ML20141A414
| ML20141A414 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/08/1996 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20141A396 | List: |
| References | |
| H4, NUDOCS 9705140286 | |
| Download: ML20141A414 (223) | |
Text
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3 Q;Cqggg-i - OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 w ' Page 2 of 223 TABLE OF CONTENTS Section Title Page OFFSITE DOSE CALCULATIONS MANUAL INTRODUCTION . . . . . . . . . . . . 9 1.0 RADIOLOGICAL EFFLUENT SPECIFICATIONS AND SURVEILLANCE R E Q U I R E M E NT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1.1 S pe cificatio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 1.2 Surveillance Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 2.0 LIQUI D E FFLU ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 , C o n ce ntrato n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Dose........................................................ 18 Liquid Radwaste Treatment Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . . 20 Lil luid Sto rage Tanks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 g 3.0 G AS EOU S E FFLU ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 W D o s e R at e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 Do se - N oble G ase s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Dose - lodine-131, lodine-133, Tritium and particulates . . . . . . . . . . . 25 l Gaseous Radwaste Treatment Systems . . . . . . . . . . . . . . . . . . . . . . . . . . 26 l Explosive Gas Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . 28 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . 29 Atmospheric Steam Dump Monitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 , I 4.0 LIQUID EFFLUENT CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 i 4.1 Monitor Alarm Setpoint Determination . . . . . . . . . . . . . . . . . . . . . 31 1 4.2 Compliance With 10C FR20 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 l 4.3 Liquid Effluent Dose - Compliance with 10CFR50 . . . . . . . . . . . 41 4.4 R e f e re n ce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 5.0 GASEOUS EFFLUENT CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . . . 47 l 5.1 Monitor Alarm Setpoint Determination . . . . . . . . . . . . . . . . . . . . . . 47 l 5.2 Gaseous Effluent Dose Rate - Compliance with 10CFR20 . . . . 51 ! 5.3 Gaseous Effluents - Compliance with 10CFR50 . . . . . . . . . . . . . 54 5.4 R e fe re n ce s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 59
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MANUAL (ODCM) REV: 14 Section , ' , j Page 3 of 223 TABLE OF CONTENTS [ CONTINUED] 2 Section Title Page 6.0 TOTAL DOSE FROM RADIOACTIVE RELEASES AND l U RANIUM FU EL SOU RC ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 i i i 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . 63 l 1 8.0 REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 l 1 1 , 8.1 Annual Radioactive Effluent Report . . . . . . . . . . . . . . . . . . . . . . . . 67 1 1 8.2 Annual Radiological Environmental Monitoring Report . . . . . . . 69
- i. 8.3 Annual Summary of Meteorological Data . . . . . . . . . . . . . . . . . . . 70 8.4 R eco rd R ete ntio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 70 BASES............................................................ 71 1
2.0 Liquid Efflue nts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 n 3.0 Gaseou s Efflue nts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 l V 6.0 Total D o se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 76 7.0 Radiological Environmental Monitoring . . . . . . . . . . . . . . . . . . . . . 76 j i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES M % gggn n. , y, TITLE: NUMBER: 94 4* p a< OFFSITE DOSE CALCULATION ? MANUAL (ODCM) REY: 14 Page 4 of 223 TABLE OF CONTENTS [ CONTINUED] Section Title Page LIST OF TABLES TABLE 1.1 - OPERATIONAL MODES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79 TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P ROG R AM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81 TABLE 2.2 - RADIOACTIVE LIQUID EFFLUENT MONITORING I N STR U M E NTATIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 85 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 87 i TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS P ROG R AM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89 TABLE 3.2 - RADIOACTIVE GASEOUS EFFLUENT MONITORING IN STR U M ENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 95 , TABLE 3.3 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 97 TABLE 4.1 - LIQUID SOURCE TERMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 TABLE 4.2 - ADULT INGESTION DOSE VALUES (Ait) FOR THE l PRAIRIE ISLAND NUCLEA.3 GENERATING PLANT l (M R EM/H R P E R MC h,i ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . 101 l TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) . . . . . . . . . . . . . 103 l l TABLE 5.1 - MONITOR ALARM SETPOINT DETERMINATION FOR l PINGP............................................. 117 I TABLE 5.2 - GASEOUS SOURCE TERMS . . . . . . . . . . . . . . . . . . . . . . . . . 119 TABLE 5.3 - CRITICAL ORGAN DOSE VALUES (P)i FOR CHILD . . . . . 121 TABLE 5.4 - DOSE FACTORS FOR NOBLE GASES * . . . . . . . . . . . . . . . 123 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GROUND, ALL AGES . . . . . . . . . 125 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE, ADULT . . . . . . . . . 126
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1 Section Title Page ; i LIST OF TABLES [ CONTINUED] TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE, TEEN . . . . . . . . . . 127 -! TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR l GENERATING PLANT * - VEGETABLE, CHILD . . . . . . . . . . 128 i TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR 1 GENERATING PLANT * - MEAT, ADULT . . . . . . . . . . . . . . . . 129 i l TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT, TEEN . . . . . . . . . . . . . . . . . 130 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT, CHILD . . . . . . . . . . . . . . . . 131 O T^e's s.s R v^ LUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, ADULT . . . . . . . . . . . 132 i l l TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR ! GENERATING PLANT * - COW MILK, TEEN . . . . . . . . . . . . 133 TABLE 5.5-10 -R VALUES FOR THE PRAIRIE ISLAND NUCLEAR l GENERATING PLANT * - COW MILK, CHILD . . . . . . . . . . . 134 ! TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, INFANT . . . . . . . . . . 135 1 TABLE 5.5-12 -R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, ADULT . . . . . . . . . . 136 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, TEEN . . . . . . . . . . . 137 TABLE 5.5-14-R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, CHILD . . . . . . . . . . . 138 TABLE 5.5-15 -R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, INFANT . . . . . . . . . . 139 TABLE 5.5-16 -R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, ADULT . . . . . . . . . 140 O T^e's s.s-47-a v^ LUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, TEEN . . . . . . . . . . 141
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OFFSITE DOSE CALCULATION REV: 14 h l' s M h#[' e MANUAL (ODCM) Page 6 of 223 TABLE OF CONTENTS [ CONTINUED] i Section Title Page LIST OF TABLES [ CONT!NUED] TABLE 5.5-18 -R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, CHILD . . . . . . . . . . 142 1 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, INFANT . . . . . . . . 143 ) TABLE 7.2 - REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATION IN ENVih0NMENTAL SAMPLES . . . . 149 TABLE 7.3 - DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(A) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 151 0 , I O
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' ' Page 7 of 223 TABLE OF CONTENTS [ CONTINUED]
Section Title Page LIST OF FIGURES FIGURE 3.1 - PRAIRIE ISLAND NUCLEAR GENERATING PLANT SlTE BOUNDARY FOR LIQUID EFFLUENTS . . . . . . . . . . . . . . . . 153 FIGURE 3.2 - PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE BOUNDARY FOR GASEOUS EFFLUENTS . . . . . . . . . . . . . 155 APPENDICES APPENDIX A - METEOROLOGICAL ANAYSIS . . . . . . . . . . . . . . . . . . . . . . . . 157 TABLE A PRAIRIE ISLAND RELEASE CONDITIONS . . . . . . . . . . . . . 161 (3 TABLE A t ,/ AREA BOUNDARY L)OCATIONS . . . . . . . . . 163 ............ TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 165 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 167 TABLE A PRAlRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 175 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 183 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 185 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS . . . . . . . . . 193 APPENDIX B- PRAIRIE ISLAND 12.2M WIND AND DT 42.7-12.2M STABILITY JOINT FREQUENCY DISTRIBUTIONS (4/1/77 - 3/31/78) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 201 APPENDIX C- DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES AN D TR ITI U M . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 209 TABLE C PARAMETERS FOR COW AND GOAT MILK PATHWAYS 219 TABLE C PARAMETERS FOR THE MEAT PATHWAY . . . . . . . . . . . . . 221 TABLE C PARAMETERS FOR THE VEGETABLE PATHWAY . . . . . . 223 0
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Pace 8 of 223 RECORD OF REVISIONS Revision No. Daig Reason for Revision Original June 7,1979 1 April 15,1980 incorporation of NRC Staff comments and corrections of miscellaneous errors. 2 August 6,1982 incorporation of NRC Staff comments. 3 February 21,1983 Change in milk sampling location. 4 November 14,1983 Change in milk sampling location and change in cooling tower blowdown. 5 March 27,1984 Change Table 3.2-1 6 February 14,1986 Change in location to collect cultivated crops (leafy green veg.) and removal of meat animals from land use census. 7 July 31,1986 Retype and format ODCM. No change in content. 8 January 8,1987 Addition of discharge Canal monitor setpoint calculation. 9 June 29,1987 Change inhalation dose factor to child and address change in land use survey. 10 April 27,1989 Change in method for calculating liquid effluent monitor setpoints. Fix of various typing errors. Change in location of two REMP sampling locations. Deletion of one REMP sampling location. 11 October 5,1989 Change in Tables 3.3-6 thru 3.3-16. Appendix C equations corrected. Section 5 figures replaced. Sample point definitions corrected. 12 June 17,1991 Change in REMP sampling locations Tables 5.1-1. Added text to address the increased volume of the new discharge pipe. 13 Septcinber 27,1995 Incorporation of RETS as defined in PINGP Technical Specifications in accordance with GL 89-01 as directed by NUREG-1301. Change grab sampling frequency from 8 hours to 12 hours when required on line monitoring equipment is out of service. Define liquid and gaseous monitor calibration. Define radiological effluent and environmental reporting and records retention. g l 14 May 15,1996 Correct typing errors and Tech. Spec. references. Update dose factor tables.
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, {Section& f Page 9 of 223 OFFSITE DOSE CALCULATIONS MANUAL INTRODUCTION i The Offsite Dose Calculation Manual (ODCM) describes the methodologies and parameters l used in: 1) the calculation of offsite doses resulting from radioactive gaseous and liquid i effluents; 2) the calculation of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. The methodology stated in this manual is acceptable for use in demonstrating compliance with 10CFR 20.1301(a)(1),10CFR 50.36A,10CFR 50, Appendix A (GDC 60 & 64) and Appendix I, and 40 CFR 190.
The ODCM is based on " Radiological Effluent Technical Specification of PWR's (NUREG-0472, October 1978)"," Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133, October 1978)", and *Offsite Dose ; Calculation Manual Guidance (NUREG-1301, April 1991). Specific plant procedures for i implementation of this manual are provided in the Count Room Manual, (Radiation Protection Implementing Procedures 4000 Series). Also included in this manual is information related to the RADIOLOGICAL j p ENVIRONMENTAL MONITORING PROGRAM (REMP). Tables 7.1,7.2 and 7.3 designate , specific sample types, reporting levels and lower limits of detection currently used to satisfy the sampling requirements for the REMP. Licensee initiated changes to the ODCM:
- 1. SHALL be documented and records of reviews performed shall contain: -
- a. Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s).
- b. A determination that the change (s) maintain the level of radioactive effluent control required by 10CFR20.1301(a)(1),10CFR50.36A,40CFR190,10CFR50, Appendix 1, and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
- 2. SHALL become effective upon review and acceptance by the Operations Committee.
- 3. SHALL be submitted to the NRC in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which the change in the ODCM was made. Each change SHALL be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed. The date (i.e., month and year) of the change SHALL be O- clearly indicated on the " Record of Revision" page.
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$b Page 11 of 223 DEFINITIONS l
. AB.NORMALBELEASE An unplanned or uncontrolled release of radioactive material from the plant. A release which results from procedural or equipment inadequacies, or personnel errors, that could i indicate a deficiency. ,
. ACTION ;
ACTION SHALL be that part of a specification which prescribes remedial measures required under designated conditions.
. BATCH RELEASE A BATCH RELEASE is a discharge of liquid or gaseous radioactive effluents of a discrete volume. Prior to release, each batch SHALL be isolated and thoroughly mixed for
( sampling and analysis.
. CHANNEL CALIBRATION A CHANNEL CAllBRATION SHALL be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.
The CHANNEL CAllBRATION SHALL encompass the entire channelincluding the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
. CHANNEL CHECK '
i CHANNEL CHECK is a quantitative determination of acceptable operability by observation of channel behavior during operation. This determination SHALL include comparison of the channel with other independent channels measuring the same variable. I e CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST consists of injecting a simulated signal into the channel as close to the primary sensor as practicable to verify that it is OPERABLE, including alarm and/or trip initiating action. O
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a >a Page 12 of 223 e CHANNEL RESPoriSE TEST A CHANNEL RESPONSE TEST consists of injecting a simulated signalinto the channel as near the sensor as practicable to measure the time for electronics and relay actions, and trip functions.
. CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of liquid or gaseous radioactive effluents of a nondiscrete volume of a system that usually has makeup flow during the release.
CONTINUOUS RELEASES are normally sampled and analyzed either during or following the release.
- DOSE EQUIVALENT l-131 DOSE EQUIVALENT l-131 is that concentration of I-131 ( Cl/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, 1-133,1-134 and 1-135 actually present. The dose conversion factors used for this calculation SHALL be the child thyroid factors listed in Table E-7 of NRC Regulatory g
Guide 1.109, Revision 1, October 1977.
. EXCLUSION AREA BOUNDARY The EXCLUSION AREA is the area encompassed by the EXCLUSION AREA BOUNDARY at a minimum distance of 715 meters from the center of either reactor.
GASEOUS RADWASTE TREATMENT SYSTEM The GASEOUS RADWASTE TREATMENT SYSTEM SHALL be any system designated and installed to reduce radioactive effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM SHALL be any system designated and installed to reduce radioactive effluents by holdup or collecting radioactive materials by means of filtering, evaporation. lon exchange or chemical reaction for the purpose of reducing the total radioactivity prior to release to the environment. O
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- LONG TERM RELEASE LONG TERM RELEASES are usually airborne CONTINUOUS RELEASES. The term "Long Term" comes from the reference to utilizing the long term dispersion factor (X/Q) from Table 5.1.
l e MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.
. OPERABLE - OPERABILITY
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As defined in the Technical Specifications. ; e PURGE - PURGING G PURGE - PURGING SHALL be any controlled process of discharging air or gas from a V 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.
- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM mEMP) l The RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM is established for monitoring the radiation and radionuclides in the environs of the plant. The program :
SHALL provide representative measurements of radioactivity in the highest potential exposure pathways and verification of the accuracy of potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of the environmental exposure pathways. The current methodology used in the conduct of the specifications of the REMP described in the ODCM are defined in the RPIP 4700 series of Radiation Protection implementing Procedures. i e SHORT TERM RELEASE 1 SHORT TERM RELEASES usually refers to airborne BATCH RtELEASES. The term "Short Term" comes from the reference to utilizing the short term dispersion factor (X/Q) from Table 5.1. O l
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, Pace 14 of 223 e SITE BOUNDARY The SITE BOUNDARIES for liquid and gaseous releases are defined in Figures 3.1 and 3.2.
- SOURCE CHECK A SOURCE CHECK SHALL be the quantitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
. UNRESTRICTED AREA l An UNRESTRICTED AREA SHALL be any area, access to which is neither limited nor controlled by the licensee, e URANIUM FUEL CYCLE The URANIUM FUEL CYCLE is defined in 40 CFR Part 190.02(b) as: "The operation of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power
,g plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive materialin support of these operations, and the use of recovered non-uranium special nuclear and by-product materials from the cycle."
. VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM SHALL be any system designed and installed to reduce gaseous radiolodine or radioactive materialin particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or ,
HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust j stream prior to the release to the environment. Such a system is not considered to have j any effect on noble gas effluents. Engineered safety feature atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. l
. VENTING VENTING SHALL be 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 NOT provided or required during VENTING.
Vent, used in system names, does not imply a venting process. The release of air or h gases via sampling equipment or instrumentation is not considered a controlled process.
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. 1.0 RADIOLOGICAL EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS ! I APPLICABILITY AND SURVEILLANCE REQUIREMENTS 1.1 Specifications l 1 1.1.1 Compliance with the Controls contained within the succeeding text is required during the conditions specified. Upon failure to meet the specifications, the
< associated ACTION requirements SHALL be met.
i 1.1.2 Noncompliance with a specification SHALL exist when the requirements of the Control and usociated ACTION requirements are not met within the specified i time interval. It t' e Controlis restored prior to expiration of the specified time interval, completion of the ACTION requirements is not required. I l
- 1.2 _ Surveillance Reauirements )
Q 1.2.1 Surveillance Requirement SHALL be met during the conditions specified for
- V individual specifications unless otherwise stated in an individual Surveillance
- Requirement.
1.2.2 Each Surveillance Requirement SHALL be performed within the specified time interval with the following exceptions: A. Specified time intervals between tests may be adjusted plus or minus 25% to accommodate normal test schedules.
, 1.2.3 Failure to perform a Surveillance Requirement within the allowed surveillance l interval, defined by Specification 1.2.2, SHALL constitute noncompliance with ;
- the OPERABILITY requirements for a Control for operation. The time limits of l l the ACTION requirements are applicable at the time it is identified that a I
. Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than )
24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. i f O v
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MANUAL (ODCM) REV: 14 a , , . ., Page 17 of 223 2.0 LIQUID EFFLUENTS ! CONCENTRATON SPECIFICATIONS 2.1 in accordance with T.S. 6.5.H.2 the concentration of liquid radioactive material released l at any time to UNRESTRICTED AREAS SHALL be limited to the concentrations specified in OLD 10 CFR Part 20, Appendix B, Table 11, 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 Ci/mi total activity. APPLICABILITY At all times. ACTION ,
- a. When the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeds the above limits, immediately restore the concentration to within the above limits.
- b. Report all deviations in the Annual Radioactive Effluent Release Report.
2.2 SURVEILLANCE REQUIREMENTS 2.2.1 Radioactive liquid wastes SHALL be sampled and analyzed according to the sampling and analysis program of Table 2.1. 2.2.2 The results of radioactive analysis SHALL be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 2.1. O
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v OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 $ Pace 18 0f 223 J J DOSE SPECIFICATIONS l 2.3 In accordance with T.S. 6.5.H.4 the dose or dose commitment to a MEMBER OF l THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to: a. During any calendar quarter to $3 mrem to the total body and to s10 mrem to any organ, and b. During any calendar year to s6 mrem to the total body and to s20 mrem to any I organ. APPLICABILITY At all times. ACTION i
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a Licensee Event Report, prepare and submit l to the Commission within 30 days a Special Report that includes the following information:
- 1. Identifies the cause(s) for exceeding the limit (s).
- 2. Defines the corrective actions taken to reduce the release.
- 3. Defines the corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
l l SURVEILLANCE REQMIREMENTS l l 2.4 Cumulative dose contributions for the current calendar quarter and current calendar year SHALL be determined monthly in accordance with the methodology and parameters in Section 4.0 of the ODCM. O
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Page19 of 223 , LIQUID RADWASTE TREATMENT SYSTEMS SPECIFICATIONS t 2.5 In accordance with T.S. 6.5.H.6 the LIQUID RADWASTE TREATMENT SYSTEM l SHALL be used to reduce the radioactive materials in liquid wastes prior to their 4 discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED ! AREAS would exceed 0.12 mrem to the whole body or 0.4 mrem to any organ in a 1 monthly period. APPLICABILITY At all times. ACTION
- a. With radioactive liquid waste being discharged without treatment and in excess of the (3 above limits,in lieu of a . Licensee Event Report, prepare and submit to the Commission V within 30 days a Special Report that includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.
l
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and '
- 3. Summary description of action (s) taken to prevent recurrence.
1 2.6 SURVEILLANCE REQUIREMENTS 2.6.1 Doses due to liquid releases SHALL be projected at least once each month in accordance with the methodology and parameters in Section 4.0 of the ODCM. i 2.6.2 The installed LIQUID RADWASTE TREATMENT SYSTEM SHALL be considered OPERABLE by meeting the Controls specified in 2.1 and 2.3. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES W TITLE: NUMBER:
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+ . RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SPECIFICATIONS 2.7 in accordance with T.S. 6.5.H.1 the radioactive liquid effluent monitoring l Instrumentation channels shown in Table 2.2 SHALL be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 2.1 are not exceeded. The alarm / trip setpoints of these channels SHALL be determined in accordance with the methodology in Section 4.0 of the ODCM. APPLICABILITY During release via the monitored pathway. ACTION
- a. With a radioactive liquid effluent monitoring instrurnentation channel alarm / trip setpoint '
I less conservative than required by the above specification, immediately suspend the ! release of radioactive effluents monitored by the effected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum required radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the Action shown in Table 2.2
- c. Report all deviations in the Annual Radioactive Effluent Release Report.
SURVEILLANCE REQUIREMENTS 2.8 Each radioactive liquid effluent monitoring instrumentation channel SHALL be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 2.3. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES pg[3M, [,,, TITLE: NUMBER: g- m'd - 1
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OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 M ~ O ">; Page 21 of 223 LIQUID STORAGE TANKS SPECIFICATIONS 2.9 In accordance with T.S. 6.5.J.3 the quantity of radioactive material contained in each of l the following tanks SHALL be limited to 10 curies, excluding tritium and dissolved or entrained gases: Condensate Storage Tanks Outside Temporary Storage Tanks APPLICABILITY-At all times. ACTION p a. With the quantity of radioactive material contained in any of the above listed tanks d exceeding the limit in 2.9 above, immediately suspend all additions of radioactive materials to the tank and within 48 hours reduce the contents to within the limit. I SURVEILLANCE REQUIREMENTS l 2.10 The quantity of radioactive material contained in each of the tanks listed in specification 2.9 SHALL be determined to be within the limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive I materials are being added to the tank. I l
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+ d Pace 23 of 223 3.0 GASEOUS EFFLUENTS DOSE RATE SPECIFICATIONS 3.1 In accordance with T.S.6.5.H.7 the dose rate due to radioactive materials released in l gaseous effluents from the site to areas at or beyond the gaseous SITE BOUNDARY (Figure 3.2) SHALL be limited to the following:
- a. For Noble Gases: s500 mrem /yr to the whole body and s3000 mrem /yr to the skin, ;
and
- b. For lodine-131, lodine-133, Tritium, and Particulates with half-lives greater than 8 days: s1500 mrem /yr to any organ.
APPLICABILITY V(3 At all times. ACTION
- a. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limits (s).
- b. Report all deviations in the Annual Radioactive Effluent Report.
3.2 SURVEILLANCE REQUIREMENTS 3.2.1 The dose rate due to noble gases in effluents SHALL be determined to be within l the above limits in accordance with the methodology and parameters in Section 5.0 of the ODCM. 3.2.2 The dose rate due to lodine-131, lodine-133, Tritium, and Particulates with half lives greater than 8 days in gaseous effluents SHALL be determined to be l within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.1. (J3
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OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 $ Page 24 of 223 DOSE - NOBLE GASES SPECIFICATIONS 3.3 in accordance with T.S.6.5.H.8 the air dose due to noble gases released in gaseous l effluents to areas at or beyond the gaseous SITE BOUNDARY (Figure 3.2) SHALL be limited to the following:
- a. During any calendar quarter: s10 mrad for gamma radiation and s20 mrad for beta radiation, and
- b. During any calendar year: s20 mrad for gamma radiation and s40 mrad for beta radiation.
APPLICABILITY At all times. ACTION
- a. With the calculated dose from the release of radioactive noble gases in gaseous effluents exceeding any of the above limits,in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that includes the following:
- 1. Identifies the cause(s) for exceeding the limit (s).
2. Defines the corrective actions taken to reduce the release. 3. Defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. SURVEILLANCE REQUIREMENTS 3.4 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases SHALL be determined monthly in accordance with the methodology and parameters in Section 5.0 of the ODCM. O
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' Page 25 of 223 DOSE -IQDINE-131. IODINE-133. TRITlUM AND PARTICULATES l SPECIFICATIONS 3.5 In accordance with T.S.6.5.H.9 the dose to any organ of a MEMBER OF THE PUBLIC l from lodine-131, lodine-133, Tritium, and all radioactive particulates with a half-life greater than 8 days in gaseous effluents released to ares at or beyond the gaseous SITE BOUNDARY (Figure 3.2) SHALL be limited to the following:
- a. During any calendar quarter: s15 mrem to any organ, and
- b. During any calendar year: s30 mrem to any organ.
APPLICABILIIX At all times. O ACTION l V
- a. With the calculated dose from the release of lodine-131, lodine-133, Tritium, and Particulates with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits,in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days a Special Report that includes the following:
- 1. Identifies the cause(s) for exceeding the limit (s).
- 2. Defines the corrective actions taken to reduce the release.
