ML071010192
| ML071010192 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/30/2007 |
| From: | Jensen J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:7691-01, FOIA/PA-2010-0209 | |
| Download: ML071010192 (244) | |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN' One Cook Place Bridgman, Ml 49106 POWERW AEPlcom A unit of American Electric Power March 30, 2007 AEP:NRC:7691-01 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2006, THROUGH DECEMBER 31, 2006 In accordance with Technical Specification 5.6.3, 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, 2006, through December 31, 2006.
The calculations inthis report were performed in accordancewith the CNP Offsite Dose Calculation Manual (ODCM). There have been two revisions made to the ODCM during this reporting period.
This letter contains no new commitments. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.
Sincerely, Joseph N. Jensen Site Vice President RSP/rdw Attachment i§6~LF8 g~-ooc~
U. S. Nuclear Regulatory Commission AEP:NRC:7691-01 Page 2 c: J. L. Caldwell, NRC Region 1II K. D. Curry, AEP Ft. Wayne, w/o attachment J. T. King, MPSC, w/o attachment MDEQ - WHMD/RPMWS, w/o attachment NRC Resident Inspector P. S. Tam, NRC Washington, DC
ATTACHMENT TO AEP:NRC:7691-01 DONALD C. COOK NUCLEAR PLANT UNITS I AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1, 2006, THROUGH DECEMBER 31, 2006
Annual Radioactive Effluent Release Report January 1, 2006 through December 31, 2006 A MERICAW ELECTRIC POWER ARPxAmetrkds Bnetfy lbxlne
TABLE OF CONTENTS Page Table of Contents i I. Introduction 1
- 11. Radioactive Releases and Radiological Impact on Man 1 Liquid Releases 2 Gaseous Releases 2 Solid Waste Disposition 2 III. Meteorological 2 IV. Offsite Dose Calculation Manual (ODCM) Changes 3 V. Total Dose 3 VI. Radiation Monitors Inoperable Greater Than 30 Days 3 VII. Conclusion 3 LIST OF APPENDICES Appendix Title Al.1 2006 Effluent and Waste Disposal Annual Report - Supplemental Information Al.2 Summary of Maximum Individual Doses: First Quarter, Second Quarter, Third Quarter and Fourth Quarter 2006 A2.1 Hours at Each Wind Speed and Direction: First Quarter, 2006 A2.2 Hours at Each Wind Speed and Direction: Second Quarter, 2006 A2.3 Hours at Each Wind Speed and Direction: Third Quarter, 2006 A2.4 Hours at Each Wind Speed and Direction: Fourth Quarter, 2006 A3.0 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 (CNP) during 2006.
- This is in accordance with the requirements of CNP Technical Specification 5.6.3.
The table below summarizes the pertinent statistics concerning the Plant's operation during the period from January 1, 2006, to December 31, 2006. The data in this table and the descriptive information on plant operation are based upon the. respective Unit's Monthly I
Operating Reports, Performance Indicators and Control Room Logs for 2006.
Parameter Unit 1 Unit 2 Gross Electrical Energy Generation (Megawatt Hour (MWH))
7,551,146 8,664,097 I
Unit Service Factor (Percent (%))
Unit Capacity Factor 82.8 82.0 88.3 88.9 I
(Maximum Dependable Capacity (MDC)) Net (%)
I Unit 1 entered the reporting period in Mode 1 at Nominal Full Power (NFP). Small power adjustments were made to facilitate main turbine valve testing throughout the year.
The unit experienced a Technical Specification shutdown on July 30, 2006, due to high i Containment temperature. The unit attained criticality on August 2, 2006,,and returned to NFP onAugust 3, 2006. The unit commenced end of cycle coast down load reduction on August .18, 2006, and entered scheduled Ul C21 refueling outage on September 16, 2006. I The unit attained criticality on November 10, 2006, and attained NFP on November 11, 2006. The unit exited the reporting period at NFP. I Unit 2 entered the reporting period in Mode 1 at NFP. Small power adjustments were made to facilitate main turbine valve testing throughout the year. The unit entered scheduled U2C16 refueling outage on March 25, 2006. The unit attained criticality on I
May 6, 2006, and attained NFP on May 10, 2006. Power was reduced to 80% on September 1, 2006, to allow for repairs of A-North Main Condenser waterbox. Repairs were completed and the unit returned to NFP on September 3, 2006. The unit exited the I
reporting period at NFP.
II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT ON MAN I
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.
I Appendix ALI.1 through A2.4 of this report present the information in accordance with Section 5.6.3 of Appendix A to the Facility Operating Licenses, as specified in the Technical Specifications, Regulatory Guide 1.21 and 10 CFR Part 50, Appendix I.
I The "MIDAS System" is a computer. code that calculates doses due to radionuclides that were released from the CNP.
I I
I
All liquid and gaseous releases were well within Offsite Dose Calculation Manual (ODCM) limits and Federal Limits.
There were no abnormal liquid or gaseous releases.
Liquid Releases During 2006 there were 64 liquid batch releases performed. During the first quarter there were 15 liquid batch releases. During the second quarter there were 16. During the third quarter there were 16. During the fourth quarter there were 17.
Estimated doses (in millirem) to maximally exposed individuals via the liquid release pathways are given in Appendix A1.2 of this report.
Gaseous Releases During the first quarter of 2006 there were two batch releases from Waste Gas Decay Tanks (GDT), one Containment Purge release, and 69 Containment Pressure Reliefs (CPR).
During the second quarter there were five batch releases from GDTs, two containment purges, and 63 CPR. During the third quarter there were four batch releases from GDT, three containment purges, and 61 CPR. During the fourth quarter there was one batch release from Unit 1 containment purge and 67 CPR. CPR continue to be listed as batch releases as described in Nuclear Regulatory Commission Inspections 50-315/89016 (DRSS) and 50-316/89017 (DRSS). Doses continue to be calculated utilizing continuous criteria as allowed by NUREG-0 133. There were -a total of 11 GDT, seven containment purges and 260 CPR gaseous batch releases made during-2006.
In calculating the dose consequences for continuous and batch gaseous releases during 2006, 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 A1.2 of this report. 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.
Solid Waste Disposition There were 64 shipments of radioactive waste made during 2006. This included shipments made from the site and the various radioactive waste processors to the ultimate disposal site.
mI. 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 2006. Hourly meteorological data is available for review and/or inspection upon request.
2
I WV. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES The Offsite Dose Calculation Manual, PMP-6010-OSD-001, was revised during the report period. Copies of Revisions 20 and 21 are included as part of the report.
V. TOTAL DOSE Section 3.2.5 of the ODCM requires that the dose or dose commitment to a real individual I 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 2006 was well within the ODCM limits. Measurements using thermoluminescent dosimeters (TLD) at 11 offsite stations indicate that the dose due to direct radiation is consistent with preoperational and current control (background) levels.
This is fully evaluated in the Annual Radiological Environmental Operating Report.
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 (I&P), the quarterly total body dose from liqu~id effluents, the quarterly critical organ dose from liquid effluents, and the Radiological, Environmental Monitoring Program onsite direct radiation TLD data. These quarterlyI values will be summed and compared to the annual limit. The table that follows here represents the above verbal description:
St nd rd th Dose i yuarer z yuarer i yuarier I+ uarter Total Body or any organ (I&P) 2.22E-02 7.39E-02 1.03E-01 7.15E-02 Total Body (Air)
Skin (Air) 2.90E-04 6.30E-04 1.50E-04 5.90E-04 1.80E-03 3.70E-02 3.40E-04 5.60E-04 I
Total Body (liquid)
Maximum organ (liquid) 5.27E-03 5.38E-03 8.82E-03 8.86E-03 5.08E-03 5.09E-03 6.87E-03 6.99E-03 I
Direct Radiation 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Total 3.38E-02 9.23E-02 Cumulative Total Dose (Total Body or any other organ) mrem 1.52E-01 8.63E-02 3.64E-01 I
Annual Dose Limit (mrem)
Percent of Limit 2.50E+0 1 1.46E+00 I VI. RADIATION MONITORS INOPERABLE GREATER THAN 30 DAYS I
There were no radiation monitors inoperable for greater than 30 days while there was a release via that pathway.
I VII. CONCLUSION Based on the information presented in this report, it is concluded that the CNP Units 1 and 2 I performed their intended design function with no demonstrable adverse affect on the health and safety of the general public.
I 3 I
2006 Effluent and Waste Disposal Annual Report SUPPLEMENTAL INFORMATION Facility: Donald C. Cook Nuclear Plant Licensee:. Indiana Michigan Power Company I 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 qua-rter, to
- 5 mrad for gamma radiation and
- 10 mrad for beta radiation.
1.1.2 During any calendar year, to
- 10 mrad for gamma radiation and
- 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
- 7.5 mrem to any organ.
1.2.2 During any calendar year to
- 15 mrem to any organ.
1.3 Liquid Effluents The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas shall be limited:
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
- 10 mrem to any organ.
Al. 1-1
I 2006 Effluent and Waste Disposal Annual Report I 1.4 Total Dose 3 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. 3 2 MAXIMUM PERMISSIBLE CONCENTRATIONS 3 2.1 Gaseous Effluents The dose rate due to radioactive materials released in I 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. I 2.1.2 For all radioiodines ard for all radioactive" materials in particulate form and radionuclides (other than noble gases) with half-lives greater than I eight days:
- 1500 mrem/yr to any organ.
Theabove 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 pLCi/ml total activity.
I I
AI. 1-2 I
2006 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. Release rates are calculated using an isotopic mix from actual samples rather than average energy.
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. Ni-63 is also currently being analyzed by the offsite vendor in response to evaluation of the 10 CFR 61 sample results.
Al. 1-3
2006 Effluent and Waste Disposal Annual Report 5 BATCH RELEASES I
5.1 Liquid 5.1.1 Number of batch releases:
15 releases in the ist quarter, 2006 i 16 16 17 releases releases releases in in in the 2 nd quarter, the 3rd quarter, the 4th quarter, 2006 2006 2006 3
5.1.2 Total time period for-batch releases: 3 10,341 minutes 5.1.3 Maximum time for a batch release: 3 231 minutes 5.1.4 Average time period for batch release:
.162 minutes 5.1.5 Minimum time period for a batch release:
121 minutes 3 5.1.6 Average stream flow during periods of release of effluent into a flowing stream: I 7.77E+5 gpm circulating water Al. 1-4
2006 Effluent and Waste Disposal Annual Report 5.2 Gaseous 5.2.1 Number of batch releases:
72 releases in the 1 st quarter, 2006 70 releases in the 2 nd quarter, 2006 68 releases in the 3 7d quarter, 2006 68 releases in the 4 th quarter, 2006 5.2.2 Total time period for batch releases:
15,909 minutes 5.2.3 Maximum time for a batch release:.
2,053 minutes 5.2.4 Average time period for batch release:
57.2 minutes 5.2.5 Minimum time period for a batch release:
5 minute:s Al. 1-5
I 2006 Effluent and Waste Disposal Annual Report I 6 ABNORMAL RELEASES I 6.1 Liquid 6.1.1 Number of Releases:
ist Quarter 2 nd Quarter 3 rd Quarter 4 th Quarter 0 0 0 0 6.1.2 Total activity released (Ci): I
- 1 st Quarter 2 nd Quarter 3 rd Quarter 4 th Quarter 0 0 0 0 I
6.2 Gaseous I
6.2.1 Number of Releases:
1 st Quarter 0
2 nd Quarter
-- 0 3 rd Quarter 0
4 th Quarter 0
I 6.2.2 Total activity released (Ci): I "It Quarter 2 nd. Quarter 3rdQuarter 4 th Quarter 0 0 0 0 I I
I I
I I
I Al. 1-6 I I
2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE INuclides Released! Unit I 1st Quarterl 2nd Quarter! 3rd Quarter! 4th Quarter!
- i. FISSION GASES I I H3 Ci 3.97E+01 I 8.23E+01 6.34E+01 9.12E+01 I AR41 I Ci I 6.46E-02 I--------- I------------*-
I KR85 I Ci I---------- I --------- I 3.97E+01 I I XEI31m Ci I5----------I-------- 5.55E-02 I I XE133m I Ci I.--------- I- -------- I 4.30E-02 I I XE133 I Ci I 1.66E-01 I 4.70E-02 I 4.84E+00 I I XE135 I Ci !--------- I- -------- I 1.27E-02 I ITotal for Period Ci - 3.99E+01 ! 8.23E+01 ! 1.08E+02 ! 9.12E+01 INuclides Releasedl Unit I 1st Quarter! 2nd Quarter! 3rd Quarterl 4th Quarter!
- 12. IODINES I ,I- I I 1 1131 1 Ci I..... .1 3.19E-07 I 7.22E-05 I 4.91E-04 I 1 132 1 Ci I-----------I- -------- 4.10E-07 I .1.02E-04 I I1133 Ci I--------- I- -------- 8.95E-06 I ITotal for Period I Ci I-------------I 3.19E-07 I 8.16E-05 I 5.93E-04 i3. PARTICULATES I - I-I MN54 I Ci I 3.75E-08 I--------- I ------------- -
CO58 I Ci I 1.81E-08 I--------- I ------------- I I C060 I Ci I 3.73E-07 I--------- I ----------- -- -
I AG1i0m I Ci I 1.38E-08 I--------- I ----------- I--
I CS134 I Ci I 7.85E-08 I ---------- -- -
I CS137 I Ci I 1.56E-05 1--------- I 1.48E-07 I IiTotal for Period I Ci I 1.61E5 I--------- I 1.48E-07 I
- DENOTES SUPPLEMENTAL ISOTOPES
-n A1.1-7
I 2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES 3 BATCH MODE Nuclides Releasedl Unit I 1st Quarterl 2nd Quarter! 3rd Quarterl 4th Quarter!
- 1. FISSION GASES I. i i 1 I H3. I Ci 1. 1.29E-01 I 4.OOE-01. I 5.95E-01. I 4.50E-02 I AR41 Ci 1.22E-01 I 5.67E-02 2.05E-01 I2.11E-01 KR85 Ci 1.52E+00 I 1.30E+00 I 2.22E+00 I-------- II I XE131M Ci 6.55E-.03 1.19E-03 I--------- - ---
I XE133M . I Ci I 2.68E-03 I 1.72E-03 I--------- I --- I I XE133 Ci I 8.5.OE-01 1 4.11E-01 I 6.84E-01 I 6.78E-02 I XE135 Ci. 5.25E-03. 1.55E-03 3.91E-03 1.32E-03 Totaf for Period I Ci I 2.64E+00 I 2.17E+-00 I 3.71E+00 I 3.25E-01
- 12. IODINES I :, I - I I J131 1. Ci II -1 ------ I 1.72E-06 I '3.54E-05 I Total for Period..! Ci I- . .72E-06 1 1-------7 I 3.54E-05 II
- 13. PARTICULATES I I I I I I CO60 Ci I --------- ---------------- I 9.72E-06 I ITotal for Period I Ci I --------- I--------- I-------- _ 9.72E-06 I I
I I
I I
I A1 .1-8i
2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Units I 1st I 2nd I 3rd I 4th jEst. I I Quarter I Quarter I Quarter I Quarter Total I I I I I IError,%F IA.IFISSION AND I I I ACTIVATION GASES I I il. Total Release I Ci I 2.74E+001 1.82E+001 4.78E+01I 2.80E-011 30.7 1
- 12. Average release luCi/secl 3.52E-011 2.31E-011 6.01E+001 3.52E-021 I Irate for period I I I I I I I3.IPercent of 1% Gammal 2.40E-021 5.24E-031 6.38E-021 1.13E-021 I F applicable limit*F Beta I 1.1OE-021 8.91E-031 5.33E-011 2.24E-031 I B.IIODINES I I I I I I I Il. Total 1-131 1 Ci I 0.00E+00C 3.19E-071 7.39E-051 5.26E-041 11.9 1
- 12. Average release -FuCi/secI 0.00E+001 4.06E-081 9.30E-061 6.62E-051 F !rate for period I I F
- 13. Percent of I % 0.00E+001 9.85E-011 1.37E+001 9.53E-011 I I applicable limit* I I IC.IPARTICULATES I . ............ ..... I I I Il. Particulates withl Ci I 1.61E-051 0.00E+00I 1.48E-071 9.72E-061 11.3 1 I half lives>8 daysl I I I I I I 12.jAverage release luCi/secl 2.07E-061 0.OOE+00l 1.86E-081 1.22E-061 I IF Irate for period I I I I I I I 13.1Percent of I% 2.95E-011 0.00E+001 1.37E+001 9.53E-011 I I Japplicable limit*I I I I I I I F4.FGross alpha I Ci I<I.13E-061<1.02E-061<1.04E-06F<8.69E-071 I I Iradioactivity I I I I I I I ID.ITRITIUM I I I I I I ll.ITotal Release I Ci I 3.99E+011 8.29E+011 6.40E+011 9.11E+011 10.6 1 12..Average release luCi/seci 5.13E+001 1.05E+011 8.05E+00F 1.15E+011 I Irate for period I I I I I I I 13.IPercent of I% 2.95E-011 9.85E-011 1.37E+001 9.53E-011 I I Japplicable limit*I I I I I I
- Applicable limits are expressed in terms of dose. See Appendices A1.2-1 through A1.2-4 Al. 1-9
2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT I
LIQUID EFFLUENTS CONTINUOUS MODE lNuclides Releasedl Unit I 1st Quarterl 2nd Quarterl 3rd Quarter! 4th Quarter!
H3 I Ci I 3.17E-01 i 1.78E-01 i 5.54E-02 I-------------I BATCH MODE i Nuclides Releasedl Unit I 1st Quarter! 2nd Quarter! 3rd Quarter! 4th Quarter!
H3 I Ci I 1.64E902 I 3.30E+02 I 2.31E+02 I 2.80E+02 I CR51 1 Ci I3--------- I 3.41E-04 I 9.57E-05 I 2.11E-04 MN54 I Ci I 5.72E-06 I 4.93E-06 I 9.97E-06 I 2.95E-05 I FE55 Ci 5..90E-04 E - 1.0E-0---------------I-------------I
-1. -5 FE59 I Ci I--------- - I 1.08E-05 I 6.26E-06 I ii C057 I Ci I 4.82E-06 I 1.79E-06 I 4.15E-05 I C058 Ci I 1.93E-04 I 8.01E-04 I 1.88E-03 I 1.24E-02 C060 I Ci - 1.58E-04 I 2.42E-04 - 1.77E-04 I 5.71E-04 I N163 Ci I- --------- I 4.19E-04 I 3.38E-04 I 5.96E-06 I ZN65 Ci I I I.. ---- 2. 95E-05 I ZR95 I Ci I ---------- !2.55E-06 I 2.35E-06 I 3. 67E-06 NB95 I Ci I- -------- 3.66E-06 I 8.16E-06 I 1.28E-05 I AG1IOM I Ci I 1.02E-05 I 2.48E-04 I 1.72E-05 I 5.09E-05 SB124 I Ci I I 4.59E-06 I 2.14E-06 I 2.91E-05 i SB125 I Ci I 4.26E-05 4.14E-05 I 7.41E-05 I 3.72E-04 I 1131 1 Ci I---------I----------- 4.16E-06 I CS134 I Ci I 1.87E-05 I--------- 2.07E-06 I 2.81E-05 I CS137 I Ci I 2.06E-05 I 1.84E-05 I 2.72E-06 I 3.36E-05
- XE133 I Ci I- 5.84E-06 I--------------!7.00E-06 I S*XE133m Ci I ---------
I------------ 1.44E-05 DENOTES SUPPLEMENTAL ISOTOPES A1.1-10 I
2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES BATCH MODE I Units I 1st I 2nd I 3rd I 4th lEst.
I I I Quarter Quarter I Quarter I Quarter Total I II I I I I I Error,%I IA.IFISSION AND I I I ACTIVATION I I I PRODUCTS I I I il.Total Release I Ci 4.54E-041 2.13E-031 3.21E-031 1.38E-021 12.6
- 12. Average diluted luCi/ml I 7.34E-I1 2.94E-101 3.75E-101 1.63E-091 I I concentration I I I I 1 1 I Iduring period I I I I I I I3.IPercent of. % 1.73E-031 2.60E-031 2.09E-031 1.07E-021 I I applicable limit I I I I I IB.ITRITIUM 1l;ITotal Release I Ci I.1.64E+021 3.30E+021 2.31E+021 2.80E+021 10.1 I 2.lAverage diluted IuCi/ml. 2.65E-051 4.56E-051 2.70E-051 3.32E-051 I Jconcentration- I I I I- I I I Iduring.period I I I I I I 13.IPercent of I . I 2.65E+.01-A.56E+001 2.O0E+001. 3.32E+001 I.
I applicable limit I I I I i IC. DISSOLVED AND I I I I I I I ENTRAINED GASES I I I Il.FTotal Release I Ci I 0.00E+001 5.84E-061 0.OOE+00I 2.14E-051 43.5 1
- 2. Average diluted IuCi/ml I 0.OOE+001 8.07E-131 0.00E+001 2.53E-12I I I concentration I I I I I I lduring period I I I I I I 13.1Percent of I % I 0.00E+001 4.03E-071 0.OOE+00 1.27E-061 I I lapplicable limit I I I I I ID. GROSS ALPHA I Ci I<8..00E-05I<8.24E-051<8.51E-051<9.00E-051 N/A I IRADIOACTIVITY I I I I I I JTOTAL RELEASE I I .I I I I IE.JVOLUME OF WASTE I Litersi 8.77E+051 9.03E+051 9.33E+051 9.87E+051 2.00 1 I RELEASED I I IF.IVOLUME OF I Litersl 6.18E+091 7.24E+091 8.56E+091 8.45E+091 3.48 1 IDILUTION WATER I I I I I I JUSED DURING I I I I I IPERIOD I I I I I Al.1-11
2006 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT I
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES CONTINUOUS MODE Units Ist 2nd [3rd I4th lEst. I I Quarter I Quarter I Quarter I Quarter [Total IIError,%l IA.IFISSION AND I I I I I ACTIVATION I I I .1 I PRODUCTS
- i. [Total Release I Ci [ 0.O0E+00[ 0.OOE+00[ 0.OOE+00[ 0.OOE+001 N/A I 2.[Average diluted [uCi/ml I 0.OOE+00[ 0.OOE+001 0.OOE+00 0.OOE+00I I [concentration I I I I I ]during period I I I I 13.IPercent of I % 0.OOE+00I 0.OOE+0O[ 0.ooE+b00 0.OOE+001 I I [applicable limit I I I I; I i I IB.ITRITIUM I I
- 1. [Total Release I Ci I 3.17E-011 1.78E-01[ 5.54E-021 0.OOE+00[ 11.3 I
[2.IAverage diluted [uCi/ml I 4.49E-.101 2.71E-101 7:12E-111 0.OOE+00 I I Iconcentration I I I I I I I I [during period I I I I 13.[Percent of % I 4.49E-051 2.71E7051 7.12E-061 0.00E+001
- 1. [applicable limit I I I I I lI
[C. DISSOLVED AND I I I IENTRAINED GASES I I Ii. Total Release I Ci I 0.OOE+00I 0.OOE+00I 0.OOE+00[ 0.OOE+001 N/A I
[uCi/ml I 0.OOE+001 0.OOE+00I 0.OOE+00[ 0.OOE+00[
I
[2. Average diluted I I [concentration I. I I 1 1 1 Iduring period I I I I I I I 13.[Percent of I % 0.00E+00[ 0.00E+00 0.00E+00 0.OOE+00 I I applicable limit I 1 . 1 1 1 1 1.
ID.IGROSS ALPHA I Ci [<I.95E-021<2.35E-02[<2.38E-02[<3.01E-I02[ N/A I I [RADIOACTIVITY I I I I I I I ITOTAL RELEASE [ I I I [ I IE.JVOLUME OF WASTE I Liters[ 5.29E+07[ 3.46E+071 2.12E+071 0.OOE+001 2.00 1 I IRELEASED I [
[F.[VOLUME OF [ Litersl 7.06E+1I[ 6.56E+11[ 7.78E+11I 0.OOE+00[ 3.48 I 1 IDILUTION WATER I I I [USED DURING I I I I I IPERIOD I . I [
A1.1-12 I
2006 Effluent and Waste Disposal Annual Report Solid Waste and Irradiated Fuel Shipments Solid Waste Shipped Offsite for Burial or Disposal
- 1) Type of Waste Unit Estimated Estimated Total Error, %
amount a) Spent resins, filters, sludge, m3 1.24E+01 1.OOE+00' evaporator bottoms, etc. Curies 1.09E+02 3.75E+00 b) Dry compressible waste, m3 1.82E+02 1.OOE+00 contaminated equipment, etc. Curies 1.08E+01 6.48E+00 m3N/A N/A Curies c) Irradiated components, control rods, etc.
d) Other m3 N/A N/A Curies
- 2) Estimate of Principle Radionuclide Composition a) Nb-95 2% Ni-63 30 % Sb-1 25 3%
Cs-137 3% C058 *8 % Nb-95 1%
Co-58 4 % Sb-125 1 %
- 3) Solid Waste Disposition No. of Shipments Mode of Transportation Destination 10 Truck Barnwell, SC 54 Truck Clive, UT Type of Containers used for Shipment: Containers used are excepted packages, Type A, Sea Land, metal boxes, drums and high integrity containers.
- 5) Solidification Agent: There were no solidifications performed during this report period.
A1.1-13
2006 Effluent and Waste Disposal Annual Report Yearly Release Rates GASES Fission and Activation Gases Total Release 5.26E+01 Curies Average Release Rate 1.67E+00 ptCi/sec
% of Applicable Limits* y 5.22E-02 %
3 2.78E-01%
Iodines Total 1-131 Release 6.OOE-04 Curies Average Release Rate 1.90E-05 ýtCi/sec
% of Applicable Limit* 1.80E+00 %
Particulates Total Release 2.60E-05 Curies Average Release Rate 8.23E-07 jiCi/sec
% of Applicable Limit* 1.80E+00 %
LIQUIDS Fission and Activation Products Total Release 1.96E-02 Curies Average Diluted Concentration 6.44E-10 gCi/ml
% of Applicable Limits* Total Body 8.68E-01 %
Organ 2.63E-01 %
Applicable limits are expressed in terms of the annual 10 CFR 50, Appendix I, dose limits.
A1.1-14
Site Boundary and Nearest Residence Listing The following distances were used in the calculation of the maximum individual doses:'
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 .964 J S 594 997 K SSW 629 942 Al. 1-15
Summary of Maximum Individual Doses First Quarter 2006 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)
(Toward) LIMIT QTR Liquid Total Body 5.27E-03 Child Receptor 1 3.51E-01 1.5E+0 Liquid Liver 5.38E-03 Child Receptor 1 1.08E-01 5.OE+O Noble Gas Air Dose 1.20E-03 Any 594 (SSE) 2.40E-02 5.OE+O (Gamma-mrad) Age Noble Gas Air dose 1.1OE-03 Any 594 (SSE) 1.1OE-02 1.0E+1 (Beta-mrad) Age lodines and Liver 2.22E-02 Child 659 (N) 2.96E-01 7.5E+O Particulates A1.2-1
I I
Summary of Maximum Individual Doses I I Second Quarter 2006 I EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT I
ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)
'(Toward) LIMIT QTR I
Liquid Total Body 8.82E-03 Child Receptor 1 5.88E-01 1.5E+0 Liquid Liver 8.86E-,03 Child Receptor 1 1.77E-01 5.OE+O I
Noble Gas Air Dose 2.62E-04 Any 651 (N) 5.24E-03 5.OE+0 I
(Gamma-mrad) Age Noble Gas Air dose 8.91E-04 Any 629 (SE) 8.91E-03 1.0E+1 I
(Beta-mrad) Age I
Iodines and Total Body, 7.39E-02 Chid 659 (N) 9.85E-01 7.5E+0 Particulates I
I I
I I
I I
I A1.2-2 I
Summary of Maximum Individual Doses Third Quarter 2006 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT ORGAN DOSE (mrem) GROUP DIST DIR (M) APPLICABLE (mrem)
(Toward) LIMIT QTR Liquid Total Body 5.08E-03 Child Receptor 1 3.39E-01 1.5E+0 Liquid GI-Tract 5.09E-03 Child Receptor 1 1.02E-01 5.OE+0 Noble Gas Air Dose 3.19E-03 Any 651 (N) 6.38E 5.0E+0 (Gamma-mrad) Age Noble Gas, Air dose 5.33E-02 Any 651 (N) 5.33E-01 1.0E+1 (Beta-mrad) Age lodines and Thyroid 1.03E-01 -Child 659 (N) 1.37E+00 7.5E+0 Particulates A1.2-3
I I
Summary of Maximum Individual Doses I Fourth Quarter 2006 I
% OF LIMIT I
EFFLUENT APPLICABLE ESTIMATED AGE LOCATION ORGAN DOSE (mrem) GROUP DIST DIR (M)
(Toward)
APPLICABLE LIMIT (mrem)
QTR I Liquid Total Body 6.87E-03 Child Receptor 1 4.58E-01 1.5E+O I
Liquid Liver 6.99E-03 Child Receptor 1 1.40E-01 5.OE+0 Noble Gas. Air Dose 5.65E-04 Any 651 (N) 1.13E-02 5.OE+0 I
(Gamma-mrad) Age I
Noble Gas Air dose 2.24E-04 Any 651 (N) 2.24E-03 1.0E+1 (Beta-mrad) Age I
Iodines and Particulates Thyroid 7.15E-02 Child 1643 (ESE) 9.53E-01 7.5E+0 I
I I
I I
I I
A1.2-4 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/06 - 3/31/06 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPTOM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-4 4-8 8-13 13-19 19-25 >25 TOTAL N 3 29 9 0 0 0 41 NNE 0 10 0 0 0 0 10 NE 0 14 1 0 0 0 15 ENE 0 8 2 0 0 0 10 E 0 7 2 0 0 0 9 ESE 1 6 2 0 0 0 9 SE 1 18 10 0 0 0 29 SSE 1 14 18 0 0 0 33 S 2 2 14 4 0 0 22 SSW 0 1 4 2 0 0 7 SW 1 11 17 1 0 0 30 WSW 1 15 12 2 0 0 30 W 2 6 7 0 0 0 15 WNW 2 31 14 0 0 0 47 NW 5 25 1 0 0 0 31 NNW 3 59 10 0 0 0 72 TOTAL 22' 256 123 9 0 0 410 PERIODS OF CALM(HOURS): 55 VARIABLE DIRECTION: 0.
HOURS OF MISSING DATA: 7 A2.1-1
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 1/1/06 - 3/31/06 B DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-4 2
4-8 5
8-13 1
13-19 19-25 >25 0 0 0 TOTAL 8
I NNE 1 1 0 0 0 0 2 NE ENE 2
0 2
0 1
2 0
0 0
0 0
0 5
2 I
0 0
2 6
3 0
1 3
.0 0
0 0
.0 0
0 0
2 7
6 I
0 1
5 1
1 2
4
,2 0
0 0
0 0
0 3
9 7
I 0
W WNW NW 0
1 1
2 2
8 2
0 4
0 0
0 0 0
0 0
0 0 13 4
3 I NNW 3 10 8 0 0 0 21 TOTAL 10 56 36 6 0 0 108 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
55 0
I HOURS OF MISSING DATA: 7 I
I I
I A2 .1-2 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/06 - 3/31/06 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR10M LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-4 4-8 8-13 13-19 19-25 >25 TOTAL N 2 5 0 0 0 0 7 NNE 0 3 0 0 0 0 3 NE 0 3 1 0 .0 0 4 ENE 0 3 2 1 0 -0 6 E 0 2 0 0 0 0 2 ESE 0 1 0 0 0 0 1 SE 1 1 1 0 0 0 3 SSE 0 5 0 0 0 0 5 S 2 1 7 0 0 0 10 SSW 1 1 4 1 0 0 7 SW 0 3 3 .1 0 0 7 WSW 1 1 '5 0 0 0 7 W 0 2 0 0 0 0 2 WNW 0 8 4 0 0 0 12 NW 0 11 5 0 0 0 16 NNW .1 16 9 0 0 0 26 TOTAL 8 66 41 3 0 0 118 PERIODS OF CALM(HOURS): 55 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 7 A2.1-3
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SPIOM 1/1/06 - 3/31/06 D DT/DZ DIRECTION:DIRIOM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-4 8
4-8 47 8-13 20 13-19 19-25 >25 1 0 0 TOTAL 76 I
NNE 11 23 0 0 0 0 34 NE ENE 7
9 9
19 19 21 11 2
6 0
0 0
0 0
0 0
0 30 39 34 I
6 34 13 11 11 13 3 0 0
0 0
0 0
0 0
0 43 38 31 I
S 9 21 27 .4 0 0 61 SSW SW WSW 4
6 3
19 16 8
38 39 27 5
0 5
0 0
0 0
0 0
66 53 51 I
.4 W
WNW NW 1
6 19 34 55 24 18 34 1
0 0
0 0
0 0
0 0
48 53 95 I
NNW 21 79 45 0 0 0 145 TOTAL 125 438 318 16 0 0 897 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
55 0"
I HOURS OF MISSING DATA: 7 I
I I
I A2. 1-4 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/06 - 3/31/06 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIRIOM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-4 4-8 8-13 13-19 19-25 >25 TOTAL N 9 10 9 3 0 0 31 NNE 6 3 0 0* 0 0 9 NE 13 4 0 0 0 0 17 ENE 13 7 3 0 0 0 23 E 14 12 13 0 0 0 39 ESE 16 6 3 0 0 0 25 SE 19 20 1 -0 0 0 40 SSE 16 23 17 0 0 '0 56 S 11 19 14 2 0 0 46 SSW 5 8 2 0 0 0 15 SW 4 3 4 1 0 0 12 WSW 3 .5 4 4 0 0 16 W 4 2 1 .0 0 0 7 WNW 2 6 2 0 0 0 10 NW 6 6 0 0 0 0 12 NNW 19 2 3 0 0 0 24 TOTAL 160 136 76 10 0 0 382 PERIODS OF CALM(HOURS): 55 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 7 A2.1-5
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 1/1/06 - 3/31/06 F DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-4 0
4-8 0
8-13 0
13-19 19-25 >25 0 0 0 TOTAL 0
I NNE 2 0 0 0 0 0 2 NE ENE E
3 5
6 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 3
5 6
4 13 0
0 5
0 0
0 0
0 0
0 0
0 15 22 29 I
S 9 7 4 .0 0 0 20 SSW SW WSW 3
1 0
0 1
.1 1
0 0
3 0
0 0
0 0
0 0
0 7
2 1
I W 1 WNW NW 1
.2 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2
1 2
I NNW 1 0 0 0 0 0 1 TOTAL 78 27 10 3 0 0 118 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
55 0
I HOURS OF MISSING DATA: 7 I
I I
I A2. 1-6 I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/06 - 3/31/06 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-4 4-8 8-13 13-19 19-25 >25 TOTAL N 1 0 0 0 0 0 1 NNE 0 0 0 0 0 0 0 NE 1 0 0 0 ;0 0 1 ENE 3 0 0 0 0 0 3 E 4 0 0 0 0 0 4 ESE 9 0 0 0 0 0 9 SE 15 2 1 0 0 0 18 SSE 9 1 2 0 0 0 12 S 3 3 6 0 0 0 12 SSW 1 0 '-0 0 0 0 1 SW 0 0 0 0 0 0 0 WSW 1 0 -0 I0 0 0 1 W I: 0 0 0 0 0 1 WNW 0 0 0 0 0 0 0 NW 2 0 0 0 0 0 2 NNW 0 0 0 0 0 0 0 TOTAL 50 6 9 0 0 0 65 PERIODS OF CALM(HOURS): 55 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 7 A2.1-7
I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 1/1/06 - 3/31/06 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)
WINDi DIRECTION 1-4 4-8 8-13 13-19 19-25 >25 TOTAL N 25 96 39 4 0 0 164 NNE 20 40 0 0 0 0 60 NE 28 42 5 0 0 0 75 ENE 30 37 20 1 0 0 88 E 31 46 24 0 0 0 101 ESE 47 .49 8 0 0 0 104 SE SSE S
68 44 36 64.
70 57 25 58 76 11 0
0 0
0 0
0 0
.0 157 172 180 I
SSW 14 30 50 12 0 0 106 SW 12 31 65 5 0 0 113 WSW 9 39 52 13 0 0 113 W 12 32 34 1 0 0 79 WNW NW NNW 7
22 48 81 105 166 38 44 75 0
0 0
0 0
0 0
0 0
126 171 289 I
TOTAL 453 985 613 47 0 .0 2098 PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
HOURS OF MISSING DATA:
55 0
7 I
I A2. 1-8i I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/06 - 6/30/06 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPIOM DIRECTION:DIRIOM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 87 15 0 0 0 108 NNE 2 7 0 0 0 0 9 NE 4 12 1 0 0 0 17 ENE 3 5 4 1 0 0 13 E 3 3 3 0 0 0 9 ESE 3 8 12 0 0 0 23 SE 3 11 18 1 0 0 33 SSE 4 22 17 1 0 0 44 S 2 23 21 3 0 0 49 SSW 2 10 9 0 0 0 21 SW 4 36 20 1 0 0 61 WSW 1 38 11 1 0 0 51 W 6 32 6 0 0 0 44 WNW 8' 35 2 0 0 0 45 NW 13 63 1 0 0 0 77 NNW 24 144 10 0 0 0 178 TOTAL 88 536 150 8 0 0 782 PERIODS OF CALM(HOURS): 16 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 3 A2.2-1
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 4/1/06.- 6/30/06 B DT/DZ DIRECTION:DIRIOM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3 5
4-7 5
8-12 2
13-18 1
19-24 >24 0 0 TOTAL 13 I
NNE 1 3 1 .0 0 0 5 NE ENE E
1 1
2 0
0 0
0 0
0 0
0 0
3 1
2 I
2 3
2 2
4 0 4
1 0
0 1
0 0
0 0
0 0
5 8
7 I
1 4
1 4
3 1
2 4
0 0
0 0
0 0
0 0
0 11 3
7 I W
WNW NW 4
4 5
3 1
4 1
0 0
0 0
0 0
0 0
0 0
0 18 8
5 9 I NNW 8 10 0 0 0 0 TOTAL 42 46 17 2 0 0 107 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
16 0
I HOURS OF MISSING DATA: 3 I
I I
I A2.2-2 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/06 - 6/30/06 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 5 9 5 0 0 0 19 NNE 1 4 0 0 0 0 5 NE 1 0 0 0 0 0 1 ENE 0 2 0 0 0 0 2 E 2 0 0 0 0 0 2 ESE 2 3 1 0 0 0 6 SE 3 5 4 0 0 0 12 SSE 1 4 1 0 0 0 6 S 3 4 2 1 0 0 10 SSW 3 3 4 0 0 0 10 SW 2 11 1 0 0 0 14 WSW 4 5 2 0 0 0 11 W 1 0 2 0 0 0 3 WNW 4 1 3 0 0 0 8 NW 3 3 1 0 0 0 7 NNW 10 5 1 0 0 0 16 TOTAL 45 59 27 1 0 0 132 PERIODS OF CALM(HOURS): 16 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 3 A2. 2-3
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: .SPEED:SP1OM 4/1/06 - 6/30/06 D DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3 22 477 31 8-12 1
13-18 19-24 >24 0 0 0 TOTAL 54 I
NNE 13 9 0 0 0 0 22 NE ENE E
10 3
2 2
4 6
0 3
8 0
0 0
0 0
0 0
0 0
17 16 5
I
24 16 10 23 2
4 0
1 0
0 0
.0 0
51 19 I
S 4 33 13 3 0 '0 53 SSW SW WSW 12 6
4 14 8
9 7
12 4
0 0
1 0
0 0
0 0
.0 21 30 26 I
W 4 10 6 0 0 0 20 WNW NW 8
7 2
1 12 1
0 0 0
0 0
0.
