licensee, confirm that the environmental impact of the 1982 disposal was very smalL.

Based on the above the staff finds that the potential environmental impacts of leaving the contaminated sludge in place are insignificant With regard to the non-radiological impacts, the staff has determined that leaving the soil in place represents the least impact to the environment.

Information PMP-6010-OSD-001 Rev. 17a Page 84 of 84 OFF-SITE DOSE CALCULATION MANUAL

. Safety Evaluation By The Office Of Nuclear Pages:

Attachment 3.24

. ... .Reactor Re uation :. 82 - 84

5. CONCLUSION Based on the staffs review of the licensee's discussion, the staff finds the licensee's proposal to retain the material in Its present location as documentcd in this Safety Evaluation acceptable. Also, this Safety Evaluation sIll be permanently incorporated as an appendix to the licensee's Offsite Dose Calculation Manual (ODCM), and any future modifications shall be reported to NRC in accordance with the applicable ODCM change protocol. -

I&M letter from E. E. Fitzpatrick to the NRC Document Control Desk, September29, 1993;.

Therefore, the licensee's proposal to consider the slightly contaminated sludge disposed by retention in place in the manner descnred in the Donald C Cook Nuclear Plant submnittals date October 9, 1991, October 23, 1991, September 3, 1993, and September29, 1993, is acceptable. - .

The guidelines used by the NRC staff for onsite disposal of licensed material and the staffs evaluation of how each guideline has been satisfied are given in Table 3.

Pursuant to 10 CFR 51.32, the Cornrnission has determined that granting of this approval will have no significant impact on the environment (October31, 1994, 59 FR 54477).

Principal Contributor. J. Minns Date November 10, 1994 I . .. TABLE3 20.2002 GUIDELINE FOR ONSITE STAFS EVALUATION DISPOSAL * . . .

.1. The radioactive material should be disposed of in such a I. Due to the nature of the disposed material, recycling to the

. manner that it is unlikely that the material would be - general public is not considered likely.

recycled.

2. - Doses to the total body and any body organ of a - 2. -This guideline was addressed in Table 2. Although the maximally exposed individuals (a menber of the general. 2.61 mremlyr is greater than staffs guidelines, the stafffinds it public or a non-occupationally exposed woker) from the acceptable due to 9 yrs decay following analysis and the probable pathways of exposure to the disposed material expected lack of activity detected in the 1991 survey.

should be less than I nrenilycar. x_ " ' i

3. Doses to the total body and any body organ of an. 3. Because the material will be land-spread, the staff considers

-'inadvertent intruder from the probable pathways of ' - .. the maximally exposed individual scenario to also address the exposure should be less than 5 mnremyear. -intruder scenario.

4. Doses to the total body and any body organ of an 4. Even if recycling were to occur after release from regulatory individual from assumed recycling of the disposed control, the dose to a majiriadly exposed member-of the material at the time the disposal site is released from public is not expected to exieed I rnrernlyear, based on regulatory control froni all likely pathways of exposure exposure scenarios considered in this analysis.

.should be less to I nremn. '

E. F. branagan, Jr. and F. I. Congel, 'Disposal of Contaninated Radioactive Wastes from ijuclear Power Plants," presented at the Health Physics Society's Mid-Year Symposium on Health Physics Consideration in Deconbmination/Decorumnssioning,

- Knoxville, Tennessee, February 1986, (CONF.860203).

SOURCE DOCUMENT LIST

.E,,-.

ACTION ITEM NO.

DESCRIPTION 2003 Annual Radioloeical Effluent Release Report TIIE FOLLOWING DOCUMENTS HAVE BEEN USED AS SOURCES OF INFORIATION FOR PREPARATION OF TIHE ATTAtCIIED. COPIES OFThIESE DOCUNIENTS AREAVAILABLE FOR REVIEWAT TIIE LOCATION SPECIFIED.

NO PAGE SOURCE DOCUMENT DESCRIPTION CURRENT SOURCE PARA. TITLE, NUIMBER, REVISION, ETC. DOC. LOCATION

_ _ (FILE NO., ETC.) . J A1.1-1 PMIP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Documentum A.1-2 PMlP-6010-OSD-01 OFF-SITE DOSE CALCULATION MIANUAL Documentum A1.1-3 PMIP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Documentum A1.1-4 12-OHIP-4021-006-004, Data Sheet 1 Env Section Files L-03-1 -* L-03-85 A1.1-5 1 and 2-OHP-4021-028-005, Data Sheet 1; 12-OHP4021-023-002, Env Section Files Data Sheet 1; 1 and 2-OHP-4021-028-004, Data Sheet 1 G-03-1 -+ G-03-28 A1.1-6 None A1.1-7 12 TEP 6020 ADAI 010, Data Sheet 1 NDMNI A1.1-8 1 and 2-OHP-4021-028-005, Data Sheet 1; 12-OHIP-4021-023-002, Env Section Files Data Sheet 1; 1 and 2-OHP-4021-023-004, Data Sheet 1 G-03-1 -+ G-03-28, 1-CPR-03-1 -+ 1-CPR-03-160 and 2-CPR-03-1 CPR-03-250 A1.1-9 Totals from pages A1.1-7 & 8. PINIP-6010-OSD-001 OFF-SITE Env Section Files and DOSE CALCULATION MANUAL (for % of quarterly limit) Documentum A1.1-10 12-OHP4021-006-004, Data Sheet 1 Env Section Files L-03-1 IL03-85 12 THP 6020 AIDM 010, Data Sheet 1 NDIMI Vendor Analysis of Quarterly Composites NDM Env Section Files and A1.1-11&12 Totals from page A1.1-10. Limits from 10 CFR Part 20, Appendix Documenti l B and PIP-6010-OSD-001 OFF-SITE DOSE CALCULATION Documentum MANUAL Env A1.1-13 Vendor Analysis of Quarterly Composites nvioSection Files and A1.1-14 Totals from page A1.1-13. Limits from 10 CFR Part 20, Appendix Env Section Files and B and PM1P-6010-OSD-001 OFF-SITE DOSE CALCULATION Documentum MANUAL A1.1-15 Radioactive Waste shipments Env Section Files and MNIM A1.1-16 Yearly totals and % of PNIP-6010-OSD-001, OFF-SITE DOSE Documentum CALCULATION MANUAL A1.1-17 Site Specific Data for Site Boundary Distances Env Section Files Page 1 of 2

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SOURCE DOCUMENT LIST ACTION ITEM NO.

DESCRIPTION 2003 Annual Radiological Effluent Release Report THE FOLLOWING DOCUMENTS HAVE BEEN USED AS SOURCES OF INFORMATION FOR PREPARATION OF THE ATTACHED. COPIES OF THESE DOCUMENTS ARE AVAILABLE FOR REVIEW AT THE LOCATION SPECIFIED.

NO PAGE SOURCE DOCUMENT DESCRIPTION CURRENT SOURCE DOC. LOCATION PARA. TITLE, NUMBER, REVISION, ETC.

(FILE NO.,ETC.)

A1.2-1 -*5 Quarterly Dose Calculations with MIDAS and Site Specific Data Env Section Files PMP-6010-OSD-001, OFF-SITE DOSE CALCULATION MANUAL A2.1 8 MIDAS System with Site Specific Data, Meteorological Joint Env Section Files A2.2-i -+8 Frequency Tables A2.3-1 -*8 A2.4-1 -*8 Page 2 of 2

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