- 3. Defines the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
l SURVEILLANCE REQUIREMENTS l 3.6 Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, Iodine-133, Tritium, and Particulates with half-lives greater than 8 days SHALL be determined monthly in accordance with the methodology and parameters in Section 5.0 of the ODCM. O
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' ,W' Page 26 of 223 GASEOUS RADWASTE TREATMENT SYSTEMS 3.7 SPECIFICATIONS 3.7.1 in accordance with T.S.6.5.H.6 the Wasje Gas Treatment System and the [
VENTILATION EXHAUST TREATMENTSYSTEM SHALL be used to reduce releases of radioactivity when the projected doses due to the gaseous effluents to areas at or beyond the gaseous SITE BOUNDARY (Figure 3.2) would exceed any of the following controls over a monthly period: A. 0.4 mrad to air from gamma radiation, or B. 0.8 mrad to air from beta radiation, or C. 0.6 mrad to any organ of a MEMBER OF THE PUBLIC. 3.7.2 In accordance with T.S.6.5.l.'2 the quantity of radioactivity contained in each gas storage tank SHALL be limited to s78,000 curies of noble gases (considered as dose equivalent Xe-133). 3.7.3 The radioactive gas contained in the Waste Gas Treatment System SHALL NOT be deliberately discharged to the environment during unfavorable wind conditions when the cooling towers are in operation. For purposes of this specification, unfavorable wind conditions are defined as wind from 5 West of North to 45 East of North at 10 miles per hour or less. APPLICABILITY At all times. ARIl_QN '
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits of 3.7.1, in lieu of a Licensee Event Report, prepare and submit to the ,
Commission within 30 days a Special Report that includes the following information:
- 1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent recurrence.
- b. With the quantity of radioactive materialin any gas storage tank exceeding the limits of O
3.7.2, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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- OFFSITE DOSE OALCULATION U MANUAL (ODCM) REV: 14 n [9Snhji Page 27 of 223 3.8 SURVEILLANCE REQUIREMENTS 3.8.1 Doses due to gaseous releases at and beyond the SITE BOUNDARY SHALL be projected at least once each month in accordance with the methodology and parameters in the ODCM. A projected dose in excess of the limits of 3.7.1 indicates that additional components or subsystems of the GASEOUS RADWASTE TREATMENT SYSTEM must be placed in service to reduce radioactive materials in the gaseous effluents.
3.8.2 The installed Waste Gas Treatment System and the VENTILATION EXHAUST TREATMENT SYSTEM SHALL be considered OPERABLE by meeting the Controls specified in 3.1,3.3 AND 3.5. 3.8.3 The quantity of radioactive material contained in each gas storage tank in use SHALL be determined to be within the limit specified in 3.7.2 monthly. If the inventory of any tank exceeds 10,000 curies, daily sampling when making . additions SHALL be performed. O l O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES I c < ' J < TITLE: NUMBER: hI
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'n Page 28 of 223 1 EXPLOSIVE GAS MONITORING INSTRUMENTATION 3.9 SPECIFICATIONS l
1 3.9.1 In accordance with T.S.6.5.1.1 the explosive gas monitoring instrumentation l channels shown in Table 3.2 SHALL be OPERABLE with their Alarm 6 rip Setpoints set to ensure the limits of 3.9.2 are not exceeded. 3.9.2 In accordance with T.S.6.5.1.1 the concentration of oxygen at the outlet of each l l operating recombiner SHALL be maintained to s2% by volume. l APPLICABILITY As shown in Table 3.2. ACTION l
- a. With an explosive gas monitoring instrumentation channel Alarm 6 rip Setpoint less conservative than required by the above specification, declare the channelinoperable and take the ACTION shown in Table 3.2.
- b. With less than the minimum required explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.2. Restore the inoperable instrumentation to OPERABLE status within 30 days and,if unsuccessful,in lieu of a License Event Report, prepare and submit a Special Report to the Commission to explain why this inoperability was not corrected in a timely manner.
- c. With the concentration of oxygen measured at the outlet of operating recombiner(s)
>2% by volume but <4% by volume, restore the concentration of oxygen to s2% by volume within 48 hours.
- d. With the concentration of oxygen measured at the outlet of operating recombiner(s)
>4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to s2% within one hour.
SURVEILLANCE REQUIREMENTS 3.10 Each explosive gas monitoring instrumentation channel SHALL be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CAllBRATION at the frequencies shown in Table 3.3.
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2 Page 29 of 223 : RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATIONS 3.11 In accordance with T.S.6.5.H.1 the radioactive gaseous effluent monitoring l instrumentation channels shown in Table 3.2 SHALL be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.1 are not exceeded. The alarm / trip setpoints of these channels SHALL be determined in accordance with i the methodology in Section 5.0 of the ODCM. , J APPLICABil,lIX : As shown in Table 3.2. ACTION
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint, A less conservative than required by the above specification,immediately suspend the d release of radioactive effluents monitored by the effected channel, or declare the :hannel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum required radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the Action shown in Table 3.2.
- c. Report all deviations in the Annual Radioactive Effluent Release Report.
SURVEILLANCE REQUIREMENTS l 3.12 Each radioactive gaseous effluent monitoring instrumentation channel SHALL be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.3.
PRAIRIE ISLAND NUCLEAR GENERATIN3 PLANT NORTHERN STATES POWER COMPANY
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. ATMOSPHERIC STEAM DUMP MONITORING SPECIFICATIONS 3.13 The dose to a MEMBER OF THE PUBLIC from lodine-131 released, via one steam dump operation, in gaseous effluents from the site at or beyond the gaseous SITE BOUNDARY (Figure 3.2) SHALL NOT be greater than twice the limit specified in 3.5.
APPLICABILITY During atmospheric steam dump operations with detectable lodine-131 activity in the Steam Generator bulk water. ACII_QH
- a. When the calculated dose from the release of lodine-131 in gaseous effluents via steam dump operations exceeds the above limit:
- 1. The milk from dairy cows grazing in the downwind area SHALL be sampled and analyzed for a period of 5 days following the release. The downwind area shall include the 221/2 degree sector of a circle having it's center at the plant and a 2 mile radius.
- 2. The lodine-131 concentration in the milk SHALL be determined daily utilizing
[ instrumentation with a minimum lodine-131 detection limit of 1.0 pCl/ml. 3.14 SMBVEILLANCE REQUIREMEHIS The lodine-131 activity released via atmospheric steam dumps SHALL be sampled and analyzed according to the sample and analysis program of Table 3.1. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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TITLE: NUMBER: H4 OFFSITE DOSE CALCULATION O g, C gja . 4 H MANUAL (ODCM) REV: 14 F y@d@g? ' Page 31 of 223 4.0 J.lOUlD EFFLUENT CALCULATIONS 4.1 Monitor Alarm Setpoint Determination This procedure determines the monitor alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released to UNRESTRICTED AREAS exceeds the specification defined in Section 2.1. Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the liquid monitor setpoint determinations should be completed using the most recent available composite sample results. Monitor high alarm or isolation setpoints will be established by one of the following:
- a. Mcnthly calculation of setpoints using the methodology of Sections 4.1.1 and 4.1.3.
- b. Calculation of alarm setpoint t,ased on analysis prior to discharge using methodology of Section 4.1.2.
- c. Alarm setpoint determined using methodology of Section 4.1.1 and 4.1.3 assuming all radionuclides have an MPC of 1E-7 Cl/ml. No recalculation of setpoints is
~
necessary unless an increase in alarm setpoint is desired. PWR GALE Code source terms (Table 4.1) may be used if there were no detectable isotopes in the previous month or in the analysis prior to release. If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint SHALL be l reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increase to the new value. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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= & M.mo.o.._n p l 4.1.1 Liould Effluent Monitor Setooints ! l The following method applies when determining the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid , Monitor- Unit 1 (1R-19), and Steam Generator Blowdown Liquid Monitor-Unit 2 (2R-19) during all operational conditions when the radwaste discharge flow rate is maintained constant at the maximum design flow rate. A. Determin9 the " mix" (radionuclides and composition) of the liquid effluent.
- 1. Determine the liquid source terms that are representative of the " mix" of the liquid effluent. Liquid source terms are the total curies of each isotope released during the previous month. Table 4.1 source terras may be used if there have been no liquid releases.
- 2. Determine the activity concentrations (AC i ) of all non-gamma emitters including H-3, Sr-89, Sr-90, Fe-55, and alpha activity.
- 3. Determine NGF (the total fraction of the MPC in the liquid effluent) for all non-gamma emitting nuclides.
ACi NGF= 7E (4,3_)) , MPCi where: ACi = Activity concentration of nuclide 'i'in the liquid effluent ( Cl/ml). i i MPCi The liquid effluent radioactivity concentration limit for ! radionuclide 'i' ( Ci/ml) from Table 4.1 or Reference 3. l I l O
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- 4. Determine Si (the fraction of the gamma emitting radioactivity in the
- liquid effluent comprised by radionuclides 'i') for each individual
- radionuclide in the liquid effluent.
S= i Ai . Ei Ai (4.1-2) I 4 where: Ai = the radioactivity of gamma emitting radionuclide 'i'in the liquid effluent. l l <
- 5. Determine WGF (the sum of fractional activities weighted by the MPC)
- for the gamma emitting nuclides in the liquid effluent.
l bi WGF=E, (4.1-3) MPC;
! where: MPCi = the liqu I offluent radioactivity concentration limit for radionuclide 'i' ( Ci/ml) from Table 4.1 or Reference 3.
R. Determine Ct (the maximum acceptable total radioactivity concentration of gamma emitting nuclides in the liquid effluent prior to dilution ( Ci/ml). Ct = 1 x F - NGF (4.1-4) WGF f where: F = Dilution water flow rate (gpm)
= 67,300 gpm from cooling tower blowdown f = The maximum attainable discharge flow rate prior to dilution (gpm)
= 60 gpm from the ADT tank pump ,
I
= 100 gpm from the CVCS tank pump
= 60 gpm from the SGBD tank pump 1
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h 1 , $secuen! 4 p, g l C. Determine C.R. (the calculated monitor count rate above background , attributed to the radionuclides (ncpm)). ! C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve l located in the Radiation Monitor Calibration file. C.R. is the count rate that corresponds to the " adjusted" total radioactivity concentration (C t). D. Determine HSP (the monitor high alarm setpoint above background (ncpm)). l HSP = TmC.R. (4.1-5) i Tm = Fraction of the radioactivity from the site Inat may be released via ) each release point to ensure that the site boundary limit is not i exceeded due to simultaneous releases from several release ' points.
= 0.90 for the Waste Effluent Liquid Monitor (R-18) !
= 0.05 for the Steam Generator Blowdown Liquid O' Monitor- Unit 1 (1 R-19)
= 0.05 for the Steam Generator Blowdown Liquid Monitor- Unit 2 (2R-19) l Tm values may be revised from the values given above.
The summation of all the Tm values for active release points SHALL NOT be greater than unity. E. The monitor high alarm setpoint above background (nepm), SHALL be set at or below the HSP value. l O l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 4 s x% ~ TITLE: NUMBER: Y OFFSITE DOSE CALCULATION H4 MANUAL (ODCM) REV: 14 b Page 35 of 223 3 4.1.2 Setooint Based on Analysis of Liauid Prior to Discharge (Octionan This method may be used in lieu of the method in Section 4.1.1 to determine the setpoints for the maximum acceptable discharge flow rate prior to dilution and to determine the associated high alarm setpoint based on this flow rate for the , Waste Effluent Liquid Monitor- Unit 1 (1 R-19), and Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19), during all operational conditions. A. Determine f (the maximum acceptable discharge flow rate prior to dilution (gpm)). ~ f I -}
= 0.8 F Tm iMCi l
p F = Dilution water ficw rate (gpm) G ,
= 67,300 gpm from cooling tower blowdown Ci = Concentration of radionuclide "i"in the liquid effluent prior to dilution ( Ci/ml) from analysis of the liquid effluent to be released.
MPCi = The liquid effluent radioactivity concentration limit for radionuclide "i"( Cl/ml) from Table 4.3 or from Reference 3. Tm = Fraction of the radioactivity from the site that may be released via each release point to ensure that the site boundary limit is not exceeded due to simultaneous releases from several release points. Refer to Section 4.1.1.D.
i l i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES e* TITLE: NUMBER: a g ? OFFSITE DOSE CALCULATION H4 g f- MANUAL (ODCM) REV: 14
)Sedianl;! p,g,3,,,3,3 B. Determine the monitor setpoint based on the radionuclide mix of the liquid I effluent. l
- 1. Determine C.R. (the calculated monitor count rate above background attributed to the radionuclides (ncpm)).
C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate point that corresponds to the " adjusted" total radioactivity , concentration (C t)- I C = Total radioactivity concentration of the radionuclides (minus ! I tritium and. other radionuclides that are only beta emitters) in the liquid discharge prior to dilution ( Ci/ml) as determined using Equation 4.1-4. l
- 2. Determine HSP (the monitor high alarm setpoint above background (ncpm)).
HSP = EEL (4.1-7) 0.8 0.8 = A correction factor to increase the monitor setpoint to prevent spurious alarms caused by deviations in the mixture of radionuclides that affects monitor response.