0 10 9
I NNW 31 3 1 0 0 47 TOTAL 145 191 87 6 0 0 429 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
16 0
I HOURS OF MISSING DATA: 3 I
I I
I A2. 2-4 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/06- 6/30/06 STABILITY CLASS: E 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 23 1 0 0 0 0 24 NNE 8 1 0 0 0 0 9 NE 9 3 0 0 0 0 12 ENE 4 6 0 0 0 0 10
ýo E 15 12 2 0 0 0 29 ESE 5 14 0 0 0 0 19 SE 9 11 0 0 0 0 20 SSE 6 12 1 0 0 0 19 S 15 30 8 0 0 0 54 1
SSW 4 9 0 0 0 13 SW 6 23 3 .0 0 0 32 WSW 5 iho 0 .0 0 0 15 W 13 2 0 0 15
~0 WNW 12 3 0 00 0 15 0
NW 13 3 0 0 16 0 0 NNW 18 5 0 0 23 TOTAL 165 145 14 1 0 0 325 PERIODS OF CALM(HOURS): 16 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 3 A2.2-5
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP10M 4/1/06 - 6/30/06 F DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3 5
4-7 0
8-12 0
13-18 19-24 0 0
>24 0
TOTAL 5
I NNE 5 0 0 0 0 0 5 NE ENE E
11 10 6 1 1
3 0
0 0
0 0
0 0
0 0
0 0
0 12 13 7
2 0
0 0
0 0
0 0
0 0
0 o
0 19 36 I
S 13 6 0 0 0 0 19 SSW SW WSW 4
5 6
0 1
0 0
"0 0
0 0
0 0
0 0
6 0
4 6
6 I
W 5 1 0 0 0 6 WNW NW 6
5 0
0 0
0 o0 0
0 0
0 0
0 0 5 6
I NNW 2 0 0 0 0 2 TOTAL 137 30 0 0 0 0 167 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
16 0
I HOURS OF MISSING DATA: 3 I
I I
I A2. 2-6 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 4/1/06 - 6/30/06 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 0 2 NNE 1 0 0 0 0 0 1 NE 5 0 0 0 0 0 5 ENE 12 0 0 0 0 0 12 E 19 0 0 0 0 0 19 ESE 26 0 0 0 0 0 26 SE 30 0 0 0 0 0 30 SSE 40 2 0 0 0 0 42 S 23 1 0 0 0 0 24 SSW 20 1 0 0 0 0 21 SW 12 1 0 0 0 0 13 WSW 11 0 0 0 0 0 11 W 5 0 0 0 0 0 5 WNW .5 0 0 0 0 0 5 NW 2 ~0 0 0 0 0 2 NNW 5 0 0 0 0 0 5 TOTAL 218 5 0 0 0 0 223
.PERIODS OF CALM(HOURS): 16 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 3 A2. 2-7
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 4/1/06 - 6/30/06 ALL DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND WIND SPEED (MPH) I DIRECTION N
1-3 68 4-7 133 8-12 23 13-18 19-24 1 0
>24 0
TOTAL 225 I
NNE 31 24 1 0 0 0 56 NE ENE E
29 41 51 20 18 25 1
7 14 0
1 0
0 0
0 0
0 0
50 67 90 I
ESE 53 56 15 0 0 0 124 SE SSE 76 82 47 64 49 24 1
3 0
0 0
0 173 173 I
S 61 98 44 8 0 0 211 SSW SW WSW 40 42 35 32 90 65 21 30 29 0
1 2
0 0
0 0
0 0
93 163 131 I
W 38 48 15 0 0 0 101 WNW NW 47 48 42 74 5
3 0
0 0
0 0
0 94 125 I
NNW 98 176 14 1 0 0 289 TOTAL 840 1012 295 18 0 0 2165 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
HOURS OF MISSING DATA:
16 0
3 I
I I
I I
A2. 2-8 i
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 STABILITY CLASS: A 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 16 64 0 0 0 0 80 NNE 8 0 0 0 0 0 8 NE 3 11 0 0 0 0 14 ENE 2 17 0 0 0 0 19 E 3 15 0 0 0 0 18 ESE 4 5 0 0 0 0 9 SE 4 10 0 0 0 0 14 SSE 12 17 0 0 0 0 29 S 9 40 7 1 0 0 57 SSW 3 21 34 0 0 0 58 SW 4 40 19 0 0 0 63 WSW 5 27 2 0 0 0 34 W 11 17 0 0 0 0 28 WNW 8 14 0 0 0 0 22 NW 15 18 0 0 0 0 33 NNW 28 67 0 0 0 0 95 TOTAL 135 383 62 1 0 0 581 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 A2.3-1
I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND WIND SPEED (MPH) i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N. 4 2 0 0 .0 0 6 NNE 0 1 0 0 0 0 1 NE 3 1 0 0 0 0 4 ENE 2 2 0 0 0 .0 4 E 1 1 0 0 0 0 2 ESE 0 1 0 0 0 0 1 SE SSE S
4 2
.2 1
1 6
0 0
4 0
0 0
.0 0
0.
0 0
0 12 5
3 I SSW 0 6 .6 0 0 0 12 SW 3 .7 2 0 0 0 12 WSW W
3 1
2 1
0
.0 0
0 0
0 0
0 5
2 i
WNW .2 0 0 0 0 0 2 NW 2 0 0 0 0 0 2 NNW 6 2 0 0 0 0 8 TOTAL . 35 34 12 0 0 0 81 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 I
I I
I A2. 3-2i I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 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 6 4 0 0 0 0 10 NNE 2 0 0 0 0 0 2 NE 1 1 0 0 0 0 2 ENE 3 1 0 0 0 0 4 E 0 3 0 0 0 0 3 ESE 1 3 0 0 0 0 4 SE 3 0 0 0 0 0 3 SSE -4 3 0 0 0 0 7 S 1 3 1 0 0 0 5 1 11 .2 0 SSW 0 0 14 SW 3 3 1 0 0 0 7 WSW 0 2 0 0 0 0 2 W 0 0 0 0 0 0 0 WNW 1 0 0 0 0 0 1 NW 0 1 0 0 0 0 1 NNW 5 0 0 0 0 0 5 TOTAL 31 35 4 0 0 0 70 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 A2. 3-3
I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 STABILITY CLASS: D DT/DZ -
ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED WIND DIRECTION 1-3 4-7 8-12 (MPH) 13-18 19-24 >24 I
TOTAL N 31 21 0 0 00 52 NNE 16 0 0 0 0 0 16 NE 10 16 0 0 0 0 26 ENE E
ESE 8
22 9
23 31 2
0 0
0 0
0 0
0 0
0 0
0 0
31 53 11 I
SE 12 4 0 0 0 0 16 SSE 16 4 0 0 0 0 20 S 14 49 7 -0 0 *0 70 SSW 7 37 27 1 0 0 72 SW 4 22 7 0 0 0 33 WSW 12 11 10 0 0 0 33 W 6 5 4 0 0 0 15 WNW 6 7 0 0 0 0 13 NW 5 6 0 0 0 0 11 NNW 10 11 0 0 0 0 21 TOTAL 188 249 55 1 0 0 493 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 I
I I
I A2. 3-4i I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPTOM DIRECTION:DIRIOM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 26 4 0 0 0 0 30 NNE 17 1 0 0 0 0 18 NE 32 20 1 0 0 0 53 ENE 20 10 1 0 0 0 31 E 24 4 0 0 0 0 28 ESE 31 4 0 0 0 0 35 SE 23 2 *0 0 0 0 25 SSE 22 3 0 0 0 25 S 37 65 3 0 0 0 105 SSW 17 22 .4 0 0 0 43 SW 3 12 7 0 0 0 22 WSW 5 2 2 0 0 0 9 W 4 3 0 0 0 0 7 WNW 1 1 0 0 0 0 2 NW 5 0 0 0 0 0 5 NNW 1i 1 0 0 .0 0 12 TOTAL 278 154 18 0 0 0 450 PERIODS OF CALM(HOURS): 0*
VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 A2. 3-5
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 7/1/06 - 9/30/06 F DT/DZ DIRECTION:DIRI0M LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3.
6 4-7 0
8-12 0
13-18 19-.24 >24 0 0 0 TOTAL 6
I NNE 5 0 0 0 0 0 5 NE ENE E
16 14 44 0
1 0
0 0
0 0
0 0
0 0
0 0
0 0
16 15 44 I
0 2
0 0
0 .0 0
0 0
0 0
0 0
0 29 26 17 I
S 41 6 1 0 0 .0 48 SSW SW WSW 3
4 3
4 0
0 1
0 0
0 0
0 0
0 0
0 0
0 8
4 3
I 0 2 W
WNW NW 2
1 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
I NNW 2 0 0 0 0 0 2 TOTAL 211 13 2 0 0 0 226 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
0 0
I HOURS OF MISSING DATA: 6 I
I I
I A2. 3-6 I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 7/1/06 - 9/30/06 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 0 0 0 0 0 5 ENE 26 0 0 0 0 0 26 E 41 0 0 0 0 0 41 ESE 34 0 0 0 0 0 34 SE 32 0 0 0 0 0 32 SSE 66 0 0 0 0 0 66 S 57 3 0 0 0 0 60 SSW 17 1 0 0 0 0 18 SW 5 0 0 0 0 0 5 WSW 5 0 0 0 0 0 5 W 2 0 0 0 0 0 2 WNW 2 0 0 0 0 0 2 NW 2 0 0 0 0 0 2 NNW 2 0 0 0 0 0 2 TOTAL 297 4 0 0 0 0 301 PERIODS OF CALM(HOURS): 0 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 6 A2. 3-7
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 7/1/06 - 9/30/06 ALL DT/DZ DIRECTION:DIRIOM LAPSE:DT60M I
WIND WIND SPEED (MPH) I DIRECTION N
1-3 89 4-7 95 8-12 0
13-18 19-24 >24 0 0 0 TOTAL 184 I
NNE 49 2 0 0 0 0 51 NE ENE E
70 75 135 49 54 54 1
1 0
0 0
0 0
0 0
0 0
0 120 130 189 I
ESE SE SSE 108 104 137 15 17 30 0
0 0
0 0
0 0
0 0
0 0
0 123 121 167 I
S 161 172 23 1 0 0 357 SSW SW WSW 48 26 33 102 84 44 74 36 14 1
0 0
0 0
0 0
0 0
225 146 91 I
W 26 26 4 0 0 0 56 WNW NW 21 29 22 25 0
0 0
0 0
0 0
0 0
43 54 I
NNW 64 81 0 0 0 145 TOTAL 1175 872 153 2 0 0 2202 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
HOURS OF MISSING DATA:
0 0
6 I
I I
I I
A2. 3-8 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/06 - 12/31/06 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPIOM DIRECTION:DIRIOM LAPSE:DT60M WIND SPEED (MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 8 1 0 0 0 9 NNE 1 3 0 0 0 0 4 NE 0 7 1 0 0 0 8 ENE 0 6 0 0 0 0 6 E 0 5 0 0 0 0 5 ESE 3 0 0 0 0 0 3 SE 2 6 0 0 0 0 8 SSE 2 20 15 0 0 0 37 S 3 19 15 2 0 0 39 SSW 1 2 8 0 0 0 11 SW 1 9 8 0 0 0 18 WSW 2 23 8 4 0 0 37 W 1 18 3 0 0 0 22 WNW 0 15 8 0 0 0 23 NW 2 14 2 0 0 0 18 NNW 1 14 0 0 0 0 15 TOTAL 19 169 69 6 0 0 263 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 0 A2.4-1
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP10M 10/1/06 - 12/31/06 B DT/DZ DIRECTION:DIR1OM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3 0
4-7
.1 8-12 2
13-18 19-24 >24 0
0 0 0 TOTAL 3
I NNE 1 0 0 0 0 1 NE ENE E
1 0
0 1
0 0
1 1
0 0
0 0
0 0
0 0
0 0
3 1
0 I
1 1
0 3
6 0
0 5 -0 0
0 0
0 0
0 0
0 12 0
4 I S 1 11 9 .,2 0 23 0
1 2
8 4
6 0
.4
.3 0
1 0
0 0
0 0
12 10 10 I
'3 0 W
WNW NW 2
0 0 2 1
.3 8
3 0
0 0
0 0
0 0
0 0
0 13
.Ii 4
5 I NNW 3 3 5 0 TOTAL 14 45 47 6 0 0 112 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
HOURS OF MISSING DATA:
1 0
I 0
I I
I I
A2. 4-2 I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/06 - 12/31/06 STABILITY CLASS: C 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 2 5 1 0 0 0 8 NNE 0 3 0 0 0 0 3 NE 0 6 0 .0 0 0 6 ENE 0 6 0 0 0 0 6 E 2 2 1 0 0 0 4 ESE 2 2 0 0 0 0 4 SE 2 3 0 0 0 0 5 SSE 0 9 1 0 0 0 10 S 4 14 14 1 0 0 33 SSW 2 4 5 1 0 0 12 SW 0 4 2 2 0 0 8 WSW 0 7 ,9 6 0 0 22 W 1 1'0 14 0 0 0 25 WNW 1 4 12 1 0 0 18 NW 1 .3 2 0 0 0 6 NNW 3 2 6 0 0 0 11 TOTAL 19 84 67 11 0 0 181 PERIODS OF CALM(HOURS) 1 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 0 A2.4-3
i i
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/06 - 12/31/06 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SP1OM DIRECTION:DIR1OM LAPSE:DT60M WIND SPEED (MPH)
WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 10 38 27 0 0 0 75 NNE 4 22 12 1 0 0 39 NE 5 21 11 0 0 *0 37 ENE 10 12 1 0 0 0 23 E 9 24 0 0 0 0 33 ESE 13 29 4 0 0 0 46 SE 14 31 9 0 :0 0 54 SSE 20 44 19 0 0 0 83i S 9 66 57 4 0 0 136 SSW 0 23 51 10 0 0 84 SW 4 8 30 6 0 0 48 WSW 4 18 41 20 0 0 83 W 2 46 33 :0 0 0 81 WNW 5 41 24 0 0 0 70 NW 12 32 19 0 0 0 63 NNW 24 28 24 0 0 0 76 TOTAL 145 483 362 41 0 0 1031 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 0 I
I I
A2.4-4I I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/06 - 12/31/06 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 N 4 3 0 0 0 0 7 NNE 13 2 0 0 0 0 15 NE 8 0 0 0 0 0 8 ENE 4 7 0 0 0 0 11 E 11 8 0 0 0 0 19 ESE 21 8 1 0 0 0 30 SE 26 18 4 0 0 0 48 SSE 18 45 4 0 0 0 67 S 15 47 10 0 0 0 72 SSW 4 16 3- 0 0 0 23 SW 4 1 1 0 0 0 6 WSW 2 2 '2 0 0 0 6 W 4 2 1 0 0 0 7 WNW 8 3 0 0 0 0 11 NW 12 8 0 0 0 0 20 NNW 4 6 0 0 0 .0 10 TOTAL 158 176 26 0 0 0 360 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 0 A2.4-5
I I
SITE: AEP COOK I
,HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SPIOM 10/1/06 - 12/31/06 F DT/DZ DIRECTION:DIRIOM LAPSE:DT60M I
WIND WIND SPEED (MPH) I DIRECTION N
1-3 2
4-7 0
8-12 0
13-18 19-24 >24 0 0 0 TOTAL 2
I NNE 3 0 0 0 0 0 3 NE ENE E
5 5
11 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0 11 6
19 31 15 1
8 0
0 0
0 0
0 0
0 0
0 0
0 10 27 46 I
S 0 12 0 0 0 0 20 SSW SW WSW 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 I
W 0 0 0 0 0 0 0 WNW NW 1
2 0 0 0 0
.0 0
0 0
0 0
1 2
I NNW 3 0 0 0 0 0 3 TOTAL 99 37 0 .0 0 0 136 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
HOURS OF MISSING DATA:
1 0
0 I
I I
I I
A2. 4-6 I
I
SITE: AEP COOK HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 10/1/06 - 12/31/06 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPIOM DIRECTION*DIR10M 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 0 2 NNE 3 0 0 0 0 0 3 NE 2 0 0 0 0 0 2 ENE 6 0 0 0 0 0 6 E 17 0 0 0 0 0 17 ESE 11 0 0 0 0 0 11 SE 20 1 0 0 0 -0 21 SSE 29 1 0 0 0 0 30 S 21 4 0 0 0 0 25 SSW 3 0 0 0 0 0 3 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 1 0 0 0 0 0 1 NW 2 0 0 0 0 0 2 NNW 1I 0 0 0 0 0 1 TOTAL 118 6 0 0 0 0 124 PERIODS OF CALM(HOURS): 1 VARIABLE DIRECTION: 0 HOURS OF MISSING DATA: 0 A2.4-7
I I
SITE: AEP COOK I HOURS AT EACH WIND SPEED AND DIRECTION I
PERIOD OF RECORD:
STABILITY CLASS:
ELEVATION: SPEED:SP1OM 10/1/06 - 12/31/06 ALL DT/DZ DIRECTION:DIRIOM LAPSE:DT60M I
WIND SPEED (MPH)
I WIND DIRECTION N
1-3 20 4-7 55 8-12 31 13-18 0
19-24 >24 0 0 TOTAL 106 I
NNE 25 30 12 1 0 0 68 NE ENE E
21 25 49 36 31 39 13 2
1 0
0 0
0 0
0 0
0 0
70 58 89 I
ESE SE SSE 59 84 101 40 70 140 13 44 5 0 0
0 0
0 0
0 0
0 104 167 285 I
S 61 173 105 9 0 0 348 SSW SW WSW 11 11 9
47 30 54 73 41 64 14 31 8
0 0
0O 0
0 0
145 90 158 I
W 79 59 0 0 148 I
10 0 WNW 16 64 47 1 0 0 128 NW 31 59 26 0 0 0 116 NNW 39 53 35 0 0 0 127 TOTAL 572 1000 571 64 0 0 2207 I PERIODS OF CALM(HOURS):
VARIABLE DIRECTION:
1 0
I HOURS OF MISSING DATA: 0 I
I I
I A2.4-8 I
I
OFF-SITE DOSE CALCULATION MANUAL The Off-Site Dose Calculation Manual, PMP-6010-OSD-001, was revised during this reporting period. Copies of Revisions 20 and 21 are included as part of the report. The PORC approval and reasons for the changes are documented under procedure Approvals and on the Revision Summary form, respectively. These changes were determined to maintain the level of radioactive effluent control required by 10 CFR 20.1302, 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.
A3.0-1
Section 1 - Procedure Information-Number: PMP-6010-OSD-001 ReV. 20
Title:
OFF-SITE DOSE CALCULATION MANUAL Sec.tin 2 - Alteration Category:
El Minor Editorial Correction El Cancellation El Major Editorial Correction (Full Review) El Superseded by (list superseding procedures):
[ Minor Revision E[] Major Revision (Full Review) LI New Procedure (Full Review) e....n 3 -- Temporary Section em
........o. .........
- o............
Procedure ...
/ R.Revision:i*....-............................................................................................................................ ..................
0 N/A 0l Temporary Procedure [I Temporary Revision AR No.:
Expiration Date / Ending Activity: NNV S I........
Section a .4.......... .:.As~
- Associated i r* °...(e
~.............................................
Configuration Impact f .Assessments: . ....... ' ...................................... ............................................ ..............................
Change Driver / CDI Tracking No(s). __ N/A Section 5- Reviews:
00 - *)
Department .p U, '. - n Reviews)
(Refer to Figure 6, Determination of Required Operations EIl 0L
[1 Site Procedure Group El M E] El MTE (I&C) El N El El E-Plan El El ER El Surveillance El1 El N El Technical El El El z I...........
Section . 6~d.*v.* - Technical
- --- Review:.a....
Updated Revision Summary and Implementation Plan (if applicable) attached? 0 Yes Implementation Plan developed? If yes, AR No.: El Yes 0 N/A Are there implementation actions to be completed prior to the effective date? El Yes Z No 10 CFR 50,59 Requirements complete? Tracking No.: El Yes [E N/A Technical Reviewer: Date: d-.2--o6
..SSection e.. . . . . . . . 7Z. -.- ..R ..
Readya.... --.f..°.r.*
for . v.......
Approval:- ........................ ..................................................................... ................ .................................................. ............
Administrative Hold Status: El Released El Reissued Z N/A CR No.:
Writer: &c\ r Date: S//I/o, El Ops Manager Concurrence: NA Date:
Section 8 - Approvals:
PORC Review Required: Z Yes 10 No Mtg No.: qZ2-Approval Authority Review/Approval: ___ Date: ýZl/dC Effective Date: Q L-1-*),6 Section 9 - Follow-up Actions:
Commitment Database update requested in accordance with PMP-2350-CMS-001? El Yes 0 N/A NDM notified of new records or changes to records that could affect record retention? El Yes M N/A Office Information For Form Tracking Only - Not Pail of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 1 of I
I REVISION
SUMMARY
I Procedure No.: PMP-6010-OSD-001 Rev. No.: 20
Title:
OFF-SITE DOSE CALCULATION MANUAL I
Alteration Justification 10 CFR 50.59
+
The changes made in this revision are specific to and implement the requirements U
of 10 CFR 20 Standards for Protection Against Radiation and was prcocessed in accordance with PMP-2010-PRC-002, I
Procedure Alterations, Review, and Approval; therefore, further 10 CFR 50.59 review is not applicable. Review is I
governed by 12-EA-6090-ENV- 114, Effectiveness Review for ODCM/PCP Programs.
I Section 2, added Term 'B' for at least once per 24 month.
ITS changed RMS frequency from 18 months to 24. CR 05343039 determined it was acceptable to do Non Tech Spec RMS I
monitors also. This is a change.
3.1.1 .c, Q* term, added clarifying Explicitly listed use reference procedure that I information for where determining quantities directs quantification activities. Editorial equations reside.
3.3.2.a Note added information linking correction criteria n.
This is an alteration to ensure Emergency I
changes to these formulas to 10 CFR 50.54 Plan review for potential impact from IN 5-(q) review by Emergency Planning. 19 (CR 06003033) evaluation. Editorial correction criteria n.
I 3.5.2.a.3 & 4 Formatted conditional If, Then Complies with PMP-2010-PRC-001, Att 2, statements correctly and added special report step 2.2. NUREG-1301 reporting criteria.
submission for exceedences. Editorial correction criteriaj.
I 3.8.1 .a, Changed Environmental Operating Report due date from May 1 to May 15 and REMP program owner has decided to take advantage of the additional 15 'days allowed I added link to reference and Tech Spec. by ITS 5.6.2. Linked reference per PRC-001, step 3.11.1 based on reviewer comment. Editorial correction criteria n. I 3.8.2.a, Added link to reference and Tech Linked reference per PRC-001, step 3.11.1 Spec. based on reviewer comment. Editorial correction criteria n.
I Att 3.2, added item 4.d and Action 5 to allow for maintaining radiation monitor operable and verifying flow within To allow flexibility desired by! Operations Department personnel in maintaining RMS monitors operable when appropriate. CR I
appropriate range 05338009. This is a change.
I Office Informationfor Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 1 of 3 I
I
REVISION
SUMMARY
Procedure No.: PMP-6010-OSD-001 Rev. No.: 20
Title:
OFF-SITE DOSE CALCULATION MANUAL Alteration Justification Att 3.2, Actions 2, 3 & 4, and Att 3.4, Clarification from action allowed by step Action 9, added clarifying verbiage 3,8.2c. CR 06051051. Editorial correction providing guidance on what actions are criteria q.
necessary if 30 or 14 day time limit is exceeded.
Aut 3.2, + footnote, added clarifying Information from Surveillance Program information pertaining to ensuring owner questioning whether all monitors are operability criteria is met prior to fulfilling being kept up to date as far as surveillance applicability criteria. requirements go. This is to ensure that this is considered prior to switching to different monitor. Editorial correction criteria p.
Att 3.3 changed items 1, 2 and 4 and Att 3.5 ITS changed RMS frequency from 18 items 1 through 5, calibration frequency months to 24. CR 05343039 determined it from 18 month, refueling cycle to 24 month. was acceptable to do other RMS monitors also. This is a change.
Att 3.4 item 3 & 4, added ** and footnote of Clarification from action allowed by Att 3.4, same designation clarifying that Action 9. Editorial correction criteria q.
compensatory duplicate sampling is allowed for containment purge as well as any other identified batch releases.
Att 3.4, Notation 2, added clarifying Clarification that-includes verbiage that is information describing actions for switching implementing procedures. Editorial from ventilate mode to clean-up mode after correction criteria q.
initial clean-up purge is complete Att 3.5, items 3 a, b and 4 a Channel check, Containment monitors (a & b) don't actually removed ** designation from these items. have releases so the designation was not appropriate. 4.a is for the check to be performed prior to the release, not during.
This is a change.
Att 3.16 Added clarifying word 'TO' with Response to Tech reviewer comment.
sector. Editorial correction criteria p.
Att 3.19 Groundwater Sample Stations and Added this well to improve monitoring Att 3.22 map, added W-15. capability. CR 06058026. This is a change.
Att 3.21 Added Conditional statement Clarifying information pertaining to required clarifying what sort of reporting is required. reporting detail. Editorial correction criteria p.
Office Informationfor Form Tracking Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 2 of 3
I REVISION
SUMMARY
U Procedure No.: PMP-6010-OSD-001 Rev. No.: 20
Title:
OFF-SITE DOSE CALCULATION MANUAL I
Alteration Justification Att 3.22, Added W-15 referenced in Att 3.19. No marginal marking used on this Added this well to improve monitoring capability. CR 06058026. This is a change.
I map. _
I I
I I
I I
I I
I I
I I
Office Informationfor Form Tracking Only - Not Partof Form I
This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 3 of 3 I
I
FOWR PMP-6010-OSD-001 Rev. 20 Page 1 of 87 OFF-SITE DOSE CALCULATION MANUAL Reference Doug Foster John Carlson Environmental Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PURPOSE AND SCOPE .............................................................................. 4 2 DEFINITIONS AND ABBREVIATIONS ..................................................... 4 3 DETAILS ................................................................................................ 5 3.1 Calculation of Off-Site Doses ................................................................. 5 3.1.1 Gaseous Effluent Releases ..................................................... 5 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 ................................................................ 16
- a. Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge ........................ ............................. 16
- b. Concentration of Releases from the TRS Discharge .................... 16
- c. Dose .......................................................................... 17
- d. Liquid Radwaste Treatment System ..................................... 17 3.2.4 Gaseous Effluents .................. . ........................ 20
- a. Dose Rate ..................... .............................................. 20
- b. Dose - Noble Gases ....................................................... 20
- c. Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form ........................................................ 20
- d. Gaseous Radwaste Treatment ............................................ 21 3.2.5 Radioactive Effluents - Total Dose .............................................. 23 3.3 Calculation of Alarm/Trip Setpoints ................................................. 24 3.3.1 Liquid Monitors ......... ....................................................... 25
- a. Liquid Batch Monitor Setpoint Methodology ............................ 25
- b. Liquid Continuous Monitor Setpoint Methodology.................. 26 3.3.2 Gaseous Monitors .............................................................. 28
- a. Plant Unit Vent ............................................................. 28
- b. Waste Gas Storage Tanks ................................................ 31
- c. Containment Purge and Exhaust System ............................... 31
- d. Steam Jet Air Ejector System (SJAE) .................................. 32
ELct PMP-6010-OSD-001 Rev. 20 Page 2 of 87 OFF-SITE DOSE CALCULATION MANUAL Reference I Doug Foster John Carlson Environmiental Writer Owner Cognizant Organization
~I
- e. Gland Seal Condenser Exhaust .............................. 33 3.4 Radioactive Effluents Total Dose...................................... 33 3.5 Radiological Environmental Monitoring Program (REMP) .............. 33 3.5.1 Purpose of the REMP ........................................... ...... 33 3.5.2 Conduct of the REM P ............................................................ 34 3.5.3 Annual Land Use Census .................................... ........ 36 3.5.4 Interlaboratory Comparison Program ...................... 37 3.6 Radioactive Equipment Storage Facility (Mausoleum) Groundwater Monitoring Program ........................................................ ....... 37 I 3.6.1 Purpose of the Radioactive Equipment Storage Facility (Mausoleum)
Groundwater Radiological Monitoring Program ................... 37 3.6.2 Conduct of the Radioactive Equipment Storage Facility (Mausoleum)
Groundwater Radiological Monitoring Program ..... .......... 38 3.7 Meteorological Model .............................................. 38 3.8 Reporting Requirements ................................................................. 38 3.8.1 Annual Radiological Environmental Operating Report (AREOR) ..... 38 3.8.2 Annual Radiological Effluent Release Report (ARERR) ................. 39 3.9 10 CFR 50.75 (g) Implementation ................................. 41 3.10 Reporting/Management Review ................................. 41 4 FINAL CONDITIONS ........................................................................ 41 3 5 REFERENCES ........................................................................................ 42 SUPPLEMENTS .1 Dose Factors for Various Pathways .............................................. Pages 44 - 47 .2 Radioactive Liquid Effluent Monitoring Instruments ........ Pages 48 - 50 .3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ............................................................ Pages 51 - 52 I .4 Radioactive Gaseous Effluent Monitoring Instrumentation ........... Pages 53 - 55 I
Pawn PMP-6010-OSD-001 Rev. 20 Page 3 of 87 OFF-SITE DOSE CALCULATION MANUAL Reference Doug Foster John Carlson Environmental Writer Owner Cognizant Organization .5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements ........................................ ................... Pages 56 - 57 .6 Radioactive Liquid Waste Sampling and Analysis Program ........ Pages 58 - 59 .7 Radioactive Gaseous Waste Sampling and Analysis Program ..... Pages 60 - 61 .8 Multiple Release Point Factors for Release Points ................................ Page 62 .9 Liquid Effluent Release Systems ........................... Page 63 .10 Plant Liquid Effluent Parameters .......................................................... Page 64 .11 Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors .......................... Page 65 .12 Counting Efficiency Curves for R-19, and R-24 .......... ................ Pages 66 - 67 .13 Counting Efficiency Curve for R-20, and R-28 ..................................... Page 68 .14 Gaseous Effluent Release Systems ............................. ..................... Page 69 .15 Plant Gaseous Effluent Parameters ........................................................ Page 70 .16 10 Year Average of 1995-2004 Data ............................................ Pages 71 - 72 .17 Annual Evaluation of ,/Q and D/Q Values For All Sectors ........ Page 73 .18 D ose Factors .......................... ................... I................................... Pages 74 - 75 .19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies ............................... Pages 76 - 79 .20 Maximum Values for Lower Limits of Detections 'B - REMP ..... Pages 80 - 81 .21 Reporting Levels for Radioactivity Concentrations in Environm ental Samples .......................................................................... Page 82 .22 On-Site Monitoring Location - REMP ................................................. Page 83 .23 Off-Site Monitoring Locations - REMP ................................................ Page 84 .24 Safety Evaluation By The Office Of Nuclear Reactor R egulation ...................................................................................... Pag es 85 - 87
I Reference 7' PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 !Page 4of 87 I
1 PURPOSE AND SCOPE I NOTE: This is an Administrative procedure and only the appropriate .sections need be I
performed per PMP-2010-PRC-003, step 3.2.7.
The Off-Site Dose Calculation Manual (ODCM) is the top tier document for I
the Radiological Environmental Monitoring Program (REMP), heý Radioactive Effluent Controls Program (RECP), contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as I
defined in NUREG-0472, and fully implements the requirements of Technical Specification 5.5.3, Radioactive Effluent Controls Prolgram.
I 0 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. I The ODCM provides flow diagrams detailing the treatment path and the major components of the radioactive liquid and gaseous waste management systems. I The ODCM presents maps of the sample locations and the meteorological model used to estimate the atmospheric dispersion and deposition parameters. I The ODCM specifically addresses the design characteristics of the Donald C. Cook Nuclear Plant based on the flow diagrams contained on the "OP Drawings" and plant "System Description" documents.
I 2 DEFINITIONS AND ABBREVIATIONS I Term:
S or shiftly D or daily Meaning:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
W or weekly M or monthly Q or quarterly At least once per 7 days At least once per 31 days At least once per 92 days I
SA or semi-annually At least once per 184 days R
S/U At least once per 549 days.
Prior to each reactor startup I
P Completed prior to each release B
Sampling evolution
-At least once per 24 months Process of changing filters or obtaining grab samples I
I I
I
Reference .PMP-6010-OSD-001. Rev. 20 Page 5 of 87 OFF-SITE DOSE CALCULATION MANUAL Member(s) of All persons who are not occupationally associated with the Public plant. Does not include employees of the utility, its contractors or its vendors. Also excluded from this .category are persons who enter the site to service equipment or to
-make deliveries. This category does include persons who*use portions of the site for recreational, occupational or other purposes not associated with the plant.
Purge/purging The controlled process of discharging air or gas from a confinement to maintain temperature, pressure; humidity, concentration or other operating condition, in'such a manner that replacement air or gas is required to purify the confinement.
Source check The qualitative .assessment of Channel response when the Channel sensor is exposed to a radioactive source.
Venting Controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required.
Vent, used in system:names, does not imply a venting process.
3 DETAILS 3.1 Calculation of Off-Site Doses 3.1.1t Gaseous Effluent Releases
- 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 MD1EQ (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 inReg. Guide 1.21 reports and 10 CFR 50 Appendix I calculations based on routine releases.
I Reference 7 PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL
_ Rev. 20 Z
Page 6 of 87 I
- c. The formula used for the calculation of the air dose is generated from site specific parameters and Reg. Guide 1.109 (Eq 7):
I Dr, Dp air = , ,[(Mi or N,)
- Qj
- 3.17E - 8] I Q
Where; I D, Dp air the gamma or beta air dose in mrad/yr to an X"/Q =
individual receptor the annual average or real time atmospheric I
dispersiofi factor over land, sec/m 3 from Attachment 3.16, .10 Year Average of 1995-2004 Data I
M = the gamma air dose factor, mrad m3 from Attachment 3.18, Dose Factors 1r pCi, I
N = the beta air dose factor, mrad m' / yr jACi, from Attachment 3.18, Dose Factors Qi the release rate of radionuclide, "i", in ItCi/yr.
Quantities are determined utilizing typical concentration times volumes equations that are documented in 12-THP-6010-RPP-606, Preparation of the Annual Radioactive Effluent I
Release Report.
3.17E-8 number of years in a second (years/second). I
- d. The value for the ground average ; / Q for each sector is calculated using equations shown below. Formula used for the calculation is generated from parameters contained in MIDAS Technical ,Manual, I
XDCALC (Eq 2).
2.03 I
/Q= umg *x*zg.*T Where; I
Xg minimum of 7,-, +- or Xg=xTF-c, I x = distance downwind of the source, meters. This information is found in parameter 5 of MIDEX. I u., wind speed for ground release, (meters/second)
I
Reference PMP-6010-OSD-001 O Rev. 20 Page 7 of 87 OFF-SITE DOSE CALCULATION MANUAL a" * = vertical dispersion coefficient for ground release, (meters),
(Reg. Guide 1.111 Fig. 1)
Hc = building height (meters) from parameter 28 of MIDER.
(Containment Building = 49.4 meters)
Tf = terrain factor (= 1 for Cook Nuclear Plant) because we consider all our releases to be ground level (see parameter 5 in MIDEX).
2.03 = -+v +0.393radians(22.5°)
- 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 pathways-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 MIDEG file.
- 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 (mrer/year)= 3.1 7E -8* (Q */Q*sf *DFBi)
Where; Sf= shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy (maximum exposed individual = 0.7 per TableE-15 of Reg. Guide 1.109)
DFB= the whole body dose factor from Table B-1 of Reg.
Guide 1.109, mrem - m3 per liCi - yr. See Attachment 3.18, Dose Factors.
Qi= the release rate of radionuclide "i", in uCi/yr
- 2. Skin Plume Pathway (Eq 11)
Reference PMP-6010-OSD-001 Rev. 20 t Page 8 of 87 I
OFF-SITE DOSE CALCULATION MANUAL' I
Dose(mrem/yr) 3.17E-8" Sf* , [((Q, 1.11DF0+ X(Q,*DFS,)] I Where;'
I 1.11 = conversion factor, tissue to air, mrem/mrad I
DF *' the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", in mrad m34/Ci yr from Table B-I, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.
I DFSi = the beta skin dose factor for a semi-infinite cloud of radionuclide "iP, in mrem m 34/Ci yr from Table B-i, I
Reg. Guide 1.109. See Attachment 3.18, Dose Factors. I
- 3. Radionuclide.and Radioactive Particulate Doses (Eq 13 & 14)
The dose, Dip in mrem/yr, to an individual from radionuclides, other I
than noble.gases, with half-lives greater than eight days iný gaseous effluents released to unrestricted areas will be determined !'as follows: I DiP (mrem/year)=3.1 7E - 8 "*(R,*W
- Q)
Where; I R = the most restrictive dose factor for each identified radionuclide "i", in m 2 mrem sec / yr 1iC~i (for food and ground pathways) or mrem mI3 yru.Ci (for inhalation pathway), for the appropriate pathway I
For sectors with existing pathways within five miles of the site, use the values of R, forthese real I
pathways, otherwise use pathways distýncel of five miles. See Attachment 3.1, Dose'Factors for Various Pathways, for the maximum %-values for I
the most controlling age group .for selected radionuclides. Ri values were generated by computer code PARTS, see NUREG-0133, I Appendix D.
W = the annual average or real time atmospheric dispersion parameters -for estimating doses to an I
individual at the worst case location, and where W is further defined as: I
" /Q for the inhalation pathway, in sec/n 3
=Wi.
-OR- I I
Reference PMP-6010-OSD-001 Rev. 20 Page 9 of 87 OFF-SITE DOSE CALCULATION MANUAL Wfg = D /Q for the food and ground pathways in 2
1/M Qi. = the release rate of those radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days, in A.Ci/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 maximum of the 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 monthly reports 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 performed to determine the amount of curies released through this pathway. (Plant established formula.)
Curies = CCi
- GPM
- time on flash tank (min)
- 3. 785E - 3 ml Where; 3.785E-3 = conversion factor, ml Ci//tCi 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 Releases, to calculate doses to members of the public.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 10 of 87 I
I 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 -tank was in service.
I
- 5. The radioiodine release rate must be determined in accordance with
- the following equation every 31 day period whenever the specific I
activity of the secondary coolant system is greater than 0.01 [Ci/g dose equivalent 1-131.
I
- 6. IF the specific activity of the secondary coolant system is less than 0.01 tLCi/g dose equivalent 1-131, THEN the release rate must be determined once every six months. Use the following plant I established equation:
Y Q=Ci* IPF* Rsb I Where; Qy = the release rate of 1-131 from the steam generator flash tank vent, in ICi/sec I Ci = the concentration (pCi/cc) of 1-131 in the secondary coolant averaged over a period not exceeding seven days I 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 I 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 I
of Operation and Surveillances of the Effluent Release Points, dose limits. Report the release rate calculations in the Annual Radioactive Effluent Release Report.
I 3.1.2 Liquid Effluent Releases I
- 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 MD1EB (EB).
I
- b. To calculate the individual dose (mrem), the program DS1LI (LD) is used. -It computes the individual dose for up to 5 receptors for 14 liquid I 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).
I I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 11 of 87 OFF-SITE DOSE CALCULATION MANUAL
- c. Steam Generators are sparged, sampled, and drained as batches usually early in outages to facilitate cooldown for entry into the steam generator.
This is typically repeated prior to startup to improve steam generator chemistry for the startup. The sample stream, if being routed to the operating unit blowdown, is classified as a continuous release for quantification purposes to maintain uniformity with this defined pathway.
- d. The equations used are generated from site specific data and Reg. Guide 1.109. They are as follows:
- 1. Potable Water (Eq 1)
Rw,=llO0 UP , Q* Dapj eA, Mp*F*2.23E-3 Where; RIpi the total annual dose to organ "j" to individuals of age groups "a" from all of the nuclides "I" in pathway "p",
in mreml/year 1100 = conversion factor, yr ft3 pCi / Ci sec L Uap = a usage factor that specifies the exposure 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 of harvest of aquatic food). Given in parameter 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, ft' min / sec gal Qi = the release rate of nuclide "i" for the time period of the run input via MIDEB, Curies/year Daipj = 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, in mrem/pCi. These values are taken from tables E-11 through E-14 of Reg. Guide 1.109 and are located within the MIDAS code.
X = the radioactive decay constant for radionuclide "i", in hours-'
Reference PMP-6010-OSD-001 Rev. 20 Page 12 of 87.
I OFF-SITE DOSE CALCULATION MANUAL I
tp =the average transit time required for nuclides to reach the point of exposure; 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This allows for nuclide I
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 I
ingestion of food or water, in hours. Given as #25 of parameter 4 in MIDEL. (tp = 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) I
- 2. Aquatic Foods (Eq 2)
Rapj 1 100, Up *Ia Bip Do,j e-Adl I Mp*F*2.23E-3 I Where, I Bip =the equilibrium bioaccumulation factor for nuclide "i" in pathway "p", expressed as pCi L / kg pCi. The factors are located within the MIDAS code and are taken from Table A-1 of Reg. Guide 1.109. See Attachment 3. 1, I
tp, Dose Factors for Various Pathways.
=the average transit time required for nuclides toý reach the I
point of exposure, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows for decay during transit through the food chain, as well as during food preparation. Given as #26 of parameter 4 in I MIDEL. (tp = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
Mp =='the dilutionfactor at the point of exposure, 1.0 for Aquatic Foods. Given in parameter 5 of MIDEL as 1.0.
I
- 3. Shoreline Deposits (Eq 3)
Rpj:=110000* U*p*W ,
- zQT," [ al, [I -Yb I
Mp*F*2.23E-3 D I
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.
I Ti" = the radioactive half-life of the nuclide, "i", in days D.ipj = the dose factor for standing on contaminated ground, in I
mrem m2 I hr pCi. The values are taken from table E-6 of Reg. Guide 1.109 and are located within the MIDAS code.
See Attachment 3.1, Dose Factors for Various Pathways.
I t = the period of time for which sediment or soil is exposed to the contaminated water, 1.31E+5 hours. Given in I MIDEL as item 6 of parameter 4.
I I
Reference T PMP-6010-OSD-001 I Rev. 20 Page 13 of 87 OFF-SITE DOSE CALCULATION MANUAL tp = the average transit time required for nuclides to reach the point of exposure, 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Given as #28 of parameter 4 in MIDEL.
110,000 conversion factor yr ft3 pCi / Ci sec m' 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 drinking water or point of harvest of aquatic food). Given in parameter 5 of MIDEL as 2.6.
- e. The MIDAS program uses the following plant specific parameters, which are entered by the operator.
- 1. Irrigation rate = 0
- 2. Fraction of time on pasture = 0
- 3. Fraction of feed on pasture = 0
- 4. Shore width factor = 0.3 (from Reg. Guide 1.109, Table A-2)
- f. The results of DS1LI are printed in LDRPT (LP). These results are used in the monthly report of liquid releases.
g& In addition, the prograrm DOSUM (DM) is used to search the results files of DS1LI 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.
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 alarm/trip 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.
Reference 7 PMP-6010-OSD-001 - Rev. 20 T Page 14 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
- c. With a radioactive liquid effluent monitoring instrumentation channel alarmltrip setpoint less conservative than a value which will ensure the I
limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are met without delay, suspend the release of radioactive liquid effluents monitored by the affected channel I
and reset or declare the monitor inoperable.
- d. With one or more radioactive liquid effluent monitoring instrumentation I
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, excluding the initial performance.
I
- e. Determine the setpoints in accordance with the methodology described in step 3.3.1, Liquid Monitors. Record the setpoints.
I
- f. Demonstrate each radioactive liquid effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL I
OPERATIONAL TEST at the frequencies shown in Attachment 3.3, Radioactive Liquid EffluentMonitoring Instrumentation Surveillance Requirements.
I BASES - LIQUID I
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential I
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 occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in I
Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
Due to the location of the Westinghouse ESW monitors, outlet line of containment spray heat exchanger (typically out of.service), weekly sampling is required of the ESW "system I
for radioactivity. This is necessary to ensure monitoring of a CCW to ESW system leak.
[Ref 5.2. lgg] I 3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation
- a. The radioactive gaseous process and effluent monitoring instrumentation I
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.
I
- b. The applicability of.each channel is shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation. I I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 15 of 87 OFF-SITE DOSE CALCULATION MANUAL
- c. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less 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 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, 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 performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Attachment 3.5, Radioactive Gaseous Effluent Monitoring Instrumentation' Surveillance Requirements.
BASES - GASEOUS The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. 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 occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
Reference I PMP-6010-OSD-001 I Rev. 20 Page 16 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
3.2.3 Liquid Effluents I
- a. Concentration Excluding Releases via the Turbine Room Surmp (TRS)
Discharge
- 1. Limit the concentration of radioactive material released via the Batch I
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 I
radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, limit the concentration to 2E4 gCi/ml total activity.
I
- 2. With the concentration of radioactive material released from the site via the Batch Release Tanks or Plant Continuous Releases ýl (other than the TRS to the Absorption Pond) exceeding the above limits; I
3.
without delay restore the concentration to within the above limits.
Sample and analyze radioactive liquid wastes according to the I
sampling and analysis program of Attachment 3.6, Radioactive 4.
Liquid Waste Sampling and Analysis Program.
Use the results of radioactive analysis in accordance with the I
methods of this document to assure that all concentrations at the point of release are maintained within limits. I
- b. Concentration of Releases from the TRS Discharge
- 1. Limit releases via the TRS discharge to the on-site Absorption Pond I to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, limit the concentration to 2E-4 ACi/ml total activity. I
- 2. With releases from the TRS exceeding the above limits, perform a dose projection due to liquid releases to UNRESTRICTED AREAS to determine if the'limits of step 3.2.3c. 1 have been exceeded. If I
the dose limits have been exceeded, follow the directions in step 3.
3.2.3c.2, as applicable.
Sample and analyze radioactive liquid wastes according to the I
program in Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program. I
- 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. I I
I I
Reference PMP-6010-OSD-001 I Rev. 20 T Page 17 of 87 OFF-SITE DOSE CALCULATION MANUAL
- 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, _<1.5 mrem/unit to the total body and
-to _<5 mremlunit to any organ, and during any calendar year to < 3 rmremrlunit to the total body and to _<10 mrem/unit to any organ.
- 2. With the calculated release of radioactive materials in liquid effluents exceeding ten times any of the limits in Steps 3.2.3a or 3.2.3b, or exceeding 3.2.3c.1 above, prepare and submit a Written Report, pursuant to 10 CFR 20.2203, within 30 days after learning of the 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. This is to include the radiological impacts on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinling Water Act (applicable due to Lake Township water treatment facility),
b) Levels of radiation and concentration of radioactive material involved, c) Cause of elevated exposures, dose rates or concentrations,
-AND-d) Corrective steps taken or planned to ensure against recurrence, including schedule for achieving conformance with applicable 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 an 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 current or future plant conditions.
- d. Liquid Radwaste Treatment System
- 1. Use the liquid radwaste treatment system to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site when averaged over 31 days, would exceed 0.06 mnrem/unit to the total body or 0.2 mrem/unit to any organ.
- 2. Project doses due to liquid releases to UNRESTRICTED AREAS at least once per 31 days, in accordance with this document.
Reference PMP-6010-OSD-001 Rev. 20 Page 18 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
- 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 I
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 I
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 I
NBAE distillate.
Drainage of high conductivity water (Component Cooling Water and ice melt water containing sodium tetraborate) shall be evaluated to ýdecide I
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 I
minimize the detrimental affect that high conductivity water has on the radioactive wastewater demineralization system. The standard concentration and volume equation can be utilized to determine the I
impact on each method and is given here. The units for concentration and volume need to be consistent across the equation:
(C)V)+ (co-vo) =(c,)(vI)
I Where; I Ci = the initial concentration of the system being added to Vi Ca Va
= the initial volume of the system being added to
= the concentration of the water that is being added !tothe system
= 'the volume of the water that is being added to the![system I
C, Vt
= the final concentration of the system after the addition
= the final volume of the system after the addition I The intent is'to keep the:
WDS below 500 ýtmhos/cc.
I
- Monitor Tank release ALARA to members of the public.
Wastewater leakage into the liquid waste disposal system will be I
monitored routinely. In the event the leak rate is determined to be over two gallons per minute (the assumed plant design leakage based on the original 2 gpm waste evaporator), increased scrutiny Will be placed on I locating inleakage, timeliness of job order activities, and/or activities causing increased production of waste water.
I I
I I
Reference - PMP-6010-OSD-001 Rev. 20 Page 19 of 87 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 limitation 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 I.A design objectives of Appendix I, 10 CFR Part 50, to an individual and 2) the limits of 10 CFR Part 20. The concentration 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 Commission on Radiological Protection (ICRP) Publication 2.
DOSE This specification is provided to implement the requirements of Sections H.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits implement the guides set forth in Section IL.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure the releases of radioactive material in liquid effluents will be kept "as low .as is reasonably 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 the facility 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 III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of 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 I", 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 I", 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.
LIQUID 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 implements 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 IL.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
Reference PMP-6010-OSD-001 Rev. 20 Page 20 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
3.2.4 Gaseous Effluents I
- a. Dose Rate I
- 1. 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 I
form and radionuclides (other than noble gases) with half-lives greater than eight days to < 1500 mrem/yr to any organ. I
- 2. With the dose rate(s) exceeding, the above limits, without delay 3.
decrease the release rate to within the above limit(s).
Determine the dose rate due to noble gases in gaseous effluents to be I
within the above limits in accordance with'the methods and 4.
-procedures described in this document.
Determine the dose rate due to radioactive materials, other than I
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 I
accordance with the sampling and analysis program in Attachment b.
3.7, Radioactive Gaseous Waste Sampling and Analysis Program.
Dose - Noble Gases I
- 1. Limit the air dose in unrestricted .areas due to noble gases released in gaseous effluents during any calendar quarter, to < 5 mrad/unit for gamma radiation and < 10 mrad/unit for beta radiation and during' I
any calendar year, to < 10 mrad/unit for gamma radiation and _*20 mrad/unit for beta radiation. I
- 2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding 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 of the event.
I
- 3. Determine cumulative and projected dose contributions for the total time period in accordance with this document at least once every 31 days. I
- c. Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form. I
- 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 than -eight days in gaseous effluents released to unrestricted areas (site boundary) to the following:
I a) During any calendar quarter to less than or equal to 7.5 mrem/unit to any organ I
b) During any calendar year to less than or equal to 15 mrem/unit to any organ. I I
Reference PMP-6010-OSD-001 Rev. 20 Page 21 of 87 OFF-SITE DOSE CALCULATION MANUAL
- 2. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding 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 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 Treatment
- 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/unit for gamma radiation and 0.4 mrad/unit for beta radiation. Use the ventilation exhaust treatment system to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days would exceed 0.3 mrem/unit to any organ.
- 2. Project doses due to gaseous releases to UNRESTRICTED AREAS at least once per 31 days in accordance with this document.
BASES -- GASEOUS EFFLUENTS.
This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an unrestricted area, either at or beyond the site boundary in excess of the design objectives of appendix I to 10 CFR 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II.C design objectives of appendix I to 10 CFR 50.
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 < 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 inhalation pathway to < 1500 mrem/yr. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR 20, Appendix B, Table 2, Column 1.
This specification applies to the release of gaseous effluents from all reactors at the site. The gaseous effluents from the shared system are, proportioned among the units sharing that system.
Reference PMP-6010-OSD-001 Rev.. 20 Page .22 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
DOSE, NOBLE GASES I This specification is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits implement the guides set forth in Section IL.B of Appendix I. I The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".
I The Surveillance Requirements implement the requirements in Section III.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 -
U 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 Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the U
Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",
I 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. I DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES I This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix 1,-10 CFR Part 50. The dose limits are the guides set forth in Section Il.C of Appendix I. I I
I I
I I
I I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 23 of 87 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 rV. 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 ODCM calculational methods specified in the surveillance requirements implement the requirements in Section IH.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, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, July 1977. These equations also 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 gaises, 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.
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 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section H1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guides forth in Sections R.B and II.C of Appendix 1, 10 CFR Part 50, for gaseous effluents.
3.2.5 Radioactive Effluents - Total Dose
- a. 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.
- b. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of steps 3.2.3c (Dose), 3.2.4b (Dose - Noble Gases), or 3.2.4c (Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form) during any calendar quarter, perform the following:
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 24 of 87 I
0 Investigate and identify the causes for such release rates; I 0 Define and initiate a program for corrective action; 0 Report these actions to the NRC within 30 days from the end of the quarter during which the release occurred. I 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 report a request for a U
variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190*11(b). Submittal of the report is considered a timely request, and a variance is granted until staff I
action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR 50, as addressed in other sections of this document.
I c.. Determine cumulative dose contributions from liquid and gaseous effluents in accordance with this document (including steps 3.2.3c I
[Dose], 3.2.4b [Dose - Noble Gases], or 3.2.4c [Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form]).
I BASES -- TOTAL, DOSE, This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from I
plant radioactive effluents exceed twice the design objective doses of Appendix I. iFor 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 remain within 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 1-90 limits. For the purposes-of the Special Report, it may be assumed that the dose I
commitment to 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 is I estimated 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 190.11), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.
I 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 3.3 Calculation of Alarm/Trip Setpoints The alarm and trip setpoints are to provide monitoring, indication, and control of liquid 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 monitors. Depending on the monitor function, it would be a continuous or batch monitor. The different types of monitors are subject to I
different setpoint methodologies.
I I
Reference 7 PMP-6010-OSD-001 Rev. 20 Page 25 of 87 OFF-SITE DOSE CALCULATION MANUAL 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 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 arbitrary, and it should be assigned based on operational performance. The values of the MRP's for each liquid release point are given in Attachment 3.8, Multiple Release Point Factors for Release Points.
The Site stance on instrument uncertainty is taken from l-PPOS-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 not be considered.
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. A list 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 function of these monitors is to act as a check on the sampling program. The sampling 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 of nuclides 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 NUREG-0133:
KE LIMITi _i MRP _<r+f
Reference PMP-6010-OSD-001 Rev. 20 Page 26 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
Where; I Ci = the concentration of nuclide "i" in j.Ci/ml LIMITi = the 10 CFR 20, Appendix B, Table 2, Column 2 limit of nuclide "i" in gCi/mI I
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.
I The dilution flow rate is a multiple of 230,000 gpm depending on the number of circulation pumps in operation.
MRP = the multiple release point factor. A factor such that I
when all the release points are operating at one ltime the 4.
limits of 10 CFR 20 will not be exceeded.
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 I
limits of operation. If the equation is not true, the effluent flow rate can be reduced or the dilution flow rate can be increased to make the equation true. .This equation may be rearranged to solve for the I 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 I
reading is greater than the predicted value from the sampling program. The predicted value is generated by converting the effluent concentration for each gamma emitting radionuclide to I
counts per unit of time as per Attachment 3.11, Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors, or Attachment 3.12, Counting I 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 determine the high alarm setpoint that will provide a high degree of conservatism and I
eliminate spurious alarms.
- b. Liquid Continuous Monitor Setpoint Methodology I
- 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 I
service water (ESW) systems.
- 2. These Westinghouse monitors (R) are being replaced by Eberline I
monitors (DRS) and are identified as:
R-19 or DRS 3100/4100 for SGBD R-24 or DRS 3200/4200 for BDT I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 27 of 87 OFF-SITE DOSE CALCULATION MANUAL 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 following dilution.
- 3. The monitors on steam generator blowdown and blowdown treatment systems have trip functions associated with their setpoints.
Essential service water monitors are equipped with an alarm function only and monitor effluent in the event the Containment Spray Heat Exchangers are used.
- 4. The equation used to determine the setpoint for continuous monitors is from Addendum AA1 of NUREG-0133:
C**Eff *M 7P*F*SF Where; Sp = setpoint of monitor (cpm).
C = 5E-7 iiCi/ml, maximum effluent control limit from 10 CFR 20, Appendix B, Table2, Column 2 of a known possible nuclide in effluent stream. (The limiting nuclide shall be evaluated annually by reviewing current nuclides against historical ones in order to determine if one with a more restrictive effluent concentration limit than Sr9O is
'found. The concentration limit shall be adjusted appropriately.)
-OR-if a mixture is to be specified, zCi Z.Ci LIMIT, Eff = Efficiency, this information is located in Attachment 3.11, Volumetric Detection 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:
Z((c,
- Eff,) replacesC
- Eff C'
LIMIT3, 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 for ESW monitors is set to 1.
Reference T PMP-6010-OSD-001 Rev. 20 Page 28 of 87 I
OFF-SITE DOSE CALCULATION MANUAL F = dilution water (circ water) flow rate in gpm obtained from Attachment 3.10, Plant Liquid Effluent Parameters.
For routine operation, the setpoint should be calculated using the minimum dilution flow rate of 230,000 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).
3.3.2 Gaseous Monitors For the purpose of implementing Step 3.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation, and Substep 3.2.4a, Dose Rate, the alarm setpoints for gaseous effluents released into unrestricted areas will Tbe 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.
NOTE: IF the setpoint calculation methodology changes or the associated factors change for Unit Vent, Air Ejector and/or Gland Seal monitors, THEN initiate a review by Emergency Planning to ensure that the requirements of 10 CFR 50.54 (q) are maintained..
- 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)
I 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 *MRP XLi Fp *Z/Q * (W,i DCFy) i Where; Sp = the maximum setpoint of the monitor in jiCi/cc for release point p', based on the.most limiting organ I
SF = an administrative operation safety factor, less than 1.0 MRP = 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:
a Compute the average release rate, Qp, (or the volumetric flow rate, fp) from each release point p.
0 Compute XQp (or Efp) for all release points.
a Ratio Qp/ZQp (or fp/Zfp) for each release point.
.This ratio is the MIRP for that specific release point Repeat the above bullets for each of the site's eight gaseous release points.
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 cfm for Unit 1 and 143,400 cfm for Unit 2.
DLj = dose rate limit to organ "j" in an unrestricted area (mrem/yr).
Based on continuous releases, the dose rate limits, DLj, from step 3.2.4a, Dose Rate, are as follows:
- Total Body _<500 mrem/year
- Skin < 3000 mrem/year
- Any Organ< 1500 mremlyear
, / Q = The worst case annual average relative concentration in the applicable sector or area, in sec/m 3 (see Attachment 3.16, 10 Year Average of 1995-2004 Data).
Wi= weighted factor for the radionuclide:
W Ci Z Ck Where, Ci = concentration of the most abundant radionuclide "i" Ck = total concentration of all identified radionuclides in that release pathway. For batch releases, this value may be set to 1 for conservatism.
Reference PMP-6010-OSD-001 I Rev. 20 1 Page 30 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
DCFij = dose conversion factor used to relate'radiation dose to organ "j", from exposure to I
radionuclide "i" in mrem m3 / yr ptCi. See following equations.
The dose conversion factor, DCFij, is I
dependent upon the organ of concern.
For the whole body: - DCF* = K I Where; K = whole body dose factor due to gamma emissions for each identified noble gas I radionuclide in mrem m3 / yr pLCi. See Attachment 3.18, Dose Factors.
For the skin: DCFj = L1 + 1.1Mi I
Where; L = skin dose factor due to beta emissions for each identified noble gas radionuclide, in I
mrem m3 / yr .iCi. See Attachment 3.18, Dose Factors.
1.1 = the ratio of tissue to air absorption I
coefficient over the energy range of photons of interest. This ratio converts absorbed dose (mrad) to dose equivalent (mrem). I
= the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad m 3 / yr p.Ci. See I Attachment 3.18, Dose Factors.
For the thyroid, via inhalation:
Where; DCFj.= PA I
PA = the dose parameter, for radionuclides other than noble gas, for the inhalation pathway in mrem M 3 / yr tiCi (and the i
food and ground path, as appropriate).
See Attachment 3.18, Dose Factors.
2.. The plant vent radiation monitor low range noble gas high alarm I
channel setpoint, Sp, 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 I
mrem/yr, 3000 mrem/yr, and 1500 mrem/yr respectively.
3.. The thyroid dose is limited to the inhalation pathway only. I
- 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 I the plant vent to determine the most limiting organ.
i I
Reference PMP-6010-OSD-001 Rev. 20 Page 31 of 87 OFF-SITE DOSE CALCULATION MANUAL
- 5. The high alarm setpoint, Sp, may be established at a lower value than the lowest computed value via the setpoint equation.
- 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 (/pCi/cc)
- Max Flowrate (cfm) - New Max cfm (pCi/cc)
New Max Concentration
-OR-Max Conc (/uCi/cc)
- Max Flowrate (cfin) New MaxuCi/cc New Max Flowrate(cfm)
- 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.
- 2. In the event of a high radiation alarm, 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 setpoint 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
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 32 of 87 I
- 1. The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust I
System are-monitored by the plant vent radiation monitor noble gas channels (VRS-1505 for Unit 1, VRS-2505 for Unit 2); and alarms and trip actions will occur prior to exceeding the limits in step I
2.
3.2.4a, Dose Rate.
For the Containment System,- a continuous air sample from the I
containment atmosphere is. drawn through a closed, sealed 'system to the radiation monitors (Tag No. ERS-1300/1400 for Unit 1 and ERS-2300/2400 for Unit 2). During purges, fhese monitor setpoints I
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 I for a Containment purge before release.
- 3. The Upper, Containment area is monitored by normal range area gamma monitors (Tag No. VRS-1101/1201 for Unit 1 and I
VRS-2101/2201 for Unit 2), which also give Purge and Exhaust 4.
Isolation Trip signals upon actuation of their high alarm.
For the Containment Pressure Relief System, no sample is "routinely I
5.
taken priorto release, but a sample is obtained twice per month.
The containment airborne and area monitors, upon actuation of their I
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 I
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). I
- 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 I
radiation monitor (Tag No. SRA-1900 for Unit 1 and SRA-2900 for Unit 2). The monitor will alarm prior to-exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the Condenser Air I
Ejector System monitor will be based on the maximum air ejector exhaust flow rate, (Attachment 3.15, Plant Gaseous Effluent Parameters). The alarm setpoint value will be established using the I
following unit analysis equation:
= SF*MRP*DLj,- I SheAEr rXIzQ*
F, (W,*. DCFu.)
Where; 1
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 33 of 87 OFF-SITE DOSE CALCULATION MANUAL SSIAE = the maximum setpoint, based on the most limiting organ, in gCi/cc and where the other terms are as previously defined
- e. Gland Seal Condenser Exhaust
- 1. The gaseous effluents from the Gland Seal Condenser Exhaust discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1800 for Unit 1 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 monitor 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
- DLj
'SGSCE M D Fr*X1W/Q*Y(W,*DCFv)
Where; SOScE = the maximum setpoint, based on the most limiting organ, in 1 iCi/cc and where the other terms are as previously defined 3.4 Radioactive Effluents Total Dose 3.4.1 The cumulative dose contributions from liquid and gaseous effluents will be determined by summing the cumulative ,doses as derived in steps 3.2.3c (Dose), 3.2.4b (Dose -'Noble Gases), and 3.2.4c (Dose - Iodine-131, -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 radiation monitoring devices located at the REMP monitoring stations. See NUREG-0133, section 3.8.
3.5 Radiological Environmental Monitoring Program (REMP) 3.5.1 Purpose of the REMP
- a. The purpose of the REMP is to:
- Establish baseline radiation and radioactivity concentrations in the environs prior to reactor operations, a Monitor critical environmental exposure pathways,
- Determine the radiological impact, if any, caused by the operation of the Donald C. Cook Nuclear Plant upon the local environment.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL I Rev. 20 Page 34 of 87 I
- b. The first purpose of the REMP was completed prior to the initial I operation of either of the two nuclear units at the Donald C. Cook Nuclear Plant Site. The second and third purposes of the REMP are an on-going operation and as such various environmental media and exposure pathways are examined. The various pathways and sample I
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 l
required, sample stations, and frequency requirements for both collection and analysis. Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, defines I
the scope of the REMP for the Donald C. Cook Nuclear Plant.
3.5.2 Conduct of the REMP [Ref. 5.2. lu] I
- a. Conduct sample collection and analysis for the REMP in accordance with Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, Attachment 3.20, I
Maximum Values for Lower Limits of DetectionsA'B - REMP, and Attachment 121, Reporting Levels for Radioactivity Concentrations in Environmental Samples. These are applicable at all times. The on-site I monitoring locations are shown on Attachment 3.22, On-Site Monitoring
-Location - REMP, and the off-site monitoring locations are shown on Attachment,3.23, Off-Site Monitoring Locations - REMP. I
- 1. Perform each surveillance requirement within the specified time interval in Attachment 3,19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample I
Frequencies, with a maximum allowable extension not to exceed 2.
25 % of the surveillance interval.
If an environmental sample cannot be collected in accordance with I
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). I Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of automatic sampling equipment. If I
the deviation from the required sampling schedule is due to the malfunction of automatic sampling equipment, make everyý effort to complete the corrective action prior to the end of the next sampling I period.
I I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 35 of 87 OFF-SITE DOSE CALCULATION MANUAL
- 3. IF A radionuclide from plant effluents is detected in any sample medium exceeding the limit established in Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples, OR More than one radionuclide from plant effluents is detected in any sample medium AND the Total Fractional Level (TFL),
when averaged over the calendar quarter, is greater than or equal to 1, based on the following formula:
TFL =Cal) + C(2) +..>_ I La) L(2)
Where; Cui) = Concentration of V detected nuclide C(2) = Concentration of 2nd detected nuclide Lo)= Reporting Level of I' nuclide from Attachment 3.21,
- Reporting Levels for Radioactivity Concentrations in Environmental Samples.
L2, Reporting Level of 2"d nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.
THEN evaluate the release conditions, environmental factors, corrective actions, or other aspects, which may have contributed to the identified levels for inclusion in a Special Report to the Commission within 30 days. Radioactivity not a result of plant effluents does not need a Special Report but shall be described in the AREOR.
- 4. IF a currently sampled milk farm location becomes unavailable, THEN conduct a special milk farm survey within 15 days.
a) IF the unavailable location was an indicator farm, THEN an alternate sample lotation 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, THEN an alternate sample location may be established greater than 15 but less than 25 miles of the Donald C. Cook Nuclear Plant in one of the less prevalent wind direction sectors, if one is available.
I I
Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 36 of 87 I
c) IF a replacement farm is unobtainable and the total number of I indicator farms is less than three or the background farms is less than one, THEN perform monthly vegetation sampling in lieu of milk sampling. I BASES - RADIOLOGICAL ENVIRONMENTAL MONITORING. PROGRAM (REMP)
The REMP provides.measurements of radiation and radioactive materials in those exposure I
pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. Thereby, this monitoring program supplements the radiological effluent monitoring program by verifying the measurable I
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 was effective for the first three years of I commercial operation. Program changes may be initiated based on operational experience in -accordance with the requirements of Technical Specification 5.5.1. c.
The detection ýcapabilities, required by Attachment 3.20, Maximum Values for Lower Limits I
of DetectionsAB - REMP, are the state-of-the-art for routine environmental measurements in industrial laboratories. I 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 manneri that the stated LLDs will be achieved under routine analysis conditions. Occasionally, background I
fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the.
contribtiting factors will be identified and described in the Annual Radiological I
Environmental Operating Report.
3.5.3 Annual Land Use Census [Ref. 5.2.1u]) I
- a. Conduct a land use census and identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the ten land I
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 I
c.
sample media, with the highest average deposition factor (D/Q) value.
Conduct this land use census annually between the dates of June 1 and I
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 I
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, if possible."
I I
I
Reference PMP-6010-OSD-001 I Rev. 20 I .Page 37 of 87 OFF-SITE DOSE CALCULATION MANUAL 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 requirements of Section 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 quantity (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% of the 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. In order 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 of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.
3.6 Radioactive Equipment Storage Facility (Mausoleum) Groundwater Monitoring Program 3.6.1 Purpose of the Radioactive Equipment Storage Facility (Mausoleum) Groundwater Radiological Monitoring Program
- a. The purpose of the temporary on-site Radioactive Equipment Storage Facility (Mausoleum) Radiological Monitoring Program was 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 locations 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.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL
[-Rev. 20 Page 38 of 87 I
3.6.2 Conduct of the Radioactive Equipment Storage Facility (Mausoleum) I Groundwater Radiological Monitoring Program a.. Collect and analyze groundwater samples in accordance with Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, I
Sample Types, Sample Frequencies. Apply the values from Attachment 3.20, Maximum Values for Lower Limits of Detections - REMP, (excluding I-131) and Attachment 3.21, Reporting Levels for Radioactivity I
Concentrations in Environmental Samples, (excluding 1-131).
3.7 Meteorological Model I 3.7.1 Three towers are used to determine the meteorological conditions at Donald C.
Cook Nuclear Plant. One of the towers is located at the Lake Michigan shoreline to determine the meteorological parameters associated with unmodified shoreline I
air. The data is accumulated by microprocessors at the tower sites and normally 3.7.2 transferred to the central computer every 15 minutes.
The central computer uses a meteorological software program to provide I
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.
I 3.8 Reporting Requirements 3.8.1 Annual Radiological Environmental Operating Report (AREOR)
I
- a. Suibmit routine radiological environmental operating reports covering the operation of the units during the previous calendar year prior to May 15 of each I year. [Ref 5.2. lj, TS 5.6.2]
- b. Include in the AREOR:
Summaries, interpretations, and statistical evaluation of the"results I
of the radiological environmental surveillance activities for the reporting period.
A comparison with pre-operational studies, operational controls (as I
appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
I 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 I
the monitoring, provide in the report an analysis of the problem and a planned course of action to alleviate the problem. I I
I I
Reference T PMP-6010-OSD-001 Rev. 20 Page 39 of 87 OFF-SITE DOSE CALCULATION MANUAL 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.
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 Comparison 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 after January 1 of each year.
[Ref 5.2.1j, TS 5.6.3]
- 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 1.21; "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with 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 may be in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint 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.
Reference T I
PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 40 of 87 I
Use the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined I
by sampling frequency and measurement) for determining the gaseous pathway doses. I
- Inoperable radiation monitor periods exceeding 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence. I
- 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 I
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 I
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. I
- e. Include in the ARERR the following information for each type of solid waste shipped off-site during the report period: I
- Volume (cubic meters),
0 Total curie quantity (specify whether determined by measurement or estimate),
I 0 Principle radionuclides (specify whether determined by measurement or estimate),
- Type of waste (example: spent resin, compacted dry waste, I
evaporator bottoms),
- Type of container (example: LSA, Type A, Type B, Large Quantity),
I
-AND-Solidification agent (example: cement). I
- f. Include in the ARERR unplanned releases of radioactive materials in gaseous and liquid effluent from the site to unrestricted areas on a quarterly basis. I
- g. Include in the ARERR any change to this procedure made during the reporting period. I
- h. Due to the site having shared gaseous and liquid waste systems dose calculations will be performed on a per site bases using the per unit values. This is ALARA and will ensure compliance with 40 CFR 141, I National Primary Drinking Water Regulations. Unit specific values are site values divided by two.
I I
I
Reference PMP-6010-OSD-001 I Rev. 20 Page 41 of 87 OFF-SITE DOSE CALCULATION MANUAL 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.
3.9.3 This information is necessary to ensure all areas outside the radiological-restricted area are documented for surveying and remediation during decommissioning. 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 instruments, 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 Evaluate any changes to this procedure for potential impact on other related Department Procedures.
3.10.5 Review this procedure during the first quarter of each year and update it if necessary. Review Attachment 3.16, 10 Year Average of 1995-2004 Data, and document using Attachment 3.17, Annual Evaluation of "/Q and D/Q Values For All Sectors. The 1/ Q 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.
I Reference PMP-6010-OSD-O01 OFF-SITE DOSE CALCULATION MANUAL I Rev. 20 Page 42 of 87 I
5 REFERENCES I 5.1 Use
References:
5.1.1 "Implementation of Programmatic Controls for Radiological Effluent Technical I
Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Off-Site Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01)", United States Nuclear Regulatory Commission, January 31, 1989 I
5.1.2 12-THP-6010-RPP-601, Preparation of the Annual Radioactive Effluent Release Report I 5.1.3 12-THP-6010-RPP-639, Annual Radiological Environmental Operating 5.2 Report (AREOR) Preparation And Submittal Writing
References:
I 5.2.1 Source
References:
- a. 10 CFR 20, Standards for Protection Against Radiation I
b.
c.
10 CFR 50, Domestic Licensing of Production and Utilization Facilities PMI-6010, Radiation Protection Plan I
- d. NUREG-0472 e.
f.
NUREG-0133 Regulatory Guide 1.109, non-listed parameters are taken from ihese data I
tables
- i. Final Safety Analysis Report (FSAR)
- j. Technical Specifications 5.4.1.e, 5.5.1.c, 5.5.3, 5.6.2, and 5.6.3
- k. Final Environmental Statement Donald. C. Cook Nuclear Plant, August I
1973
- 1. NUREG-0017
- m. ODCM Setpoints for Liquid [and Gaseous] Effluent Monitors (Bases),
I ENGR 107-04 8112.1 Environs Rad Monitor System
- n. HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits I
- o. Watts - Bar Jones (WBJ) Document, R-86-C-001, The Primary Calibration of Eberline Instrument Corporation SPING - 3/4 Low, Mid, and High Range Noble Gas Detectors I
WBJ Document, R-86-C-003, The Primary Calibration of Eberline p.
q.
Instrument Corporation DAM-4 and Water Monitor 40 CFR 190, Environmental Radiation Protection Standards for I
r.
s.
Nuclear Power Operations NRC Commitment 6309 (N94083 dated 11/10/94)
NRC Commitment 1151 I
- t. NRC Commitment 1217 I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 43 of 87 OFF-SITE DOSE CALCULATION MANUAL
- u. NRC Commitment 3240
- v. NRC Commitment 3850
- w. NRC Commitment 4859
- x. NRC Commitment 6442
- y. NRC Commitment 3768
- 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. HPS N13.30-1996, Appendix A Rationale for Methods of Determining Minimum Detectable Amount (MDA) and -Minimum Testing Level (MDL ee. DIT-B-01971-00i 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 gg. NRC Commitment 1010 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.00f, Event-Initiated Surveillance Testing
- e. Environmental Position Paper, Fe Impact on Release Rates, approved 3/14/00
- f. Environmental Position Paper, Methodology Change from Sampling Secondary System Gaseous Effluents for Power Changes Exceeding 15 % within 1 hr to Responding to Gaseous Alert Alarms, approved 4/4/00
- g. CR 02150078, RRS-1000. efficiency curve usage
- h. Environmental Position Paper, Unit Vent Compensatory Sampling, approved 4/14/05
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 44 of 87 I
Attachment 3.1 Dose Factors for Various Pathways Pages:
44-..47 I
R- Dose Factors PATHWAY I
Nuclide H-3 Ground 0.OE+00 Vegetable 4.OE+03
- Meat 3.3E+02 Cow Milk 2.4E+03 Goat Milk 4.9E+03 Inhalation 1.3E+03 I C-14 0.0E+00 3.5E+06 5.3E+05 3.2E+06 3.2E+06 3.6E+04 Cr-51 Mn-54 5.4E+06 1.6E+09 1.1E+07 9.4E+08 9.6E+08 1.5E+06 2.1E+07 1.7E+09 6.9E+06 2.9E+07 3.1E+08 8.3E+05 3.5E+06 4.OE+07 2.1E+04 2.0E+06 1.5E+06 I
Fe-59 3.2E+08 Co-58 Co-60 Zn-65 4.4E+08 2.5E+10 8.5E+08 6.OE+08 3.2E+09 2.7E+09 2.9E+08 1.OE+09 9.5E+08 8.4E+07 2.7E+08 1.6E+10 1.0E+07 3.2E+07 1.9E+09 1.3E+06 8.6E+06 1.2E+06 I
Sr-89 Sr-90 Zr-95 2.5E+04 0.OE+00 2.9E+08 3.5E+10 1.4E+12 1.2E+09 3.8E+08 9.6E+0.9.
1.5E+09 9.9E+09 9.4E+10 9.3E+05 2.1E+10 2.0E+1 1 1.1E+05 2.4E+06 1.1E+08 2.7E+06 I
Sb-124 1-131 1-133 6.9E+08 1.0E1+07 1.5E+06
- 3.OE+09 2.4E+10 4.OE+08 4.4E+08 2.5E+09 6.0E+01 7.2E+08 4.8E+l1 4.4E+09 8.6E+07 5.8E+l11 5.3E+09 3.8E+06 1.6E+07 3.8E+06 I
Cs-134 7.9E+09 2.5E÷10 1.1E+09 5.OE+10
- l.5E+l-1 1.1E+06 Cs-136 Cs-137 1.7E+08 1.2E+10 2.2E+08 2.5E+10 4.2E+07 1.0E+09 5.1E+09 4.5E+10 1.5E+10 1.4E+1I 1.9E+05 9.OE+05 I
Ba-140 2.3E+07 2.7E+08 5.2E+07 2.1E+08 2.6E+07 2.OE+06 Ce-141 Ce-144 1.5E+07 7.9E+07 5.3E+08 1.3E+10 3.OE+07 3.6E+08 8.3E+07 7.3E+08 1.0E+07 8.7E+07 6.1E+05 1.3E+07 I
Units for all except inhalation pathway are m2 mr sec / yr /Ci, inhalation pathway units are mr mn / yrl pUCi.
I Uap Values to be Used For the Maximum Exposed Individual I
Pathway Infant Child Teen Adult Fruits, vegetables and grain (kg/yr)
Leafy vegetables (kg/yr) 520 26 630 42 520 64 I
Milk (L/yr)
Meat and poultry (kg/yr) 330 330 41 400 65 310 110 I Fish (kg/yr) -- 6.9 16 21 Drinking water (L/yr)
Shoreline recreation (hr/yr) 330 510 14 510 67 730 12 I
Inhalation (m 3/yr)
Table E-5 of Reg. Guide 1.109.
1400 3700 8000 8000 I
I I
[ Reference PMP-6010-OSD-001 Rev. 20 Page 45 of 87 OFF-SITE DOSE CALCULATION MANUAL .1 Dose Factors for Various Pathways Pages:
44 - 47 Bit Factors for Aquatic Foods pCi 1/ kg pCi Element Fish Invertebrate H 9.0E-1 9.0E-1 C 4.6E3 9.1E3 Na 1.0E2 2.0E2 P 1.0E5 2.0E4 Cr 2.0E2 2.0E3 Mn 4.0E2 9.0E4 Fe 1.0E2 3.2E3 Co 5.0E1 2.0E2 Ni 1.0E2 1,0E2 Cu 5.0E1 4.0E2 Zn 2.0E3 1.0E4 Br 4.2E2 3.3E2 Rb 2.0E3 1.0E3' Sr 3.0E1 1.0E2 Y
_ 2.5E1 1.0E3 Zr 3.3E0 6.7E0 Nb 3.0E4 1.0E2 Mo 1.OE1 V.OE1 Tc 1.5E1 5.0E0 Ru 1.OE1 3.0E2 Rh 1.OE1 3.0E2 Te 4.0E2 6.1E3 I 1.5E1 5.0E0 Cs 2.0E3 1.0E3 Ba 4.0E0 2.0E2 La 2.5E1 1.0E3 Ce LOEO 1.0E3 Pr 2.5E1 1.003 Nd 2.5E1 1.003 W 1.2E3 1.01E Np 1.01E 4.0E2 Table A-I of Reg. Guide 1.109.
Reference PMP-6010-OSD-001 Rev. 20 Page 46 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I .1 Dose Factors for Various Pathways 1
Pages:
44 - 47 I Dwpi External Dose Factors for Standing on Contaminated Ground mrem m2 / hr pCi I
H-3 C-14 Radionuclide Total Body 0
0 Skin 0
0 I
Na-24 P-32 Cr-51 2.5E-8 0
2.2E-10 2.9E-8 0
2.6E-10 I
Mn-54 5.8E-9 6.8E-9 Mn-56 Fe-55 1.1E-8 0
1.3E-8 0
I Fe-59 8.OE-9 9.4E-9 Co-58 Co-60 7.OE-9 1.7E-8 8.2E-9 2.OE-8 I
Ni-63 0 0 Ni-65 Cu-64 3.7E&9 1.5E-9 4.3E-9 1.7E-9 I
Zn-65 4.OE-9 4.6E-9 Zn-69 Br-83 0
6.4E-11 0
9.3E-11 I Br-84 1.2E-8 1.4E-8 Br-85 Rb-86 0
6.3E-10 0
7.2E-10 I Rb-88 3.5E79 4.OE-9 Rb-89 Sr-89 Sr-91 1.5E-8 5.6E-13 7.1E-9 1.8E-8 6.5E-13 8.3E-9 I
Sr-92 Y-90 Y-91m 9.OE-9 2.2E-12 3.8E-9 1.OE-8 2.6E-12 4.4E-9 I
Yý91 2.4E-11 2.7E-11.I Y-92 Y-93 1.6E-9 5.7E-10 1.9E-9 7.8E-10 I
Zr-95 5.OE-9 5.8E-9 Zr-97 Nb-95 5.5E-9
- 5. 1 E-9 6.4E-9 6.OE-9 I
Mo-99 1.9E-9 2.2E-9 Tc-99rn Tc-101 9.6E-10 2.7E-9 1.1E-9
.3.0E-9 I
Ru-103. 3.6E-9 4.2E-9 Ru-105 Ru-106 4.5E-9 1.5E-9 5.1E-9 1.8E-9 I
Ag-1 10m 1.8E-8 2.1E-8 Te-125m 3.5E-11 4.8E-11 I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 47 of 87 OFF-SITE DOSE CALCULATION MANUAL SAttachment 3.1Atahmn
.1DseFcor Dose Factors for Various Pathways orVrou atwy Pages:
44 -47 Radionuclide Total Body Skin Te-127m 1.1E-12 1.3E-12 Te-127 1.OE-11 1.1E-11 Te-129m 7.7E-10 9.OE-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.OE-9 1-130 1.4E-8 1.7E-8 1-131 2.8E-9 3.4E-9 1-132 1.7E-8 2.OE-8 1-133 3.7E-9 4.5E-9, 1-134 1.6E-8 1.9E-8 1-135 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. IE-8 2.4E-8 Ba-139 2.4E-9 2.7E-9 Ba-140 2:1E-9 2.4E-9 Ba-141 4.3E-9 4.9E-9 Ba-142 .7.9E-9 9.OE-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.OE-10 2.3E-10 Nd-147 L.OE-9 1.2E-9 W-187 3.1E-9 3.6E-9 Np-239 9.5E-10 1.LE-9 Table E-6 of Reg. Guide 1.109.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 48 of 87 I
Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments Pages:
48 - 50 I INSTRUMENT Minimum Channels Applicability Action I Operablea
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination a., Liquid Radwaste (1)# At timesof release 1 I
Effluent Line (RRS-1001)
- b. Steam Generator Blowdown Line (R,19, DRS 3/4100 +)
(1)# At times of release** 2 I
- c. Steam Generator Blowdown Treatment Effluent (R-24, DRS 3/4200 +)
(1)# At times of release 2 I
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water (1) per. At all times 3 I
System Effluent Line (R-20, R-28) train
- 3. Continuous Composite Sampler Flow Monitor I
- a. Turbine Building Sump (1) At all times 3 Effluent Line
- 4. Flow Rate Measurement Devices I
- a. Liquid Radwaste Line (RFI-285)
(1) At times of release 4 I
- b. Discharge Pipes*, (1) At all times NA
- c. Steam Generator Blowdown Treatment Effluent (DFI-352)
(1)
At times of release 4 I
- d. Individual Steam Generator sample flow (1) per At times of release 5 to Blowdown radiation monitors alarm (DFA-310, 320, 330 and 340) generator I
- 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.