- 3. The monitor high alarm setpoint above background SHALL be set at or below this HSP value when this optional method is selected. The maximum discharge flow SHALL NOT exceed the value of f as determined in Section 4.1.2.A. when this optional method is selected.
4.1.3 Discharae Canal Monitor The following method determines the high alarm setpoint for the Discharge Canal Monitor (R-21) during all operational conditions. A. Determine the " mix" (radionuclides and composition) of the liquid effluent.
- 1. Determine the liquid source terms that are representative of the " mix" of all liquids released into the discharge canal. Liquid source terms are the total curies of each isotope released during the previous month.
g Table 4.1 source terms may be used if there have been no liquid releases.
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- 2. Determine the activity concentrations (AC i ) of all non-gamma emitters including H-3, Sr-89, Sr-90, Fe-55, and alpha activity.
I
- 3. Determine NGF (the total fraction of the MPC in the liquid released to the discharge canal) for all non-gamma emitting nuclides. The volume used to calculate the non-gamma emitting activity concentrations is the ,
volume released via cooling tower blowdown during a one month period at the minimum flow rate of 67,300 gpm. NGF = AB iMPC where: ACi = Activity concentration of nuclide 'i' released to the discharge canal ( Ci/ml) MPCi = The liquid effluent radioactivity concentration limit for l radionuclide 'i'( Cl/ml) from Table 4.3 or Reference 3. j
- 4. Determine Si (the fraction of the gamma emitting radioactivity in the liquid released to the discharge canal comprised by radionuclide 'i') for each individual radionuclide released to the discharge canal.
Si = Ai I Ai where: Ai = The radioactivity of gamma emitting radionuclide 'i' released to the discharge canal.
- 5. Determine WGF (the sum of fractional activities weighted by the MPC) for the gamma emitting nuclides released to the discharge canal.
g, WGF = IEMPC i
,s.
where: MPCi = The liquid effluent radioactivity concentration limit for q radionuclide 'i' ( Cl/ml) from Table 4.3 or Reference 3. NJ
l 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT i NORTHERN STATES POWER COMPANY H PROCEDURES
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Page 38 of 223 B. Determine C: (the maximum acceptable total radioactivity concentration of gamma emitting nuclides released to the discharge canal ( Ci/ml)). C= 1-NGF WGF C. Determine C.R. (the calculated monitor count rate above background attributed tot he radionuclides (nepm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate that corresponds to the " adjusted" total radioactivity concentration (C:). D. The monitor high alarm setpoint above background (ncpm) SHALL be set at : or below the C.R. value. 4.1.4 Monitor Calibration Liquid effluent monitors are calibrated periodically using a Cs-137 standard. Since the actualisotopic mixes of the liquids released may contain nuclides with different gamma energies and yields than the calibration standard, the response of the monitor varies with respect to the actual energies and abundances of the nuclides in the mix being monitored when compared to Cs-137. Effluent release computer calculations that compute setpoint determinations or expected monitor readings during or prior to a release compensate for the difference in gamma energies and yields and adjust the monitor setpoint or predicted monitor reading according to the actual nuclide mix. The assumption { is made that the monitor's response is directly proportional to the gamma j energies. The cumulative errors associated with the monitor calibration methodology are I not accounted for in the determination of the individual monitor setpoints. There is sufficient conservatism built into the selection of the actual monitor setpoint; plus the fact that the monitor fractions used in the setpoint determination ' equation determine that it would be necessary for all of the effluent monitors to be in alarm before the limits of 10CFR Part 20 would be exceeded. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 7 $g ;w TITLE: NUMBER: O J eg OFFSITE DOSE CALCULATION
*i ___i . [ MANUAL (ODCM) REV: 14 PaQe 39 of 223 4.2 Compliance With 10CFR20 In order to comply with 10CFR20, the concentrations of radionuclides in liquid effluents will not exceed the maximum permissible concentrations (MPC) as defined in Appendix B, Table 11 of 10CFR20. For CONTINUOUS RELEASES, the alarm trip ,
setpoints discussed in Section 4.1 will assure that these concentrations are not I exceeded. For BATCH RELEASES, concentrations of radioactidty in effluents prior to dilution will be determined, providing protection in addition to the alarm trip setpoint discussed in Section 4.1. Concentration in diluted effluents will be calculated using these results. 4.2.1 Continuous Releases 1 Continuous liquid releases can occur from PINGP through steam generator blowdown. The alarm trip setpoints discussed in Section 4.1 will assure that releases from this pathway will not exceed the limits of 10CFR20. p Other minor releases of a continuous nature have occurred at PINGP through ; () the turbine building sump system. These releases were minor and are not expected to occur in the future. However, a continuous composite sample will be maintained at the discharge from the turbine building sump with samples being taken and analyzed weekly. If these samples indicate detectable levels of I radionuclides, the mathodolcgies given in Section 4.2.2 will be applied to the l turbine sump weekly releases and the limit in Equation 4.2-2 will be lowered to ! account for this source term. O i
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4.2.2 Batch Releases I l To further show compliance with 10CFR20, the radioactivity content of each ! BATCH RELEASE will be determined prior to release. The concentration of the I various radionuclides in the BATCH RELEASE prior to dilution, is divided by the i minimum dilution flow to obtain the concentration at the SITE BOUNDARY. This 1 calculation is shown in the following equation: Conci= Ci R (4.2-1) MDF l where l 1 Conci = concentration of radionuclide i at the site boundary, Ci/ml; l l Ci = concentration of radionuclide i in the potential batch release, pCi/ml; I R = release rate of the batch MDF = minimum dilution flow (=67,300 gpm) The projected concentration at the SITE BOUNDARY is compared to the MPCs l in Appendix B, Table 11 of 10CFR20 which are given in Table 4.1. Before a l release may occur, Equation 4.?-2 must be met for all isotopes. l l {. lConci $; 0.9 MPCi (4.2-2)
= Maximum permissible concentration of MPCi radionuclide i from Table 4.3 or Appendix B, Table ll of 10CFR20. Cl/ml The summation has been reduced from 1.0 to 0.9 to account for simultaneous CONTINUOUS RELEASES from steam generator blowdown as given in Section 4.1.1.E. As noted earlier, this fraction may be adjusted based on experience.
The summation of all source terms SHALL NOT be greater than 1.0 of the 10CFR20 limit. O
- -. _ --- - - _ _ _ - - - . - . - . - _ .- = _ - .
1 j PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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Since the volume of the discharge pipe will contain the volume of 2 to 3 waste batch tanks, to ensure compliance with 10CFR20 when the maximum acceptable discharge flow rate, as calculated in Section 4.1.2, is less than the maximum possible release rate from all release sources, the discharge pipe SHALL be flushed with a volume of at least the volume of the discharge pipe. The flush rate SHALL NOT exceed the maximum discharge flow rate and may be accomplished with water from other release paths. If more than one waste batch tank requiring flushing are to be released, the discharge pipe may be flushed following the final tank release. Volume of discharge pipe = 15,500 gal. 4.3 Liauld Effluent Dose - Comnliance with 10CFR50 Doses resulting from liquid effluents will be calculated monthly to show compliance with 10CFR50. A cumulative summation of total body and organ doses for each calendar quarter and calender year will be maintained as well as projected doses for the next p month. V Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the monthly 2 quid effluent dose calculations and comparisons to quarterly and annual limits should be cor1pleted using the most recent available composite sample results. The quarterly and annual dose calculations SHALL be completed using the i actual composite sample results. l The limits of 10CFR50 are on a per reactor unit basis. The liquid radwaste system at l PINGP is shared by both reactor units making it impossible to separate the releases of the two units. The releases that can be separated by unit, steam generator blowdown , and turbine building sump releases, contribute a very small portion of the total liquid l releases from PINGP. Therefore, for compliance with 10CFR50 the releases from both units will be summed and the limits of Appendix I will be doubled. 4 V
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT , NORTHERN STATES POWER COMPANY H PROCEDURES ! ' g' gj N' TITLE: NUMBER: M g J OFFSITE DOSE CALCULATION REV: 14 g! MANUAL (ODCM) 71 fsssWR w p 4.3.1 Determination of Liould Effluent Dilution To determine doses from liquid effluents the near field average dilution factor for i the period of release must be calculated. This di!ution factor must be calculated l for each BATCH RELEASE and each CONTINUOUS RELEASE mode. The dilution factor is determined by: Fk = Ru (4.3-1) X ADFk where: i Rk = release rate of the batch or continuous release during the period, k, gpm. ADFk= average dilution flow during the time period of release k, gpm. The value of X is the site specific factor for the mixing effect of the PINGP discharge structure. This value is 10 for PINGP while operating in the closed cycle cooling mode. The product of X and ADFk is limited to 1000 cfs (4.5 x 10s cle is 150 cfs, the gpm). Therefore, denominator of Equationsince 4.3-1 isblowdown always 4.5 x 10flow in closed cyin closed cycle. through or helper mode, the value if X is reduced to 1.0, 4.3.2 Dose Calculations The dose contribution from the release of liquid effluents will be calculated monthly. The dose contribution will be calculated using the following: where: Dr = I E A ix tg Cik Fk (4.3-2) i ki ; l where: D, = the dose commitment to the total body or any organ t, from the liquid effluents for the period of I release, mrem; g Cgi = the average concentration of radionuclide, i, in undiluted liquid effluent for liquid release k, Cl/ml;
1 l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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Mnigg@ ' Page 43 of 223 l Ax i = the site related ingestion dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter, mrem /hr per Cl/ml; Fk = the near field average dilution factor for Cik during liquid effluent release k, . l ik = the duration of release k, hours. The dose factor Asi was calculated for an adult for each isotope using the following equation: Axi = 1.14 x 105 [21BFi DFh] (4.3-3) where: p 1.14 x 105 = 106 p.Cl x 103 ml x 1 yr - ( pCi I 8760 hr 21 = adult fish consumption, Kglyr; BFi = bio accumulation factor for radionuclide i in fish from Table A-1 of Regulatory Guide 1.109 Rev.1 (5) pCl/Kg per pCi/l; DFit = dose conversion factor for radionuclide i for adults for a particular organ T from Table E-11 of Regulatory Guide 1.109 Rev.1, (5) mrem /pCl. A table of Axi values for an adult at the PINGP are presented in Table 4.2. Mississippi River water is not used as a potable water supply within 300 miles downstream of the PINGP. Wells are used for irrigation downstream of the plant. /
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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TITLE: NUMBER: 1 e-MNd OFFSITE DOSE CALCULATION MANUAL (ODCM) REY: 14 Page 44 of 223 h{ 1 4.3.3 Cumulation of Doses I Doses calculated monthly will be summed for comparison with quarterly and annuallimits. The monthly results should be added to the doses cumulated from tha other months in the quarter of interest and in the year of interest for the cot'ibined releases of both reactor units and compared to the limits given in Section 2.3. The quarterly limits represent one half of the annual design objective. If these quarterly or annual limits are exceeded, a special report should be submitted to the USNRC identifying the cause and corrective action to be taken. If twice the , quarterly or annual limits are exceeded, a special report SHALL be submitted showing compliance with 40CFR190. 4.3.4 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly. If the projected doses for the month exceed 2 percent of the limit specified in Section 2.3.b, additional components of the liquid radwaste
,g treatment system will be used to process waste. The projected doses will be calculated using Equation 4.3-2. The dilution factor, F k, will be calculated by replacing the term ADFk in Equation 4.3-1 with the term MDF from Equation 4.2-1. The total source term utilized for the most recent dose calculation should be used for the projections unless information exists indicating that actual releases could differ significantly in the next month. In this case, the source term would be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the i coming month.
I I 1 1 1 Ol b
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 9 ^ TITLE: NUMBER: Q "' E'i OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 Page 45 of 223 4.4 References
- 1. " Prairie Island Final Environmental Statement," USAEC, May,1973, p. V-26.
- 2. "NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No.1 - Docket No. 50-282 and 50-306," Table 2.1-1.
ll
- 3. "Old 10CFR20," Appendix B, Table 11, Column 2.
- 4. "NSP - Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No.1 - docket 50- 282 and 50-306," July 21,1976, Table 2.1-2.
- 5. U.S. Nuclear Regulatory Commission, " Regulatory Guide 1.109 - Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10CFR50, Appendix I," Rev.1,1977.