OPERABILITY of RRS-1001 includes OPERABILITY of sample flow switch RFS-1010, which is an attendant instrument as defined in Technical Specification section 1.1, under the term Operable - Operability. This item is also applicable for all I
Eberline liquid monitors (and their respective flow switches) listed here.
- Since these monitors can be used for either batch or continuous release the appropriate action statement of 1 or 2 should apply (that is, Action 1 if a steam generator drain is being performed in lieu of Action 2). Ii is possible, due to the steam generator sampling system lineup, that BOTH action statements are actually entered. This would be the case when sampling for steam generator draining requires duplicate samples while the sample system is lined up to discharge to the operating units blowdown system. In this case the steam generator drain samples can fulfill the sample requirement for Action 2 also. Action 2 would be Ii exited when sampling was terminated.
+ Some Westinghouse (R) radiation monitors are being replaced by Eberline (DRS) monitors. Either monitor can fulfill the operability requirement. Ensure surveillances are current for operability of the instrumentation prior to'using it to satisfy applicability requirement.
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 49 of 87 OFF-SITE DOSE CALCULATION MANUAL Radioactive Liquid Effluent Monitoring Instruments Pages:
Attachment 3.2 1 48-50 a IF an RMS monitor is inoperable solely as the result of the loss of its control room alarm annunciation, 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 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.
TABLE NOTATION Action 1 With the number 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 Step 3.2.3a 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 are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 pCi/gram:
- 1. At least once per shift when the specific activity of the secondary coolant is > 0.01 .tCi/gram DOSE EQUIVALENT 1-131.
- 2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is _<0.01 pCi/gram DOSE EQUIVALENT 1-131.
After 30 days, IF the channels are not OPERABLE, ThEN continue releases with required grab samples provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.
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 collectedand analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 pCi/ml. Since the Westinghouse ESW monitors (R-20 and R-
- 28) are only used for post LOCA leak detection and have no auto trip function associated with them, grab samples are only needed if the Containment Spray Heat Exchanger is in service. After 30 days, IF the channels are not OPERABLE,"'ITEN'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.
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not OPERABLE, THE[EN 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.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 50 of 87 I I Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments 48 - 50 Pages:
Action 5 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 verified to be within the required band at least once per. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases . After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples ponce per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report. ýIF the flow cannot be obtained within the desired band, THEN declare the radiation monitor inoperable and enter the appropriate actions statement, Action 2.
Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing I
I I
I I
I I
I I
I I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 51 of 87 OFF-SITE DOSE CALCULATION MANUAL Radioactive Liquid Effluent Monitoring Pages:
Instrumentation Surveillance Requirements 51 - 52 Instrument CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION OPERATIONAL TEST
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste D* P B(3) Q(5)
Effluent Line (RRS-1001)
- b. Steam Generator D* M B(3) Q(1)
Blowdown Effluent Line
- c. Steam Generator D* M B(3) Q(1)
Blowdown Treatment Effluent Line
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water D M B(3) Q(2)
System Effluent Line
- 3. Continuous Composite Samplers
- a. Turbine Building D* N/A N/A N/A Sump Effluent'Line .
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste D(4)* N/A B Q Effluent
- b. Steam Generator D(4)* N/A N/A N/A Blowdown Treatment Line
- During releases via this pathway
Reference PMP-6010-OSD-001 Rev. 20 Page 52 of 87 I
OFF-SITE DOSE CALCULATION MANUAL .1 Radioactive Liquid Effluent Monitoring Pages:
Attachment 33 Instrumentation Surveillance Requirements 51 - 52 -
TABLE NOTATION 3 I Demonstrate with the CHANNEL OPERATIONAL 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 alarm/trip setpoint.
- 2. Circuit failure.*
- 3. Instrument indicates a downscale failure.*
- 4. Instrument control not set in operating mode.*
- 5. Loss of sample flow.*
- 2. Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
I
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operating mode.
I
- 3. Perform the initial CHANNEL CALIBRATION using one or more sources with traceability back to the National Institute of Standards and Technology (NIST). These sources permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources I
that have been related to the initial calibration may 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made.
- 5. Demonstrate with the CHANNEL OPERATIONAL 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 alarm/trip setpoint. I
- 2. Circuit failure.**
- 3. Instrument indicates a downscale failure.**
- 4. Instrument control not set in operating mode.*
- 5. Loss of sample flow.
I
- Instrument indicates, but does not provide for automatic isolation S* Instrument indicates, but does not necessarily cause automatic isolation. No credit is taken for the automatic isolation on such occurrences.
I Operations currently performs the routine channel checks and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests. Chemistry performs the channel check on the continuous composite sampler.
These responsibilities are subject to change without revision to this document. 3 I
I I
I
Reference PMP-6010-OSD-001 Rev. 20 'Page 53 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
- 53-55 Instrument (Instrument #) Operable'. Minimum Action Channels Action
- 1. Condenser Evacuation System
- a. Noble Gas Activity (1) 6 Monitor (SRA-1905/2905)
- b. Flow Rate Monitor (SFR-401, - (1) 5 1/2-MR-054 and/or SRA- 1910/2910) OR (SFR-402 and 1/2-MR-054)
- 2. Unit Vent. Auxiliary Building Ventilation System a.. Noble Gas Activity (1) 6 Monitor (VRS- 1505/2505)
- b. Iodine Sampler (1) 8 Cartridge for VRA-1503/2503
- c. Particulate Sampler Filter (1)
- 8 for VRA-1501/2501
- d. Effluent System Flow Rate (1) 55.
Measuring Device (VFR-315, MR-054 and/or VFR-1510/2510)
- e. Sampler Flow Rate 51 Measuring Device (VFS-1521/2521)
- 3. Containment Purge and Containment Pressure Relief (Vent) *
- a. Containment Noble Gas Activity Monitor .() .****2.3 7 ERS-13/1405 (ERS-23/2405)
- b. Containment Particulate Sampler Filter (1) **** 10 ERS-13/1401 (ERS-23/2401) ,..
- 4. Waste Gas Holdup System and CVCS HUT (Batch releases)**
- a. Noble Gas Activity (1) ****4 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
- Containment Purge and other identified gaseous batch releases can be released utilizing the same double sampling compensatory action requirements of action 9 identified here even if there is no termination function associated with it like that associaied with the two specific tank types listed .here.,
- During releases via this pathway
PMP-6010-OSD-001 Rev. 20 Page 54 of 87 I
Reference OFF-SITE DOSE CALCULATION MANUAL 3 Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
I 53 -55 TABLE NOTATIONS
- 1. IF an RMS monitor is inoperable solely as the result of the loss of it's control room alarm annunciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:
I
- 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:
0 The Coniainment Purge System is in operation and Containment Operability is applicable,
-OR- .I
- 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 degai and depressurization of the RCS. 3 IF neither of the above are applicable, THEN the containment purge system is acting as a ventilation system (an extension of the Auxiliary Building) and is covered by Item 2 of this Attachment.
-OR- I A Containment Pressure Relief (CPR) is being performed.
Once Purge (clean-up) has been completed and 'Ventilation' mode of Purge has commenced - resultant return to 'Clean-up' mode can be made with no additional sampling requirements or paperwork - so long as either ERS-1305/2305 OR ERS-1405/2405 are operable: Containment particulate channels are not needed since the RCS has been degassed and depressurized so leak detection is not an issue.
- 3. For purge (including pressure relief) purposes only. Reference TS 3.6.1, Containment Purge Supply and Exhaust System Isolation Instrumentation and 3.4.15, RCS Leakage Detection Instrumentation for additional information.
- 4. For waste gas releases only, see Item 2 (Unit Vent, Auxiliary Building Ventilation System)"for additional requirements.
5.
ACTIONS With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE U
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with estimation of the flow rate once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and provide a description of why the inoperabiliiy I
was not corrected in the next Annual Radiological Effluent Release Report.
- 6. With the number 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 I
per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why l the inoperability was not corrected in the next Annual Radiological Effluent release Report.
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 55 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3-4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
53-55
- 7. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, immediately suspend PURGING or VENTING (CPR) of radioactive effluents via this pathway.
- 8. 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 with 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 with sample collection by auxiliary 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 number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release:
- a. At least two independent 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.
After 14 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling
-equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report
- 10. See Technical Specification 3.4.15, RCS Leakage Detection System Instrumentation.
Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing.
Reference PMP-6010-OSD-001 Rev. 20 Page 56 of 87 I
OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Pages:
56 -57 I
Instrument CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL OPERATIONAL TEST I
- 1. Condenser Evacuation Alarm Only System
- a. Noble Gas Activity Monitor (SRA- 1905/2905)
D** M B(2) Q(1) I
- b. System Effluent Flow Rate (SFR-401, SFR-402, MR-054, SRA-1910/2910)
D** NA B Q I
- 2. Auxiliary Building Unit Ventilation System
- a. Noble Gas Activity Monitor Alarm Only D* M B(2) Q(1)
I (VRS- 1505/2505)
- b. Iodine Sampler (For VRA-1503/2503)
W* NA NA. NA I
- c. Particulate Sampler W* NA NA NA (For VRA-1501/2501)
- d. System Effluent Flow Rate D* NA B Q Measurement Device (VFR-315, MR-054, VRS-1510/2510)
- e. Sampler Flow Rate Measuring Device D* N/A B Q I
(VFS-1521/2521)
- 3. Containment Purge System and Containment Pressure Relief
- a. Containment Noble Gas Alarm and Trip S P B(2) Q I
Activity Monitor (ERS-13/1405 and ERS-23/2405)
- b. Containment Particulate Sampler (ERS-13/1401 and S
NA B Q I ERS-23/2401)
- 4. Waste Gas Holdup System Including CVCS HUT Alarm and Trip I
- a. Noble Gas Activity Monitor P P B(2) Q(3)
Providing Alarm and Termination (VRS- 1505/2505)
I
- 5. Gland Seal Exhaust
- a. Noble Gas Activity (SRA- 1805/2805)
I
- b. System Effluent Flow Rate (SFR-201, MR-054, SRA-1810/2810)
- At all times
- During releases via this pathway I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 57 of 87 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Monitoring EffluentRequirements Pages:
Attachment 3.5 Instrumnentation Surveillance 56 -57 TABLE NOTATIONS
- 1. Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument 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 energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.
- 3. Demonstrate with the CHANNEL OPERATIONAL 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 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 perform channel calibrations and channel operational tests. These responsibilities are subject to change without revision to this document.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 58 of 87 I
Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program Pages:
158 -591 I
[Ref. 5.2.ls]
LIQUID SAMPLING MINIMUM TYPE OF LOWER I
RELEASE FREQUENCY ANALYSIS ACTIVITY LIMIT OF TYPE FREQUENCY ANALYSIS DETECTION (LLD)
I (PCi/ml) H A. Batch Waste Release Tanks C P
Each Batch P
Each Batch Principal Gamma 5x10-7 I Emitters C
.. P P 1-131 Dissolved and lx10 6 I Each Batch Each Batch Entrained Gases (Gamma Emitters) _
lx10 5 I
1x10.5 P
Each.Batch M
Compositeb H-3 Ix107 I
Gross Alpha P
Each Batch Q
Composite b Sr-89, Sr-90 5x10s I Fe-55 Ix10-"
B. Plant Continuous Daily W
Composite b Principal Gamma 5x10.
I Releases* d Emitters 1-131 1x106 I M M Dissolved and Grab Sample Entrained Gases (Gamma 1x10 5 I
Emitters)
Daily M
Composite '
Gross Alpha 1xl0-Daily Q
Compositeb Sr-89, Sr-90 5x10-8 I Fe-55 1x10 6
- During releases via this pathway I This table provides the minimum requirements for the liquid sampling program. If additional sampling is performed then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification.
Examples of these samples are the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> secondary coolant activity and Monitor Tank tritium samples.
I I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 59 of 87 OFF-SITE DOSE CALCULATION MANUAL Pages:
Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program 58P-59 TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits 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. Examples of these are Monitor Tank and Steam Generator Drains. Before a batch is released the tank is sampled and analyzed to determine that it can be released without exceeding federal standards.
- d. A continuous release is the discharge of liquid of a non-discrete volume; e.g. from a volume of system that has an input flow during the continuous release. This type of release includes the Turbine Room Sump, Steam Generator Blowdown and the Steam Generator Sampling System.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zr-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144.
This list does not mean that only these nuclides are to be detected and reported. Identify and report other peaks, which are measurable and identifiable, together with the above nuclides.
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 60 of 87 I
Radioactive Gaseous Waste Sampling and Analysis Program Pages:
60-61 I
Gaseous Release Type Frequency Minimum Analysis Type of Activity Lower Limit of Detection I
Frequency Analysis (1C0i/cc),
- a. Waste Gas Storage Tanks and CVCS HUTs P
Each Tank Grab Sample p
Each Tank I rnia Emitters d Gamma 1 x 10z I H-3 I x 10
- b. Containment Purge P Each Purge P
Each Purge Principal Gamma Emitters I1 x 10ý I
-CPR `(vent)"* ---------------- Twice per Month Twice per Month H-3 I1 x 106 I
- c. Condenser Evacuation System Gland Seal Exhaust* '
W or M Grab Sample M
Particulate Sample M
Principal Gamma Emittersd H-3 1 x 10"-1 i x 10-6 I
Wg Noble Gas Principle Gamma Emitters 1x-l 4
I M 1-131 Continuous Iodine Adsorbing Media W g Noble Gases I x 10-2 I
Noble'Gas Monitor 1 x 104
- d. Auxiliary.Building Unit Vent*
Continuous'. Wb Iodine Adsorbing 1-131 I x 10n12 I
Media Continuous '. W b Particulate Sample Principal Gamma Emittersd 1 x 101 I Continuous C M Gross Alpha W
Composite Particulate Sample w h H-3 I 1 x 107 I
Grab Sample H-3 Sample I x 106 W gj Noble Gas Principle Gamma Emitters d I x 10- I Continuous c Q Sr-89, Sr-90 Composite Particulate Sample I x 10"1 I
Continuous C Noble Gas Monitor Noble Gases 1 x 10-6
- e. Incinerated Oil'
- During releases via this pathway P
Each Batch P
Each Batch' Principal Gamma Emitters d 5 x 10"7 I
- Only a twice per month sampling program for containment noble gases and H3 is required This table provides the minimum requirements for the gaseous sampling program. If additional sampling is I
performed then those sample results can be used to quantify releases in lieu of composite data for a. more accurate quantification. Examples of these samples are verification or compensatory action sample results.
I I
Reference PMP7-6010-OSD-001 Rev. 20 Page 61 of 87 OFF-SITE DOSE CALCULATION MANUAL Radioactive.Gaseous Waste Sampling and Pages:
Analysis Program 60 - 61 TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of Detections"B - REMP
- b. Change samples at least once per 7 days and complete analyses within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.
Perform analyses at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or THERMAL POWER change greater than 15 % per hour of RATED THERMAL POWER. WHEN samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, THEN the corresponding LLDs may be increased by a factor of
- 10. This requirement does not apply IF (1) analysis shows that DOSEQ 1131 concentration in the RCS.
has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. IF the daily sample requirement has been entered, THEN it can be exited early once both the radiation monitor reading and the RCS DOSEQ 1131 levels have returned to within the factor of 3 of the pre-event 'norm'al'.[Ref. 5.2.1y]
- c. Know the ratio of the sample flow rate to the sampled stream flow rate for the time period covered by each dose or dose rate calculation made in accordance with steps 3.2.4a, 3.2.4b, and 3.2.4c of this document.
Sampling evolutions are not an interruption of a continuous release or sampling period.
- d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134,-Cs-137, Ce-141-and Ce-144 for particulate emissions. This list does not 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.
- e. Releases from incinerated oil are discharged through the Auxiliary Boiler System. Account for releases based on pre-release grab sample data.
- f. Collect samples of waste oil to be incinerated from the container in which the waste oil is stored (example: waste oil storage tanks, 55 gal. drums) prior to transfer to the Auxiliary Boiler System.
Ensure samples are representative of container contents.
- g. Obtain and analyze a gas marinelli grab sample weekly for noble gases effluent quantification.
- h. Take tritium grab samples at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.
- i. Grab sampling of the Gland Seal Exhaust pathway need not be performed if the RMS low range channel (SRA-1805/2805) readings are less than IE-6 pC/cc. Attach the RMS daily averages in lieu of sampling. This is based on operating experience indicating no activity is detected in the Gland Seal Exhaust below this value. Compensatory sampling for out of service monitor is still required in the event 1805/2805 is inoperable.
- j. Sampling and analysis shall also be performed following shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a one hour period. This noble gas sample shall be performed within four hours of the event. Evaluation of the sample results, based on previous samples, will be performed to determine if any further sampling is necessary.
Reference PMP-6010-OSD-001 Rev. 20 Page 62 of 87 OFF-SITE DOSE CALCULATION MANUAL for eleae PontsPage:
Multiple Release Point Factors for Release Points 62 Attachment 3.8 Liquid Factors Monitor Description Monitor Number MRP #
U I SG Blowdown 1R19/24, DRS 3100/3200* 0.35 U 2 SG Blowdown 2R19/24, DRS 4100/4200* 0.35 U 1 & 2 Liquid Waste Discharge RRS-1000 0.30 Sources of radioactivity released from the Turbine Room Sump (TRS) typically originate from the secondary cycle which is already being monitored by instrumentation that utilizes multiple release point (MRP) factors. The MRP is an administrative value that is used to assist with maintaining releases ALARA. The TRS has no actual radiation monitor, but utilizes an automatic compositor for monitoring what has been released. The batch release path, through RRS-1000, is the predominant release path by several magnitudes. Tritium is the predominant radionuclide released from the site and the radiation monitors do not respond to this low energy beta emitter. Based on this information and the large degree of conservatism built into the radiation monitor setpoint methodology it does not appear to warrant further reduction for the TRS release path since its source is predominantly the secondary cycle which is adequately covered by this factor.
Gaseous Factors Monitor. Description Monitor Number Flow Rate (cfm) MRP # -
Unit I Unit Vent VRS-1500 186,600 0.54 Gland Seal Vent SRA-1800 1,260 0.00363 Steam Jet Air Ejector SRA-1900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 192,996 Unit 2 Unit Vent VRS-2500 143,400 0.41 Gland Seal Vent SRA-2800 5,508 (a) 0.02 Steam Jet Air Ejector SRA-2900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 154,044
- Either R-19, 24, DRS 3/4100 or 3/4200 can be used for blowdown monitoring as the Eberline monitors (DRS) are replacing the Westinghouse (R) monitors.
- Nominal Values a Two release points of 2;754 cfm each are totaled for this value.
b This is the total design maximum of the Start Up Air Ejectors. This is a conservative value for unit 1.
Reference PMP-6010-OSD-001 Rev. 20 Page 63 of 87 OFF-SITE DOSE CALCULATION MANUAL Liquid Effluent Release Systems Page: .9 63
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 64 of 87 I
Attachment 3.10 Plant Liquid Effluent Parameters 64 I SYSTEM COMPONENTS CAPACITY FLOW RATE I
I Waste Disposal System TANKS PUMPS (EACH) (EACH)*
I
" Chemical Drain Tank 1 1 600 GAL. 20 GPM
+ Laundry & Hot Shower Tanks 2 1 600 GAL. 20 GPM I
+ Monitor Tanks 4 2 21,600 GAL. 150 GPM
+ Waste Holdup Tanks
+ Waste Evaporators 2
3 25,000 GAL.
30 GPM I
+ Waste Evaporator Condensate 2 2 6,450 GAL 150 GPM Tanks II Steam Generator Blowdown
__ I and Blowdown Treatment Systems I
+ Start-up Flash Tank (Vented)# 1 1,800 GAL. 580 GPM
+ Normal Flash Tank (Not Vented) 1 525 GAL. 100 GPM I
+ Blowdown Treatment System 1 60 GPM III Essential Service Water System
+ Water Pumps .4 10,000 GPM I
+ Containment Spray Heat Exchanger Outlet 4 3,300 GPM I
IV Circulating Water Pumps _
Unit 1 Unit 2 3
4 230,000 GPM 230,000 GPM I
- Nominal Values The 580 gpm value is calculated from the Estimated Steam Generator Blowdown Flow vs. DRV Valve Position letter prepared by M. J. O'Keefe, dated 9/27/93. This is 830 gpm times the 70% that remains I
as liquid while the other 30% flashes to steam and exhausts out the flash tank vent.
I I
I I
I
Reference PMP-6010-OSD-001 Rev. 20 Page 65 of 87 OFF-SITE DOSE CALCULATION MANUAL Atthm t 3 1 Volumetric Detection Efficiencies for Principle Gamma Page:
Emitting Radionuclides for Eberline Liquid Monitors 65 This includes the following monitors: RRS-1000, DRS 3100, DRS 3200, DRS 4100, and DRS 4200.
[Ref. 5.2. lp]
NUCLIDE EFFICIENCY (cpm/ Ci/cc) 1-131 3.78 E7 Cs-137 3.00 E7 Cs-134 7.93 E7 Co-60 5.75 E7 Co-58 4.58 E7 Cr-51 3.60 E6 Mn-54 3.30 E7 Zn-65 1.58 E7 Ag-110M 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 Ce-144 4.83 E6 Co-57 3.80 E7 Cs-136 1.07 E8 Fe-59 2.83 E7 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 Sb-122 2.55 E7 Sb-125 3.15 E7 Sn-113 7.33 E5 Sr-85 3.70 E7 Sr-89 2.88 E3 Sr-92 3.67 E7 Tc-99M 3.60 E7 Y-88 5.25 E7 Zr-95 3.38 E7 Zr-97 3.10 E7 Kr-85 1.56 E5 Kr-85M 3.53 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
Reference PMP-6010-OSD-001 Rev. 20 Page 66 of 87 OFF-SITE DOSE CALCULATION MANUAL Pages:
Attachment 3.12 Counting Efficiency Curves for R-1 9, and R-24 66P-67 Counting Efficiency Curve for R-19 Efficiency Factor = 4.2 E6 cpm/uCi/ml (Based on empirical data taken during pre-operational testing with Cs.137) 1.00E+07 1.OOE+06 1.OOE+05
-o 0
S1.00E+03 1.OOE+02 1.00E+01 1.00E+00 99 MN C0 9 0 9- 0 0 0 r 0 0ue 0
microcuries/int
= -i M-- -M M I- = - =-- M - M
m- mm mm m - - - - - m -
Reference PMP-6010-OSD-001 Rev. 20 Page 67 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.12 Counting Efficiency Curves for R- 19, and R-24 *P6ge-s6 Counting Efficien'cy Curve for R-24 Efficiency Factor = 7.5E6 cpm/uCi/rnl (Based on empirical data taken during pre-operational testing with Mn-54) 1.OOEi-07 1.00E+06 I .00E405
_2 1.OOE+04 u
.00E0 S1.0OE+.01*
1.OOE+02 to MI N5 00 o 9 9 9 9 +
Wl LI U WI LUw o 0ý 0 0 0. 0 0 UJ microcurieslml
Reference PMP-6010-OSD-001 Rev. 20 Page 68 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.13 Counting Efficiency Curve for R-20, and R-28 age:
1 68 Counting Efficiency Curve for R-20 and R-28 Efficiency Factor = 4.3 E6 cpm/uCi/ml (Based on empirical data taken during pro-operational testing with Co-SB) 1.OOE+07 I OOE+06 I .OOE+05
~a1.OOE+04 0
1.OOE*03 I .OOE.00 U
0s0 0 0 0 0
- - mlerocurlesiml -
mm I -- - I-- - /-- / /
Reference PMP-6010-OSD-001 Rev. 20 Page 69 of 87 OFF-SITE DOSE CALCULATION MANUAL Page: .14 Gaseous Effluent Release Systems 69 I
S.~ kg Po,~
E~J.
- '~~' Ibi
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION .'MANUAL Rev. 20 Page 70 of 87 I
Attachment 3.15 Plant Gaseous Effluent Parameters Page:
70 I
SYSTEM UNIT EXHAUST CAPACITY I
FLOW RATE PLANT AUXILIARY BUILDING 1 (CFM) 186,600 max I
UNIT VENT ..2 143,400 max WASTE GAS DECAY TANKS (8)
AND CHEMICAL & VOLUME 1 125 4082 FT 3 @100 psig 28,741 ft max I
CONTROL SYSTEM HOLD UP @ 8#, 0 level TANKS (3).
+ AUXILIARY BUILDING 1 72,660 I
EXHAUST 2 59,400
+ ENG. SAFETY FEATURES VENT 1&2 50,000 I
+ FUEL HANDLING AREA VENT.
SYSTEM CONTAINMENT PURGE SYSTEM' 1
1 &2 30,000 32,000 _
I CONTAINMENT PRESSURE RELIEF SYSTEM I&2 1,000 I
INSTRUMENT ROOM PURGE 1& 2 -1,000 SYSTEM I
II CONDENSER AIR EJECTOR 2 Release Points SYSTEM NORMAL STEAM JET AIR 1&2 230 One for Each Unit I EJECTORS START UP STEAM JET AIR EJECTORS 1& 2 3,600 I III TURBINE SEALS SYSTEM 1 1,260 I 2 5,508 2 Release Points for Unit 2 I
IV START UP FLASH TANK VENT 1 1,536
+ Designates total flow for all fans.
2 1,536 I I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 71 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.16 10 Year Average of 1995-2004 Data Pages: 71 - 72 I/Q GROUND AVERAGE (sec/M 3)
DIRECTION DISTANCE (METERS)
(WIND FROM) 594 2416 4020 5630 7240 N 4.17E-06 4.82E-07 2.25E-07 1.33E-07 9.32E-08 NNE 3.02E-06 3.64E-07 1.73E-07 1.04E-07 7.29E-08 NE 4.54E-06 5.31E-07 2.60E-07 1.59E-07 1.13E-07 ENE 7.16E-06. 7.99E-07 4.04E-07 2.52E-07 1.80E-07 E 1.04E-05 1. 3E-06 5.82E-07 3.66E-07 2.63E-07 ESE 1.07E-05 1.18E-06 6.04E-07 3.78E-07 2.72E-07 SE 1.15E-05 1.24E-06 6.36E-07 4.00E-07 2.88E-07 SSE 1.30E-05 1.42E-06 7.27E-07 4.57E-07 3.29E-07 S 1.41E-05 1.57E-06 7.92E-07 4.93E-07 3.54E-07 SSW 7.03E-06 7.81E-07 . 3.90E-07 2.41E-07 1.72E-07 SW 4.12E-06 4.73E-07 " 2.28E-07 1.38E-07 9.73E-08 WSW 3.29E-06 3.65E-07' 1.76E-07 i.06E-07 7.52E-08 W 3.63E-06 4.11E-07 1.96E-07 1.18E-07 8.31E-08 WNW 3.02E-06 3.43E-07 1.61E-07 9.59E-08 6.71E-08 NW 3.22E-06 3.61E-07 1.71E-07 1.02E-07 7.16E-08 NNW . 3.84E-06 4.29E-07 2.02E-07 1.20E-07 8.40E-08 DIRECTION DISTANCE (METERS)
(WIND FROM) 12067 24135 40225 56315 80500.
N 4.64E-08 1.79E-08 8.89E-09 5.68E-09 3.56E-09 NNE 3.66E-08 1.43E-08 7.13E-09 4.56E-09 2.87E-09 NE 5.75E-08 2.30E-08 1.15E-08 7.41E-09 4.72E-09 ENE 9.30E-08 3.80E-08 1.91E-08 1.23E-08 7.90E-09 E 1.37E-07 5.65E-08 2.85E-08 1.83E-08 1. 18E-08 ESE 1.41E-07 5-.81E-08 2.93E-08 1.88E-08 1.22E-08 SE 1.50E-07 6.20E-08 3.12E-08 2.01E-08 1.30E-08 SSE 1.71E-07 7.06E-08 3.56E-08 2.29E-08 1.48E-08 S 1.84E-07 7.49E-08 3.77E-08 2.43E-08 1.56EL08 SSW 8.86E-08 3.59E-08 1.80E-08 1.15E-08 7.39E-09 SW 4.93E-08 1.96E-08 9.77E-09 6.27E-09 3.98E-09 WSW 3.80E-08 1.5 1E-08 7.53E-09 4.83E-09 3.07E-09 W 4.17E-08 1.64E-08 8.13E-09 5.20E-09 3.28E-09 WNW 3.34E-08 1.29E-08 6.41E-09 4. 1OE-09 2.57E-09 NW 3.57E-08 1.39E-08 6.89E-09 4.41E-09 2.77E-09 NNW 4.19E-08 3.35E-08 8.1OE-09 5.19E-09 3.27E-09 DIRECTION TO - SECTOR N =A E =E S =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 NNW = R Worst Case X/Q = 2.04E-05 sec/m 3 in Sector H 2004
I Reference PMP-6010-OSD-001 Rev. 20 Page 72 of 87 OFF-SITE DOSE CALCULATION MANUAL I
Attachment 3.16 10 .Year Average of 1995-2004 Data Pages: 71 - 72 I DIRECTION T D/Q DEPOSITION (1/m 2)
-DISTANCE (METERS)
I (WIND FROM) 594 2416 4020 5630 7240 N
NNE 2.37E-08 9.86E-09 2.29E-09 9.52E-10 1.04E-09 4.32E-10 5.44E-10 2.27E-10 3147E-10 1.45E-10 I,
NE 1.29E-08 1.25E-09 5.67E-10 2.97E-10 1.90E-10 ENE E
1.59E-08 1.87E-08 1.54E&09 1.81E-09 6.97E-10 8.20E-10 3.66E-10 4.30E-10 2.33E-10 2,75E-10 I
ESE 1.85E-08 1.79E-09 8.12E-10 4.26E-10 2.72E-10 SE SSE S
1.90E-08 2.40E-08 3.68E-08 1.83E-09 2.32E-09 3.56E-09 8.30E-10 1.05E-09 1.61E-09 4.36E-10 5.52E-10 8.46E-10 2.78E-10 3.52E-10 5.40E-10 I
SSW 2.30E-08 2.22E-09 1.O1E-09 5.28E-10 3.37E-10 SW WSW W
2.22E-08 2.11E-08 2.00E-08 2.15E-09 2.04E-09 1.93E-09 9.74E-10 9.23E-10 8.74E-10 5.1'IE-10 4.84E-10 4.59E-10 3.26E-10 3.09E-10 2.93E-10 I
WNW 1.75E-08 1.69E-09 7.64E-10 4.01E-10 2156E-10 NW NNW 1.58E-08 2.30E-08 1.53E-09 2.22E-09 6.94E-10 1.01E-09 3.64E-10
[ 5.28E-10 2.32E-10 3.37E-10 I DIRECTION (WIND FROM) 12067
_DISTANCE 24135 40225 (METERS)
]56315 80500 I,
N NNE NE 1.45E-10 6.36E-11 8.07E-11 4.72E-11 1.97E-11 2.58E-11 1.74E-11 7.24E-12 9.51E-12 9.27E-12 3.86E-12 5.07E-12 4.65E-12 l'94E-12 2154E-12 I
ENE 9.77E-11 3.17E-11 1.17E-I 1 6.23E-12 3.13E-12 E
ESE SE 1.14E-10 1.13E-10 1.16E-10 3.73E-11 3.70E-1I 3.78E-1I 1.37E-11 1.36E-11 1.39E-11 7.34E-12 7.26E-12 7.42E-12 3;68E-12 3.64E-12 3.72E-12 I
SSE 1.47E-10 4.79E-11 _I 1.76E-1_ 9.41E-12 4.72E-12 S
SSW SW 2.25E-10 1.41E-10 1.36E-10 7.34E-1I 4.59E-11 4.43E-11 2.70E- I11 "1.69E-11 1.63E-11 1.44E-11 9.01E-12 8.71E-12 7.23E-12 4.52E-12 4.37E-12 I
WSW 1.29E-10 4.20E-1I 1.55E-11 8.26E-12 4.14E-12 W
WNW 1.22E-10 1.07E-10 3.98E-11 3.48E- 1I 1.47E-11 1.28E-1I 7.82E-12 6.84E-12 3.92E-12 3:;43E-12 I NW 9.70E-11 3.16E- 11 1.16E-11 6.20E-12 3,11E-12 NNW DIRECTION TO - SECTOR 1.41E-10 4.58E-11 1.69E-11 9.OOE-12 4.52E-12 II N =A E =E- S =J W =,IN NNE NE ENE
=B
=C
= F
= G
= H
=K
=L
=M WNW NW NNW
= P
= Q
= R i
Worst Case D/Q = 4.46E-08 1/rn2 in Sector A 2001 I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 73 of 87 OFF-SITE DOSE CALCULATION MANUAL Annual Evaluation of ý/Q and D/Q Values For Page:
Attachment 3.17 j All Sectors 73
- 1. Performed or received annual update of ,/Q and D/Q values. Provide a description of what has been received.
, /
Signature Date Environmental Department (print name, title)
- 2. Worst /.Q and D/Q value and sector determined. PMP-6010-OSD-O01 has been updated, if necessary. Provide an evaluation.
/
Signature Date Environmental Department (print name, title)
- 3. Review nuclide mix for gaseous -and liquid release paths to determine if the dose conversion factor of total body is still applicable.. Provide an evaluation.
- /
Signature Date Environmental Department (print name, title)
- 4. Approved and verified by:
/
Signature Date Environmental Department (print name, title)
- 5. Copy to NS&A for information.
/
Signature Date Environmental Department (print name, title)
I Reference, PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL
[ Rev. 20 Page 74 of 87 I
Attachment 3.18 Dose Factors Pages:
74- 75 I I
DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*
TOTAL BODY SKIN DOSE GAMMA AIR' BETA AIR I
DOSE FACTOR FACTOR DOSE FACTOR DOSE FACTOR
.K (DFBi) mrem m3 Li (DFSi)
(mrem m 3 Mi (DF'i)
(mrad m 3 N, (DFO)
(mrad m 3 I RADIONUCLIDE per pCi yr) per p.tCi yr) per jiCi yr) per [Ci yr)
Kr-83m Kr-85m 7.56E-02 1.17E +03 1.46E+03 1.93E+01 1.23E+03 2.88E+02 1.97E-+ 03 I
Kr-85 Kr-87 1.61E+01 5.92E +03 1.34E.+03 9.73E+03 1.72E+01 6.17E+03 1.95E+03 1.03E+04 I Kr-88 1.47E+04 2.37E +03 1.52E+04 2.93E+03.
Kr-89 Kr-90 1.66E+04 1.56E+04 1.01E+04 7.29E+03 1.73E+04 1.63E+04 1.06E+04 7.83E+03 I
Xe-131m Xe-133m 9.15E+01 2.51E+02 4.76E+02 9.94E+02 1.56E+02 3.27E+02 1-11E+03 1.48E+03 I
Xe-133 2.94E+02 3.06E+02- 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 I Xe-135 1.81E+03 1.86E+03 1:.92E+03 2.46E+03 Xe-137 Xe-138 1.42E+03 8.83E+03 1.22E+04 4.13E+03 1.51E+03 9.21E+03 1.27E+04 4.75E+03 I
Ar-41 8.84E +03 2.69E+03 9.30E+03 3.28E+03 I
I I
- The listed dose factors are for radionuclides that may be detected in gaseous effluents, from Reg. Guide 1.109; Table B-1.
I I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 75 of 87 OFF-SITE DOSE CALCULATION MANUAL Dose Factors Pages: .18 1 74 -7 DOSE FACTORS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, IN GASEOUS EFFLUENTS FOR CHILD* Ref. 5.2.lee and ff Pi Pi INHALATION FOOD & GROUND PATHWAY PATHWAY RADIONUCLiDE (trem m 3 (mrem m2 sec per JLCi yr) per AtCi yr)
H-3 1.12E+03 1.57E+03#
P-32 2.60E+06 7.76E+10 Cr-51 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+08 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 l.013E+08 1.12E+11 Y-91 '2.63E+06 6.72E+06 Zr-95 2.23E+06 3.44E-+ 08 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-110m 5.48E+06 1.99E+10 1-131 1.62E+07 4.34E+ 11 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 1.01E+06 4.OOE+10 Cs-136 1.71E+05 3.OOE+09 Cs-137 9.07E+05 3.34E+ 10 Ba-140 1.74E+06 1.46E+08 Ce-141 5.44E+05 3.31E+07 Ce-144 1.20E+07 1.91E+08
- As Sr-90, Ru-106 and 1-131 analyses are performed, THEN use Pi given in P-32 for nonlisted radionuclides.
3
' The units for both H3 factors are the same. mrem M per 1iCi yr
Reference PMP-6010-OSD-001 Rev. 20 Page 76 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
Attachment 3.19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies Pages:
76 - 79 I
[Ref. 5.2.1v, 5.2.1x, 5.2.1t]
SAMPLE STATION I DESCRIPTION/
LOCATION SAMPLE TYPE SAMPLE FREQUENCY ANALYSIS TYPE ANALYSIS FREQUENCY I
ON-SITE AIRBORNE AND DIRECT RADIATION (TLD) STATIONS ONS-l (T-I) 1945 ft @ 180 from Plant Axis Airborne Particulate Weekly Gross Beta Gamma Isotopic Weekly Quart. Comp.
I Airborne 1-131 Weekly ONS-2 (T-2) 2338 ft @ 480 from Plant Axis Radioiodine TLD" Airborne Particulate Quarterly Weekly Direct Radiation Gross Beta Quarterly Weekly I
Gamma Isotopic Quart. Comp.
ONS-3 (T-3)
_ _ _TLD 2407 ft @ 90* from Plant Axis Airborne Radioiodine Airborne Particulate Quarterly Weekly 1-131 Direct Radiation Gross Beta Weekly i Quarterly
[Weekly I
Gamma Isotopic 1Quart. Comp.
Airborne Radioiodine
__TLD Quarterly 1-131 Direct Radiation Weekly Quarterly I
ONS-4 (T-4) 1852 ft. @ 118- from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Airborne Radioiodine TLD. Quarterly Gamma Isotopic 1-131 Direct Radiation Quart. Comp.
Weekly Quarterly I
ONS-5 (T-5) 1895 ft @ 1890 from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.
Airborne 1-131 1Weekly ONS-6 (T-6) 1917 ft @ 2100 from Plant Axis Radioiodine TLD' Airborne Particulate Quarterly Weekly Direct Radiation Gross Beta I[Quarterly Weekly I
- Gamma Isotopic I Quart. Comp.
Airborne 1-131 Weekly Radioiodine T-7 T-8 T-9 -.
2103 ft @ 360 from Plant Axis 2208 ft @ 820 from Plant Axis 1368 ft @ 1490 from Plant Axis TLD TLD TLD TLD Quarterly Quarterly Quarterly Quarterly Direct Radiation Direct Radiation Direct Radiation Direct Radiation Quarterly Quarterly Quarterly Quarterly I
T-10 T-11 T-12 1390 ft @ 1270 from Plant Axis 1969 ft @ 110 from Plant Axis 2292 ft @ 630 from Plant Axis TLD TLD TLD Quarterly Quarterly Quarterly Direct Radiation Direct Radiation Direct Radiation Quarterly Quarterly Quarterly I
CONTROL AIRBORNE AND DIRECT.RADIATION (TLD) STATIONS NBF 15.6 miles SSW New Buffalo, MI Airborne Particulate Weekly Gross Beta Gamma Isotopic Weekly
((Quart. Comp.
,I Airborne Radioiodine 1-131 Weekly SBN 26.2 miles SE South Bend, IN TLD Airborne Particulate Airborne Radioiodine Quarterly Weekly Direct Radiation Gross Beta Gamma Isotopic 1-131 Quarterly Weekly Quart. Comp.
Weekly U
TLD Quarterly Direct Radiation Quarterly DOW 24.3 miles ENE Dowagiac, MI Airborne Particulate Airborne Radioiodine Weekly Gross Beta Gamma:Isotopic 1-131 -
Weekly Quart. Comp.
Weekly I
TLD Quarterly Direct Radiation Quarterly COL 18.9 miles NNE Coloma, MI Airborne Particulate Airborne Radioiodine Weekly Gross Beta Gamma Isotopic 1-131
,Weekly Quart. Comp.