O O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY l H PROCEDURES i , .u. x" s ^ ' fp ' - TITLE: NUMBER: { sa L.I ,~*~ OFFSITE DOSE CALCULATION H4 e [-l: .a ggj;;. '"* 2 MANUAL (ODCM) REV: 14 Page 46 of 223 l l THis PAGE IS LEFT INTENTIONALLY BLANK I O
l l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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5.1 Monitor Alarm Setooint Determination This procedure determines the monitor alarm setpoint that indicates if the dose rate in i UNRESTRICTED AREAS due to noble gas radionuclides in the gaseous effluent released from the site exceeds 500 mrem / year to the whole body or exceeds 3000 mrem / year to the skin. Monitor high alarm or isolation setpoints will be established in one of the following ! ways:
- a. Monthly calcuici:,i of setpoint using the methodology of Section 5.1.1 for CONTINUOUS RELEASES using previous month releases as source term.
- b. Prior to each containment PURGE, recalculation of the setpoint using the j methodology of Section 5.1.1 based on the sample taken prior to PURGING.
- c. In lieu of (5.1.a) and (5.1.b) above, alarm setpoints may be established using the methodology of Section 5.1.1 using conservative assumptions (e.g.,100% Kr-89).
No recalculation of setpoints is necessary unless an increase is desired. PWR GALE Code source terms (Table 5.2) may be used if there were no detectable isotopes in the previous month or in the analysis prior to PURGING. If the newly calculated setpoint is less than the existing monitor setpoint, the setpoint SHALL be l reduced to the new value. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or increased to the new value. 5.1.1 Effluent Monitors The following method applies when determining the isolation or high alarm setpoint for the monitors listed in Table 5.1. A. Determine the " mix"(noble gas radionuclides and composition) of the i gaseous effluent.
- 1. Determine the gaseous source terms that are representative of the gaseous effluent. Gaseous source terms are the total curies of each noble gas released during the previous month or a representative i
{ analysis of the gaseous effluent. Table 5.2 source terms may be used if the releases for the previous month were below the lower limits of j j detection (LLD).
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- 2. Determine Si (the fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i") for each individual noble gas radionuclide in the gaseous effluent.
Si = Ai IAi (5.1-1) i Ai = The radioactivity of noble gas radionuclide "i"in the gaseous effluent from either the previous months releases or from Table 5.2 if there were no releases during the previous month. B. Determine Q: (the maximum acceptable total release rate of all noble gas radionuclides in the gaseous effluent ( Ci/sec)) based upon the whole body , exposure limit. ! Q = 500 (X /Q) I K i S (5.1-2) g i (x /Q) = The highest calculated annual average relative concentration of effluents released via the plant vents for any area at or beyond the site boundary for all sectors (sec/m3) from the "x /Q" column in Table 5.1. Ki = The total whole body dose factor due to gamma emissions from noble gas radionuclide "i"(mrem / year / Ci/m3 ) from Table 5.4. C. Determine Qt based upon the skin exposure limit. Qt = 3000 (5.1-3) (x /Q) I (L i+ 1.1 M)i Si i Li + 1.1 Mi = The total skin dose factor due to gamma and beta emissions from noble gas radionuclide "i" (mrem / year / Ci/m3 ) from Table 5.4. O
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Page 49 of 223 D. Determine Ct (the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the gaseous effluent (/ Ci/cc)). Ct = 2.12 E-3 Ot (5.1-4) F
%xO.. g*g Use the lower of the Qi values obtained in Section 5.1.1.B
. : .< and 5.1.1.C.
F = The maximum effluent flow rate at the point of release (cfm) from the " Effluent Flow Rate" column in Table 5.1. 2.12 E-3 = Unit conversion constant to convert pCi/sec/cfm to Ci/cc. E. Determine C.R. (the calculated monitor count rate above background attributed to the noble gas radionuclides (ncpm)). C.R. is obtained by using the applicable Effluent Monitor Efficiency Curve located in the Radiation Monitor Calibration file. C.R. is the count rate point that corresponds to the total radioactivity concentration (C t). F. Determine HSP (the monitor high alarm setpoint above background (ncpm)). HSP = Tm C.R. (5.1-5) Tm = Fraction of the total radioactivity from the site that may be released via each release point to ensure that the SITE BOUNDARY limit is not exceeded due to simultaneous releases from several release points from the " Release Fraction" column in Table 5.1. G. The isolation or high alarm setpoints above background (nepm) for the monitors should be set at or below the HSP values.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j
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a" ' e m OFFSITE DOSE CALCULATION H4 REV: 14 g ' QQ:,a~ e' ' , MANUAL (ODCM) q wm Page 50 of 223 l 5.1.2 Air Elector Monitors ! Radiation monitors 1R-15 and 2R-15 provide an indication of gross noble gas ! activity at the main condenser air ejector of Unit 1 and Unit 2, respectively. l These monitors are provided to give rapid indication of steam generator tube l leakage. They are not effluent monitors since the air ejectors are vented to the auxiliary building vents during normal plant operation and re!sases are monitored by the auxiliary building vent monitoring system. 5.1.3 Monitor Calibration i Gaseous effluent monitors are calibrated periodically using available gas mixes existing in plant systems. Since the available gas mixes vary in isotopic ratios and the energies of those isotopes span a range of energies, more than one gas l mix is used during the calibration. One mix is predominantly Xe-133 with lower level beta and gamma energies and a second mix which contains a larger variety of longer lived plant gases that more accurately represent the higher beta energy , range. The result of this method of calibration is two separate calibration curves for each monitor. One curve to be used when the isotopic mix being monitored g , is primarily Xe-133 and the other curve is for use when the mix is unknown or is known to contain a mixture of other fission and activation gases. l I Effluent release computer calculations that compute setpoint determinations or expected monitor readings during or prior to a release utilize the correct calibration curves and adjust the monitor setpoint or predicted monitor reading according to the actual nuclide mix. < The cumulative errors associated with the monitor calibration methodology are not accounted for in the determina' tion of the individual monitor setpoints. There is sufficient conservatism built into the selection of the actual monitor setpoint; plus the fact that the monitor fractions used in the setpoint determination equation determine that it would be necessary for all the effluent monitors to be in alarm before the limits of 10CFR Part 20 would be exceeded. O
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P~ OFFSITE DOSE CALCULATION y_ __ ' MANUAL (ODCM) REV: 14 g sSection) Page 51 of 223 5.2 Gaseous Effluent Dose Rate - Comollance with 10CFR2Q Dose rates resulting from the release of noble gases, and radioiodines and particulates must be calculated to show compliance with 10CFR20. The limits of 10CFR20 must be met on an instantaneous basis at the hypothetical worst case location, and apply on a per site basis. Releases made via the shield building vents as a result of routine surveillance tests or scheduled short term maintenance / work activities of 2 hours or less do not require the ! sampling and analysis of shield building vent stack samples described in Table 3.1 for the following reasons:
- a. Shield building effluent particulates and iodines are filtered through a PAC (Particulate Absolute Charcoal) system and the auxiliary building vent normal ventilation has no filtration.
- b. The lower limit of detection limits specified in Table 3.1 can not be obtained on all A the specified nuclides with normal sample flow and a sample duration of less than V 2 hours.
- c. Shield building vent releases are monitored via a noble gas monitor.
- d. Auxiliary building normal ventilation flow is higher than the special ventilation fans that vent via the shield building vent stack.
Therefore, it is conservative to assume that the auxiliary building normal ventilation system would continue to run during the testing / maintenance period. The surveillance test or maintenance / work being performed should be evaluated to ensure the airborne activity in the affected areas will not increase during the evolution. If this evaluation indicates a possible increase in airborne effluents, or radiation monitors or continuous air monitors in the affected buildings indicate higher than normal background airborne activity before the evolution begins, the shield building vent stack sample SHALL be sampled and analyzed as described in Table 3.1. Since Sr-89 and Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly airborne dose calculations and comparisons to quarterly and annual limits should be completed using the most recent available composite sample results. The quarterly dose i '!ue? and critical receptors reported to the USNRC SHALL be calculated using the actual composite results. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 3M' TITLE: NUMBER: y "g g[ y^ w g 'M i ny OFFSITE DOSE CALCULATION H4 REV: 14 g MANUAL (ODCM) Di . Page 52 of 223 5.2.1 Noble Cases To comply with the 10CFR20 dose limit of 100 mrem TEDE to MEMBERS OF THE PUBLIC, the dose rate at the SITE BOUNDARY resulting from noble gas effluents is limited to 500 mrem /yr to the total body and 3000 mrem /yr to the skin. The setpoint determinations discussed in the previous section are based on the dose calculational method presented in NUREG-0133. They represent a backward solution to the limiting dose equations in NUREG-0133. Setting alarm set trip points in this manner will assure that the limits of 10CFR20 are met for noble gas releases. Therefore, no routine dose calculations for noble gases will be needed to show compliance with this part. Routine calculations will be made for doses from noble gas releases to show compliance with 10CFR50, Appendix I as discussed in Section 5.3.1. 5.2.2 Radiciodine. Radioactive Particulates. and Other Radionuclides For compliance with 10CFR20, the dose rate at the SITE BOUNDARY resulting from the release of radiciodines and particulates with half lives greater than 8 & W days is limited to 1500 mrem /yr to any organ. Calculations showing compliance l with this dose rate limit will be performed for BATCH RELEASES prior to the i release and weekly for all releases. To show compliance, Equations 5.2-1 will l be evaluated for I-131,1-133, tritium, and radioactive particulates with half-lives greater than eight days. I Pi (x/Qy) Ovi < 1500 mrem /yr (5.2-1) where: l Pi = child critical organ dose parameter for radionuclide i for the I inhalation pathway, mrem /yr per Cl/m3 (Table 5.3); (x/Qy) = annual average relative concentration for LONG-TERM release at the criticallocation, sec/m3(Appendix A, Table A-3); Qvi = the total release rate of radionuclide i from all vents form both units for the batch or week of interest, Cl/sec; Radiciodines, tritium, and radioactive particulates will be released form up to six individual vents all within 300 feet of each other. For showing compliance with 10CFR20, calculations based on Equation 5.2-1 will be made once per week. The source terms (Ov) will be determined from the results of analysis of vent W i particulate filters and charcoal canisters and vent flow rate. These source terms include all gaseous releases from PINGP.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REY: 14 YN @ Page 53 of 223 Significant short term BATCH RELEASES of long-lived radioactive particulates and tritium will result from containment PURGES. Calculations will be made for these releases separately to further assure compliance with 10CFR Part 20 prior to release. These calculations will be used only to determine whether or not the PURGE release will be allowed to occur. Source terms will be determined from the results of isotopic analyses of samples from containment prior to release. j Equation 5.2.1 will be used in conjunction with the following relationship to demonstrate that the BATCH RELEASE does not exceed the dose rate limit: BL = 1500 -(Dy - Dp) (5.2-2) where: BL = limiting dose rate for the batch, mrem /yr; , Dy = previous week's dose rate from all continuous and batch releases mrem /yr; Dp = previous week's dose rate from all PURGE releases mrem /yr. 5.2.3 Critical Receotor identification Compliance with 10CFR20 radiation dose limits for individual MEMBERS OF THE PUBLIC will be demonstrated by identifying critical receptor locations based on 10CFR50 App I ALARA design objectives. Since the doses associated with 10CFR50 are more restrictive than the 10CFR20 limits, this method satisfies the 10CFR20 requirements. O
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Page 54 of 223 5.3 Gaseous Effluents - Comollance with 10CFR50 1 Doses resulting from the release of noble gases, radioiodines and particulates must be , calculated to show compliance with Appendix I of 10CFR50. The calculations will be i performed monthly for all gaseous effluents. ) The limits of 10CFR50 are on a per reactor unit basis. The GASEOUS RADWASTE I TREATMENT SYSTEM and the auxiliary building at PINGP is shared by both reactor l units making it impossible to separate the releases of the two units. The releases that j can be separated by unit contribute a very small portion of the total gaseous releases l form PINGP. Therefore, for compliance with 10CFR50 the releases from both units will i be summed and the limits of Appendix I will be doubled. Releases made via the shield building vents as a result of routine surveillance tests or I scheduled short term maintenance / work activities of 2 hours or less do not require the sampling and analysis of shield building vent stack samples described in Table 3.1 for the following reasons:
- a. Shield building effluent particulates and lodines are filtered through a PAC (Particulate Absolute Charcoal) system and the auxiliary building vent normal ventilation has no filtration.
- b. The lower limit of detection limits specified in Table 3.1 can not be obtained on all the specified nuclides with normal sample flow and a sample duration of less than 2 hours.
- c. Shield building vent releases are monitored via noble gas monitor,
- d. Auxiliary building normal ventilation flow is higher than the special ventilation fans that vent via the shield building vent stack.