Weekly I
TLD Quarterly " Direct Radiation iQuarterly I
I
Reference PMP-6010-OSD-001 Rev. 20. Page 77 of 87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.19 Radiological Environmental Monitoring Program Pages:
Sample Stations, Sample Types, Sample Frequencies 76 - 79 SAM[PLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY OFF-SITE DIRECT RADIATION (TLD) STATIONS OFT-I 4.5 miles NE, Pole #B294-44 TLD Quarterly Direct Radiation Quarterly OFT-2 3.6 miles, NE, Stevensville TLD Quarterly Direct Radiation Quarterly Substation OFT-3 5.1 miles NE, Pole #B296-13 TLD Quarterly Direct Radiation Quarterly OFT-4 4.1 miles, E, Pole #B350-72 TLD Quarterly Direct Radiation Quarterly OFT-5 4.2 miles ESE, Pole #B387-32 TLD Quarterly Direct Radiation Quarterly OFT-6 4.9 miles SE, Pole #B426-1 TLD Quarterly Direct Radiation Quarterly OFT-7 2.5 miles S, Bridgman Substation TLD Quarterly Direct Radiation Quarterly OFT-8 4.0 miles S, Pole #B424-20 TLD Quarterly Direct Radiation Quarterly OFT-9 4.4 miles ESE, Pole #B369-214 TLD Quarterly Direct Radiation Quarterly OFT-10 3.8 miles S, Pole #B422-99 TLD Quarterly Direct Radiation Quarterly OFT-I1 3.8 miles S, Pole #B423-12 TLD Quarterly Direct Radiation Quarterly GROUNDWATER (WELL WATER) SAMPLE STATIONS W-1 1969 ft @ 110 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-2 2302 ft @ 630 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-3 3279 ft @ 1070 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-4 418 ft @ 3011 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-5 404 ft @ 290' from Plant Axis . Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-6 -. 424 ft @ 273' from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-7 1895 ft @ 189' from Plant Axis Groundwater. Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-8 1274 ft @ 540 from Plant Axis . Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-9 1447 ft @ 22* from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly
__Tritium Quarterly W-10 4216 ft @ 1290 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly.
Tritium Quarterly W-I 1 3206 ft @ 1530 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-12 2631 ft @ 1620 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-13 2152 ft.@ 1820 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-14 1780 ft @ 1640 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly W- 15 _ Tritium Quarterly W-15 725 ft @ 2020 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-12C Tritium Quarterly DRINKING WATER STJ St. Joseph Public Intake Sta. 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. Comp.
LTW Lake Twp. Public Intake Sta. Drinking water Once per calendar Gross Beta 14 day Comp.
0.6 mi. S . Day Gamma.lsotopic 14 day Comp.
1-131 14 day Comp.
Tritium Quart. Comp
I Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 78 of 87 I
Attachment 3.19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies Pages:
76 - 79 I I
I I
SEDIMENT SL-2 Plant Site Boundary - South
- 500 ft. south of Plant Centerline Sediment Semi-Ann. Gamma Isotopic Semi-Annual I
SL-3 Plant Site Boundary - North Sediment Semi-Ann. Gamma Isotopic Semi-Annual SL-4
- 500 ft. north of Plant Centerline Plant Site Boundary - South-South storm drain culvert to lake Sediment Quarterly .Gamma Isotopic Quarterly I SL-5 Plant Site Boundary - North Sediment. Quarterly Gamma Isotopic Quarterly North storm drain culvert to lake SL-4 & 5 are data collection points only not actual REMP samples I
GROUNDWATER (RADIOACTIVE MATERIAL STORAGE FACILITY [MAUSOLEUM]) SAMPLE STATIONS SG-1 0.8 mi. @ 95' from Plant Axis Groundwater Quarterly Gross Alpha Gross Beta Quarterly
. Quarterly I
Gamma Isotopic ,!Quarterly SG-2 0.7 mi. @ 92' from Plant Axis Groundwater Quarterly Gross Alpha Gross Beta Gamma Isotopic iQuarterly
]/Quarterly Quarterly I
SG-4 0.7 mi. a 93' from Plant Axis Groundwater Quarterly Gross Alpha ýQuarterly SG-5 0.7 mi. @ 92' from Plant Axis. Groundwater Quarterly Gross Beta Gamma Isotopic Gross Alpha Gross Beta Quarterly IIQuarterly j[Quarterly rQuarterly I
Gamma Isotopic Quarterly SG-l, 2, 4 and 5 are data collection points only not actual REMP samples_ I INGESTION - MILK Indicator Farms" Milk Milk Once every 15 days Once every 1-131 Gamma Isotopic 1-131
-per sample
'per sample 1per sample I
15 days Gamma Isotopic iper sample Milk Once every 15 days 1-131 Gamma Isotopic
!ýper sample "per sample U INGESTION - MILK Background Farmsn Milk Milk Once every 15 days Once every
[1-131 Gamma Isotopic
.1-131 iper sample per sample
!per sample I
15 days Gamma Isotopic per sample I
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 79 of .87 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.19 Radiological Environmental Monitoring Program Pages:
Sample Stations, Sample Types, Sample Frequencies 76 - 79 SAMPLE DESCRIWIrON/ SAMPLE SAMPLE" ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY INGESTION - FISH ONS-N j 0.3 mile N, Lake Michigan Fish - edible portion [ 2/year Gamma Isotopic per sample ONS-S 1 0.4 mile S.- Lake Michigan Fish - edible portion 2/year Gamma Isotopic per sample OFS-N 3.5 mile N, Lake Michigan Fish -. edible portion 2/year Gamma Isotopic per sample OFS-S 5.0 mile S. Lake Michigan Fish - edible portion 2/year Gamma Isotopic per sample INGESTION - BROADLEAF IN LIEU OF MILK 3 indicator samples of broad leaf vegetation Broadleaf Monthly Gamma Isotopic Monthly collected at different locations, within eight vegetation when available 1131 when available miles of the plant in the highest annual average D/Q land sector.
I background sample of similar vegetation Broadleaf Monthly Gamma Isotopic Monthly grown 15-25 miles distant in one of 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 for gross beta activity 24 or more hours following filter removal. This will allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, perform gamma isotopic analysis on the individual samples.
If at least three indicator milk samples and one background milk sample cannot be 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, one 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 milk indicator and two background farms will be determined by the Annual Land Use Census and those that are willing to participate. IF it is determined that the milk animals are fed stored feed. THEN monthly sampling is appropriate for that time period.
Reference PMP-6010-OSD-001 Rev. 20 Page 80 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I Maximum Values for Lower Limits of DetectionsA,'B - REMP Pages:
Attachment 3.20 80 -.81 I
[Ref. 5.2. Iv]
Radionuclides Food Product pCi/kg, wet Water pCi/1 Milk pCi/!
Air Filter pCi/m3 Fish pCi/kg, wet "Sediment pCi/kg, dry I
Gross Beta H-3 4'
2000 0.01 I
Ba-140 60 60 La-140 Cs-134 60 15 15 15 15 0.06 130 150 I
Cs-137 Zr-95 60 18 30.
18 0.06 150 180 I
15 Nb-95 Mn-54 15 130 I Fe-59 30 260 Zn-65 Co-58 30 15 260 130 I
Co-60 1-131 60 15 1 1 0.07 130 I
This Data is directly from our plant-specific Technical Specification.
I
- LLD for drinking water I
I I
I I
I I
I
Reference PMP-6010,OSD-001 Rev. 20 Page 81 of 87 OFF-SITE DOSE CALCULATION MANUAL .20 Maximum Values for Lower Limits of DetectionsA'B - REMP Pages:
80-81 J NOTES A, The Lower Limit of Detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will be detected with 95% probability and 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation), the LL) is given by the equation:
LLD = 4.660
- S E*V* 2.22*Y*e(A'I)
Where LLD is the aapriorialower limit of detection as defined'above (as pCi per unit mass or volume). Perform analysis in such a manner that the stated LLDs 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 LLD represents the capability of a measurement system and not as an after the fact limit for a particular measurement.
S is the standard deviation of the background counting rate or of the counting rate of a blank sample.as appropriate (as counts per minute).
E is the counting efficiency of the detection equipment as counts per transformation (that is, disintegration)
V is the sample size in appropriate mass or volume units 2.22 is the conversion factor from picocuries (pCi) to transformations (disintegrations) per minute Y is the fractional radiochemnical 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 measurable and identifiable, together with the radionuclides listed in Attachment 3.20, Maximum Values for Lower Limits of DetectionsAB - REMP.
A 2.71 value may be added to the equation to provide correction for deviations in the Poisson distribution at low count rates, that is, 2.71 + 4.66 x S.
Reference PMP-6010-OSD-001 Rev. 20 Page 82 of 87 I
OFF-SITE DOSE CALCULATION MANUAL I
Attachment 3.21 Reporting Levels for Radioactivity Concentrations Page:
in Environmental Samples 82 I
Radionuclides Food Product pCi/kg, wet Water pCi/1 Milk pCi/l Air Filter pCi/m 3 Fish pCi/kg, wet I
H-3 20000 Ba-140 La-140 200 200 300 300*
I Cs-134 Cs-137 1000 2000 30 50 601 70 10 20 1000 2000 I
Zr-95 Nb-95.
400 400 I Mn-54 1000 30000 Fe-59 Zn-65 400 300 10000 20000 I
Co-58 Co-60 1000.
300 30000 10000 I 1-131' 100 2 3 0.90 I
IF any of the above concentration levels are exceeded THEN submit a 30 day special report using the guidance supplied in PMP-7030-001-002, Licensee Event Reports, Special and Routihei local officials about this exceedance also.
Reporting. Consider informing the State of Michigan and I
I I
I I
I I
I I
I Reference PMP-6010-OSD-001 Rev. 20 Page 83 of 87 OFF-SITE DOSE CALCULATION MANUAL Page: .22 On-Site Monitoring Location - REMP 83 ONS-South ONS-North Surface Water TLD T-6 TLD) T-5 SWL-3 Air ONS- Air ONS-5 Surface Water Wll W-6 Well 6L 'L_ / / ~Sediment SWL-2 S,-2 */ /LW_ /w Sediment SL-3 Well LEGEND ONS ONS-6: Air Sampling Station T T-12: TLD Sampling Station W-1 -W-15: REMP Groundwater Wells SWL- 2, 3: Surface Water Sampling Stations SL-2 SL-3: Sediment Sampling Stations ONS-N & S: Fish sampling locations SG-1, 2, 4 and 5: Non REMP information Wells
Reference PMP-6010-OSD-001 Rev. 20 Page 84 of 87 OFF-SITE DOSE CALCULATION MANUALI .23
,o12PZ~L~tf 7 I7O Off-Site Monitoring Locations - REMP M 0Mie84 Page:
81 Legend Coloma SubstationIt Offsite REMP Moniong Locations Background
':C AiTLi,. (:
OL;ý.'*I - ;; =#
ii] l}1't iet.:
HOFo-1 r .. * ý* -", Ra di:
- OFT-Background 11: TLD AirrrLD Locations Stations [ [*c1ii.
i;- ! * !31/'16 ..
Drinking Water Locations Indicator Milk Farm Locations B S:
.B 1. __ I Background Milk Farm Locations OFS Oftite Fish locations Ha"i,, ilug i,~l
.- . . St Jose1 h %Nater .1 C TLD OFT3 (DOW)
~
TLD OFT-4 n ea ~.i -. i~ *ae
":' "" 'q">
!T
-' Substation TLD eOFT r5 t n..... . l;"
D.C. Cook 1 Lake Tonolý Berrrieeme
- F TLDOFr-7 (LTVA Plant -S uh '
- - q;]-
J. Monro
,:',r
. M5140 I
- M-O C .;. I!.
TILD OFT- 11 TLD OFr-TB 4 -
, TLD OFT-69 ew.... 1_y ..Cleveland Rd . ..
H. rere a t ,94 d -~ 'L, :-1--"
New Buffalo10 j I Substation
. . -n . L .
Backgroundo leaThr.e Vjý I
.*~...;*. -131 Bypass
- i;,*:.I
- i"b' ' . .j: .':";*:*
Lapol acround
'VHwy 20
~
Rolling rieSouth
~&jA 2 Bend Milk Farm Ray Livinghouse o ~ w.2 Hwy ~ ~ Kankakee StationI
- Background Hwy 23 .'-Air ."LD (SBN)3
Reference PMP-6010-OSD-001 Rev. 20 Page 85 of 87 OFF-SITE DOSE CALCULATION MANUAL Safety Evaluation By The Office Of Nuclear Pages:
Attachment 3.24 Reactor Regulation 85-87 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO DISPOSAL OF SLIGHTLY CONTAMINATED SLUDGE INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316 [Ref. 5.2.1r]
(This is a 10 CFR 50.75 (g) item)
L INTRODUCTION By letters dated October 9, 1991, October 23, 1991, September 3. 1993, and September 29, 1993, Indiana Michigan Power Company (I&M) requested approval pursuant to 10 CFR 20.2002 for the on-site disposal of licensed material not previously considered in the Donald C. Cook Nuclear Plant Final Environmental 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 sump absorption pond and pumped to the upper parking lot located within the exclusion area of the Donald C. Cook Nuclear Plant. The contaminated sludge was spread over an area of approximately 4.7 acres. The sludge contained a total radionuclide inventory of 8.89 millicuries (mCi) of Cesium-137, Cesium-136, Cesium-134, Cobalt-60 and. Iodine- 131.
In its submittal,, the licensee addressed specific information requested in accordance with 10 CFR 20.2002(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated information pertinent to the impacts on the environment of the proposed disposal of licensed material, and committed to follow specific procedures to minimize the risk of unexpected exposures.
- 2. DESCRIPTION OF WASTE The turbine room sump absorption pond isa 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 sump, a recognized release pathway. Sludge, consisting mainly of leayes and-roots mixed with 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 pumped to a containment area located within'the exclusion area. The total volume of 942 cubic meters of the radioactive sludge that was dredged from the bottom. of the turbine room absorption pond was subsequently spread and made into a graveled road over the upper parking lot area of approximately 4.7 acres.
The principal radionuclides identified in the dredged material are listed below.
TABLE 1 NUCLIDE ACTIVITY (mCi) ACTIVITY (mCi)
(half-life) 1982 1991 36
" Cs (13.2 d) 0.03 NA*
134Cs (2.1 y) 2.34 0.18 131Cs (30.2 y) 5.59 4.57 6°Co (5.6 y) 0.90 0.27 1311 (8.04 d) 0.03 NA*
TOTAL: .8.89 5.02
- NA: not applicable due to decay
I Reference PMP-6010-OSD-Q01 OFF-SITE DOSE CALCULATION MANUAL Rev. 20 Page 86 of 87 Pages:
1 Attachment 3.24 Safety Evaluation By The Office Of Nuclear Reactor Regulation 85-87
- 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:
(1) 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. 3 The staff has reviewed the licensee's calculational methods and assumptions and finds that they are consistent with NUREG-I101, "Onsite Disposal of Radioactive Waste," Volumes I and 2, November 1986 and February 1987, respectively. The staff finds the assessment methodology acceptable. Table 2 lists the doses calculated by the licensee for the maximally exposed member of the public based on a total activity of 8.89 mCi disposed in that year.
TABLE 2 Pathway Whole Body Dose Received by I
Maximally Exposed Individual (mrem/year) I Groundshine 0.94 Inhalation Groundwater Ingestion 0.94 0.73 U
Total 2:61 On July 5, 1991, the licensee re-sampled the onsite disposal area to assure that no significant impacts and adverse effects had I
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-sampling 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.
I
- 4. ENVIRONMENTAL FINDING AND CONCLUSION The staff has evaluated the environmental impact of the proposal to leave in place approximately 942 cubic meters of slightly contaminated sludge underneath the upper parking lot on the Donald C.. Cook Nuclear Plant site.
I In 1982, the licensee evaluated the potential exposure to members of the general public from the 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 mrem/yr. The staff has reviewed the licensee's calculational methods and assumptions and I
found that they are consistent with NUREG-1 101, Onsite Disposal of Radioactive Waste, Volumes 1 and 2,' November 1986 and February 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 a whole-body dose rate of about 89 mrem 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-I sampling by the licensee, confirm that the environmental impact of the 1982 disposal was yery 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 I
the least impact to the environment.
I I
Reference PMP-6010-OSD-001 Rev. 20 Page 87 of 87 OFF-SITE DOSE CALCULATION MANUAL Safety Evaluation By The Office Of Nuclear Pages:
Attachment 3.24 Reactor Regulation 85 - 87
- 5. CONCLUSION Based on the staff's review of the licensee's discussion, the staff finds the licensee's proposal to retain the material in its present location as documented in this Safety Evaluation acceptable. Also, this Safety Evaluation shall 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, September 29, 1993 Therefore, the licensee's proposal to consider the slightly contaminated sludge disposed by retention in place in the manner described in the Donald C. Cook Nuclear Plant submittals date October 9, 1991, October 23, .1991, September 3, 1993, and September 29, 1993, is acceptable.
The guidelines used by the NRC staff for onsite disposal of licensed material and the staff's evaluation of how each guideline has-been satisfied are given in Table 3..
Pursuant to 10 CFR 51.32, the Commission has determined that granting of this approval will have no significant impact on the environment (October 31, 1994, 59 FR 54477).
Principal Contributor: J. Minas Date: November 10, 1994 TABLE 3 20.2002 GUIDELINE FOR ONSITE STAFF'S EVALUATION DISPOSALV I The radioactive material should be disposed of in such I. Due to the natureof the disposed material, recycling to the a manner that it is unlikely that the material would be general public is not considered likely.
recycled.
- 2. Dose5 to the total body and any body organ of a. 2. This guideline was addressed in Table 2. Although the maximally exposed individuals (a member of the 2.61 mrem/yr is greater than staffs guidelines, the staff general public or a non-occupationally exposed worker) finds it acceptable due to 9 yrs decay following analysis and from the probable pathways of exposure to the disposed the expected lack of activity detected in the 1991 survey.
material should be less than 1 mnrem/year.
- 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 exposure should be less than 5 mrem/year. the 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 maximally exposed member of the material at the time the disposal site is released from public is not expected to exceed I mrem/year, based on regulatory control from all likely pathways of exposure exposure scenarios considered in this analysis.
should be less than, I mrem.
E. F. Branagan, Jr. and F. J. Congel. "Disposal of Contaminated Radioactive Wastes from Nuclear Power Plants,"
presented at the Health Physics Society's Mid-Year Symposium on Health Physics Consideration in Decontamination/Decommissioning,.Knoxville, Tennessee, February 1986, (CONF-860203).
Document No.: PMP-6010-OSD-001 Revision No.: 021
Title:
OFF-SITE DOSE CALCULATION MANUAL Alteration Category: Minor Revision CDI/50.59 No(s): N/A PORC Mtg. No.: 4244 CR No.: 06058026 Superceding Procedure(s): N/A Temporary Procedure Expiration Date:
Temporary Change Expiration Date:
Temporary Procedure/Change Ending Activity: N/A Effective Date: 31 -Jul-2006 12:00:00 AM Approvals Name J*eview/Approval Type/Capacity jDate Hamer, Jon Technical Review 24-Jul-2006 01:31:09 PM Newmiller, Julie PORC 28-Jul-2006 01:05:05 PM Mott], Teri Approval Authority 3 1-Jul-2006 07:32:19 AM Signature Comments PROCEDURE APPROVAL AUTHORIZED BY L. WEBER, PLANT MANAGER. TLM Document Number: PMP-6010-OSD-001 Revision: 021 Page I of 1
REVISION
SUMMARY
I Procedure No.
Title:
PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. No.: 21 I
-. Alteration .. Justification Revision 'was created to address comments I
General 7 i-identified as part. of the, "D.C. Cook..
Nuclear Plant Groundwater Protection Project Charter" generated in response to the I
Nuclear Energy Institutes, "Industry Initiative on Managing Situation Involving Inadvertent Radiological Releases to Groundwater" (CR I
'10 CFR 50.59 is not applicable to this 06058026).
Per definition in Attachment 1 of PMP-2010-I procedure revision. PRC-002. This .is an administrative procedure governing the conduct of facility Operations.
o I Se&tion 2 Definitions and Abbreviations: Pdr PMP-2010-PRC-002, Edit~rials Added. the definition, of Total Fractional Level (TFL). .from Correction Criteria "q" moyed definition the procedure body to the definition I
section 'to clarify wor~ding.
- Step 3.5.2a.4 and a.5: Re'iorded and added- Per PMP-2010-PRC-002, Editorial I clarifying information on report and . . Correction.Criteria "p" added clarifying communications'. ... , S. hinformation.and reworded which does not
.. ].change, intent.%Moved definition of TFL to I
..- ,: section 2 Definition's for clarity. .19: Deletedfefeierice to non-REMP samples in the 'Groundwater Well' Per PMP-2010-PRC-002, Editorial Correction Criteria "p" removed references I
Water Sample Stations' and 'Sediment' . to non-REMP 'samples. Information appears sections. elsewhere in' appropriate plant documents (OSDL-001, section 3.6 and RPP-401 data I
sheet 5). .21: Reworded attachment note to provide users with guidance if limits are Per PMP-2010-PRC-002, Editorial Correction Criteria "p" added clarifying I
exceeded.. 'information and reworded which. does not change. intent. Refers user to appropriate procedure steps for guidance.
I I
I Office Informationfor Form Tracking Only - Not Part of Form I
This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 1 of 1 I
I
PMP-6010-OSD-001 Rev. 21 Page 1 of 91 OFF-SITE DOSE CALCULATION MANUAL Reference Doug Foster Environmental Manager Environmental Writer Document Owner Cognizant Organization-TABLE OF CONTENTS I PURPOSE AND SCOPE ...................... ..................................................... 4 2 DEFINITIONS AND ABBREVIATIONS .................................................... 4 3 DETAILS ..... .. .................. 6 3.1 Calculation of Off-Site Doses ........................ 6 3.1.1 Gaseous Effluent Releases ........................................................ 6 3.1.2 Liquid Effluent Releases-........... 11 3.2 Limits ofOperatiob and Surveillances of the Effluent Release Points ........ 14 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation .......... 14 3..2.2. Radioactive Gaseous Effluent Monitoring Instrumentation ....... ...... 16 3.2.31 Liquid Effluents........................ .................. 17
.,a. Concentration Excluding Releases via the Turbine Room Sump:,,_,
- b. (TR S) Discharge ..;.-.. ........................................................ 17
- b. Concentiatioin of Releases from the TRS Discharge ................. 17 S Dose ......... . ......... . . . ...... . ........ ............ .. 18 d., Liquid Radwste fregtmentSystem . ..... ............ '.....18 3.2.4 Gaseous Effluents........................ . .21 a.. D ose Rate.......... ..... ...................................................... 21
- b. Dose - Noble-Gases ....................................................... 21
- c. Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material
. in Particulate Form ...................... . ..................................22
- d. Gaseous Radwaste Treatment..........................*22 3.2.5 Radioactive Effluents - Total Dose .......................................... 25 3.3 Calculation of Alarm/Trip Setpoints .................................................. 26 3.3.1 Liquid Monitors ......................................... 27
- a. Liquid Batch Monitor Setpoint Methodology ......................... 27
- b. Liquid Continuous Monitor Setpoint Methodology .................. 28 3.3.2 Gaseous Monitors .................................... 30
- a. Plant Unit V ent ............................................................ 30
- b. W aste Gas Storage Tanks ............................................... 33
- c. Containment Purge and Exhaust System.................... 34
- d. Steam Jet Air Ejector-System (SJAE) .: ............. ..... 35
- e. . Gland Seal Condenser Exhaust............... ............................ 35
EI-CTR PMP-6010-OSD-001 Rev. 21 Page 2 of 91 OFF-SITE DOSE CALCULATION -MANUAL Reference Doug Foster Environmental Manager Environmental Writer Document Owner Cognizant Organization 3.4 Radioactive Effluents Total Dose ................ ................ ................... 36 3.5 Radiological Environmental Monitoring Pi3ogram (REMP) ...................... 36 3.5.1 Purpose'of the REMP ................ ............................. 36 3.5.2 Conduct of the REMP ......... .................. 37 3.5.3 Annual Land Use Census. ................................ ... ........ 39 3.5.4 Interlaboratory Comparison Program ........................................ 40 3.6 Radioactive Equipment Storage Facility (Mausoleum) Groundwater Monitoring Program .................................... ...... 40 3.6.1 Purpose of the Radioactive Equipment Storage Facility (Mausoleum)
Groundwater Radiological Monitoring Program ........ ........40 3.6.2 Conduct of the Radioactive Equipment Storage Facility (Mausoleum)
Groundwater Radiological Monitoring Program,:.......................... 41' 3.7 M eteorological. M odel........ .............; ..........: .......................... ... 41 3.8 Reporting Requirements ................. ..... ........................
..... ......... 41 3.8.1 Annual Radiological Environmental Operating Report (AREOR) ..... 41 3.8.2 Annual Radiological Effluent Release Report (ARERR) ....... ......... 42 3.9 10 CFR 50.75 (g) Implementation ............................ ....................... 44 3.10 Reporting/Management Review ........... .............. ............................ 44 4 FINAL CONDITIONS ............... ! ...................................... 45 5 REFERENCES .................................................... *. 45.
SUPPLEMENTS I .1 Dose Factors for Various Pathways .............................................. Pages 48- 51 Ar .2 Radioactive Liquid Effluent Monitoring Instruments............Pages 52-54 .3 Radioactive Liquid Effluent Monitoring InstrumentationI Surveillance Requirements ................................................ ..... Pages 55 - 56 .4 Radioactive Gaseous Efflu~ent Monitoring Instrumentation .......... Pages 57 - 59
M AMAIW" PMP-6010-OSD-001 ' Rev. 21 Page 3 of 91 OFF-SITE' DOSE CALCULATION MANUAL Reference D6ug Foster Environmental Manager Environmental Writer Document Owner Cognizant Organization .5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirem ents ............................................................. Pages 60 -61 .6 Radioactive Liquid Waste Sampling and Analysis Program, ....... .Pages 62 - 63 .7' Radioactive Gaseous Waste Sampling and Analysis Program ..... Pages 64 - 65 .8 Multiple Reldase Point Factors for Release Points ............... Page 66 .9 Liquid Effluent Release Systems ............... ............................. Page 67 .10 Plant Liquid Effluent Parameters ........................... ...................... Page 68 .11 Volumetric Detectionl Efficiencies for Pijhcip1e Gamma Emitting 'Radionuclidesfor Eberlihne Liquid Monitors.. .......... Page 69 .12 Counting Efficiency Curves for,R-19,,and R-24...................... Pages 70 - 71 Attachment, 3.13 Counting Efficiency Curve for R-20, and R-28! ......... Page 72 Ga'seous-Effluent Release Systems .......... ...' ' Page 73 Attachmeht 3.14: .15 Plant Gaseous Effluent Parameters - .... .................. Page 74 .16 10 Year Average of 1995-2004 Data ......................... ................ Pages 75 - 76 . 17 Annual Evaluation of X/Q and D/Q Values ForAll Sectors...-............. Page 77 Attachment' 3.18 D ose Factors ........ :................................................. ......... Pages 78 - 79 .19 Radiological. Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies ............................... Pages 80 - 83 .20 Maximum Values for Lower Limits of DetectionsAB - REMP ..... Pages 84 - 85 .21 Reporting Levels for Radioactivity Concentrations in Environmental Samples .................................. Page-86 .22 On-Site Monitoring Location - REMP ..................... . : ............... Page 87 .23 Off-Site Monitoring Locations'- REMP....................... Page 88 .24 Safety Evaluation By The Office Of Nuclear Reactor Regulation ....................................... Pages 89 91
Reference PMP-6010-OSD-001 7 Rev. 21 Page 4 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
PURPOSE AND SCOPE I
NOTE: This is an Administrative procedure and only the appropriate sections need be
-performed per PMP-2010-PRC-003, step 3.2.7.
I The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the, I
Radioactive Effluent Controls Program (RECP), contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as defined in NUREG-0472, and fully implements the requirements of I
Technical Specification 5.5.3, Radioactive Effluent Controls Program.
- ie 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 I
calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.
The ODCM provides flow diagrams detailing the treatment path and the major I
components of the radioactive liquid and gaseous waste management systems.
The ODCM presents maps of the sample locations and the meteorological I
model used to estimate the atmospheric dispersion and deposition parameters.
- The ODCM.specificaily addresses the design characteristics of the Donald I
C: Cook Nuclear Plant based onithe flow diagrams contained on the "OP Drawings" and plant "System- Description" documents.
I 2 DEFINITIONS AND ABBREVIATIONS I
Term: Meaning:
S or shiftly D or daily W oi weekly' At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> At least' once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s*
At least once per 7 days I
M or monthly Q or quarterly' SA or semi-annually At least once per'31, days At least once per 92 days At least once per 184 days I
R At least once per 549 days.
S/U Prior to each reactor startup P
B Completed prior to each release At least once per 24 months I
Sampling evolution Process of changing filters or obtaining grab samples I I
I I
- Reference PMP-6010-OSD-001 Rev. 21 Page 5 of 91 i OFF-SITE DOSE CALCULATION MANUAL Member(s) of All persons who are not occupationally associated with the Public plant. Does not include employees of the utility, its contractors. or its vendors. Also excluded from this category are persons.who enter the site to service equipment or to make. deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
Purge/purging The controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner
'that replacementt air or gas is required to purify. the confinement' Source check The qualitative assessment of Channel response when the
'Channel sensor-is exposed to aradibactive source.
Total Fractional Level (TFL) Total Fractional Level is defined as:
TFL = +C2)
-C(l) >_
L(j) L(2)
Where;
-C(j) . -Concentration of 1' detected nuclide C(2) . Concentration of 2 d.detected nuclide
'_l :=. Reporting Level of isI nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.
L(2) = ,'Reporting, LeYelWof 2 "dnuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.-
Venting Cohitrolled process of discharging air or gas from a confinement to maintain temperature, pfessure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is!not provided.or required.
Vent, used in system names, does not imply a venting process.
Reference T PMP-6010-OSD-001 Rev. 21 _Page 6 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
3 3.1 DETAILS Calculation of Off-Site Doses I
3.1.1 Gaseous Effluent Releases I
- 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 I
,the following subprograms:
- MIDER I
- MIDEX MIDEL MIDEG MIDEN I
- b. The subprogram used to enter and edit gaseous release data is called MD1EQ (EQ). The data entered in EQ can be used to calculate the I
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 I
for use in Reg. Guide 1.21 reports and 10 CFR 50 Appendix I calculations based on routine releases.
I cl. The -formula used for-the calculation- of the air dose is generated from site specific parameters and Reg. Guide 1. 109 (Eq 7):
Dr,D0air:X*Z[(M, or N* Q,* 3.17E-8]
I Q I Where; DY, Dp air = thegamma or beta air dose in mrad/yr to an I individual receptor
"/Q the annual average or real time atmospheric I dispersion factor over land, sec/m 3 from Attachment 3.16, 10 Year Average of 1995-2004 Data I the- gamma air dose factor, mrad in 3 / yr MCi, Mi =
from Attachment 3.18, Dose-Factors I N the beta air dose factor, mrad in 3 yr ACi, from
=
Attachment 3:18, Dose Factors I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 7 of 91 OFF-SITE DOSE CALCULATION MANUAL Qi = the release rate of radionuclide, "i", in MCi/yr.
Quantities are determined utilizing typical concentration times volumes equations that are documented in 12-THP-6010-RPP-606, Preparation of the Annual Radioactive Effluent Release Report.
3.17E-8 -= number of years in'a second (years/second).
- d. The value for the ground average ,./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).
X/Q=_ 2.03
-*x* zyg
- T rg
'Where;
-2 minimum or g=
x = distance downwind of the source, meters. This
-. information is.found in-parameter,5 of(MIDEX.
u., = wind speed for ground release, (meters/second)
= vertical dispersion coefficiefit for ground release, (meters),
(Reg. Guide 1.111 Fig.1)
H,= building height (meters) from parameter 28 of MIDER.
(Containment Building = 49.4 meters)
Tf = terrain factor (= 1 for Cook Nuclear Plant) because we consider all our releases to be ground level (see parameter
.5 in MIDEX).
2.03 = 2/-÷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.
Reference T PMP-6010-OSD-001 Rev. 21 Page 8 of 91 I OFF-SITE, DOSE CALCULATION MANUAL I
- f. Calculations are based on the environmental pathways-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 I
g.
from the MIDEG file.
The formulas used for the following calculations are generated from I
site specific parameters and Reg. Guide 1.109:
- 1. Total Body Plume Pathway (Eq 10) -
I Dose (mrem/year) 3.4 7E - 8* (Q, *Z/Q* Sf *DFB,) I Where; Sf = shielding factor that accounts for the dose reduction due I
'- to shielding provided by residential structures during o:6ccupancy (mfkinmum exposed individual = 0.7 per Table E-15 of Reg. Guide 1.109) I
- DFBi. =the whole body dose factor from Table B-1 of Reg.
- Guide 1.109, mrem - m3 per ICi - yr. See Attachment I 3.18, 1 DoseFactors.
Q = the release rate of radionuclide "i", in [Ci/yr I S 2. Skin Plume Pathway (Eq 11)'
I Dose (mrem/yr)=3.17E- 8* S1 *[Z, (Q,, 1.11
- DFY) + (Q
- DFS,)]
Where; .
I 1.11 = conversion factor, tissue to air, mrem/mrad I DF iY 'the gamma air dose factor for a.uniform semi-infinite 1 cloud of radionuclide "i", in mrad m3//LCi yr from Tableý B- 1, Reg. Guide 1.109. See Attachment 3.18, I
Dose Factors.
DFS = the beta skin dose factor for a semi-infinite cloud of I
radionuclide "i", in mrem m 3/txCi yr from Table B-i,
. Reg. Guide 1.109. See Attachment 3.18, Dose
-.. - ., Factors. I I
I I
Reference PMP-6010-OSD-001' Rev.'21 Page 9.of 91 OFF-SITE DOSE CALCULATION MANUAL
- 3. Radionuclide and Radioactive Particulate, Doses (Eq 13 & 14)
The dose, Dip 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::
Die (mrem/year) 3.17E -8* 8 (R
- W
- Q)
Where; R = the most restrictive dose factor for each identified radionuclide "i", in m' mrem sec / yr[C~i (for food and ground pathways) or mrem m3 / yr zCi (for inhalation pathway), for the appropriate pathway For, sectors with existing pathways within five miles of the site, use the. values of R for these real o..
. pathways,
. . otherwise use pathways distance of five miles., See Attachment 3.1, Dose Factors for Various Pathways, for the maximum R1values for J *the most controlling age. group for selected radionuclides. R values were generated by computer codePARTS, see NUREG-0133, Appendix D.
W = the annual average or real time atmospheric dispersionparameters for estimating doses to an individual at the worst case location, and where W is further defined as:
Wý "=, /Q for the inhalation pathway, in sec/m 3
-OR-Wfg = D /Q for the food and ground pathways in r 1/rn 2.
= the release. rate of those radioiodines, radioactive materials in-particulate form and radionuclides other than noble gases with half-lives greater than eight days, in /Ci/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 maximum of the cow milk or goat milk pathway (not both) is included in the total.
Reference PMP-6010-OSD-001, Rev. 21. Page 10 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
- i. In addition to the above routines, the QUICKG routine of the MIDAS system is used to provide data used in the monthly reports due to its ability to use annual average meteorological data rather than real time I
data, thus shortening the run time inVolved.
j.
Steam Generator Blowdown System (Start Up Flash Tank Vent)
I
- 1. The amount of radioiodine and other radionuclides that are released via the start up flash tank and its vent are calculated through actual I
sample results while the start p flash tank is in service.
- 2. The following calculation is performed to determine the amount of I curies released through this pathway. (Plant established formula.)
Curies =Ci , GPM
- time on flash tank (min)
- 3. 785E - 3 I
nil.
Where;' 3.785E-3 =conversion factor, nil Ci/jzCi gal. I
- 3. The flow rate is determined from'the blowdown valve position and the time on the start up tank. Chemistry Department performs the sampling sand analysis of the samples.
I
.4> 'This; data: is provided to7 the. MIDAS' comnputer and dose calculations (liquid and gas) are performed :to ensuire' compliance with Subsection I
3.2, Limits:of Operation and Surfveillances of the Effluent Release Points, dose limits. MIDAS uses the formulas given in step 3.1.2, Liquid Effluent Releases, to calculate~doses to members of the-I public.
I This section provides the minimum requiriemrents 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 tank was in service.
I
-5. The radioiodine release rate must be determined. in accordance with the following equation every 31 day period whenever the specific I
activity of the secondary coolant system is greater than 0.01 pCi/g dose equivalent 1-131. I I
1 I
I
Reference - PMP-6010-OSD-001 Rev. 21 Page 11 of 91 OFF-SITE DOSE CALCULATION MANUAL
.6.' IF the specific activity, of the"secondary Coolant system is less than 0.01 ItCi/g dose equivalent 1-131, THEN the'release rate must be determined once every six months.* Use the following plant established equation:
Qy Ci* IPF R*
Where; Qy. = the release rate of.I-131 from the steam generator flash taAk vent, in /Ci/sec Ci= the, concentration (ftCi/cc) of 1-131 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 doseprojections 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.,
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 MD !EB -(EB)....
- b. To cniate the individual dose'(mrem), the program DSlLI (LD) is used. It computes the individual dgse for up 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. Steam Generators are sparged, sampled, and drained as batches usually early in outages to facilitate cooldown for entry into the steam generator.
This is typically repeated prior to startup to improve steam generator chemistry for thestartup. The sample stream, if being routed to the operating unit blowdown, is classified as a continuous release for quantification purposes to maintain uniformity with this defined pathway.
Reference PMP-6010-OSD-001 I Rev. 21 Page 12 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
- d. The equations used. are generated from site specific data and Reg. Guide 1.109. They are as follows: I
- 1. Potable Water (Eq 1)
Rqpi =1100.*
i U,,,." *ZEQ
- Dc,i,,je"t'
- I*~q, I
Where; Mp*F*2.23E-3 I
Rpj= the total annual dose to organ "j" to individuals. of age groups "a'." from all of the nuclides "i" in pathway "p",
I in inrem/year 1100 = conversion -factor, yr ft3 .pCi Ci sec L I Uap = a usage factor that specifies the exposure time or intake rate for an individual of age group "a" associated with pathway "p".. Given in #29-84 of parameter 4 in I
MIDEL and Reg. Guide 1.109 Table E-5. See Attachment 3,1, Dose Factors for Various Pathways. I Xp ,te dilutionfactor at the point of exposure (or the point of withdrawal-of dinkng. water or point of harvest of.
.aquatic food). Given in parameter 5 of MIDEL as 2.6.
I F = the circulation water system water flow rate, in gpm, is
. used for evaluating dose via these pathways as dilution I
flow 2.23E-3 = conversion factor, ft3 min / sec gal I Qj the release rate of nuclide "i" 'forý the time period of the run input via MIDEB, Curies/year I Daipj = 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 I
radionuclide, in mrem/pCi. These values are taken from tables E-11 through E-14 of Reg. Guide 1.109 and are located within the MIDAS code.
I ki = the radioactive decay constant for radionuclide 'i", in hours-"
I I
I I
Reference, PMP-6010-OSD-001 Rev. 21 Page 13 of 91 OFF-SITE DOSE CALCULATION MANUAL tp = the average transit time required for nuclides to reach the point of exposure, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This> allows 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 or water, in hours. Given as #25 of parameter 4 in MIDEL. (tp = 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
- 2. Aquatic Foods (Eq 2) o U-" . ...
a10iBip *D
- Mp*F*2.23E-*3 D Where, Bi= the equilibrium bioadcumulation factor for nuclide "i" in pathway "p", expressed as pCi L / kg pCi. The factors are located wvithin the MIDAS' code and are taken from Table A-1 .of Reg. Guide 1.109. See Attachment 3.1,
' " ": Dose Factors forVarious Pathways.
't _ the average transit-time required for nuclides to reach the point of exposure, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows for decay
- -, " duf ring transit through the food. chain, as well as during
'foo predpraiin.. Given as #26 of parameter 4 in MIDEL. (tp= 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) p =the dilutin: factor at the point of exposure, 1.0 for
" q 1 FooAticFods. 'Given in parameter 5 of MIDEL as 1.0.
- 3. Shoreline Deposits (Eq 3)
R,pj 110,000* " * * *Dapj[e-e
,MP* F2.23E-3, D
.....W here; .. .
Wher. 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.
Ti. = the radioactive half-life of the nuclide, "i", in days Daipj = the dose factor for standing on contaminated ground, in mrem m2 / hr pCi.. The values are taken from table E-6 of Reg. Guide 1.109 and are located within the MIDAS code.
See Attachment 3.1, Dose Factors for Various Pathways.
Reference PMP-6010-OSD-001 Rev. 21 Page 14 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
tb = the. period of time for which sediment or soil is exposed to the contaminated water, 1.31E+5 hours. Given in MIDEL as item 6 of parameter. 4..,
I tp = the average transit time required for nuclides to reach the point of exposure, 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Given a's #28 of parameter 4 I
in MIDEL.
110,000 = conversion factor yr ft3 pCi / Ci sec m2 day, this I
accounts for, proportionality constant in the sediment radioactivity model I
=P the dilution factor at the point of exposure (or the point of withdrawal of drinkig water or..point of haryest of aquatic food). Given in parameter 5.of MIDEL as 2.6. I
- e. The MIDAS program uses the following plant specific parameters, which are entered by 'the operator. I
- 1. Irrigation rate = 0 2.
3.