Therefore, it is conservative to assume that the auxiliary building normal ventilation system would continue to run during the testing / maintenance period. The surveillance test or maintenance / work being performed should be evaluated to ensure the airborne activity in the affected areas will not increase during the evolution. If this evaluation indicates a possible increase in airborne eff!uents, or radiation monitors or continuous air monitors in the affected buildings indicate higher than normal background airborne activity before the evolution begins, the shield building vent stack sampled SHALL be sampled and analyzed as described in Table 3.1. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES S TITLE: NUMBER: m , II4
' ]yrus emIg, OFFSITE DOSE CALCULATION s
MANUAL (ODCM) REV: 14 issete.-
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Page 55 of 223 Since Sr-89 and Sr-90 concentrations are determined from composite samples, the pre-release, weekly and monthly airborne dose calculations and comparisons to quarterly and annuallimits should be completed using the most recent available composite sample results. The quarterly dose values and critical receptors reported to the USNRC SHALL be calculated using the actual composite results. 5.3.1 Noble Gas A. Dose Ecuations The air dose at the critical receptor due to noble gases released in gaseous effluents is determined by Equations 5.3-1 and 5.3-2. The critical receptor will be identified es described in Section 5.3.4. For gamma radiation: 3,17 x 10-8 IMi i (x/Q)v Qv i + (x/q)vgiv L) < 10 mrad for any calendar quarter
< 20 mrad for any calendar year (5.3-1)
For beta radiation: 3.17 x 10-8 INi I (x/Q)v Qv i + (x/q)vqiv
< 20 mrad for any calendar quarter
< 40 mrad for any calendar year (5.3-2) where:
Mi = The air dose factor due to gamma emission for each identified noble gas radionuclide i, mrad /yr per Ci/m3;(Table 5.4) Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide i, ' mrad /yr per Ci/m3;(Table 5.4) l i
1 l PRAIRIE CLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY
" ' H PROCEDURES
. TITLE:
NUMBER: e. M '
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OFFSITE DOSE CALCULATION "4 h, MANUAL (ODCM) . ' ' eM $$ REV: 14 Page 56 of 223 (y/Q)y = the annual average relative concentration for areas i at or beyond the restricted area boundary for LONG-TERM vent releases (greater than 500 hr/ year), sec/m3 (Appendix A. Table A-4); (x/q)y = The relative concentration for areas at or beyond the ; restricted area boundary for SHORT-TERM vent releases (equal to or less than 500 hrs / year), sec/m3 i (Appendix A, Table A-7); qiy = The total release of noble gas radionuclide iin gaseous effluents for SHORT-TERM vent releases from both units (equal to or less than 500 hrs / year), Cl; Oy = i the total release of noble gas radionuclide i in gaseous ! effluents for LONG-TERM vent releases from both units { (greater than 500 hrs /yr), Ci; ' 3.17 x 10-8 = the inverse of the number of seconds in a year. Noble gases will be released from PINGP from up to six vents. i LONG-TERM x/O's were given in Appendix A. SHORT-TERM x/q's were calculated using the USNRC computer code "XOODOQ" assuming 100 hours per year SHORT TERM RELEASES and are given in Appendix A (Table A-7). Values of M and N are taken directly from Reg Guide 1.109 and are given in Table 5.4. B. Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits. The monthly results will be added to the doses calculated from the other months in the quarter of interest and the year of interest and compared to the limits given in Section 3.3. If these limits are exceeded, a special report will be submitted to the USNRC. If twice the limits are exceeded, a special report showing compliance with 40CFR190 will be submitted. O
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES MSEM@E @' , h TITLE: NUMBER: r) ~
.EiE 'g i OFFSITE DOSE CALCULATION MANUAL (ODCM) REY: 14
]Sectioni ~ Page 57 of 223 5.3.2 Radiciodine. Particulates. and Other Radionuclides A. Dose Ecuations The worst case dose to an individual from I-131,1-133, tritium, and radioactive particulates with half-lives greater than eight days in gaseous effluents released to UNRESTRICTED AREAS is determined by the following expressions:
During any calendar quarter or year-3.17 x 10-8 II R jaki (5.3-3) Ji WyO i v + wvqiv
< 15 mrem (per quarter)
< 30 mrem (per calendar year) where:
Ov i
= release of radionuclide i for LONG-TERM vent releases from both units (greater than 500 hrs /yr), Ci; giv = release of radionuclide i for SHORT-TERM purge releases l from both units (equal to or less than 500 hrs /yr); Ci; Wy = the dispersion parameter for estimating the dose to an individual at the controlling location for LONG-TERM vent releases (greater than 500 hrs /yr);
wy = the dispersion parameter for estimating the dose to an individual at the controlling location for SHORT-TERM vent releases (equal to or less than 500 hrs /yr); 3.17 x 10-8 = the inverse of the number of seconds in a year; R ijak = the dose factor for each identified radionuclide i, pathway j, age group a, and organ k, m2 mrem /yr per Ci/sec or mrem /yr per Ci/m3. l O '
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY ' H PROCEDURES TITLE: NUMBER: F gjfSecdoni
< 'M A OFFSITE DOSE CALCULATION MANUAL (ODCM)
H4 REV: 14 g Page 58 of 223
)
The above equation will be applied to each combination of age group and organ. Values of R ilak have been calculated using the methodology given in ' NUREG-0133 and are given in Tables 5.5-1 through 5.5-19. Dose factors for isotopes not listed will be determined in accordance with the methodology in Appendix C. Equations 5.3-3 will be applied to a controlling location which will have one or more of the following: residence, vegetable garden and milk animal. The selection of the actual receptor is discussed in Section 5.3.4. The source terms and dispersion parameters in Equation 5.3-3 are obtained in the 3 same manner as in Section 5.2. The W values are in terms l of x/Q(sec/m ) for the inhalation pathways and for tritium (Tables A-4 and ! 2 A-7) and in terms of D/Q(1/m ) for all other pathways (Tables A-5 and A-8). ! B. Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and ' annuallimits. The monthly results should be added to the doses cumulated from the other months in the quarter of interest and in the year of interest and compared with the limits in Section 3.5. If these limits are exceeded, a special report will be submitted to the USNRC. If twice the limits are M W exceeded, a special report showing compliance with 40CFR190 will be submitted. 5.3.3 Projection of Doses Doses resulting from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source terms will be adjusted to reflect this ' information and the justification for the adjustment noted. If the projected release of noble gases for the month exceeds 2 percent of the calendar year . limits of equation 5.3-1 or 5.3-2, additional waste gas treatment will be provided. l If the projected release of I-131,1-133, tritium, and radioactive particulates with half-lives greater than 8 days exceeds 2 percent of the calendar year limit of equation 5.3-3, operation of the ventilation exhaust treatment equipment is l required if not currently in use. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l
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NUMBER:
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- 14 PaDe 59 of 223 i 5.3.4 Critical Receotor Identification For compliance with 10CFR50 App I ALARA design objectives, two critical i receptor locations will be identified to demonstrate compliance with limits on !
dose to air or individual MEMBERS OF THE PUBLIC in unrestricted areas from plant effluents. h For noble gases the critical location will be based on the beta and gamma air doses only. This location will be the offsite location with the highest long term i vent x/O values given in Appendix A, Table A-3. This location will remain the ! i same unless meteorological data is reevaluated or the SITE BOUNDARY
- changes.
The critical location for the 1-131,1-133, tritium, and long-lived particulate ! pathway will be selected once each year. The selection will follow the annual land use census performed within 5 miles of the PINGP. Each of the following locations will be evaluated as potential critical receptors.
- 1. Residence in each sector
- 2. Vegetable garden producing leafy green vegetables
- 3. All identified milk animal locations Following the annual survey, doses will be calculated using Equation 5.3-3 for all new identified receptors and those receptors whose characteristics have !
changed significantly. The calculation willinclude appropriate information about ; each new location. The dispersion parameters given in this manual should be I employed. The total releases reported for the previous calendar year should be used as the source terms. 5.4 References "NSP-Prairie Island Nuclear Generating Plant, Appendix I Analysis - Supplement No.1
- Docket No. 50-282 and 50-306", Table 2.1-4. a i
I
& k i
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 g l tiSection?
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Page 60 of 223 1 I l I l l THIS PAGE IS LEFT INTENTIONALLY BLANK l l
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 4
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H' ~' '> ' MANUAL (ODCM) REV: 14 l Page 61 of 223 l 6.0 TOTAL DOSE FROM RADIOACTIVE RELEASES AND URANIUM FUEL SOURCES SPECIFICATIONS 6.1 In accordance with T.S.6.5.H.10 the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from UR CYCLE sources SHALL be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which SHALL be limited to less than or equal to 75 mrems. APPLICABILITY At all times. ACTION
- a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 2.3.a,2.3.b,3.3.a 3.3.b,3.5.a. or 3.5.b, calculations SHALL be made including direct radiation contributions from the r reactor units (including outside storage tanks) to determine whether the above limits k have been exceeded. If such is the case,in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, a Special Report that includes the following:
- 1. Defines the corrective action (s) to be taken to reduce subsequent releases to prevent reoccurrence of exceeding the above limits.
- 2. Includes the schedule for achieving conformance with the above limits.
- 3. This special report as defined in 10CFR20.2203(a), SHALL include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.
- 4. Describe levels of radiation and concentrations of radioactive materialinvolved, and cause of the exposure levels and concentrations.
- 5. If the estimated dose (s) exceed the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the special report SHALL include a request for a variance in accordance with the provisions of
, 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY j H PROCEDURES PS p u3 2c ' W' TITLE: NUM'BER: H4 A T
. . . .,1 OFFSITE DOSE CALCULATION W )
.f. .
MANUAL (ODCM) REV: 14 5 N) Pace 62 of 223 SURVEILLANCE REQUIREMENTS 6.2 Cumulative dose contributions from liquid and gaseous effluents SHALL be determined in accordance with Surveillance Requirements 2.4,3.4, and 3.6, and in accordance with the methodology and parameters in the ODCM. 6.3 Cumulative dose contributions from direct radiation from the reactor units SHALL be determined. This application is applicable only under conditions set forth in ACTION (a) of Specification 6.1 above.
~t i
1 l l l l O
1 i l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
%RS Mg ' , M, TITLE: NUMBER:
"4 i
O y, WifGg OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14
', # ga Page 63 of 223 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l -
l MONITORING PROGRAM SPECIFICATIONS l l 7.1 In accordance with T.S.6.5.E the Radiological Environmental Monitoring Program l (REMP) SHALL be conducted as specified in Table 7.1. APPLICABILITY At all times. ACTION !
- a. Whenever the Radiological Environmental Monitoring Program is not being conducted as described in Table 7.1 the Annual Radiological Environmental Monitoring Report SHALL include a description of the reasons for not conducting the program as required and the plans for the prevention of a recurrence. l f3 V b. Deviations are permitted from the required sampling schedule if samples are unobtainable due to hazardous conditions, seasonable unavailability, or to malfunctions i of automatic sampling equipment. If the latter occurs, every effort SHALL be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule SHALL be reported in the Annual Radiological Environmental Monitoring Report.
- c. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 7.2 when averaged over any calendar quarter,in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Special Report that includes the following:
- 1. Identifies the cause(s) for exceeding the limit (s).
- 2. Defines the corrective act;ons that have been taken to reduce radioactive effluents I so that the potential annual dose1 to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 2.3,3.3, or 3.5.
O 1 The Methodology and parameters used to estimate the potential annual dose to a member of the public SHALL be indicated in the report.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES fl2 TITLE: NUMBER:
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i_m OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h
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Pace 64 of 223 When more than one of the nuclides in Table 7.2 are detected in the sampling medium, this report SHALL be submitted if: concentration (1) concentrathn (2)
+ +.. 2 1.0 reporting level (1) reporting level (2)
When nuclides other than those in Table 7.2 are detected and are the result of plant effluents, this report SHALL be submitted if the potential annual dose2 to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Specifications 2.3,3.3, or 3.5. This report is not required if the measured level of radioactivity was not the result of plant effluents; however,in uch an event, the condition SHALL be reported and described in the Annual Radiological Environmental Monitoring Report.
- d. Although deviations from the sampling schedule are permitted under Paragraph b.
above, whenever milk or leafy vegetation samples can no longer be obtained from the designated sample locations required by Table 7.1, the Annual Radiological Environmental Monitoring Report SHALL explain why the samples can no longer be obtained and identify the new locations added to and deleted from the monitoring program. SURVEILLANCE REQUIREMENTS 7.2 The radiological environmental monitoring samples SHALL be collected pursuant to Table 7.1 from the specific locations of the radiological environmental monitoring sampling program described in the Radiation Protection implementing Procedure (RPIP) 4700, and SHALL be analyzed pursuant to the requirements of Table 7.1 and the detection capabilities required by Table 7.3. O 2 The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC SHALL be indicated in this report.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
>;LV TITLE: NUMBER:
O LE4W,i' H4 l OFFSITE DOSE CALCULATION - y - REV: 14 MANUAL (ODCM) l Page 65 of 223 i LAND USE CENSUS I SPECIFICATIONS I 7.3 A Land Use Census SHALL be conducted and SHALL identify: l
- a. The location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetation in each of the 16 meteorological sectors within a distance of 5 miles. l
- b. Fields or gardens of greater than 500 fta producing corn that are irrigated with water l taken from the Mississippi River between the plant and a point 5 miles downstream.