Fraction of time on-pasture = 0 Fraction of feed on pasture 0 I
- 4. Shore width factor. = 0.3 (from Reg. Guide 1.109, Table' A-2)
- f. The results of DS1LI are printed in LDRPT (LP). 'These results are I
used in the-monthly report of -liquid releases.,
- g. In, addition, the program DOSUM (DM) is used to search the results files I of DS1LI 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 I
Annual Radioactive Effluent Release Reports, required by Reg. Guide 1.21. I NOTE: The performance of each surveillance requirement must be withi' the specified I time interval with a maximum allowable extension not to exceed 25 of the specified surveillance interval.
I 3.2 Limits of Operation.and Surveillances of the Effluent Release Points 3.2.1. Radioactive Liquid Effluent Monitoring Instrumentation I-I I
I
Reference PMP-6010-OSD-O01 Rev. 21 Page 15 of 91 OFF-SITE DOSE CALCULATION MANUAL
- a. The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, are- operable with their alarm/trip 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 alarm/trip setpoint less conservative than a value which will ensure the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are 'met without delay, suspend the release of radioactive liquid effluents monitored by the affected channel and reset or declare the monitor inoperable.
- d. With oný or mo-e radioactive'liquid effluent monitoiring 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, excluding the initial performance. -.
e: Determine the setpoints in accoidance with the methodology described in s~tep 3.3.1, Liquid Monitors. Record the setpoints.
- f. Demonstrate eachi iradioac'tdie liquid effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE
-CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST 't the frequiencies shown in Attachment 3.3,
- Radioactive Liquid Effluent Monitoring In'strumentation Surveillance
'Requirements. -
BASES - LIQUID The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. 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, occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
Due to the location of the Westinghouse ESW monitors, outlet line of containment spray heat exchanger (typically out of service), weekly sampling is required of the ESW system for radioactivity. This is necessary-to ensure monitoring of a CCW to ESW system leak.
[Ref 5.2. lgg]
Reference l PMP-6010-OSD-001 Rev. 21 Page 16 of 91 I OFF-SITE. DOSE CALCULATION MANUAL I
3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation
- a. The radioactive gaseous process and effluent monitoring instrumentation I
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.
U
- b. The applicability of each channel is shown in Attachment 3.4, 11 Radioactive Gaseous Effluent Monitoring Instrumentation.
I
- c. With axradioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value I
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.
I
- d. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation, channels ,operable, take the action shown in I
Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, with a maximum allowable extension not to exceed 25 % of the surveillance interval, excluding the initial performance.
I NO'rE: This surveillance requirement dde'snot apply to the waste gas holdup system I
hydrogen and oxygen monitors,' as their setpoints are not addressed in this document. I
- e. Determine -the setpoints in. accordance with the methodology as described in step 3.3.2,. Gaseous Monitors. Record the setpoints. I
- f. Demonstrate each radioactive gaseous process or effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and I
CHANNEL OPERATIONAL TEST operations at the frequendies shown in Attachment 3.5, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.
I BASES - GASEOUS The radioactive gaseous effluent instrumentation is provided to monitor and control, as I
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 I accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.
I I
I
Reference PMP-6010-OSD-001. Rev.'21 Page 17 of 91 OFF-SITE DOSE CALCULATION MANUAL 3.2.3 Liquid'Effluents
Discharge
- 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 [tCi/ml total activity.
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 the above limits, without delay restore the concentration to within the above limits.
- 3. Sample and analyze riadioactive liquid wastes according to the sampling and analysis program of Attachment 3.6, Radioactive Liquid Waste Samplinlg 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
- b. - 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 2E-4 ICi/ml total activity.
- 2. With' releases from the TRS exceeding'the' above limits, perform a dose projection due toi'liquid releases to UNRESTRICTED AREAS to determine if the limits of step _3.2.3c. 1 have been 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.
- 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 main'tained within the limits stated above..
Reference PMP-6010-OSD-001 J Rev. 21 Page 18 of 91 I
OFF7SITE DOSE CALCULATION MANUAL I
- c. Dose 1; Limit the dose or dose commitment to an individual from radioactive I
material in liquid effluents released to unrestricted areas during any calendar quarter to s 1.5 mrem/unit to the total body and to S 5 mrem/unit to any organ, and during any calendar year to <_3 I
mrem/unit to the total body and to 110 mrem/unit to any organ.
- 2. With the calculated release of radioactive materials in liquid I effluents exceeding ten times any of the limits in Steps 3.2.3a or 3.2.3b; or exceeding 3.2.3c. 1 above, prepare and submit a Written Report, pursuant to 10 CFR 20.2203, within,30 days after learning of the'event. This report must describe the extent of exposure of I
individuals'to radiation and radioactive material, including, as appropriate: I a) Estimate of each individual's dose. This is toinclude the radiological impacts 'on 'finished drinking water supplies with regard' to the requirements of 40 CFR 141.' Safe Drinking Water I
Act (applicable due to Lake Township watertreatment 'facility),
b) Levels of radiation and concentration of radioactive material involved, I
c) Cause of elevated exposures, dose rates or concentrations, d)
-AND-Corrective steps taken or planned to ensure against recurrence, I including schedule for achiee',ing conformance with applicable limits.
These reports mut be form'atted'in accordance with PMP-7030-001-I 002,. Licensee Event Reports, Special. and Routine Reports even though this is not afn LER. I
- 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 I
projections and current or future plant conditions.
- d. Liquid Radwaste Treatment System I
- 1. Use the liquid radwaste treatment system to reduce the radioactive materials in liquid wastes prior to their discharge when theprojected I doses due to the liquid effluent from the site when averaged over 31 days, would exceed 0.06 mrem/unit to the total body or 0.2 mrem/unit to any organ. " " I
- 2. Project doses due to liquid releases to UNRESTRICTED AREAS at least once per 31 days, in accordance with this document.
Reference PMP-6010-OSD-001 ' Rev. 21 Page 19 of 91 OFF-SITE DOSE CALCULATION MANUAL
- e. During times of primary to secondaiy 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 NBAE distillate....
Drainage of high conductivity water (Component Cooling Water and ice meltwater 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 minimize the detrimental affect that high conduhctivity water has on the
- radioactive wastewater demineralization system. The standard concentration and-volume equation can be utilized to determine the jimpact on each method and is giyen here. The units for concentration
- and -volume need to be consistent across the&equation:
(c,)(v) + (Ca)(Va) (Cl)( V)
Where; QC.- the initial cofincentration of thesystem being added to Vi = the initial volume.o the of system being added to Ca = the concentration of the water that is being added to the system
-Va = the. volume of the water that is being added to the system
. Ct = the final cncntratidn of the system after the addition V = the final volume of the system after the addition
-The intent is to keep the:
WDS below 500 pimhos/cc.
- Monitor Tank 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 leakage based on the original 2 gpm waste evaporator), increased scrufiny will be placed on locating inleakage, timeliness of job order activities, and/or activities causing increased production of waste water.
Reference PMP-6010-OSD-001 Rev. 21 Page 20 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
BASES - CONCENTRATION This specification is provided to ensure the concentration of radioactive materials released in I
liquid waste effluents from the site to unrestricted areas will be.less than the concentration levels specified in 1 CFR Part 20, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the I
site will not result :m exposures greater than 1) the Section II.A design objectives of Appendix Ij 10 CFR Part 50, to an individual and 2) the limits of. 10 CFR Part 20. The concentration limit for noble gasses is based upon the assumption that -Xe-135, is the I
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 Commission on Radiological Protection (ICRP) Publication 2.
I DOSE This specification is provided to implement the requirements of Sections II.A, III.A, and I
IV.A of Appendix I, 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 I
I to assure the releases of radioactive material in liquid effluents will be kept "as 1ow as is reasonably achievable'". Also, .ýfor freshwater siteswith drinking water supplies which can be potentially 'affected by plant operations` there is reasonable- assurance that the operation I,
of the facility 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 III.A of Appendix I that conformance with the guides I
of Appendix I be shown by &alcuiational'procedlires based bn models and data such that the actual exposure of an individual th'rough a~ppoipr-iate-pathwV ys' is unlikely to be substantially underestimated. The- equations specified in the ODCM for calculating the doses due to the I actuial release rates of radioactive materials in liquid *ents-Will be consistent with the methodology provided in Regulatory Guide 1.109,, "Calculation 6Of Annual Doses to Man from Routine Releases of Reactor Effluents foi-'the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, and Regulatory Guide 1'. 113, I
"Estimating Aquatic. Dispersion .of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix, I', April 1977. .NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.
I 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.
I I
I I
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 21 of 91 OFF-SITE DOSE CALCULATION MANUAL LIQUID WASTE TREATMENT The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid. effluents require tregtment prior to release, to the environment. The requirements that the appropriate -portions of this system be used when specified provide"iassurance that the releases of radioactive materials in liquid effluents will be kept "as low 'as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.4 of the Final Safety Analysis Report for the Donald C. Cook .Nuclear Plant, and design objective Section II.D of Appendix I to 40 CFR Part 50. 'The specified limits governing theuse of appropriate portions of the liquidzradwaste treatment'system were specified as a suitable fraction of the dose design objectives set forth in Section I.A of Appendix 1, 10 CFR Part.ý 50, for liquid effluents.
3.2.4 Gaseous Effluents
- a. .'Dose Rate . ,,
1., Limit the. dose ratedue to. radioactive materials released in gaseous effluents from the. site to <C500 mrem/yr .to the tQtal body; and
. 3000 mrem/yr to the skin for noble gases. Limit the dose rate due
-.o all radioiodines and for all radioactive materials. in particulate.
form,and radionuclides (other than.noblegases) with half-lives
,grater than eight days .to *1500 mrfrri/yr to any, organ.
- 2. With the dose rate(s) exceedin~g the,above limits, without delay-.,:;
- j decrease the release rate to within the above limit(s). .
if" 3 -Determnine .the.ddse Yate dii;&e. tn6ble gases .in gaseous effluents t bo*
Within the aBov'6 lilmits. ii accordance With 'the metholds and
'procedures descfibed in this docum~nt..
- 4. Determifie 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 andprocedures of this document by-obtaining irepresentative samples and performing- analyses in accordance with the sampling and analysis program in Attachment 3.7, Radioactive Gaseous'Waste Sampling and-Analysis Program.
- b. Dose - Noble Gases
- 1. Limit the air dose in unrestricted areas due to noble gases released in gaseous effluents during any calendar quarter, to _<5 mrad/unit for gamma radiation and *5 10 mrad/unit for beta radiation and during any calendar year, to _*10 mrad/unit for gamma radiation and _<20 mrad/unit for beta radiation.
Reference PMP-6010-OSD-001 Rev. 21 Page 22 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
- 2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits,: prepare and submit a Written Report, pursuant to10 CFR 20.2203 and addressed in step I
3.2.3c.2, within 30 days after learning of the event.
3: Determine cumulative and projected dose :contributionis for, the total time I
period in accordance with'this document at*least once every 31 days.
- c. Dose - Iodine-i 31, Iodine-133, Tritium, and Radioactive Material in Particulate Form I
- 1. Limit the-dose to a MEMBER OF-THE PUBLIC from, radioiodine, radioactive materials in particulate form, and radionuclides other. than I
,noble :gases with half-lives greater than eight days in gaseous effluents released to unrestricted' areas (site b6undary) to the following: " I a) During any calendar. quarter to less than orequal to 7.5 I
" .-. mrem/unit to-any organ b) During any calendar year to less.than or equal to 15 mrem/unit to any .organ.
I
- 2. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides .Other than noble gases in gaseous effluents exceeding any of the above limits, prepare and.submit aWfitten Report, pursuant to 10 CFR 20.2203
,I and addressediin step 3.:2.3c2, within 30 days-after learning of the event. I
- 3. Determine cumulative and projected dose contributions for, the total time'period in aicc6rdance withi thisýdocument at least oncel every 31 days.,
I
- d. Gaseous Radwaste -Treatment.' U 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 .tounrestricted areas when averaged over I
31 days, would exceed 0.2 mrad/unit for-gamma radiation and 0.4
,mradlunit for beta radiation.. Use the ventilation exhaust treatment system to reduce radioactive materials in gaseous waste prior to their I
discharge when the projected doses due to-gaseous effluent releases to unrestricted areas when averaged over 31 days would exceed 0.3 mrem/unit to any organ.
I
- 2. Project doses due to gaseous releases to UNRESTRICTED AREAS at least once per 31 days in accordance with this document.
I I
I
Reference I PMP-6010-OSD-001 Rev. 21 Page 23 of 91 oFF-SITE DOSE CALCULATION MANUAL BASES -- GASEOUS EFFLUENTS This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an unrestricted area, either at or beyond thesite boundary in excess of the design objectives of appendix I to 10 CFR 50.%. This -.specification is provided to, ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section.II.A and II.C design objectives of appendix I to 10 CFR 50.
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 thatrfor the site boundary. The specified instantaneous release rate limits restrict, at all times, the corresponding gamma and beta, dosef rates; above, background to an individual at or beyond the site boundary to < 500 mrem/yr 'to.the totat 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 inhalation pathway to < 1500 mrem/yr. Limitations on the dose rate resulting from radioactive-material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR 20, Appendix B, Table 2, Column 1.
This specification applies to the release of gaseous effluents from all reactors 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 Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50.::The dose..li~mits implement the -guides set forth in Section II.B of Appendix I.
The ACTION statements provide the required operating flexibility and at- the same time implement the guides set -forth in section IV.A'of.AppendixbI to assure that the releases of radioactive material in gaseous effluenis. will be kept "as I6w as is' reasonably achievable".
The Surveillance Requirements implement the requirements in Section III.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 calculatihg the'doses due to the actual release rates of radioactive noble gases in gaseous -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 I", Revision 1, October 1977 and Regulatory GuideJ l 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",
Revision 1, July:1.977. 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.
Reference PMP-6010-OSD-001 Rev. 21 Page 24 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES I This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits are the. giides set forth in Section II.C of Appendix I. I The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".
i The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section lIlAI.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 I
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 II Releases of Reactor Effluents for the Purp6se of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous !Effluents in Routine Releases from Light-I Water-Cooled Reactors",,.Revision 1, July 1977. These equations alsoprovide the
.,methodology for determining the actual :doses; based upon the historical average atmospheric conditions,. The release rate specifications for radioi.odines, radioactive material in, particulate I
form, and radionuclides, other than noble gases, .aredep6Adent on the'existing radionuclide pathways to man,.in the unrestricted area. The .ptltw'ays'which are examined in the development of these cafculations are: 1) individual inhalation 6f airborne radionuclides, 2) deposition :of radionuclides, onto green leafy vegetation with subseqiientlconsumption by man, I
- 3) deposition onto grassy areas wherd milk animals and meat producinig ýnimals graze with consumption of the milk and meat by man, and 4) dep6si'i n on the ground with subsequent exposure of man.
I GASEOUS WASTE.TREATMENT '
I The operability of the gaseous radwaste trea tn'ineni 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 I
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 11. 1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear I Plant, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guides forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 11 I
U I
I I
Reference T PMP-6010-OSD-001 Rev. 21 Page 25 of 91 OFF;-SITE DOSE CALCULATION MANUAL 3.2.5 Radioactive Effluents - Total Dose
- a. The dose or dose commitment to a real individual from all uranium fuel cycle soiurces 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.
- b. With the calculated doses from the release of radioactive materi.l s in liquid or gaseous effluents exceeding twice the limits of steps 3.2.3c (Dose),, 32.4b (Dose - Noble*,Gases), or 3.2.4c (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 resuilting in viblation has not already been corrected prior to
':"< violationof 40-CFR 190.THEN include in the report a request for a?
variance in aac.ordance with the provisions of 40 CFR 190 and including the. specified infoimati6n of paragraph- 190.11(b). Submittal of the
-' report is considered a ttimiely request, and a variance is granted until staff-action on the reuest is cofnplete. Th6variance only relates to the limits of 40; CFR 190, and does iot apply in any way'to the requirementsfor' dose limitation of4.10 CFR50 aS addressed in other sections of this .
document.
- c. Determine cumulative dose contributions.from liquid and gaseous effluents in accordance with this document (including steps 3.2.3c
'[Dose]., 3.2.4b [Dose- Noble Gases],,or 3..2.4c,[Dose - Iodine-131, Iodine-133, Tritium, and -Radioactive Material in Particulate Form]).
Reference PMP-6010-OSD-001 - Rev. 21 Page 26 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
BASES -- TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The specification I
requires the preparation and.submittal of a Special Report whenever the calculated doses from plaht radioactive effluentsexceed twice the design .objective doses of Appendix I. For sites containing -up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public I
will exceed-the' dose limits of 40 CER 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action, which should result in the limitations of dose to amember of the public for 12 consecutive -months to within the I
40 CFR 190 limits. For the purposes of the Special Report; it may be assumed that the dose commitment to 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 I or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to -exceed the r'equirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation bf 40 CFR 190 have not already been corrected, in accordance with the ptoyision of 40 CFR 190.1 i), is considered to be a I
timely request and fulfills the requ.irements.6f 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 carryin'g outany operation, which is part of the nuclear fuel cycle.
I 3.3 Calculation of Alarm/Trip Setpoints I The alarm and trip setpoints are to provide monitoring, indication, and control of liquid and gaseous effluents. The setpoints are used in conjunction with sampling programs to assure thatthe releases are kept within the limits ofrl0 CFR 20, Appendix B, Table 2. I Establish setpoints for liquid and gaseous monitors.. Depending on the monitor function, it would be a c6ntinuous or batch monitor. 'The different types of monitors ,are subject to different setpoint miethodologies. '- , ' I One variableused 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 value will not be exceeded. The MRP'is determined such that the sum of the I
MRP's for that effluent'type (liquid or gaseous)'is less 'than or equal to 1. The value of the MRP is arbitrary, and 'it should be assigned based on operational performance. The values of the MRP's for each liquid release point are given in Attachment 3.8, Multiple I
Release Point Factors f6r Release Points.
The Site stance on instrument uncertainty is taken from HPPOS-223, Consideration of I,
Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits, which state's the NRC position is the result of a valid measurement Obtained by a method, which provides a reasonable demonstration of compliance. This value should I be accepted and the uncertainty in that measured value need not be considered.
I I
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 27 of 91 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. A. list 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
" " releases.
bGenerator l~atch Blowdown. radiationis 'maonitors This monitor as RRS-1000.
identifiedAlso Steam can be used'to m~nitoir' batch releases while draining steam gefierators.' The furiction of these monitors is to act as a check oni the sampling program. The sampling-'
program'deterrfines the-nnucides and cohcehtrations 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 of nuclides 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 andý 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 fromi Addefdum AA1 Of NUREG-0133:
5 Z *F, f -<F+f" LLIMIT _i MRP : i , *: .
- Where; .F'f Ci = -the concentration of nuclide "i" -in pCi/ml LIMIT = the 10 CFR 20, Appendix B, Table 2, Column 2 limit of nuclide "i" in ýtCi/ml 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 in operation.
Reference PMP-6010-OSD-001. i Rev. 21 Page 28 of 91 I OEF-SITE DOSE CALCULATION MANUAL I
MRP = the multiple release point factor. A factor such that when all the release points are operating at one time the I
limits ofl10 CFR 20 will not be exceeded.
- 4. This equation mustbe true during thebatch 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 I
limits of operation. If the equation is not true, the effluent flow rate can be reduced or the dilution flow rate can be increased to make the equation true. This equation may be rearranged to solve for the I 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 U
reading is greater than the predicted value from the sampling program.: The predicted value is generated by converting the effluent concentration for each gamma emitting radionuclide to I
- counts per unit of time as-per Attachment 3.11, Volumetric Detection Efficiencies- for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors, or.Attachment 3.12, Counting I1 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 iifadtor to determine the high alarm I setpoint that will provide a high 'degree of conservatism and b.
eliminate spurious alarms. "
Liquid Continuous:Monitor Setpoint Methodology I
- 1. There are eight monitors used as potential continuous liquid release monitors. These monitors are used in the steam generator I
blowdown (SGBD), blowdown treatment (BDT), and essential service water (ESW) systems. I
- 2. These Westinghouse monitors (R) are being replaced by Eberline monitors (DRS) and are identified as:
I
- R-24 or DRS 3200/4200 for BDT The function of these monitors is to assure that releases are kept I
within the concentration limits of 10 CFR 20, Appendix B, Table 2, Column 2, entering the unrestricted area following dilution'. I I
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 29 of 91 OFF-SITE DOSE CALCULATION MANUAL
- 3. The monitors on steam generator blowdown and blowdown treatment systems have trip functions associated with their setpoints.
Essential service water monitors are equipped with an alarm function only and monitor effluent in the event the Containment Spray Heat Exchangers are used. 4
- 4. The equation used to determine the setpoint for continuous monitors is from Addendum AA1 of NUREG-0133:
" S < C *;Eff f *MRP*F*SFF sp*
Where; Sp setpoint of monitor, (cpm) 1, C = 5E-7 pCi/ml,' maximum effluent control limit from 10 CFR 20, Appendix B, Table 2, Column 2 of a known
" possible ýnuclide'in-effluent stream. (The limiting nuclide shall be evaluated annually by reviewing current nuclides against historical ones in'orderito determine if one with a more restrictive effluent concentration limit than Sr90 is
, found. The concentration, limit shall be adjusted appropriately.).,,
-OR-if amixture is to be specified, ZCi LIMITi Eff = Efficiency, this information is located in Attachment 3.11 Volurnetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors; through Attachmentr3.13, 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:
Y-(Ci ** Efft,)
Ef-)replacesC *Eff LIMITi,
Reference PMP-6010-OSD-001 Rev. 21 Page. 30 of 91 I OFF-SITE DOSE CALCULATION MANUAL I 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, I
Multiple Release Point Faciors for Release Points). The MRP for ESW maonitors is set to 1. I F = dilution water (circ water) flow rate in gpm obtained from Attachment 3.10, Plant Liquid Effluent Parameters.
For routine operation, the setpoint should be calculated I using the minimum dilution flow rate of 230,000 gpm.
SF = Safety Factor, 0.9. I 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 I
Liquid Effluent Parameters).
3.3.2 Gaseous Monitors I i'V -
For the purpose of implementing Step 3.2.2, Radioactive Gaseous Effluent Monitoring nStfrumentatiohn, -andSubstep'3.2.4a, Dose Rate, the alarm setpoints for gaseous effluents released into unrestricted areas will be I
established using'the following mejthodology. In addition, the above steps do not apply to instantaneous alarm and trip setpoints for integrating radiation monitors samplingiradioiodinesý, radioactive materials in particulate form and I
- " ' "
- radionuclides other than noble gases. ýA 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 I 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%,4 of the setpoint) for I
ALARA purposes. Alert alarms will normally be set to provide adequate indications of small changes in radiological conditions.
I NOTE: . IF the setpoint calculation methodology changes or the associated factors change for Unit Vent, Air Ejector and/or Gland Seal monitors, THEN initiate I
a review by Emergency Planning to ensure that the requirements of 10 CFR 50.54 (q) are maintained.
I
- a. Plant Unit Vent i
U i
I
Reference PMP-6010-OSD-001 I Rev. 21 Page 31 of 91 OFF-SITE DOSE CALCULATION MANUAL 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*M SP= SF PP*DLj Fp */Q* (W,* DCFO)
Where; Sp. =.the maximum, setpofint of the monitor in ýtCi/cc for release point p, based on the most limiting organ SF = an administrative operation safety factor, less than 1.0 MRP = 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-arbitrafy. value based on the ratio of the release rate or the volumetric flow rate of each effluent point ýo the` total, respective.flow rate value of the plant and will be consistent with past operational experience.
The Mk1is'computed as follows:
Compute the average release rate, Qp, (or the volumetric flow rate, fp) from each release point p.
.Compute ZQp (or Efp). for all release points.
, Ratio Qp/EQp (or fp/Xfp) for each release point.
- This ratio is the'MRP for that specific release point
, Repeat the above bullets for each of the site's eight*
gaseous release points.
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 cfm for Unit 1 and 143,400 cfmi for Unit 2.
DLj = dose rate limit to organ "j" in an unrestricted area (mrem/yr).
Based on continuous releases, the dose rate limits, DLj, from step 3.2.4a, Dose Rate, are as follows:
- Total Body < 500 mrem/year
- Skin < 3000 mrem/year
- Any Organ_< 1500 mrem/year
Reference PMP-6010-OSD-001 T Rev. 21 Page 32 of 91 I OFF-SITE DOSE, CALCULATION MANUAL I
I/ Q = The worst case annual average relative concentration in the applicable sector or area, in sec/m 3 (see Attachment I 3.16, 10 Year Average of 1995-2004 Data).
W = weighted factor for the radionuclide: I Wi-C ZCk I Where, Ci = concentration of the most abundant radionuclide "i" I
Ck = total concentration of all identified radionuclides in that release pathway. For I batch releases, this value may be set to 1 for conservatism.
DCFij = dose conversion factor used to relate radiation I
dose'to organ "j", from exposure to radionuclide "i" in mrem m3 / yr pCi. See
-" '"-"following'eqiiations I
- The.dose conversion. factor; DCFij, is
- dependent
- upon the organ of concern. I Foi thie ;,hole bodyý: DCFij Ki Where;"'
=
I K1 = whole body dose factor due to gamma emissions; for each identified noble gas I radionuclide in mrem m 3 / yr tCi. See
, "Attachment 3.18, Dose Factorsý'
For the skiil: DCFj = Li + 1.1Mi I
Where; I Li = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem m3 / yr [tCi. See Attachment I
3.18, Dose Factors.
"1.1 = the ratio of tissue to air absorption coefficient over the energy range of photons I
of interest. This ratio converts absorbed dose (mrad) to dose equivalent (mrem). I I
I
Reference T PMP-6010-OSD-001 I Rev. 21 Page 33 of 91 OFF-SITE DOSE CALCULATION MANUAL M - the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad m3 / yr 1 iCi. See Attachment 3.18, Dose Factors.
For the thyroid, via inhalation: DCFij = Pi Where; Pi = the dose parameter, for radionuclides other than noble gas, for the inhalation pathway in mrem m3 / yr 1tCi (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 -Sp, 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 ventradiation 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 detennine the most limiting organ.
- 5. The high alarm setpoint, Sp, may be established at a lower value than the lowest computed value via the setpoint equation.
- 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 maybe 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 (,uCi/cc)
- Max Flowrate(cfm) New Max cfm New Max Concentration(/Ci/cc)
-OR-Max Conc (pCi/cc)
- Max Flowrate(cfn) _ New Max pCi/cc
- NewMax Flowrate(cfm)
I b.. Waste Gas Storage Tanks
Reference PMP-6010-OSD-O001 Rev. 21 Page 34 of 91 I OFF-SITE DOSE CALCULATION MANUAL
,I
- 1. The gaseous effluents discharged from the Waste Gas System are monitored by the vent stack monitors VRS-1505 and VRS-2505. !
- 2. In the event of a high radiation.alarm, 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-, 505 or I
VRS-2505). Therefore, for any gaseous release configuration, which includes normal operation and waste gas system gaseous discharges, the alarm setpoint :of the plant vent radiation monitor I
will be recomputed to determine te most limiting organ based on all gaseous effluent source terms.
I 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.
I
- 3. It is normally prudent to allow 4.5 ,days of decay prior to releasing a Gas Decay Tank (GDT)., There are extenuating, operational I
circumstances that may preyent this from occurring. Under these circumstances, such as high oxygen concentration creating a combustible atmosphere, it is prudent to,.waive the 45-day decay I
for safety's sake.
- c. Containment Purge and Exhaust System I
- 1. The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust I System are monitored by the plant vent ra'diation monitor noble gas channels (VRS-1505 for Unit 1, VRS-2505 for Unit 2); and alarms and trip'actions will occur prior to exceeding the limits in step 3.2.4a, Dose Rate.
I I
C,.,
- 2. For the Containment System, a continuous air sample from the containment atmosphere is drawn through a closed, sealedý system to the radiation monitors (Tag No. ERS-1300/1400 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 I
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.
I
- 3. The Upper Containment area is monitored by normal range area gamma monitors (Tag No. VRS-1101/1201 for Unit 1 and VRS-2101/2201 for Unit 2), which also give Purge and Exhaust I
Isolation Trip signals upon actuation of their high alarm.
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 35 of 91 OFF-SITE DOSE CALCULATION MANUAL.
- 4. For the Containment Pressure Relief System, no sample is routinely taken prior to re:lease, but a sample is obtained twice per month.
- 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-1101/2101) and one of the two Train B monitors- (ERS- 1400/2400 or VRIS-1201/2201).
- d. Steam Jet Air Ejector System (SJAE)
- 1. The gaseous effluents from the Steam Jet Air Ejector System discharged to the environmient 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 exceeding the limits of step 3.2.4a, Dose Rate. The alairm seitpoint for the Condenser Air Ejector System monitor will be based;on the maximum air ejector exhaust flow rate, (Attachment 3.15(,'Plant Gaseous Effluent Parameters). "Thealarm se*point Valie will be established using the following unit analysis equation:
SF
- MRP DL1 FPX/Q* (W* DCF,,)
Where; SSJAE the miaimurm setpoint, based on the most limiting organ, in p.Ci/cc and where the other terms are as previously deftied
- e. Gland Seal Conderiser Exhaust
- 1. The gaseous effluents from the Gland Seal.Condenser Exhaust discharged to the environment are continuou0sly monitored by radiation monitor (Tag No. SRA-1800for Unit 1 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 monitor 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:
1
-_ý' , .
Reference PMP-6010-OSD-001 Rev. 21 Page 36 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
SGSCE --
SF*MRP
- DLj Fp* /Q* (W,* DCFj)
I Where i
= the maximum setpoint, based on the most limiting SGscE organ, in pýCi/cc and where the other terms are as previously defined I
3.4 Radioactive. Effluents Total Dose I 3.4.1 " The cumulative dose contributions from liquid and gaseous effluents will be determined by summing the cumulative doses as. derived in steps 3.2.3c (Dose), .:3.2.4b (Dose - Noble Gasps), and 3.2.4c (Dose - Iodine-131, Iodine- I 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 radiation monitoring devices located at the REMP monitoring stations.. See NUREG-0133., section 3.8.t I
'3.5 Radiological Environmental MonitoringProgram (R.MP. I 3.5.1 Purpose of the REMP
- a. The purpose of theýREMP is to:
I Establish. baseline radiation and radioactivity concentrations in the environs prior to reactor: operations,.
3
-Monitor critical environmental exposure pathways, Determine the radiological impact, if any, caused by the operation U
b.
of the Donald C. Cook Nuclear Plant upon the local environment.
The first purpose of the REMP was completed prior to the initial U
operation of either of the two nuclear units at the Donald C. Cook Nuclear Plant Site. The second and third purposes of the REMP are an on-going operation and as such various environmental media and I
exposure pathways are examined. The various pathways and sample media used are delineated in Attachment 3.19, Radiological ý Environmental Monitoring Program Sample Stations, Sample Types, I
Sample Frequencies. Included is a list of the sample media, analysis required, sample stations, and frequency requirements for both! collection and analysis. Attachment 3.19, Radiological Environmental Monitoring I Program Sample Stations, Sample Types, Sample Frequencies,'ý defines the scope of the REMP for the Donald C. Cook Nuclear Plant.
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 37 of 91 OFF-SITE DOSE CALCULATION MANUAL' 3.5.2 Conduct of the REMP [Ref. 5.2. lu]
- a. Conduct sample collection and analysis for the REMP in accordance with Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, Attachment 3.20, Maximum Values for Lower Limits of DetectionsA,B - 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 Attachment 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 collected in accordance with step 3.5.2a, submit a description of the reasons for deviation and the actions taken toprev6nta teoccurrence as part of the Annual Radiological Environmental Operating Report (AREOR).
- 3. Deviations from the required saffipling'schedule:are permitted if specimens are unobtainable due to hazardous conditions, seasonal unavailabilityi or malfiunction. 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.
Reference PMP-6010-OSD-001 Rev. 21 Page 38 of 91 I OFF-SITE DOSE .CALCULATION MANUAL I NOTE: Only one report per event is required. I NOTE: Radioactivity from sources other than plant effluents do not require a Special I
Report.
- 4. IF any of the following conditions are identified:
I
- A radionuclide associated with plant effluents is detected in any REMP sample medium AND its concentration exceeded the I
limits specified~in Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples, I
- More than one radionuclide associated with plant effluents is
)*o ,
detected in any, REMP sample medium AND the Total Fractional Level, when* averaged oVer the calendar quarter,. is I
greater than or equal to 1.
THEN complete the.following steps, as' applicable:
I
- Submit a Special Report to the Nuclear Regulatory. Conmmission within 30 days.: I
- Subinit-a Special Report'to designated state and local ofganizatioris for gr'oundwxater or surface water media ,which could 1e used as drinking water. N
- Evaluate the fo6f10¢ing iteim sfor inclusiofi in Special Reports:
'Release 'coniditions I Environemental factors 3) 4)
Corrective actions Additional factors which may have contributed to the identified levels I
- 5. WHEN submission of a, Special Report to designated state and local organizations is required, THEN perform the following:
I Communicate event specific information to designated state and local organization personnel by the end of the next business day.
I I
I I
I
Reference PMP-6010-OSD-001 I, Rev. 21 Page 39 of 91 OFF-SITE DOSE CALCULATION MANUAL
- 6. IF a currently sampled milk farm location becomes unavailable, THEN conduct a special milk farm survey within 15 days.
a) IF the unavailable location was an indicator farm, THEN 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, THEN an alternate sample location may be established greater than 15 but less than 25 miles of the Donald C. Cook Nuclear Plant in one of the less prevalent wind direction sectors, if one is available.
S 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, THEN perform monthly vegetation sampling in lieu S..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 station operation. Thereby, this monitoring program supplements the radiological: effluent monitoring program by yerifying the measurable concentration of radioactive materials and levels of radiationare not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways;. The. initially specified REMP, was effective for. the. first three years of commercial operation. Program changes may.be .initiated based on operational experience in accordance with the requirements of Technical, Specification 5.5.1. c.
The detection capabilities, required by Attachment 3.20, Maximum Values for Lower Limits of DetectionsA,B - REMP, are the state-of-the-art. for -routine environmental measurements in industrial laboratories.
It should be recognized that &e LLD'is defined as a priori (bef6re 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 LLDs will be achieved under routine analy.sis conditi'6n;. 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 the Annual Radiological Environmental Operating Report.
3.5.3 Annual Land Use Census [Ref. 5.2.1u].
- a. Conduct a land use census and identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the ten land sectors within a distance of five miles.
Reference "PMP-6010-OSD-001 Rev. 21 Page 40 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
In lieu of the garden census,,grape and broad leaf vegetation sampling may be b.. Iperformed as.close to the site bounI dary as possible in a land sector, containing sample media, with the highest average deposition factor (D/Q) value.
I
- c. Conduct this land iuse census annually between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local I
agricultural authorities.
- 1. With a land use census identifying a locatiori(s), which yields a I
- 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, if possible.
I BASES -- LAND USE CENSUS I
This is provided to ensure changes.in the use of unfestricte~d areas are identified and modifications to the monitoring program are 'mide,in accordance with' requirements of TS 6.8.4b, if required by .th&r'esults of the census., This census satisfies the requirements of Section IV.B .3 of Appendix I to 10 CFR Part 50. Restricting the cerisus to gardens of greater I
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 quantity (25 kg/yr) of leafy vegetables assumed in Regulatory Guide- 1.109 for consumption I
of, a child. To determine this minimum garden size, the f6llowing assumpiions were used: 1) that,20% of the garden was used for growing broad leaf vegetation (that is, similar to lettuce.
and cabbage), and 2) a. vegeiation field of,2 kgmsquare meter.' I 3.5,4 Interlaboratory Comparison Program U
a.., In order to comply with Reg. Guides 4.1 and 4.15, the analytical vendor participates in an Interlaboratory Comparison Prograim, for radioactive materials. Address program results'and identified deficiencies -in the AREOR. I
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the AREOR.
I BASES -- INTERLABORATORY COMPARISON PROGRAM I The requirement for participation in an Interlaboratory Comparison Program is provided to ensure independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample -matrices are performed as part of the quality assurance I
program for environmental monitoring in order to demonstrate the results are reasonably valid.
3.6 Radioactive. Equipment Storage Facility (Mausoleum) Groundwater Monitoring Program I 3.6.1 Purpose of the Radioactive Equipment Storage Facility (Mausoleum) Groundwater Radiological Monitoring Program I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 41 of 91 OFF-SITE DOSE CALCULATION MANUAL
- a. The.purp6se of the temporary on-site Radioactive Equipment Storage Facility (Mausoleum) Radiological Monitoring Program was 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 tomonitor the groundwater through observation wells with locations 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 Radioactive Equipment'Storage Facility (Mausoleum)
" Groundwater Radiological Monitoring -Program
- 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 Valued for L6wer Limits of DetlctionsA,B - REMP, (ekcluding I1131)'and Attachment 3.21, Reporting Levels forRadioactivity Cdncentrations in Environmehtal Samples, (excluding 1-131).
3.7 Meteorological Model ' " ' -
-3,7.'1 Three to wers areiused' tddeterm.iri the meteorological conditions at' Donald 'C.
Cook Nuclear Plant.' One of the towers is Iodated at the Lake Michigani shoreline to detdrmine'the meteorological parameters associated'with- unmodified shoreline air. The data is accumulated by:-iicroproc.ssors at-the tower sites -and normally transferred to the central computer every 15 minutes.
3.7.2. The central computer uses a meteorological software program to provide
.t..ospheric dispersion and deposltl0f parameteirs. The meteorological model used is based on guidahce provided rinReg. Guide 1'.111 for routine releases. All cflculitiofis use the Gaussian plume m6del.
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 15 of each year. [Ref 5.2. lj, TS 5.6.2]
- b. Include in' the AREOR:
Summaries, interpretations, and statistical evaluation of the results of the radiological' environmbntal surveillance activities for the reporting period.
Reference PMP-6010-OSD-001 Rev. 21 Page ý42 of 91 I
OFF-SITE DOSE CALCULATION MANUAL I
A comparison with pre-operational studies, operational controls (as appropriate),ý and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the
,I environment.
- The results of the land-use censuses required by step 3.5.3, Annual I
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 I
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 descriptionof the REMP including sampling methods I
for each sample type, size and physical characteristics of each sampletype, sample preparation methods, analytical methods, and measuring equipment used.
I
- A map of all sample 1Q,:ations keyed to a table giving distances and directions from one reactor. I
. The results of participation in the, Interlaboratory Comparison Program required by step 3.5.4, Interlaboratory Comparison Program.
I 3.8.2 -.Annual Radiological Effluent Release Report (ARERR) I
- a. r: Submit routine ARERR covering the operation of the unit during the S. previous 12 months of operation within 90 days after January 1 of each year.
[Ref 5.2.1j, TS 5.6.3]
I 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 1.21, "Measuring, Evaluating and Reporting in Solid I
Wastes and Releases of Radioacti e Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B, I
thereof.
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 43 of 91 OFF-SITE -DOSE CALCULATION MANUAL
- 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 may be in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint 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 ihside" thesite boundary during the reporting. period. Include all assumptions used in making these assessments (that is, specific activity, exposure time and'location) in these reports.
Use the meteorological conditions concurrent with the time of release of radioactive materials in gaseous. effluents (as determined by sampling frequency and measurement) for determining the gaseous' pathway doses. -
. Inoperable radiation monitor periods exceeding 30 continuous "days; explain 'cauisesý.6f'inoperability and actions taken to prevent reoccurrence." - .:-' ..
- d. Submit the ARERR [Ref. 5.2.1 w] 90 days after January 1 of each year and include an assessment Of radiation dosesto the likely most exposed member of the public from reactor releases and other nearby uranium
'fuel cycle soui-rces (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 calcfilating the dose contribution ýfrom 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),
Reference 7 PMP-6010-OSD-001 Rev. 21 Page 44 of 91 I OFF-SITE ,DOSE CALCULATION MANUAL I
- Principle, radionuclides (specify whether determined by measurement or estimate), I Type of waste (example: spent resin, compacted dry waste, evaporator bottoms), I
- Type of c6n tainer (example: LSA, Type A, Type B, Large Quantity),
-AND-I
- Solidification agent (example: cement).
- f. Include in the ARERR unplanned releases df radioactive materials in I
gaseous 'and liquid effluent-from the-site to unrestricted areas on a g.
- quarterly basis.
Include in the ARERR any change to this procedure made during the I
reporting period.
- h. Due to the site having shared gaseous and liquid waste systemsi dose I
calculations will be performed on a per site bases using the per, unit values. This is ALARA and will ensure compliance with 40 CFR 141, National Primary Drinking Water Regulations. Unit specific values are I
site values divided by two.
3.9 10 CFR 50.75 (g) Implementation I
3.9,1 Records of spills or; other unusual occurrences involving the spread of cdntamination in and around the, site. These records may be 'limited to instances I
. .when significanhtconntamination'retnainsý after- decontamination or when there is a reasonable likelihood that cOntamin-anits may have spread to inaccessible areas, as in the case of possible seepages. I 3.9,2 These records shall include any known information 'or identification of involved nuclides, quantities, and concentrations. I 3.9,3 This information'is necessary to ensure all areas outside the radiological-restricted area are documented for surveying and remediation during decommissioning. There is a retention schedule file-number where this I
information is filed in Nuclear Documents Management. to ensure.!!all required areas are listed to prevent their omission.