APPLICABILITY At all times. ACTION
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose ,
commitment greater than the values currently being calculated in Specification 3.6, in lieu of a Licensee Event Report, identify the new location (s)in the next Annual Radiological Environmental Monitoring Report.
- b. With the Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 7.1, add the new location (s) to the Radiological Environmental Monitoring Program within 30 days. The sampling location (s) excluding the control station location, having a lower calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program. Identify the new location (s) in the next Annual Radiological Environmental Monitoring Report.
- c. If fields or gardens larger than 500 ft2 producing corn are being irrigated with Mississippi River water, appropriate samples SHALL be collected and analyzed per Table 7.1.
,m
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER:
.1 OFFSITE DOSE CALCULATION h, bl_ MANUAL (ODCM) REV: 14 Pace 66 of 223 SURVElLLANCE REQUIREMENTS 7.4 The Land Use Census SHALL be conducted at least once per 12 months between the dates of May 1 and October 31 by door to door survey, aerial survey, or by consulting local agricultural authorities or associations. A summary of the results of the land use census SHALL be included in the Annual Radiological Environmental Monitoring .
Report. l INTERLABORATORY COMPARISON PROGRAM SPECIFICATIONS 7.5 An analysis SHALL be performed on radioactive materials, supplied by an NRC l approved crosscheck program. This program involves the analyses of samples provided by a control laboratory as well as with other laboratories which receive portions of the same samples. Media used in this program (air, milk, water, etc.) SHALL be limited to those found in the radiation environmental monitoring program. g APPLICABILITY l At all times. ACTION
- a. When required analyses are not performed, corrective action SHALL be reported in the i Annual Radiological Environmental Monitoring Report.
l 1 SURVElLLANCE REQUIREMENTS 7.6 The summary results of analyses performed as part of the above required Interlaboratory Comparison Program SHALL be included in tha Annual Radiological i Environmental Monitoring Report. ' i O
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l PRAIRIE ISLAND NUCLEAR GENERATING PLANT j NORTHERN STATES POWER COMPANY H PROCEDURES j ,! l'lf r/<f wm s ; >'?V ym, % TITLE: NUMBER: P? W OFFSITE DOSE CALCULATION 94 ! 'M 2, jY MANUAL (ODCM) REY: 14 f ; SGCHon^ (p ' Page 67 of 223 l 8.0 REPORTING REQUIREMENTS 1 8.1 Annual Rad!ometive Effluent Renort in accordance with T.S.6.7.A.4 the Annual Radioactive Effluent Report covering the operation of the units SHALL be submitted in accordance with 10CFR50.36A and j SHALL include: i a.- The Annual Radioactive Effluent Report covering the operation of the plant during l the previous calendar year SHALL be submitted by May 15 of each calendar year j to the Administrator of the appropriate Regional NRC office or designee. i b. The Annual Radioactive Effluent Report SHALL include a summary of the quantities of radioactive liquid and gaseous effluents released from the plant as outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June,1974, with data summarized on a quarterly basis, in the event that some results are not available I for inclusion with the report, the report SHALL be submitted noting and explaining j the reasons for the missing results. The missing data SHALL be submitted as ; ( soon as possible in a supplementary report. )
- c. The Annual Radioactive Effluent Report SHALL include an assessment of the radiation doses from radioactive effluents released from the plant during the previous calendar year. The report SHALL also include an assessment of the radiation doses from radioactive liquids and gaseous effluents to individuals due to their activities inside the SITE BOUNDARY (Figures 3.1 and 3.2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) SHALL be included in the report.
- d. The Annual Radioactive Effluent Report SHALL include the following information l for solid waste shipped offsite during the report period.
- 1. Container volume,
- 2. Total curie quantity (specify whether determined by measurement or estimate),
- 3. Principal radionuclides (specify whether determined by measurement or estimate),
- 4. Type of waste (e.g., spent resin, compacted dry waste, evaporated bottoms),
- 5. Type of container (e.g., LSA, Type A, Type B, Large Quantity), and
- 6. Solidification agent (e.g., cement, urea formaldehyde).
- e. The Annual Radioactive Effluent Report SHALL include ABNORMAL RELEASES O from the site of radioactive materials in gaseous and liquid effluents on a quarterly basis.
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT i NORTHERN STATES POWER COMPANY H PROCEDURES I TITLE: NUMBER:
' li _,
^
OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h Pace 68 of 223
- f. If the calculated dose from the release of radioactive materials in liquid or gaseous I effluents exceeds twice the limits of 10 CFR 50, Appendix I, the Annual Radioactive Effluent Report SHALL also include an assessment of radiation doses to the most i
likely exposed MEMBER OF THE GENERAL PUBLIC from reactor releases and l ~ other nearby uranium fuel cycle sources (including doses from primary effluent l pathways and direct radiation) for the previous 12 consecutive months to show compliance with 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operation,
- g. The Annual Radioactive Effluent Report SHALL include a description (including cause, response and prevention of reoccurrence) of occurrences when the sampling frequency, minimum analysis frequency, or lower limit of detection requirements specified in Tables 2.1 and 3.1 were exceeded.
- h. The Annual Radioactive Effluent Report SHALL include a description of occurrences when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable as required in Tables 2.2 and 3.2.
- i. The Annual Radioactive Effluent Report SHALL include a description of the circumstances which caused the failure to complete the minimum sample and/or analysis frequency required by Tables 2.1 and 3.1. The report SHALL include the actions taken to restore the sampler, actions taken to prevent recurrence, and a summary of the occurrences effect on the analysis validity.
J. The Annual Radioactive Effluent Report SHALL include a description of the circumstances which result in LLD's higher than those listed in Tables 2.1 and 3.1.
- k. The Annual Radioactive Effluent Report SHALL include an assessment of the radiation doses from radioactive effluents released from the ISFSI during the previous calendar year.
- l. Licensee initiated changes to the ODCM SHALL be submitted to the NRC in the form of a complete legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the report in which the change in the ODCM was made. Each change SHALL be identified by markings in the margin of the affected pages clearly indicating the area of the page that was changed. The date (i.e., month and year) of the change SHALL be clearly indicated on the Record of Revisions page.
- m. The Annual Radioactive Effluent Report SHALL include description of changes to the Process Control Program.
.. ~..~...- _ . - ._- - - - - - . ....._- . - - - -._.-- - _ _ __ - _
! PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l 4 Plm ; y s ,M,Q P TITLE: NUMBER: : !O ;EWhF i t?' , OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 { l
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8.2 Annual Radiological Environmental Monitorina Renort i in accordance with T.S.6.7.C.1 the Annual Radiological Environmental Monitoring
- Report covering the operation of the offsite monitoring program SHALL include
j a. The Annual Radiological Environmental Monitoring Report covering the operation ; j of the plant during the previous calendar year SHALL be submitted by May 15 of ; i each year to the Administrator of the appropriate Regional NRC office or his ; designee. l
~
! b. The Annual Radiological Environmental Monitoring Report SHALL include i summarized and tabulated results in the format of Regulatory Guide 4.8, ,
- December 1975 of all radiological environmental samples taken during the report i period. In the event that some results are not available for inclusion with the report, i the report SHALL be submitted noting and explaining the reasons for the missing i results. The missing data SHALL be submitted as soon as possible in a ;
i supplementary report. -
- c. The Annual Radiological Environmental Monitoring Report SHALL include
- summaries, interpretations, and an analysis of trends of the radiological !
l environmental surveillance activities for the report period, including a comparicon ; with preoperational studies, operational controls (as appropriate), and previous ! environmental surveillance reports and an assessment of the observed impacts of j the plant opeistion on the environment. The report SHALL also include a summary i of the results of the land use census. If harmful effects or evidence of irreversible damage are detecMd by the monitoring, the report SHALL provide an analysis of the problem and a plan..ad course of action to alleviate the problem. 1
- d. The Annual Radiological Environmental Monitoring Report SHALL also include the following: a summary description of the radiological environmental monitoring program; a map of sampling locations within a distance of five miles keyed to a table giving distances and directions from the reactor; and the results of licensee participation in the Interlaboratory Comparison Program.
- e. The Annual Radiological Environmental Monitoring Report SHALL include reasons i for all deviations from the REMP sampling program as specified in Table 7.1 and plans for the prevention of a recurrence,if applicable.
I
- f. The Annual Radiological Environmental Monitoring Report SHALL contain a p
description of when and why milk or leafy vegetable samples specified in Table 7.1 l cannot be obtained from the designated sample locations, and identify the new l locations added to and deleted from the monitoring program.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES m . 4 TITLE: NUMBER: e a H4 & e OFFSITE DOSE CALCULATION W ga , - lSection} [ P MANUAL (ODCM) REV: 14 Pace 70 of 223
- g. If the level of radioactivity in an environmental sampling medium at a specified location exceeds the reporting levels of Table 7.2 for the sample type specified in Table 7.1 and is NOT the results of plant effluents, the condition SHALL be reported in the Annual Radiological Environmental Monitoring Report.
- h. A summary of the Interlaboratory Comparison Program SHALL be included in the Annual Radiological Environmental Monitoring Report. If the required Interlaboratory Comparison Program analyses are NOT performed, corrective action SHALL be reported in the Annual Radiological Environmental Monitoring Report
- i. The Annual Radiological Environmental Monitoring Report SHALL NOTinclude the Complete Analysis Data Tables. These contain the results of each sampla analysis and SHALL be maintained by the licensee.
8.3 Annual Summarv of Meteoroloalcal Data An annual summary of meteorological data SHALL be submitted, at the request of the Commission, for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. 8.4 Record Retention ,
- a. Records retained for Five Years:
- 1. Periodic checks, inspections, tests and calibrations of components and systems as related to the specifications and treatment systems defined in the ODCM.
- 2. Records of wind speed and direction,
- b. The following records SHALL be retained for the Life of the Plant:
- 1. Liquid and airborne radioactive releases to the environment.
- 2. Off-site environmental monitoring surveys.
- 3. Records of reviews performed for changes made to the Offsite Dose Calculation Manual.
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT j NORTHERN STATES POWER COMPANY H PROCEDURES l f@{ y@ l TITLE: NUMBER: i H4 lO @WS j Y+,e T M' t -
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1 J oresire ooSE CALCULATION MANUAL (ODCM) REV: 14 Page 71 of 223 l ' ) BASES i ) 2.0 LIQUID EFFLUENTS i j 2.1/2.2 CONCENTRATION ! This control is provided to ensure that 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 10CFR20, Appendix B, Table 11, Column 2. ! This limitation provides additional assurance that the levels of radioactive materials in j bodies of water outside the site will not result in exposures exceeding (1) the , Section ll.A design objectives of Appendix I,10CFR Part 50, and (2) the limits of
- 10CFR Part 20.1301(a)(1). The. concentration limit for dissolved or entrained noble i gases is based upon the assumption that Xe-135 is the controlling radioisotope and its j MPC in air (submersion) was converted to an equivalent concentration in water using j the methods described in International Commission on Radiological Protection (ICRP) d Publication 2.