I 3.10 Reporting/Management Review 3.10:1 Incorporate any changes to this procedure in the ARERR. I 3.10.2 Update this procedure when the Radiation Monitoring System, its instruments, or the specifications of instruments are changed.- I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 45,of 91 OFF-SITE DOSE CALCULATION MANUAL 3.10.3 Review or revise this procedure as appiopriate based on the results of the land use census and REMP.
3.10.4 Evaluate any changes to this procedure for potential-impact on other related Department Procedures.
3.10.5 Review this-procedure during the first quarter of each year and update it if necessary. Review Attachment 3.16, 10 Year Average of 1995-2004 Data, and document using Attachment 3.17, Annual Evaluation of -/Q and D/Q Values For All Sectors. The X / Q and D1)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 x/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 "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in, the Administrative Controls Section of the. Technical.
Specifications and the Relocation of Procedural Details of RETS to the Off-Site Dose Calculation Manual or. to the Process Control Program (Generic Letter 89-
, 01)",. United States Nuclear Regulatory Cornmission, 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 Environimental Operating Report (AREOR) Preparation And Submittal 5.2 Writing
References:
5.2.1 Source
References:
- a. 10 CFR 20, Standards for Protection Against Radiation
- b. 10 CFR 50, Domestic Licensing of Production and Utilization Facilities
- c. PMI-6010, Radiation Protection Plan
- d. NUREG-0472 . . ..
Reference PMP-6010-OSD-001, Rev. 21 Page 46 of 91 I OFF-SITE DOSE CALCULATION MANUAL
- e. NUREG-0133
- f. -Regulatory Guide 1. 109, non-listed parameters are taken from these data I tables 9g..Regulatory Guide1.111 3
- i. Final Safety Analysis Report (FSAR) I
- j. Technical Specifications 5.4.1.e, 5.5.1.c, 5.5.3, 5.6.2,, and 5.6.3
- k. Final EnvironmentalStatemen.t Donald. C.: Cook Nuclear Plani, August 1973
- 1. NUREG-0017
- m. ODCM Setpoints for Liquid [and Gaseous] Effluent Monitors (Bases),
...ENGR 107-04 81.12.1 Environs Rad Monitor System 3
- n. HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Leyels, Approaching Regulatory Limits
- o. Watts - Bar Jones (WBJ) Document, R-86-C-001, The Primary Calibration of Eberline Instrument Corporation SiING - 3/4 Low, Mid, and High Range Noble Gas Detectors 3 p.. WBJ Document, R-86-C-003, The Primary Calibration of Eb rline .
Instrument Corporation DAM-4 and Water Monitor
- q. 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations r.. NRC Conimitment 6309 (N94083 dated 11/10/94)
- s. NRC Commitment 1151
- t. NRC Commitment 1217 I u., NRC Commitment 3240.
- v. NRC Commitment 3850
- w. NRC Commitment 4859
- x. NRC Commitment 6442
- y. NRC Commitment 3768 3
- z. DIT-B-00277-00, HVAC Systems Design Flows aa. Regulatory Guide 1.21 3
Reference PMP-6010-OSD-001 Rev. 21 Page .47 of 91 OFF-SITE DOSE CALCULATION MANUAL bb. Regulatory Guide 4.1 cc l-2-V3-02-Calc #4, Unit Vent Sample Flow rate-for isokinetic particulates and Iodine sampling :
dd. HPS N13.30-1996, Appendix:A Rationale for Methods of Determining Minimum Detectable Amount (MDA) and Minimum Testing Level (MDL ee. DIT-B-01971-00, Dose Factors for Radioactixe: 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 gg. NRC Commitment 1010 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. A*EP Design Information.Transnmittal on Aux Building Ventilation Systems
- d. PMP-4030.EIS.001; Event'l-nitiated Surveillance Testing
- e. Environmental Position Paper, Fe Impact on Release Rates, approved 3/14/00 -- .
- f. Environmental Position Paper, Methodology Change from Sampling Secondary System Gaseous Effluents for'Power Changes Exceeding 15 % within 1 hr to Responding to Gaseous Alert Alarms, approved 4/4/00
- g. CR 02150078, RRS-1000 efficiency curve usage
- h. Environmental Position Paper, -Unit Vent Compensatory Sampling, approved 4/14/05
Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUAL Rev. 21 Page 48 of 91 I
Attachment 3.1 Dose Factors for Various Pathways Pages:
I
- ., 48 -51 R, Dose Factors I
PATHWAY Nuclide Ground Vegetable Meat Cow Milk Goat Milk Inhalation I
H-3 0.0E+00 4.0Et03 3,3E+02 2.4E+03 4.9E+03 1.3E+03 C-14 Cr-51 0.0E+00 5.4E+06 3.5E+06 1.1 E+07 5.3E+05 1.5E+06 3.2E+06 6.9E+06 3.2E+06 8.3E+05 3.6E+04 2.1E+04 I
Mn-54 1.6E+09 9.4E+08 2.1E+07 2:.9E+07 3.51E+06 2.0E+06 Fe-59 Co-58 3.2E+08 4.4E+08 9.6E+08 6.OE+08 1.7E+09 2.9E+08 3'. 1E+08 8.4E+07 4.OE+07 1.0E+07 1.5E+06 1.3E+06 I
Co-60 2.5E+10 3.2E+09: 1.0E+09 2.7E+08 3.2E+07 8.6E+06 Zn-65 Sr-89 8.5E+08 2.5E+04 2.7E+09 3.5E+10 9.5E+08 3.8E+08 1.6E+10 9.9E+09 1.9E+09.
2.1E+10 1.2E+06 2.4E+06 I Sr-90 0.OE+00 1.4E+12 9.6E+09 9.4E+ 10 2.0E+11 1.1 E+08 Zr-95 Sb-124 1-131 2.9E+08 6,9E+08 1.OE+07 1.2E+09 3.0E+09 2.4E+10 1.5E÷09 4.4E+08 2:5E+09 9.3E+05 7.2E+08-.
4.8E+1-1 1.IE+05 8.6E+07 5.8E+11 2.7E+06 3.8E+06
!.6E+07 I
1-133 Cs-134
- Cs-136 1.5E+06 7.9E+09 1.7E+08 4.0E+08 2.5E+10 2.2E+08 6.0E+01 I.1E+09 4.2E+07 4.4E+09 5.OE+10-5.1E+09 5.3E+09 1.5E+11 1.5E+10 3.8E+06 1 1E+06 i1.9E+05 I
Cs-137 Ba-140 1.2E+10 2.3E+07 2.5E+10' 2.7E+08
.. OE+09 .
5.2E+07 4.5E+10, 2.-1E+08
.1.4E+11 2.6E+07 19.0E-H)5
- 2.OE+06 I Ce-141 Ce-144 1.5E+07 7.9E+07 5.3E+08 1.3EA1,0 I 3.OE+07 3.6E+08 8.3E+07 7.3EA08 1.OE+07 8.7E+07 6.1E+05 1.3E+07 I
Units for all except inhalation pathway are m2 mr sec / yr /Ci,,inhalation pathway units are mr m33 / yr uCi.
Up Values to be Used For the Maximum Exposed Individual I
Pathway Fruits, vegetables and grain (kg/yr)
Infant Child 520 Teen 630 Adult 520 I
Leafy vegetables (kg/yr) -- 26 42 64 Milk (L/yr) 330 330 400 310 Meat and poultry (kg/yr) 41 65 110 I.
Fish (kg/yr)
Drinking water (L/yr) 330 6.9 510 16 510 21 730 I
Shoreline recreation (hr/yr) -- 14 67 12 Inhalation (m3/yr) 1400 3700 8000 8000 Table E-5 of Reg. Guide 1. 109.
Reference PMP-6010-OSD-001 Rev. 21 Page 49 of 91 OFF-SITE DOSE CALCULATION MANUAL Dose Factors for Various Pathways Pages: .1 48-51 Bip Factors for Aquatic Foods pCi I-/kg pCi Element Fish - Invertebrate H 9.OE-1 9.0E-1 C;_ 4.6E3 9.1E3 Na 1.0E2 2.0E2 P 1.0E5 2.0E4 Cr 2.0E2 2.0E3 Mn 4.0E2 9.0E4 Fe 1.0E2 3.2E3 Co 5.OEl 2.0E2 Ni L.0E2. 1.0E2 Cu 5.OE I 4.0E2 Zn -2.0E3 - 1..0E4 Br 4.2E2 3.3E2 Rb- -. 2.0E3 1.0E3 Sr, 3.OE1 . 1.0E2 Y" -- 2.5E1 1.0E3 Zr - .3.3E0 6.7E0 Nb .. 3.0E4 1.0E2 Mo 1..E1 1.OE1 Tc 1.5E1--" 5.OEO:
Ru .1.0E1 3.0E2 Rh 1.0E1' 3.0E2 Te 4.0E2 6.1E3 I 1.5E1 5.OEO
-1 .i Cs 2.0E3 1.0E3 Ba. 4.OEO 2.0E2 La 2.5EI. 1.0E3 Ce 1.0E0 1.0E3 Pr 2.5E1 1.0E3 Nd 2.5E1 1.0E3 W 1.2E3 1.OEI Np 1.OE1 4.0E2 Table A-1 of Reg. Guide 1.109.
Refere nce PMP-6010-OSD-001 Rev. 21 Page 50 of 91 3 OFF-SITE DOSE CALCULATION MANUAL Attachme nt 3.1 Dose Factors for Various Pathways Pages:
48- 51 i
Daipj External Dose Factors for, Standing on Contaminated Ground 1 mrem m' / hr pCi -
H-3 Radionuclide Total Body 0
Skin 0
I C-14 Na-24 0
2.5E 0 2.9E-8 I
P-32 0 0 Cr-51.
Mn-54 2.2E-10 5.8E 2.6E-10
.6.8E-9 I
Mn-56 - 1.1E-8. 1.3E-8 Fe-55 Fe-59
.0 8.0E&9
- 0 9.4E79 I
Co-58 7.0E-9 .8.2E-9 Co-60 Ni 1.7E-8 0-2.0E-8 0
I Ni-65 3.7E-9 4.3E-9, Cu-64 Zn-65 -
1.5E-9 4.0E-9 1.7E-9 4.6E-9 U Zn-69 " 0 " 0 Br-83 Br-84
. 6.4E-11:
1.2E-8 9.3E-11 1.4E-8 I Br-85 0 0 Rb-86 Rb-88 6.3E-10'.
3.5E&9 1.5E:8-7.2E-10.
4.OE-9 1.8E-8 I
Rb-89.
Sr Sr-91 Sr 5.6E-13 7T1E9&"
9.OE-9 6.5E-13 8.3E-9 1.OE-8 I
Y-90 Y-91m Y-91 i-2.2E-12 3.8E-9..
2.4E-11 2.6E-12.
4.4E-9 2.7E-11 U
Y-92 1-.6E-9 .1.9E-9 Y-93 Zr-95 5.7E-10 5.OE-9 7.8E-10 5.8E-9 I
Zr-97 5.5E-9 6.4E-9 Nb-95 Mo-99 5.1E-9 1.9E-9 6.OE-9 2.2E-9 I
Tc-99m 9.6E-10 1.1E-9 Tc-101 Ru-103 2.7E-9 3.6E-9 3.OE-9 4.2E-9 I
Ru-105 4.5E-9 5.1E-9 Ru-106 Ag-110m 1.5E-9 1.8E-8 1.8E-9 2.1E-8 I
Te-125m 3.5E-11 4.8E-11 I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 51 of 91 OFF-SITE DOSE CALCULATION MANUAL .1 .
Doge Facto'rs- for VariousFPages:
Pathways 48 -51 Radionuclide Total Body' Skin*
Te-127m 1.1E-12 1.3E-12 Te-127 1.OE*,-17 1.,1E-11 Te-129m* 7.7E;10 9.0El0 Te-129 7.1E-10 8.4E--10 -
Te-131rfi 8.4E-9 9.9E-9 Te-131 2.2E-9 2.6E-6 Te-132 . 1.7E-9 2.OE-9 1-130 1.4E-8 .1.7E-8 1*131 -2.8W-9 3.4E-9 1-132 1.7E-8 2.OE-8 1-133 3.7E-9 4.5E-9 1-134 1.6E-8 1.9E-8--
1-135 1.2E-8 1.4E-8 Cs-134 1.2E-8 1.4E-8 Cs-136 1".5E-8 1.7E-8 Cs-137 4.2E79 4.9E-9 Cs-138, 2. 1E-8 2.4E-8 Ba-139 2.4E-9 2.7E-9.
Ba-140 2.lE-9 2.4E-9 Ba-141 4.3E-9 ' 4.9E-9 Ba-142 -7.9E9 .9.0E-9 La-140 1.5E-8 1.7E-8 La-142 1.5E-8 1.8E-8 Ce-141 5.5E-.fO 6.2E-10 Ce-143 2.2E-9 2.5E-9 Ce-144 3.2E-i0 3.7E-10 Pr-143 0 7 0 Pr-144. 2.OE-10 2.3E-*10 Nd-147 1.0E-9 1.2E-9 W-187 3.1E-9 3.6E-9 Np-239 9.5E;-10 ".lE-9 Table E-6 of Reg. Guide 1.109.
Reference PMP-6010-OSD-001 Rev. 21 Page 52 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
Radioactive Liquid Effluent Monitoring Instruments Pages:
Attachment 3.2 52-54 U
INSTRUMENT Minimum Applicability Action Channels Operablea I
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste Effluent Line (RRS-100!)
(1)# At times of release 1 I
- b. Steam Generator (1)# At times of release**" 2 Blowdown Line (R-19, DRS 3/4100 +).
- c. Steam Generator (1)#
At times of release 2 I
Blowdown Treatment 2.
Effluent (R-24, DRS 3/4200 +)
Gross Radioactivity Monitors Not-Providing Automatic Release Termination I
- a. Service Water, System Effluent Line (R-20, R-28) j (1) per
,train At all times 3 I
3.' Continuous Comlposi.te Sampler Flow Monitor ,_..-..
- a. Turbine Building Sump. (1)
A a t At, all times3 I
Effluent Line. I I
- 4. 'Flow Rate Measur-ement Devices (1)
- a. Liquid Radwaste Line a.
(1)' At' times of release (RFI-285)
- b. Discharge Pipes*
(1) At all times. I
- c. Steam Generator.Blowdown (1) At'tines of release Treatment Effluent (DFI-352)
- d. Individual Steam Generator sample flow (1) per At times of release I
to Blowdown radiationmonitors alarmi- generator (DFA-310,_320,_330 and_340) _ _.*
I
- 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.
OPERABILITY of RRS-1001 includes OPERABILITY of sample flow switch RFS-1010, which is an attendant instrument as defined in Technical Specification section 1.1, under the term Operable - Operability. This item is also applicable for all I
Eberline liquid monitors (and their respective flow switches) listed here.
- Since these monitors can be used for either batch or continuous release the appropriate action statement of 1 or 2 should apply (that is, Action 1 if a steam generator drain is being performed in lieu of Action 2). It is possible, due to the steam generator sampling system lineup, that BOTH action statements are actually entered. This would be the case when sampling for steam I
generator draining requires duplicate samples while the sample system is lined upto discharge to the operating units blowdown
+
system. In this case the steam generator drain samples can;fulfill the sample requirement for Action 2 also. Action 2 would be exited when sampling was terminated.
. Some Westinghouse.(R) radiation monitors are being replaced by Eberline (DRS) monitors. Either monitor can fulfill the I
operability requirement. Ensure surveillances are current for operability of the instrumentation prior to0rusing it to satisfy applicability requirement.
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 53 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments Pages:
52 - 54 a IF an RMS monitor is inoperable solely as the result of the loss of its control room alarm annunciation, 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 (mbre frequently than) the action frequency..
IF the RMS monitor is inoperable for reasons other than the lossýof 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.
TABLENOTATION, Action 1 With the number of channels OPERABLE-less than required by the Minimum Chlaimels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:. J,
- 1. At least two independent samples are analyzed in accordance with Step 3.2.3a 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 Minirmuni Channels OPERABLE requirement, effluent releases via thlis-pathway may continue fr UP to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of.at least 10-7 pCi/gram:
- 1. At ieast once per shift when' the specific activity of the'secondary coolant is >-0.01 pCi/gram DOSE EQUIVALENT 1-131.
- 2. At least once per-24 hours when.the specific activity of the secondary coolant is . 0.01
. p.Ci/gram DOSE'EQUIVALENT 1-131'..,
After 30 days,, IF the 7channels -are not-OPERABLE, THEN continue releases with required grab samples provide a description of why the inoperability, Was not corrected in the next Annual Radiological Effluent release Report.
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 p'Ci/ml. Since the Westinghouse ESW monitors (R-20 and R-
- 28) are only used for post LOCA leak detection and have noauto trip functioni associated with them, grab samples are only needed if the Containment Spray Heat Exchanger is in service. After 30 days, IF the channels are not OPERABLE, THEN continue releases with gr.ab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radi0logical Effluent release Report.
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not
. OPERABLE, THEN continue releases with grab samples once per shift and provide a description of whythe inoperability.was'not corrected in the next Annual Radiological Effluent release Report.
Reference t PMP-6010-OSD-001 Rev. 21 Page.54 of 91 OFF-SITE DOSE CALCULATION MANUAL Instrments Pages:
52 -P54's Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments Action 5 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 verified to be within the required band atleast once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.,! 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. iF the flow cannot be obtained within the desired band, THEN declare the radiation monitor inoperable and enter the appropriate actions statement, Action 2.
Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing
- r I
.. .I . I"
- .. . .....!U
,iI I
I I
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 55 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.3 Radioactive Liquid Effluent Monitoring Pages:
Instrumentation Surveillance Requirements 55-'56 Instrumerit 1 _._
CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION
_ _JEST CHANNEL OPERATIONAL
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste D* P B(3) Q(5)
Effluent Line (RRS- 1001)
- b. Steam Generator D* M B(3) Q(l)
Blowdown Effluent Line
- c. Steam Generator D* M B(3) Q(1)
Blowdown Treatment Effluent Line
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water D M B(3) Q(2)
System Effluent Line
- 3. Continuous Composite Samplers.
- a. Turbine Building D* N/A N/A N/A Sump Effluent Line I
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste D(4)* N/A B Q Effluent
- b. Steam Generator D(4)* N/A N/A N/A Blowdown Treatment Line
- During releases via this pathway
Reference PMP-6010-OSD-001 Rev., 21 Page 56 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Pages:
.55 -.56 I
TABLE NOTATION
.1.. Demonstrate with the CHANNEL OPERATIONAL 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 alarm/trip setpoint.
- 2. Circuit failure.*
- 3. Instrument indicates a downscale failure.*
- 4. Instrument control not set in operating mode.*"
- 5. Loss of sample flow. * . . . l
- 2. Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:
- i. Instrument indicates measured levels above the alarn setpoint.
- 2. Circuit failure.
I
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operating mrode.
- 3. Perform the initial CHANNEL CALIBRATION using one or more sources with.traceability, back to the National Institute of Standards and Technology (NIST):. These sources, permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL.CALIBRATION, sources that have been related to the initial calibration ma b6 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which c-ntiniiuous,periodic or bitch releases are rlnade. .3 5.. Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control roomialarm annunciation occurs if any of the f6l1owingconditions exists:,
- 1. Instrument indicates measured levels above the alarm/trip setpoint.
- 2. Circuit failure.***
- 3. Instrument 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 forthe automatic isolation on such occurrences. . --
Operations currently performs the routine channel checks and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests. Chemistry performs the channel check on the continuous composite sampler.
I These responsibilities are subject to change without revision to this document.
I I
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 57 of 91 OFF-SITE DOSE CALCULATION MANUAL
' ' Pages:
Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
I 157 -59 Instrument (Instrument #) Operable' Minimum Action Channels Action
- 1. Condenser Evacuation: System
- a. Noble Gas Activity 6 6(1)
Monitor (SRA- 1905/2905) ....
b* Flow Rate Monitor (SFR-401, (1) 5 1/2-MR-054 and/or SRA- 1910/2910) OR j (SFR-402 and 1/2-MR-054) "__ _
- 2. Unit Vent. Auxiliary Building Ventilation System
- a. Noble Gas Activity (1)
- 6 Monitor (VRS-1505/2505) ,.
- b. Iodine Sampler
- 88(1)
Cartridge for VRA-1503/2503
- c. Particulate Sampler Filter 8(1) for VRA-1501/2501 " .
- d. Effluent System Flow Rate . - .." " (1) .
- 5 Measuring Device (VFR-315, MR-0542 " "
and/or VFR-1510/2510) . . ..
- e. Sampler Flow Rate " (1)
- 5 Measuring.Device (VFS,1521/2521),., _____ ___.____....
- 3. Containment Purge and Containment Pressure'_
Relief (Vent) t***... .. ..... ,________.. ... , ___,
- a. Containment Noble Gas Activity Monitbr .. ***i2.32,(1) 7.
ERS-13/1405 (ERS-23/2405) -... .. . *
- b. Containment Particulate Sampler Filter (1)
- 10 ERS-13/1401 (ERS-23/2401) _ ____*_.,. . _..
- 4. Waste Gas Holdup System and CVCS HUT (Batch releases)**
- a. Noble Gas Activity (1) ****4 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
- Containment Purge and other identified gaseous batch releases can be. released utilizing the same double sampling compensatory action requirements of action 9 identified here even if there is no termination function associated with it like that associated with the two specific tank types listed here.
- During releases via this pathway
Reference PMP-6010-OSD-001 Rev. 21 Page 58 of 91 I OFF-SITE DOSE CALCULATION MANUAL Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
57 - 59 1
TABLE NOTATIONS
- 1. TF an RMS monitor is inoperable solely as the result of the loss of it's control room alarm annunciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance
' requiremhent:
- 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 greaier than (more frequently than) the action frequency.
EF the RMS monitor is inoperable for reasons other than the loss of control room annunciation, THEN the only when isthetaking grab sampleaction acceptable grabis samples monitor and conducting laboratory analyses as, the reading is equivalent to a functional.
.2. Consider releases as occurring "via this pathway" under the following conditions:
- The
-OR-Containment
,! :' System is in operation and Purge Containment Operiability is applicable,
'""" "1
- , 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 (an extension of the Auxiliary Building) and is covered by Item 2 of this Attachment.
1
-OR-A Containment Pressure Relief (CPR) is being performed.
Once Purge (clean-up) has been completed and 'Ventilation' mode of Purge has commenced - resultant return to 'Clean-up' mode can be made with no additional sampling requirements or paperwork - so long as either ERS-1305/2305 OR ERS-1405/2405 are operable. Containment particulate channels are not needed since the RCS has been degassed and depressurized so leak detection is not an issue.
- 3. For purge (including pressure relief) purposes only. Reference TS 3.6.1, Containment Purge Supply and Exhaust System Isolation Instrumentation and 3.4.15, RCS Leakage Detection Instrumentation for additional I
informnation.
- 4. For waste gas releases only, see Item 2 (Unit Vent, Auxiliary Building Ventilation System) for additional requirements.
ACTIONS
- 5. 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. After 30 days, iF the channels are not OPERABLE, THEN continue releases with estimation of the flow rate once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.
I
- 6. With the number 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 30 days, iF the channels are I
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. 3 I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 59 of 91 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Effluent Monitoring Instrumentation Pages:
Attachment 3.4 57-59
- 7. With the number of channels OPERABLE less than- required by the Minimum Channels OPERABLE requirements, immediately suspend PURGING or VENTING (CPR) of radioactive effluents via this pathway.
- 8. 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 with 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 with sample collection by auxiliary 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 number of channels OPERABLE less than required by .the Minimum Channels.OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior.to initiating the release:
- a. At least two independent 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.
After 14 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling equipment and provide a description of-whythe inoperability was not corrected in the next Annual Radiological Effluent Release Report ' . '" -'
- 10. See Technical Specification 3.4.15, RCS Leakage Detection System Instrumentation.
z.
Compensatory actions are governed by PMP-4030-EIS-00i, Event.-Initiated Surveillance Testing.
Reference . PMP-6010-OSD=001 Rev. 21 Page 60 of 91 I
OFF-SITE DOSE CALCULATION MANUAL A Radioactive Gaseous Effluent Monitoring Pages:
I Instrumentation Surveillance Requirements 60 - 61 Instrument CHANNEL ,, SOURCE CHANNEL CHANNEL OPERATIONAL I
CHECK.:I CHECK CALIBRATION TEST
- 1. Condenser Evacuation System Alarm Only U
- a. Noble Gas Activity Monitor D** M B(2) Q(1)
(SRA- 1905/2905).
- b. System Effluent Flow Rate D** NA. B Q I
(SFR-401, SFR-402, MR-054, SRA-1910/2910) *___..
- 2. Auxiliary Building Unit Ventilation System Alarm Only I
- a. Noble Gas Activity Monitor (VRS-1505/2505)
- b. Iodine Sampler D*
W*NA M
B(2),
NA Q(1)
NA I
(For VRA-1503/2503)
- c. Particulate Sampler (For VRA-1501/2501)
W*
NA NA
, ,NA I
- d. System Effluent Flow Rate D* NA. B Q, Measurement Device (VFR-315, MR-.054, VRS-1510/2510) _ ..... _ _ _ _
I
- e. Sampler Flow Rate Measuring Device (VFS-1521/2521)
D* I N/A B Q U
- 3. Containment Purge System and Alarm and Trip Containment Pressure Relief
- a. Containment Noble Gas S P B(2) Q I
Activity Monitor (ERS-13/1405 and ERS-23/2405)
- b. Containment Particulate Sampler (ERS-13/1401 and S NA B Q I ERS-23/2401)
- 4. Waste Gas Holdup System Including CVCS HUT I
- a. Noble Gas Activity Monitor Q(3)
Providing Alarm and Termination (VRS- 1505/2505)
I
- 5. Gland Seal Exhaust
- a. Noble Gas Activity (SRA-1805/2805)
Q(1) I
- b. System Effluent Flow Rate (SFR-201, MR-054, SRA-1810/2810)
Q i
- At all times
- During releases via this pathway I
Reference PMP-6010-OSD-001 Rev. 21 Page 61 of 91 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Effluent Monitoring Pages:
Instrumentation Surveillance Requiriements 60 - 61 TABLE NOTATIONS Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm'annunciation occurs if any of the following conditions exists:
- 1. Instrument 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 energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial. calibration may be used. -
- 3. Demonstrate with the CHANNEL OPERATIONAL 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 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 perform channel calibrations and channel operational tests. These responsibilities are subject to change without revision to this document.
- i ,
Reference PMP-6010-OSD-001 Rev. 21 Page 62 of 91 I OFF-SITE DOSE CALCULATION MANUAL Pages:
I Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program 62 -63
[Ref. 5.2.1s]
I LIQUID RELEASE SAMPLING FREQUENCY MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF I TYPE FREQUENCY ANALYSIS DETECTION (LLD)
(p.Ci/ml) a I A. Batch Waste P . p Principal, ... 5xfO-7 Release Tanks' Each Batch Each Batch Gamma Emitters e I
.1-131 lx10-6
. P P Dissblved, and Entrained Gases I
Each Batch Each Batch (Gamma lx1 O P, M Emitters) 1-3 "x10- 5 I
Each Batch r Composite," ____ .. _" ...
Gross Alpha lx107 I
" Sr.-89. Sr-'90 . 5X10 Each Batch Composite b Fe-55 lx10-6 I
B. Plant W Principal Continuous Releases* d Daily Composite' Gamma Emitters' 5x 10-7 I
1x10 6 M M 1-131 Dissolved and Entrained Gases lx10s I
(Gamma Emitters)
Daily Composite' Gross Alpha Ix10 7
I
.Q Sr-89, Sr-90 5x10 8 Daily Composite b Fe-55 1x10-6 I
- During releases via this pathway This table provides the minimum requirements for the liquidsampling program. If additional sampling is performed I
then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification.
Examples of these samples are the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> secondary coolant activity and Monitor Tank tritium samples.
I I
I
Reference" PMP-6010-OSD-001 Rev. 21 Page 63 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.6 Radioactive Liquid Waste: Sampling and Analysis Program Pages:
Atahmn"3662- 63 TABLE NOTATION .
- a. The lower limit of detection (LLD) is defined'in Table Notation A. of A~ttachment 3.20, Maximum Values for Lower Limits of DetectionsA," -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 t-ensure thorough mixing. Examples of these are Monitor Tank and Steam Generator Drains. Before a batch is released the tank is sampled and analyzed to determine that it can be released without exceeding federal standards.
- d. A continuous release is the discharge of liquid of a non-discrete volume; e.g. from a volume of system that has an input flow during the continuous release., This type of release includes the Turbine Room Sump, Steam Generator Blowdown and the Steam Generator Sampling Syitem.
- 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.
This list does notrmiean 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.
Reference PMP-6010-OSD-001 Rev. 21 Page 64 of 91 I OFF-SITE DOSE CALCULATION MANUAL Radioactive..Gaseous Waste Sampling and Pages:
I Attachment 3.7 Analysis Program 64 - 65 I
Gaseous Release Type Frequency Minimum Type of Lower Limit
- a. Waste-Gas Storage P Analysis Frequency P,
Activity Analysis Principal Gamma' of Detection (ItCi/cc) a I Tanks and CVCS HUTs Each Tank Each Tank Emitters d . 1 x 10-4 Grab Sample H-3 'I lx10 6 I
- b. Containment Purge P P Principal Gamrma CPR (vent)**'
Each Purge'"
Twice per'-
Each Purge Thice per Month Emitters "... II..x 10-4 I
Month
- c. Condenser Evacuation 4
WorM . M.
H-3 Principal Gamma 1 x'i0.6 I
System Grab Sample Particulate Sample Emitters d x 101 Gland.Seal Exhaust* :, *.'
- "M W
W M1)'
H-3!: .,:x.
Prindiple.Gamnii Im, 1
10-04 I
Noble Gas Emitters d M
Iodine Adsorbing.
1-131
... . 'x10: 2 I
Media
. Continuo6s
" W
-Noble Gas'Monitor
' Noble Gases;
' ' 1 x 10"6 I
- d. Auxiliary Building Unit Continuousc ' Wb . 1-131" Vent* " '"" '
Continuous
' : "! Iodine"-Adsorbihig
.. ;M edia--
W b.
Principal Gamma
' 1 x10' 2 I
Continuous' Particulate Sample M
Composite Particulate
'Emitters Gro's Alpha d 1x 101 I x 10x1l I
... ______. ___ Sample.
W Grab Sample w h, H-3 Sample H-3
' I1 x 10-6 I
,Wg Principle Gamma I1x 10-4 Continuous' '
Noble Gas Q
Emitters Sr-89, Sr-90 I
Composite Particulate 1 x 1011 Sample __ ,__
- e. Incinerated Oilc Continuous '
P Noble Gas Monitor P
Noble Gases' Principal Gamma 1 x 106 I 5 x fO7
- During releases via this pathway Each Batch' Each Batch '
"*Only a twice per month sampling program for containment noble gases and H3 is required Emitters d '
I This table provides the minimum, requirements for, the gaseous sampling program. If additional, sampling is performed then those sample results can be used to quantify releases in' lieu of composite data for a more acctrate I
quantification. Examples of these samples are verification or compensatory action sample results.
I I
Reference PMP-6010-OSD-001 'Rev. 21 Page 65 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.7 Radioactive Gaseous Waste'Sampling and Pages:
Analysis Progriam 64-65 TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of DetectionsA' - REMP
- b. Change: samples at least once per 7 days and complete analyses within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.
Perform analyses at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or THERMAL POWER change greater than 15 % per hour of RATED THERMAL POWER. WHEN samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, THEN the corresponding LLDs may be increased by a factor of
- 10. This requirement does not apply IF (1) analysis shows that DOSEQ 1131 concentration in the RCS has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. IF the daily sample requirement has been entered, THEN it can be exited early once both the radiation monitor reading and the RCS DOSEQ 1131 levels have returned .
to within the factor of 3 of the pre-event 'normal'. [Ref. 5.2. ly]
- c. Know the ratio of the sample flow rate to the sampled stream flow rate for the time-period covered by each dose or dose rate calculation 'made in accordance With steps 3.2.4a, 3.2.4b, and 3.2.4c of this document.
Sampling evolutions are not an interruption of a continuous'release or sampling period.
- d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, !Ce-141 and Ce-144 for particulate emissions. This list does not 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.
- e. Releases from incinerated.oil are discharged thr6ugh the Auxiliary Boiler System. Account for releases based on pre-release grab sample data. .
- f. Collect samples of waste oil to be incinerated from the container in which the waste oil is stored (example: waste oil storage tanks, 55 gal. drums) prior to transfer to the Auxiliary Boiler System.
Ensure samples are representative of container c6ntents.
- g. Obtain and analyze a gas marinelli grab sample weekly for noble gases effluent quantification.
- h. Take tritium grab samples at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.
- i. Grab sampling of the Gland Seal Exhaust pathway need not be performed if the RMS low range channel (SRA-1805/2805) readings are-less than 1E-6 gC/cc. Attach the RMS daily averages in lieu of sampling. This is based on operating experience indicating no activity is detected in the Gland Seal Exhaust below this value. Compensatory sampling for out of service monitor is still required in the event 1805/2805 is inoperable.
- j. Sampling and analysis shall also be performed following shutdown, startup or THERMAL POWER change exceeding 1.5 % of RATED THERMAL POWER within a one hour period. This noble gas
'sample shall be performed within four hours of'the event. Evaluation of the sample results, based on
'previous samples,will be perfrmed to determine if any fu*ther sampling isnecessary.
Reference PMP-6010-OSD-001 Rev. 21 Page 66 of 91 I OFF&SITE DOSE CALCULATION MANUAL I Attachment 3.8 Multiple Release Point Factors for Release Points ge I
Liquid Factors Monitor Description
- UISG-Blowdown .
Monitor Number 1R19/241- DRS 3100/3200"
-, MRP #
0.35 I
- 2 SGBlowdown
- 1 & 2 Liquid Waste Discharge 2R19/24, DRS 4100/4200" -
RRS-1000 "
0.35, 0*.30 I Sources of radioactivity released from the Turbine Room Sump (TRS) typically originate! from the secondary cycle which is already being monitored by instrumentation that utilizes multiple release poirit (MRP) factors. The MRP is I
an administrative value that is used to assist with maintaining releases ALARA. The TRS has no actual radiation monitor, but utilizes an automatic compositor for monitoring what has beeji released. Thebatch release path, through RRS- 1000, is the predomhinant release path by several magnitudes. Tritium is the predominant radionuclide released from the site and the radiation monitors do not respond to this low energy beta ehmitter. Based on this I
information and the large degree of conseivatism built into the radiation monItor setpointimethodologyl it does not appear to warrant further reduction for the TRS release path since its source is predominantly the secondary cycle which is adequately covered by'this factor. I I Monitor Descriptioni . Monitor Number Gaseous Factors
-. -Flow Rate (cfm) .. MRP #
I Unit 1 Unit Vent VRS-1500 186,600 0.54 I
j 0.00363 Gland Seal Vent Steam Jet Air Ejector_
Start Up FT Vent SRA-.1800 SRA-1900..- .
1,260 3,600 (b) 1,536
. 0.01 0.004 I
Total Unit22 192,996 I
Unit Vent Gland Seal.Vent
' VRS-2500 SRA-2800 143,400 5,508 (a) .
0.41 0.02 I Steam Jet Air Ejector SRA-2900 3,600 (b) 0.01 Start Up FT Vent Total 1,536 154,044 I 0.004 I
- Either R-19, 24, DRS 3/4100 or 3/4200 can be used for blowdown monitoring as the Eberline monitors (DRS) are replacing the Westinghouse (R) monitors.
I a
Nominal Values Two release points of 2,754 cfm each are totaled for this value. I b This is the total design maximum of the Start Up Air Ejectors. This is a conservative value for unit 1.
I I
I
Reference PMP-6010-OSD-001 Rev. 21. Page 67 of 91 OFF-SITE DOSE CALCULATION MANUAL Liquid Effluent Release Systems Page: .9 67
Reference PMP-6010-OSD-001 Rev. 21 Page 68 of 91 U OFF-SITE DOSE CALCULATION MANUAL]
Plant Liquid Effluent Parameters Pa Attachment 3.10 I
SYSTEM COMPONENTS
' TANKS IPUMPS CAPACITY (EACH)
FLOW RATE (EACH)*
I I Waste Disposal System
+ Chemical Drain Tank 1 1 600 GAL. 20 GPM I
+ Laundry & Hot Shower Tanks 2- 1 600 GA9L. 20 GPM
+ Monitor Tanks 4,- 2 21,600 GAL. 150 GPM I
" Waste Holdup Tanks .2 25,000 GAL.
+ Waste Evaporators
+ Waste Evaporator Condensate 3
2 .2 6,450 GAL 30 GPM 150 GPM I
Tanks I
II Steam Generator Blowdown and Blowdown Treatment Systems
- Start-up Flash Tank (Vented)#
1-1 ,800 GAL. 580 GPM I
+ Normal Flash Tank (Not. 1 525 GAL. 1i00 GPM Vented)
+ Blowdown Treatment System , j I
_ _ 60GPM I
III Essential Service Water Systeni- '
+ Water Pumps . '4 ..... 10,000 GPM I
" Containment Spray Heat 4,
{3,300 GPM Exchanger Outlet -
IV Circulating Water Pumps '_.____'
. i_
I Unit 1 1 ... I....__ 230,000 GPM Unit 2 1 4 ' I 230,000GPM U Nominal Values The 580 gpm value is calculated from. the Estimated Steam-Generator Blowdown Flow vs. DRV Valve Position letter prepared by M. J. O'Keefe, dated 9/27/93. ,This is 830 gpm times the 70% that remains I
as liquid while the other 30% flashes to steam and exhausts out the flash tank vent.
I 1
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 69 of 91 OFF-SITE DOSE CALCULATION MANUAL Page: .11 Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Eberline Liquid Monitors 69 This includes the following monitors: RRS-1000, DRS 3100, DRS 3200, DRS 4100, and DRS 4200.
[Ref. 5.2. lp].
NUCLIDE EFFICIENCY (cpmn/Ci/cc) 1-131 3.78 E7 Cs'-137 3.00 E7'
-Cs-134 ... 7.93 E7 Co-60 5.75 E7 Co-58 - 4.58 E7 Cr1 51 3.60E6 Mn-54 3.30 E7 Zn-65 1.58 E7 Ag-110M :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 Ce-144 4.83 E6 Co-57 3.80 E7 Cs-136 1.07 E8 Fe-59 2.83 E7 Sb-124 5.93 E7 1-133 . .. 3.40 E7-1-134 7.23 E7 1-135 3.95 E7 Mo-99 .. .. 8.68E6 Na=24 4.45 E7
.Nb-95 " 3.28 E7 -
Nb-97 3.50 E7 Rb-89. 5.00EE7 Ru- 103 3.48 E7 Ru-106 1.23 E7 Sb-122 2.55 E7 Sb-125 3.15 E7 Sn-113 7.33E5 Sr-85 3.70 E7 Sr-89 2.88 E3 Sr-92 ,, 3.67 E7 Tc-99M 3.60 E7 Y+88 5.25 E7 Zr-95 3.38 E7 Zr-97 3.10 E7 Kr-85 1.56 E5 Kr-85M 3.53 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
Reference PMP-6010-OSD-001 Rev. 21 Page 70 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.12 Counting Efficiency Curves for:R-19, and R-24 Pages:
70 - 71 Counting Efficiency Curve for R-19 Efficiency Factor = 4.2 E6 cpm/uCi/ml (Based on empirical data taken during pre-operational testing with Cs-137) 1.OOE+07 1.00E+06 1.OOE+05 r
1.00E+04 0
0 1.OOE+03 1.OOE+02 1.00E+01 1 .OOE+01 1 .bOE+00 q( Sl) S4 0
SD 9 -- --
o
+
[9 wU w W iiLb 0
m ocuoies om
- .. . , micrc~ures/m M -
M -M -M -M -M M
Reference PMP-6010-OSD-001 Rev. 21 Page 71 of 91 OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency Curves for R-19, and R-24 Pages: .12 70 - 71 Counting Efficiency Curve for R-24 Efficiency Factor = 7.5E6 cpm/uCVml (Based onf empirical data taken during pre-operational testing with Mn-54) 1.00E+07 1.00E+06 M1.00E+05 1.OOE+04 0.1.00E+03 1.OOE+02 1.00E+01 1.OOE+00 to 0 0D w
0.I 9.- ' . 9° g.
w C?e w . .. 9. w uJ 0
0.
microcurieslml -
Reference PMP-6010-OSD-001 Rev. 21 Page 72 of 91 OFF-SITE DOSE CALCULATION MANUAL Counting Efficiency Curve for R-20; and R-28 Page:
tae Attachment 3.13.
Counting Efficiency Curve for R-20 and R-28 Efficiency FaCtor!= 4.3 E6 cpmh/iCi/ml (Based on emnpiricail'data taken~during pre-operalional testing with Co-58) 1.OOE+07 1.OOE+06 1.00E+05 0
o 1.00E+03 1.00E+03 1.OOE+01 1.00E+00 so 10 C? wU w Lit w~
0 0U 0, 0 000 0
microcuries/ml
= M M - M M M-- = M = -M =--- M
Reference PMP-6010-OSD-001 Rev. 21 Page 73 of 91 OFF-SITE DOSE CALCULATION MANUAL Gaseous Effluent Release Systems Page:
Attachment 3.14 73 RELEASE ISURES] SYSTEMS POINTS WasteGas Decay Tanks and CVCS HUT Auk BuildingVent en61 Pnlan. l*
Engin-emd Safety aa FeaturesVent System F aen re$ V teultopVSh Fn Pg Fromanmn Hedr Vnttonyeu 0
E
.] _. .... ...... ::F ..
Foel Handling Ventiltion Filmler Roomsp Containment Prge V S ft purgtrea~ndaiur r end Relief Syrtrt CogVece F.-Ft., Ft.
.EPA F_
(771.6- puntyuel HEEP C.-
HEE tnsvumentRoom Flee al e VFit Fitter PlantVent to Purge System _V Mlnitot lntO~~menta~Tim HEA abo.-F M-gIe"-e-;foat Ate. Re.eto montr tjnit Vent TtN. ]-We..en Rediction on roge hieht=
Asmr.
Steam Geneator L-1e Eohauo 131oodmeTreatmet Sf Ble.ordo System a.-.sphere Tokngaoeouereleeee .
Condenser Air Ejector System SSampling PointJ SSampling Point FlmDt Gland Se.l Condenser Exhaust IT..E-.heu.i Steam xasePacking I aditon Monitor
- Fo oio
.phj
Reference PMP-6010-OSD-001 Rev. 21 Page 74 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
Plant Gaseous Effluent Parameters Page:
Attachmnent 3.15 74 I
SYSTEM UNIT EXHAUST FLOW RATE CAPACITY I
(CFM)
'PLANT AUXILIARY BUILDING UNIT VENT 2 1 186,600 max 143,400 max :a I
WASTE GAS DECAY TANKS (8) 1 125:, 4082 FT 3 @100 psig AND CHEMICAL & VOLUME
'CONTROL SYSTEM HOLD UP 28,741 ft3 max
@ 8#, 0 level I
TANKS -(3)
+ AUXILIARY BUILDING EXHAUST 2 1 72,660:,
59,400 U
+ ENG. SAFETY FEATURES -1& 2 50,000 VENT
+ FUEL HANDLING AREA VENT 1 30,000 I
SYSTEM CONTAINMENT PURGE SYSTEM 1&2 32,000' I CONTAINMENT PRESSURE. 1 & 2, 1,000 RELIEF SYSTEM INSTRUMENT ROOM PURGE 1& 2 .1,000.
I SYSTEM. ,", __,___.__ '
II CONDENSER AIR EJECTOR -2Release Points I
SYSTEM One for Each Unit NORMAL STEAM JET AIR EJECTORS 1&2 230'- I START UP STEAM JET AIR.
EJECTORS 1 &2
__J___
i 3,600
" _ I II TURBINE SEALS SYSTEM "1 2
1,260.
5,508 2 Release Points I for Unit 2 IV START UP FLASH TANK VENT 1 1,536 __
I Ds t t2 1,536o
+ Designates total flow for all fans.
- I I
I I
Reference PMP-6010-OSD-001 Rev. 21 Page 75 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.16 10 Year Average of 1995'-2004 Data Pages: 75 - 76 z/Q GROUND AVERAGE (sec/m 3 )
DIRECTION DISTANCE (METERS)
(WIND FROM) 594 2416 4020 5630 7240 N 4.17E-06 4.82E-07 2.25E-07 1.33E-07. 9.32E-08' NNE 3.02E:06 3.64E-07 1.73E-07 1.04E-07 '7.29E-08 NE 4.54E-06 5.31E-07 . 2.60E-07 1.59E.07 1.13E-07 ENE 7.16E-06 7.99E-07 4.04E-07 2.52E-07 '1.80E-07 E 1.04E-05 1.13E-06 5.82E-07 -3.66E-07 21. 63E-07 ESE 1.07E-05 1.18E-06 6.04E-07 3.78E-07 .2.72E-07, SE 1.15E-05 1.24E-06 6.36E-07 4.OOE-07 2.88E-07 SSE 1.30E-05 *. 1.42E-06 7.27E-07 4.57E-07 3.29E-07 S 1.41E-05 1.57E-06 7.92E-07 4.93E-07 3'.54E-07 SSW 7.03E-06 - 7.81E-07 3.90E-07 2.41E-07 1.72E-07 SW 4.12E-06 4.73E-07 2.28E-07 1.38E-07 9.73E-08 WSW 3.29E-06 3.65E-07 1.76E-07 1.06E-07 7.52E-08 W .3.63E706 .4..1E-07 1.96E-07 1.18E-07 8.31E-08 WNW 3.02E-06'- 3.43E-07 1,:61E-07 9.59E-08 6.71E-08.
NW 3.22E-06 3.61E-07 1.71E-07 1.02E-07 7.16E-08 NNW ... 3.84E-06 4.29E-07 2.02E-07 1.20E-07 8.40E-08 DIRECTION DISTANCE (METERS) -
(WIND FROM) 12067 24135 40225 56315. 80500 N 4.64E-08 1.79E-08 8.89E-09 5.68E-09 3.56E-09 NNE .3.66E-08 1.43E-08 7.13E-09 4.56E-09 2:87E-09 NE 5.75E-08 2.30E-08 1.15E-08 7.41E-09 4.72E-09 ENE 9.30E-08 3.80E-08 :1.91E-08.. 1.23E-08 7.90E-09 E 1.37E-07 5.65E-08 2.85E-08 --1:83E-08 1.18E-08 ESE 1.41E-07 5.81E-08 2.93E-08 1.88E-08. 1.22E-08 SE 1.50E-07,;. 6.20E-08 3.12E-08 - 2.01E-08 1.30E-08 SSE 1.71E-07 7.06E-08 3.56E-08 2.29E-08 1.48E-08 S . 84E-07 .7.49E-08 3.77E-08 2.43E-08 1.56E-08 SSW 8.86E-08 3.59E-08 1.80E-08 ,, 1.15E-08 7.39E-09 SW 4.93E-08 1.96E-08 9.77E-09 6.27E-09 3.98E-09 WSW 3.80E .1.51E-08 ... 7.53E-09. 4.83E-09 3.07E-09 W 4.17E-08 1.64E-08 8.13E-09 5.20E-09 3.28E-09 WNW 3.34E-08 1.29E-08 6.41E-09 4.10EE09 2.57E-09 NW -3.57E-08 1.39E 6.89E-09 4.41E-09 2.77E-09 NNW 4.19E-08 3.35E-08 8.1OE-09 5.19E-09 3.27E-09 DIRECTION TO -SECTOR N A. E E: S .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 NNW =R 3
Worst Case X/Q = 2.04E-05 sec/m in Sector H 2004
Reference PMP-6010-OSD-001 Rev. 21 Page 76 of 91 I OFF-SITE DOSE CALCULATION MANUAL I Attachment 3.16 10 Year Average of 1995-2004 Data Pages: 75 - 76 I
D/Q DEPOSITION (1/M2)
DIRECTION (WIND FROM) 594 2416 DISTANCE (METERS) 4020 5630 7240 I
N-NNE NE 2.37E-08 9.86E-09
.1.29E-08 2.29E-09 9.52E-10 1.25E-09 1.04E-09 4.32E-10 5.67E-10 5.44E-10 2.27E-10 2.97E-10 3.47E-10 1.45E-10 1.90E-10 I
ENE 1.59E-08 1.54E-09 6.97E-10 3.66E-10 2.33E-10 E '.
ESE SE 1.87E-08 1.85E-08 1.81E-09 1.79E-09 8.20E-10 8.12E-10 4.30E-10 4.26E-10 2.75E-10 2:72E- 10 I
1.90E-08 1.83E-09 8.30E-10 4.36E-10 2.78E-10 SSE S
SSW 2.40E-08 3.68EL-08 2.30E-08 2.32E-09 3.56E-09' 2.22E-09 1.05E-09
- 1.61E-09 1.01E-09, 5.52E-10 8.46E-'10 5.28E-10 3152E-10 5!40E-10
,3.37E-10 I
SW 2.22E-08 2.15E-09 9.74E-10 5.11E-10 3.26E-10 WSW W
WNW
" 2.1 1E-08 2.OOE-08 1.75E-08 2.04E-09 1.93E-09 1.69E-09 9.23E-10 8.74E-10 7.64E-10 4.84E-10 4.59E-10 4.01E-10 3.09E-10 2.93E-10 2.56E-10 I
NW' 1.58E-08 1.53E-09 6.94E-10 3.64E-10 2132E-10 NNW - 2.30E-08 2.22E-09 1.01E-09 5.28E-10 3.37E-10 I
DIRECTION DISTANCE (METERS)
'(WIND FROM)
N
- 12067.
1.45E-10
[24135' 4.72E-11 "5 40225 1.74E-11 t 5631i5 9.27E-12
. 80500 4.65E-12 I
- NNE NE ENE 6.36E-11 8.07E-11 I9.77E 1
1.97E-11 2.58E-11 3.17E-11 7.24E-12 9.51E-12 1.17E-11 3.86E-12 5.07E- 12 6.23E-12 1.94E-12 2'!54E-12 3.13E-12 I
E 1 14E- 10 3.73E-11 1.37E-11 7.34E-12 3.68E-12 ESE SE SSE 1.13E-10 1.16E-10 1.47E-10 3.70E-11 3.78E-11 4.79E-11 1.36E- 11 1.39E- 11 1.76E- 11 7.26E-12 7.42E-12 9.41 E- 12 3.64E- 12 3.172E-12 4.72E-12 U
S 2.25E-10 7.34E-11 2.70E-11 1.44E-11 7123E.12 I
SSW 1.41E-10 4.59E-11 1.69E-11 9.01E-12 4.152E- 12 SW 1.36E-10 4.43E- 11 1.63E-11 8.71E-12 4.37E-12 WSW 1.29E-10 4.20E-11 1.55E- 11 8.26E- 12 4.14E-12 W
WNW' NW 1.22E-10 1.07E-10 9.70E- 11 3.98E-11 3.48E-11 3.16E-11 1.47E-11 1.28E-11 1.16E-11 7.82E- 12 6.84E-12 6.20E- 12 3.92E-12 3.43E-12 3.411E-12 I
NNW 1.41E-10 4.58E- 11 1.69E- 11 9.00E-12 4 '52E- 12 DIRECTION TO - SECTOR N A E =E S = W N I
NNE NE ENE
=B
=C
=F
=G
=K
=L
= M WNW NW NNW
= P
= Q
= R I
Worst Case D/Q = 4.46E-08 1/m2 in Sector A 2001 I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 77 of 91 OFF-SITE DOSE CALCULATION MANUAL Annual Evaluation of z/Q and D/Q Values For Page-Attachment 3.17 All Sectors 77
- 1. -Performed or received annual update of x/Q and D/Q values. Provide a description of
-what has been received.
Signature Date
- Environmental Department
._ - . - (print name, title)
- 2. Worst I/Q and D/Q value and sector determined. PMP-6010-OSD-001 has been updated, if necessary. Provide an evaluation.
Signature Date
- Environmental Department (print name, title)
- 3. Review nuclide nmix-for' gaseous -and liqiiid release ,paths to deteftnine if the dose conversion factor of total body is still applicable. Prdvidean evaluation.
Signature Date Environmental Depaitment (print name, title)
- 4. Approved and. verified by:
Signature Date Environmental Department (print name, title)
- 5. Copy to NS&A for information.
/
Signature Date Environmental Department (print name, title)
Reference PMP-6010-OSD-001 Rev. 21 Page 78 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
Dose Factors Pages:
Attachment 3.18 78 -79 I
DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS* I TOTAL BODY DOSE FACTOR Ki (DFBi)
SKIN DOSE FACTOR L (DFS)
GAMMA AIR DOSE FACTOR Mi (DFY)
BETA AIR DOSE FACTOR Ni (DFi)
I (mrad m 3 (mrad m 3 RADIONUCLIDE mrem m3 per ý,Ciý yr) .
(mieem m 3 per ýtCi *'r). per ýtCi yr) per ýtCi yr) I Kr-83m "7.56E-02 - - 1.93E+01 2.88E+02 Kr-85m Kr-85 Li17E+03 1.61E+01 1.46E+03 1.34E+03 1.23E+03 1.72E-01 1:97E+03 1.95E+03 I
Kr-87 Kr-88 5.92E+03.
1.47E +04 9.73E+03 2.37E+ 03 6.17E+03 1.52E+04 11.03E+04 2.93E+03 I
Kr-89 1.66E+04 . .01E+04 1.73E+04 1:06E+04 I
Kr-90 1.5"6E+04 t 7.29E-P03 1.63E+04 7.83E+03 Xe-131m 9.ISE-01 4.'76E 062 1.56E_+02 1.1.1E+03 Xe-133m Xe-133
.2.51E+02 2.94E402 9.94E+'02 3.06E+02 3.27E+02-3.53E+02
- 1.48E+03
.-1105E+03 I
Xe-135m '3.12E+03 . .. 11E+02 .3.36E+03 .739E+02 Xe-135 :.1..81E+03 1.86E 1.92E+03 2.46E+03 I Xe-137 1.42E+03 1.22E + 04- 1.51E+03 1.27E+04 Xe-138 Ar-41
[
[
. .8.83E+03 8.84E+03 4.13E+003 2.69E+03 9.21E+03 9.30E+03 41.75E+03 3.28E+03 I
I II
- The listed dose factors are forradionuclides that may bedetected in gaseous effluents, from Reg. Guide 1.109, Table B-1.
I I
I I
I
Reference PMP-6010-OSD-001 Rev'. 21 Page 79 of 91 OFF-SITE DOSE CALCULATION MANUAL
'Dose Factors Pages: .18 78 - 79 DOSE FACTORS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, IN'GASEOUS EFFLLUENTS FOR CHILD* Ref.'5,2.1ee and ff Pi "Pi INHALATION FOOD & GROUND PATHWAY PATHWAY (mrem m3 (mrem m2 sec per ýiCi yr) per jCi yr)
H-3 . 1.12E+03 1.57E+03'1 -
- P-32 -2.60E+06 7.76E4+/-10 Cr-51 I.'70E+Q4 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+08" 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 1.01E+08 . 1.12E+11 Y-91 2.63E+06 6.72E +06" Zr-95 -2.23E-#06 -> 3.44E+08 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-ll0m 5..48E+06 . . 1.99E+10
- 1-131 --1.62E+07 ... 4.34E+ 11
.- 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 1.01E+06 4.OOE+10 Cs-136 1.71E+05 3.OOE+09 Cs-137 9.07E+05 3.34E+10 Ba-140 1.74E+06 1.46E+08 Ce-141 5.44E+05 3.31E+07 Ce-144 1.20E+07 1.91E+08
- As Sr-90, Ru-106 and 1-131 analyses are performed, THEN 's Pi given in P-32 for nonlisted radionuclides.
3
' The units for both H3 factors are the same, mrem m per pCi yr
Reference PMP-6010-OSD-001 Rev. 21 Page 80 of 91 I
.OFF-SITE DOSE CALCULATION MANUAL I
Radiological Environmental Monitoring Program Pages:
Attachment 3.19 Sample Stations, Sample Types, Sample Frequencies 80 - 83 I
[Ref. 5.2.1v, 5.2.1x, 5.2.1t]
SAMPLE STATION DESCRIPTION/
LOCATION ON-SITE AIRBORNE AND DIRECT RADIATION (TLD) STATIONS SAMPLE TYPE.
SAMPLE FREQUENCY ANALYSIS TYPE ANALYSIS FREQUENCY I ONS-1 (T-l) 1945 ft @ 180 from Plant Axis Airborne Particulate Airborne Radioiodine Weekly Gross Beta
-Gamma Isotopic 1-131 Weekly Quart. Comp.
Weekly I Quarterly.: Direct Radiation Quarterly I
__"___TLD ONS-2 (T-2)'. 2338 ft @48° from Plant Axis, Airborne Particulate Weekly 'Gross 'Beta . ', Weekly
'Gamma Isotopic Quart. Comp.
--Airborne 1131 . Weekly
., * .," " .. , Radioiodine .. . '
ONS-3 (T-3) 2407 ft @ 90° from Plant Axis Airborne TLD.
Airborne Particulate Quarterly
-Weekly, Direct Radiation Gross Beta
,Gamma Isotopic 1131 Quarterly Weekly Quart. Comp.
Weekly I
ONS-4 (T-4) 1852 ft.'@ 1180. from Plant Axis Radioiodine TLD Airborne Particulate:
' . Quarterly Weekly.
Direct Radiation' Gross Beta Gamma Isotopic Quarterly Weekly Quart. Comp.
I Airborne. .' .. . 1-131. "-- Weekly ONS-5 (T-5) 1895 ft @h1890 from Plant Axis Radioiodine TLD Airborne Particulate
-Quarterly Weekly '
Direct Radiation Gross Beta Quarterly Weekly I
.. Gamma Isotopic Quart. Comp..
ONS-6 (T-6) 1917 ft @ 210' from Plant.Axis Airborne.
- .-: Radioiodine
- i TLD Airborne Particulate,.
Quarterly Weekly 1"31 .
'Direct Radiation Gross Beta Weekly Quarterly Weekly I
.Airborne-Radioiodine "'
TLD Quarterly Gamma Isotopic 1-131 Direct Radiation Quart. Comp.
Weekly Quarterly I
T 2103 ft @ 36° from Plant Axis TLD Quarterly, ' Direct Radiationi Quarterly
ýT-8 T-9 T-10 2208.ft @ 82' from Plant Axis, 1368 ft @.1490 from Plant Axis' 1390-ft @-1276 from Plant Axis TLD.. ...
TLD TLD
, Quarterly....
Quarterly'
Quarterly Direct Radiation Direct, Radiation'
'Direct Radiation Quarterly Quarterly Quarterly I
T-11 1969 ft'@ 110 from Plant Axis TLD ' Quaiierly " 'Direct Radiation Quarterly T-12 2292 ft @ 630 'from Plant Axis TLD Quarterly DirectRadiation Quarterly I
CONTROL AIRBORNE AND DIRECT RADIATION (TLD) STATIONS NBF 15.6 miles SSW New Buffalo, MI Airborne Particulate TLD Airborne Radioiodine Weekly Quarterly Gross Beta Gamma Isotopic 1-131 Direct Radiation Weekly Quart. Comp.
Weekly Quarterly I
SBN 26.2 miles SE Airborne Particulate Weekly Gross Beta Weekly Soth Bend, IN Airborne Radioiodine TLD Quarterly Gamma Isotopic 1-131 Direct Radiation '
Quart. Comp.
Weekly Quarterly I
DOW 24.3 miles ENE Airborne Particulate Weekly Gross Beta Weekly Dowagiac, MI Airborne Radioiodine TLD Quarterly Gamma Isotopic 1-131 Direct Radiation Quart. Comp.
Weekly Quarterly I
COL 18.9 miles NNE Airborne Particulate Weekly Gross Beta Weekly Coloma, MI - Gamma Isotopic'- Quart. Comp.
Airborne Radioiodine 1-131 Weekly
" ' . TLD Quarterly Direct Radiation Quarterly I
Reference PMP-6010-OSD-001 Rev. 21 Page 81 of 91 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental ,Monitoring Program Pages:.
Sample Stations, Sample Types, Sample Frequiencies 80- 83 SAMPLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION .. TYPE FREQUENCY TYPE FREQUENCY OFF-SITE DIRECT RADIATION (TLD) STATIONS OFTAI 4.5 miles NE, Pole #B294-44 TLD Quarterly Direct Radiation Quarterly OFT-2 3.6 miles, NE, Stevensville TLD Quarterly Direct Radiation' Quarterly Substation OFT-3 5.1 miles NE, Pole #B296-13 - - TLD. Quarterly Direct Radiation Quarterly OFT-4 4.2'miles, E, Pole #B350-72 TLD Quarterly Direct Radiation Quarterly OFT-5 4.2 miles ESE Pole #B387-32 TLD" Quarterly Dire'ct Radiation Quarterly OFT1-6 4.9 miles SE, Pole #B426-1 TLD Quarterly Direct Radiation Quarterly OFT-7 2.5 miles S, Bridgman Substation TLD Quarterly Direct Radiation Quarterly OFT-8 4ý0 miles S, Pole #B424-20. TLD - Quarterly Direct Radiation Quarterly OFT-9 4.4 miles ESE, Pole #B369-214 TLD Quarterly . Direct Radiation. Quarterly OFT-10'- 3.8 miles S, Pole #B422-99 TLD Quarterly - Direct' Radiation Quarterly OFT-l 3.8 miles S, Pole #B423-12 TLD Quarterly Direct Radiation Quarterly GROUNDWATER (WELL WATER) SAMPLE STATIONS __.__.
W-1 1969 ft @g11V from Plant Axis ; Groundwater *" Quarterly.s Gamma Isotopic Quarterly' S.Tritium Quarterly W-2 2302 ft @ 630 from Plant Axis Groundwater : Quarterly Gamma Isotopic Quarterly
. ... . . . .. _ Tritium Quarterly W-3 3279 ft @ 1070 from Plant Axis . -GroundwAter , - . Quarterly Gamma Isotopic I Quarterly
"______ _____Tritium Quarterly W-4 418 ft @ 3010 from Plant Axis Groundwater --':'- Quarterly Gamma Isotopic Quarterly
- __,__ ___Tritium Quarterly W-5 , - 404 ft @ 2900 from Plant Axis '"-"Groundwater Quarterly Gamma Isotopic Quarterly
"Tritium Quarterly W-6, - 4424 ft @ 273. from Plant Axis Groundwater . Quarterly Gamma Isotopic Quarterly
._.. .... _,7 Tritium Quarterly W-7 1895 ft @ 1890 from Plant Axis Groundwater .,,. Quarterly Gamma Isotopic Quarterly
,.____... . ._.--.. __ :Tritium Quarterly W-8 ,1274 ft @'540 froin Plant. Axis . ... Groundwater - Quarterly -Gamma Isotopic Quarterly' Tritium " " Quarterly' W-9 7447 f7-220 .from_ PliiiAxi - ......... Groundwater .. Quarterly, 'Gamma Isotopic Quarterly
,____-___._.___._"" ,__.. Tritium : .. Quarterly W-10 4216 ft @ 1290 fromPlant Ax,*s .. '. Groundwater Quarterly. Gamma Isotopic. Quarterly
._. 7.. .. ........ Tritium - . Quarterly W-1 1 3206 ft @ 1530 from Plant Axis ' Groundwater"- Quarterly Gamma Isotopic. Quarterly S._ ... . ...... ... Tritium Quarterly W-12 2631 ft @ 1620 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly
...... ____Tritium Quarterly "
W-13 2152 ft @-1820 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly
- __ _ _Tritium Quarterly W-14 1780 ft.@ 1640 from Plant Axis* Groundwater Quarterly Gamma Isotopic Quarterly
,_Tritium " Quarterly W-15 725 ft @ 2020 from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly
_ NPDES well MW-12C .,,. Tritium Quarterly DRINKING WATER. -
STJ' St. Joseph Public Intake Sta. Drinking water Once per calendar Gross Beta 14 day Comp.
9 mi. NE - Day Gamma Isotopic 14 day Comp.
1-131 14 dayComp.
"_._ __._ Tritium Quart. Comp.
LTW Lake Twp. Public Intake Sta. Drinking water Once per calendar Gross Beta 14 day Comp.
"' 0.6 mi. S : . Day Gamma Isotopic 14 day Comp.
1-131 -- 14 day Comp.
I Tritium Quart. Comp
Reference PMP-6010-OSD-001 Rev. 21 Page 82 of 91 I OFF-SITE DOSE CALCULATION MANUAL I
Radiological Environmental Monitoring Program Pages:
Attachment 3.19 Sample Stations, Sample Types, Sample Frequencies 80 - 83 I
I I
Ii I
INGESTION- MILK Indicator Farms' I Milk Milk
Milk Once every 15 days
'15 Once every days Once every 1-131, Gamma Isotopic 1-131 Isotopic:
'Gamma 1-131 '
4 per sample per sample per sample pesmle per sample I
15 days Gamma Isotopic per sarriple _
F INGESTION - MILK*' .
Background Farms*. .. . -. , .. ;t-M lk ,.
... = * - * ,., ,.- ,.
IOnce,every On 15 days. ,
-1 1 per sample
" jper Gamma Isotopic ýp rs m l I
[ __15
. Milk . Once every days
ý1-131 .
Gamma Isotopic
- per sample I' per sample I
SAMPLE DESCRIPTION/.._ SAMPLE~ SAMPLE ANALYSIS ANALYSIS STATION INGESTION ONS-N
- FISH LOCATION 0.3 mile N, Lake Michigan Fish -
TYPE edible portion .
FREQUENCY 2/year.,;
Gamma TYPE Isotopic -
FREQUENCY per sample I
ONS-S 0.4 mile S, Lake Michigan Fish - edible portion" 2/year Gamma Isotopic. per sample OFS-N OFS-S 3.5 mile N, Lake Michigan 5.0 mile S, Lake Michigan Fish -
Fish -
edible edible portion portion 2/year 2/year Gamma Gamma Isotopic Isotopic
- per per sample sample I I
I I
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 83 of 91 OFF-SITE DOSE CALCULATION MANUAL A Radiological Environmental Monitoring Program Pages:
Sample Stations, Sample Types, Sample Frequencies 80 - 83 INGESTION: - FOOD PRODUCTS On Site
-ONS-G Nearest sample to Plant in the Grapes . At time of Gamma Isotopic At time of highest D/Q land sector harvest harvest containing media.
ONS-V , ,Broadleaf . At time of Gamma Isotopic. At time of vegetation harvest harvest Off Site -
OFS-G In a land sector containing Grapes At time of Gamma Isotopic At time of grapes, approximately 20 miles .... - harvest Harvest from the plant, in one of the less prevalent D/Q land sectors -" "
OFS-V Broadleaf At time of Gamma Isotopic At time of vegetation harvest harvest INGESTION - BROADLEAF IN LIEU OF MILK 3 indicator samples of broad leaf vegetation Broadleaf - Monthly - Gamma Isotopic Monthly collected at different locations, within eight . vegetation when available 1131
- when available miles of the plant in the highest annual average. D/Q land sector. : .
I background sample of similar vegetation ... Broadleaf Monthly Gamma Isonopic Monthly growt 15:25 miles distant in'-nc of vegetation . when available 1131 when available theless prevalent Wind directions. "
Collect 'Composite samples of Drinking and Surface water at least daily. :.Analyze particulate sample filters for gross beta activity 24 or more hours following filter rem6val.: This will allow-for radon and'thoron daughter decay. If gross beta activity in air or water is greater thar. 10 times theyearly mean of control samples for any mediumperform gamma isotopic analysis on the individual s~imples.
If at least three indicator milk samples and one background milk sample cannot. be obtained, three indicator broad leaf samples will be collected at different locations, within eight miles of the plant, in the land sect6r with the highestDI5/Q (rfefers to the highest annual average D/Q). Algo, one background broad leaf sample will, beý ollected 15 to2"5 miles from the plant in one ofthe*less prevalent D/Q land sectors.
The three-milk indicator and two backgroundffarns will 6e deteimined by the Aniual IUnd Use Cetisus and those:that are willing to-participate.. IF it is determined that the milk animals are fed stored feed, THENrmnoithl, sampling is appropriate-for that time period:
Reference PMP-6010-OSD-001 T Rev. 21 Page 84 of 91 I
OFF-SITE DOSE CALCULATION MANUAL Attachment 3.20 Maximum Values for Lower Limits of DetectionsA'B - REMP Pages:
- 85 I
Atta..2e f84
[Ref. 5,2. 1v]
I Radionuclides Food Product Water Milk Air Filter Fish Sediment Gross Beta pCi/kg, wet pCi/1 4*
pCi/il, pCi/m3 0.01 pCi/kg, wet pCi/kg, dry U H-3 Ba-140 2000 60 .60 I
La-140 Cs-134 60 15 15 15, 15 0.06 130 150 I C's-137 60 18 18' '0.06 150 180 Zr-95.
Nb-95
. 30 15 I
Mn 15 130 Fe-59 30 260 Zn-65 30 ., __ ., 260.
Co-58 15 130 Co-___60 130 1-131 601I 60,ji 1 0.07 This Data is directly from our plant-specific Technical Specification.
- LLD for drinking water I
I I
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 85 of 91 OFF-SITE DOSE' CALCULATION MANUAL Attachment 3.20 Maximum Values for Lower Limits of DetectionsAB -EMP *Pages:
84 -85 NOTES A. TheLower Limit of Detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will be detected with 95% probability and 5% probability of falsely concluding that a blank observation represents a "real" signal:
For a particular measurement system (which may include radiochemical separation), the LLD is given by the equation:
-4}66..* S
= 4 S LLD E*V*l 2.22*Y*e(-AI)
Where'LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume). Perform analysis in such a manner that the stated LLDs 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 LLD represents.the capability of a measurement system and not as an after the fact limit for a particular measurement.
.S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as.'counts per minute).
E. is the counting efficiency of the detection equipment as counts per transformation (that is, disintegration)
V is the sample size in appropriate mass or volume units 2.22 is the conversion factor from picocuries (pCi) to transformations (disintegrations) per minute Y is the fractional radiochemical yield as appropriate k 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 measurable and identifiable, together with the radionuclides listed in Attachment 3.20, Maximum Values for Lower Limits of DetectionsA,B- REMP.
a A 2.71 value may be added to the equation to provide correction for deviations in the Poisson distribution at low count rates, that is, 2.71 + 4.66 x S.
Reference PMP-6010-OSD-001 Rev. 21 Page 86 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.21 Reporting Levels for Radioactivity Concentrations Page:
"'in Environmental Samples 86 I
Radionuclides Food Product Water Milk Air Filter Fish pCi/kg, wet pCiVY pCi/l ,pCi/mn3 pCi/kg, 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 Nb-95. 400 Mn-54 1000 ' 30000 Fe.-59 400 . __ 10000 Zn-65 .. ,__.____ 300 - 120000 Co-58 ____ _ *. 1000, 30000 Co-60 . 300 _______. . _ _10000 1-131 ,,100 "2 3 0.90 IF any of the above concentration levels are exceeded THEN see guidance contained in step 13.5.2a. for additional information. '
I.. I" Reference PMP-6010-OSD-001 Rev. 21 Page 87 of 91 OFF-SITE DOSE CALCULATION MANUAL
' ': * ,. Page: .22 On-Site MonitoringLocation - REMP Pa87 ONS-South ONS-North Surface Water TLD T-6 TLD T-5 SWL-3 Air ONS-6 Air' bNS-5 SWL-2 Surface Water Well W-6 W-5WellWell S ediment SL-3 Well S Ld2TLD* ,-5 ,w-4 W-9 Well W-1 m n
W el I ,I .
- T-8 .
WelWellD a-llT-12 TLD T-3 T Air ONS-3,'
Well D ,I T-C SGt LEGEND ONS ONS-6: Air Sampling Station T-1 -T-12: TLD Sampling Station W-1 -W-15: REMP Groundwater Wells SWL- 2, 3: Surface Water Sampling Stations SL-2 SL-3: Sediment Sampling Stations ONS-N & S: Fish sampling locations SG-1, 2 4 and 5: Non REMP information Wells
Reference PMP-6010-OSD-001 Rev. 21 Page 88 of 91 I OFF-SITE DOSE CALCULATION MANUAL I .23 Off-Site Monitoring. .. . Locations * - REMP ;88 P '
I Legend Offsite REMP Monitoring Locations Coloma Substation Background Air/TLD (COL)
I Watervliet I
Coloma Rd OFT OFT-11 : TLD Location's 31/1-196 Background Air/TLD Stations M-63 Drinking Water Locations Indicator Milk Farm Locations Twelve. 1-94 Background Milk Farm Locations Benton 20 Mile Radius OFS Offsite Fish locations St Joseph Harbor M
Corners B.R 4 Millburg I St.Joseph Water -139.
Treatment Plant OFS-North (STJ).
M-63 Dowagiac Substation
Background
I Air/TLD
, Sodus TLD TLD TLD TLD TLD OFT-3 OFT-1 OFT-2' OFT-4 OFT-9 Stevensvi~ w Eau M-51 (DOW)
Colby St I
TLD OFT-5 Linco Rd, Claire I
M-62 D . 0. Cook Berrien -
Lake Townf-Nulear Planto,' .
Center Water Treatment Baroda Berrien Shawnee Rd Springs M-140 I
Plant (LTW) Brdgman TLD OFT-7 Snow Rd J.Monroe TLD-OFT-10 Indicator MilkFarms G.G. Sctuler TLD OFT-1l1 TLD OFT-8 /
/
TLD OFT-6
_F^-Souh /"New HOaber-touth
,, . Harbert. IT94" Troy - Cleveland Rd' I
New Buffalo Substation
Background
Union Pier Three Buchanan Niles I
AirrTLD Oaks US 12 Galien (NBF)
Old 31 I
80/90 31 Bypass I
Hwy 20 Laporte Background Hwy 20 Rolling "
Prairie Hwy 2 South Bend I
Milk Farm Ray Livinghouse Hwy 35
-Hwy 2 Kankakee Station
Background
I Hwy 23 Air/rLD (SBN)
I I
I
Reference PMP-6010-OSD-001 Rev. 21 Page 89 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.24 Safety Evaluation By. The: Office Of Nuclear , Pages:
Reactor Regulation 89-91 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO DISPOSAL OF SLIGHTLY CONTAMINATED SLUDGE INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NOS. .1AND 2, DOCKET NOS. 50-315 AND 50-316 [Ref. 5.2.lr]
(This is a 10 CFR 50.75 (g) item)'
- 1. INTRODUCTION By letters dated October 9, 1991, October 23, 1991, September 3, 1993, and September 29, 1993, Indiana Michigan Power Company (I&M) requested approval pursuant to 10 CFR 20.2002 for the on-site disposal of licensed material not previ6usly considered in the Donald C. Cook Nuclear Plant Final Environmental 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 sump absorption pond and pumped to the upper parking lot located within the exclusion area of the Donald C. Cook Nuclear Plant. The contaminated sludge was spread over an area of approximately 4.7 acres. The sludge contained a total radionuclide inventory of 8.89 millicuries (mCi) of Cesium-137, Cesium-136, Cesium-134, Cobalt-60 and Iodine-131.
In its submittal, the licensee addressed specific informationi requested in accordance with 10 CFR 20.2002(a), provided a detailh'd description of the licensed material, thoroughly analyzed and evaluated information pertinent to the impacts on the environment of the proposed disposal of licensed material, and committed to follow specific procedures to minimize the tisk of unexpected exposures. ". .
- 2. DESCRIPTION OF. WASTE The turbine room sump absorption pond is 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 sump, a recognized release pathway. Sludge, consisting mainly of leaves and, roots mixed 'ith 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 pumped to a containment area located within the exclusion area. The total volume of 942 cubic rheters of the radioactive sludge that was dredged from the bottom of the turbine room absorption pond was subsequently spread and made into a graveled road over the upper parking lot area of approximately 4.7 acres.
The principal radionuclides identified in the dredged material are listed below.
[_ TABLE 1 NUCLIDE ACTIVITY (mCi) ACTIVITY (mCi)
(half-life) 1982 1991
'36Cs (13.2 d) 0.03 NA*
134Cs (2.1 y) 2.34 0.18 37
" Cs (30.2 y) 5.59 :4.57 6°Co (5.6 y) 0.90 0.27
'31I(8.04 d) 0.03 NA*
TOTAL: 8.89 5.02
- NA: not applicable due to-decay.
'Reference PMP-6010-OSD-001 OFF-SITE DOSE CALCULATION MANUALI Rev. 21 Page 90 of 91 I
Attachment 3.24 Safety Evaluation By The Office Of Nuclear f Pages:
I Reactor Regulation " 89-91 I
- 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 (1) external exposure caused by groundshine from the disposal site; (2) internal exposure caused by inhalation of re suspended radionuclide;
-AND-I (3) internal exposure from ingesting ground water. " -
The staff has reviewed the licensee's calculational methods and assumptions and find that they are consistent with NUREG-1101, "Onsite Disposal of Radioactive Waste," -Volumes 1 and 2, Noveml ber 1986 and February 1987, respectively. The staff finds the assessment methodology acceptable. Table 2 lists the dos -s calculated by the licensee for the maximally exposed member of I the public based on a total activity of 8.89 mCi disposed I
TABLE 2 ii n that.year.
I Pathway Whole Body Dose Received by Maximally Exposed IndividuMI I
___ _ (nirem/year)
Groundshine ___ _.... 0.94_......
Inhalation Groundwater Ingestion I. ' . .0.941 0..0Q73.
. I Total 2..i On July 5, 1991, the licensee re-sampled the onsite disposal area to assure that no significarit.impfcts and adverse effects had occurred.- A counting procedure based on the appropriate environmental, low-level doses was used by .the licensee; howvever, no activity was detected -during the re-sarripling1 - This'is consistent with, the original activiiy of the material and the decay I 4.
ti-rme. The 1991 re-sampling process usedby, the licensee confirms that the environmental impact of the 1982 disposal was v ery sinall. The staff finds the licensee's methodology acceptable.
ENVIRONMENTAL FINDING AND CONCLUSION I
The staff has evaluated the environnental impact of the proposal to leave in place approximately 942 cubic meters of slightly contaninated sludge underneath the.upper parking lot on the Donald C. Cook.Nuclear Plant site..
In 1982, the licensee evaluated the potential exposure to members of the gneiral public from the tadionuclides in the sludge I
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 mrem/yr. The staff has reviewed the licensee's calculationral methods and assumptions and found that they are consistent with NUREG-1i101, Onsite Disposal of Radioactive Waste, V6lumes 1 and 2, November 1986 and February 1987, respectively. The staff finds the assessment methodology acceptable.! For comparison" the radiation I
from the naturally occurring radionuclides in soils and rocks plus cosmic radiation gives a person in Michigan a whole-body dose rate of about 89 mrem 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 ver small.
I 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 inliplace represents the least impact to the environment.
I I
I
,i
Reference PMP-6010-OSD-001 Rev. 21 Page 91 of 91 OFF-SITE DOSE CALCULATION MANUAL Attachment 324 Safety Evaluation By The Office Of Nuclear Pages:
Reactoi Regulation .89 - 91
- 5. CONCLUSION Based on the staff's review of the licensee's discussion, the staff finds the licensee's proposal to retain the material in its present location as documented in this Safety Evaluation acceptable. Also, this Safety Evaluation shall be permanently incorporated as an appendix to the licensee's Offsite Dose Calculation'Manuai (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, September 29, 1993 Therefore, the licensee's proposal to consider the slightly contaminated sludge disposed by retention in place in the manner described in the Donald C. Cook Nuclear Plant submittals date October 9,1991, October 23, 1991, September 3, 1993, and September 29, .1993, is acceptable. . . - .
The guidelines used by the NRC staff for onsite disposal of licensed material and the staff s evaluation of how each guideline has been satisfied are-given in Table-3.
Pursuant to 10 CFR 51.32, the Commission has determined that granting 6f this approval will have no significant impact on the environment (October 31, 1994, 59 FR 54477)._
Principal Contributor: J. Minns Date: November 10, 1994 I- .
TABLE 3 20.2002 GUIDELINE FOR ONSITE - . STAFF'S EVALUATIONý,
DISPOSALV.
- 1. The radioactive material-should be disposed of in such l. Due to the nature of the disposed material, recycling to the a 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 ofa: , :-. 2 . This guideline was addressed.-in Table,2. Although the maximally exposed individuals (a-member of the . - 2.61 mrem/yr-is .greater, than staff s guidelines, the staff.
general public or a non-occupationally exposed worker) ,. findsit acceptable due to 9 yrs decay, following analysis and from the probable pathways of exposure to the disposed the expected lack of activity detected in the 1991 survey.
material should be less than 1 mrem/year. . '. * . *
- 3. Doses to the totalbody 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 exposure should be less than 5 mremlyear. the intruder scenario.
- 4. Doses to theiotal body, and any body organ of an 4.-" : Exen if recycling were to -occuiti*fter release from regulatory individual from assumed recycling of the disposed' - - - "control, thL dose to a maximally exposed member of the material at the time the disposal site is released from pubbic is n6t expected to exceed 1 mremryear, based on -
regulatory control from all likely pathways of exposure .' _exposure sLkharios' considered in this analysis.
should be less than 1 mrem.
E. F. Branagan, Jr. and F. J. Congel;: "Disposal of Contaminated Radioactive Wastes from Nuclear Power- Plants,"
presented at the Health Physics Society's Mid-Year Symposium on Health Physics ' Corisideration in Decontamination/Decommissioning, Knoxville, Tennessee, February 1986, (CONF-860203).