lv This control applies to the releases of radioactive materials in liquid effluents from all units at the site. l j Secondary condenser drains were not included in the routine sampling requirements of Table 2.1. Operating experience has shown that the condenser activity during plant transients normally consists of very low levels of tritium. _ Condensers are normally only j released directly to the environment during plant startups and shutdowns and these ! volumes combined with the low levels of activity are insignificant when compared to the l waste tank activities. Condenser releases should be sampled and analyzed during a significant plant event (i.e. steam generator tube rupture, or steam dump to the condenser with a primary to secondary leak >725 gpd). l l j 2.3/2.4 DOSE i ! Provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix I, i 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth l In Section ll.A of Appendix I. The ACTION statements provide operating flexibility and l at the same time implement the guides set forth in Section IV.A of Appendix I to assure j that the releases of radioactive material in liquid effluents will be kept "as low as is
.. reasonably achievable". Considering that the nearest drinking water supply using the
! river for drinking water is more than 300 miles downstream, there is reasonable ! assurance that the operation of the facility will not result in radioactive concentrations in j' the drinking water that are in excess of the 40CFR141 requirements. i [ i i
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j
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[S5blotN . 5 p yg j 2.5/2.6 LIQUID RADWASTE TREATMENT SYSTEMS
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Provides assurance that the liquid radwaste treatment system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents be kept "as low as reasonably achievable". This controlimplements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10CFR Part 50 and the design objective given in Section ll.D of Appendix I to 10CFR Part 50. The limits governing the use of appropriate portions of the liquid radwaste system were specified as a suitable fraction of the guide set forth in Section ll.A of Appendix I,10CFR Part 50, for liquid effluents. 4 The liquid radwaste treatment system is shared by both units. It is not practical to determine the contribution from each unit to liquid radwaste releases. For this reason, liquid radwaste releases will be allocated equally to each unit. 2.7/2.8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION g The radioactive liquid effluent monitoring instrumentation is provided to monitor and . control, as applicable, the releases of radioactive materials in liquid effluents during l actual or potential releases of liquid effluents. The Alarm / Trip Setpoint for these l instruments SHALL be calculated and adjusted in accordance with the methodologies and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10CFR Part 50. 2.9/2.10 LIQUID STORAGE TANKS Restricting the quantities of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the contents of the tank, the resulting concentrations would be less than the limits of 10CFR ~Part 20, Appendix B, Table 11, Column 2,in an UNRESTRICTED AREA. O
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i PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY H PROCEDUPES _ i i TITLE: NUMBER:
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p 73 g3 3.0 GASEOUS EFFLUENTS 3.1/3.2 DOSE RATE i This controlis provided to ensure that the dose rate at any time at the SITE i BOUNDARY from gaseous effluents from all units on the site will be within the annual 2 dose limits of 10CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are i the doses associated with the concentrations of 10CFR 20, Appendix B, Table 11, Column 1. These limits provide reasonable assurance that the radioactive material
- discharged in gaseous effluents will not result in the exposure of an individual in an
- UNRESTRICTED AREA to annual average concentrations exceeding limits specified in Appendix B, Table ll of 10CFR Part 20. For individuals who may at times be within the l 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 release rate limits restrict, at all times, the corresponding i gamma and beta dose rates above background to an individual at or beyond the SITE
! BOUNDARY to less than or equal to 500 mrem / year to the total body or to less than or i equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to less than or equal to j 1500 mrem / year at or beyond the SITE BOUNDARY. This control applies to the release of radioactive materials in gaseous effluent from all units at the site. l 3.3/3.4 DOSE FROM NOBLE GAS i l This control is provided to implement the requirements of Sections 11.B, Ill.A and IV.A of Appendix I,10CFR Part 50. The Limiting Conditions for Operation implement the j guides set forth in Section ll.B of Appendix I. The ACTION statement provides the
- required operating flexibility and at the same time implements the guides set forth in ,
j Section IV.A of Appendix I to assure that the release of radioactive material in gaseous j effluents will be kept "as low as reasonably achievable". i ! ? s, [O
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY l H PROCEDURES I TITLE: NUMBER: !
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Pace 74 of 223 3.5/3.6 DOSE FROM IODINE 131. IODINE 133. TRITIUM & PARTICUL ATES Implements the requirements of Section ll.C, Ill.A and IV.A of Appendix I, 10CFR Part 50. The Limiting Conditions for Operation are the guides set forth in I Section ll.C of Appendix I. The ACTIONS statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonable achievable". The release rate specifications for 1-131, 1-133, tritium and radioactive particulates with half-lives greater than eight days are - dependent on the existing radionuclide pathways to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA, using child dose conversion factors. The pathways which are examined in the development of these calculations are: 1)individualinhalation of l airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with l subsequent consumption by man, 3) deposition onto grassy areas where milk animals j and meat producing animals graze with consumption of the milk and meat by man, and
- 4) deposition on the ground with subsequent exposure of man.
3.7/3.8 GASEOUS RADWASTE TREATMENT SYSTEMS 'g l This control provides assurance that the Waste Gas Treatment System and the l VENTILATION EXHAUST TREATMENT SYSTEMS will be available for use whenever I gaseous wastes are released to the environment. The requirement that the appropriate portions of the Waste Gas Treatment System be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10CFR 50.36a, General Design Criterion 60 of Appendix A to l 10CFR Part 50, and the design objective given in Section ll.D of Appendix I to l 10CFR Part 50. The specified limits governing the use of appropriate portions of the I systems were specified as a suitable fraction of the guide set forth in Sections ll.B and ll.C of Appendix I,10CFR Part 50, for gaseous effluents. J The Waste Gas Treatment System, containment purge release vent, and spent fuel pool are shared by both units. Experience has also shown that contributions from both units are released from each auxiliary building vent. For these reasons,it is not , practical to allocate releases to a specific unit. All releases will be allocated equally in determining conformance to the design objectives of 10CFR Part 50, Appendix I. Restricting the quantities of radioactivity which can be stored in one decay tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at the nearest EXCLUSION AREA BOUNDARY will not exceed 0.5 rem. g
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY H PROCEDURES j 1: G , , ,' .,4'.)v'
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s sectionf ' page 75 of 223 i j The cooling towers at Prairie Island are located to the south of the plant and are within i j 500 to 2000 feet from the point of release. At low wind velocities (below 10 mph) the l l l gaseous activity released from the gaseous radwaste system could be at or near ) { ground level near the cooling towers and remain long enough to be drawn into the l j circulating water in the tower. This control minimizes the possibility of releases of gaseous effluents from entering the river from cooling tower scrubbing. l ) 3.9/3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION , To ensure the concentration of potentially explosive gas mixtures contained in the ! waste gas treatment system is maintained below the flammability limits of hydrogen and i oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. Maintaining the concentrations below the flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10CFR Part 50. The waste gas treatment system is a pressurized system with two potential sources of O- oxygen: 1) oxygen added for recombiner operation, and 2) placing tanks vented for l maintenance back on the system. The system is operated with flow through the l recombiners and with excess hydrogen in the system. By verifying that oxygen is less than or equal to 2% at the recombiner outlet, there will be no explosive mixtures in the system. Waste gas system oxygen is monitored by the two recombiner oxygen analyzers and the 121 gas analyzer. The 121 gas analyzer only monitors the low level loop of the waste gas system. If the required gas analyzers are not operable, tha oxygen to the recombiner will be isolated to prevent oxygen from entering the system from this source. Tanks that may undergo maintenance are normally purged with nitrogen before placing them in service to eliminate this as a source of oxygen, 3.11/3.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoint for these instruments SHALL be calculated and adjusted in accordance with the methodologies and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A to 10CFR Part 50. 4 i j j i _ _ _
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHEftN STATES POWER COMPANY H PROCEDURES
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Paae 76 of 223 6.0 TOTAL DOSE This controlis provided to meet the dose limitations of 10CFR Part 190 that have been incorporated into 10CFR 20 b/ FR 18525. The control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the j whole body or to any organ, except the thyroid, which SHALL be limited to less than or ; equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40CFR Part 190 if the indi /idual reactors remain within twice the dose design objectives i of Appendix I, and if direct radiation doses from the units (including outside storage j tanks, etc.) are kept small. The Special Report will describe a course of action that l should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to : within 40CFR Part 190 limits. For the purposes of the Special Report,it may be I assumed that the dose commitment to the 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 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the g requirements of 40CFR Part 190, the Special Report with a request for a variance w , (provided the release conditions resulting in violation of 40CFR Part 190 have not ' already been corrected),in accordance with the provisions of 40CFR 190.11 & 10CFR 20.405c,is considered to be a timely request and fulfills the requirements of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190, and dose not apply in any way to the other requirements for dose limitation of 10CFR Part 20, as addressed in Specification 2.1 and 3.1. An individualis not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. l i 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 7.1/7.2 MONITORING PROGRAM 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 plant operation. This program thereby i supplements the radiological effluent monitoring by verifying that the measurable l
concentrations of radioactive materials and levels are not higher than expected in the l bases of the effluent measurements and modeling of the environmental exposure ! pathways. l The detection capabilities required by Table 7.1 are state-of-the art for routine environmental measurements in industrial laboratories and the LLDs for drinking water
- meet the requirement of 40CFR Part 141.
l l l l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT ! NORTHERN STATES POWER COMPANY H PROCEDURES 1 x ? '"1 ,,t<G^, TITLE: NUMBER: ' m g4 d '::v. a r e g%:
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i 7.3/7.4 LAND USE CENSUS l This controlis provided to ensure that changes in the use of off site areas are identified and that modifications to the monitoring program are made if required by the results of - the census. The best survay information from door-to-door, aerial or consulting with local agricultural authorities SHALL be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR 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 1 minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in l Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden ! I size, the following assumptions were used: 1) that 20% of the garden was used for growing broad laaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yie'd of 2 kg/ square meter. 1 7.5/7.6 INTERLABORATORY COMPARISON PROGRAM e The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. l O
_ - ~ . - . . - . _ . . _ , _ _ _ _ - PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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i OFFSITE DOSE CALCULATION MANUAL (ODCM) REY:14 4 b1,g { } 7 1d ' Page 79 of 223 . l , TABLE 1.1 - OPERATIONAL MODES 1 i REACTOR
% RATED AVERAGE VESSEL HEAD 1
REACTIVITY THERMAL COOLANT CLOSURE BOLTS MODE TITLE CONDITION POWER TEMPERATURE FULLY TENSIONED q 1 POWER OPERATION Critical >2% NA YES 4 2 HOT STANDBY" Critical s2% NA YES 3 HOT SHUTDOWN" Subcritical NA 2 350*F YES 4 INTERMEDIATE Subcritical NA < 350*F YES l SHUTDOWN" 2 200*F ! } 5 COLD SHUTDOWN Subcritical NA < 200*F YES I 6 REFUELING NA* NA NA NO 1 i
- /*
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- l Boron concentration of the reactor coolant system and the refueling cavity sufficient to ensure that the j more restrictive of the following conditions is met:
- a. Ken d 0.95, or j b. Boron concentration 2 2000 ppm.
Prairie Island specific MODF 'dte, not consistent with Standard Technical Specification MODE titles, q MODE numbers are con:hicin whh Standard Technical Specification MODE numbers. i j
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES F OWER COMPANY H PROCEDURES
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' I' MANUAL (ODCM) REY: 14 Page 81 of 223 :
2 TABLE 2.1 - , 7 Uquid Relemas Wpawn f@j; Sampling;j , ' Minimump . ' Type of Activityf Lowertimitofn M M' M dN :
- 3 h![NI!3'hN*$$$s$f&$$$W $P ' 'w k ' $,,' ; 5 Frequency
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Batch Releases 9: Each Batch Each Batch Principal Gamma 5 x 10-7 Waste Tanks (Prior to (Prior to Emitterse , Release) Release) 1-131 1 x 10-6 One Batch One Batch Dissolved and 1 x 10-5 Each Month Each Month Entrained Gases Each Batch Monthly H-3 1 x 10-5 Composite d Gross alpha 1 x 10-7 Each Batch Quarterly Sr-89, Sr-90 5 x 10-8 Compositeb Fe-55 1 x 10-6 Continuous Release': Continuousj,h,k Weekly Principal Gamma 5 x 10-7 Turbine Building Compositef Emitterso Sumps 1-131 1 x 10 Weekly Grab Each Sample Dissolved and 1 x 10-5 Sample Entrained Gases Continuousj,k Monthly H-3 1 x 10-5 Compositef Gross Alpha 1 x 10-7 Continuousj,k Quarterly Sr-89, Sr-90 5 x 10-8 Compositef Fe-55 1 x 10-6 Continuous Release *: Weekly Grab Each Sample Principal Gamma 5 x 10-7 Steam Generator Sample During Compositeb Emitterse Blowdown Releasesi 1-131 1 x 10-6 Grab Sample Each Sample Dissolved and 1 x 10-5 Each Month Entrained Gases During Releases Weekly Grab Monthly H-3 1 x 10-5 Sample During Composite d Releasesi Gross Alpha 1 x 10-7 Weekly Grab Quarterly Sr-89, Sr-90 5 x 10-e Sample During Compositeb Releasesi Fe-55 1 x 10-6
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ' H PROCEDURES
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*isectiong Pace 82 of 223 TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
[ CONT'D] TABLE NOTATIONS
- a. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will de detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation: LLD = 4.66ss E V . 2.22 x 10 6 Y exp (-AAT) where: LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume), g i sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), l l , E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), i 2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec-1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V, Y, and At should be used in the calculation, it should be recognized that the LLD is defined as an a 911QIl (before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the g fact) limit for a particular measurement.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES A' f TITLE: NUMBER: O a-
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H,2 ,u OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 l Page 83 of 223 TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM [ CONT'D] TABLE NOTATIONS [ CONT'D] '
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharge and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only the nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with i the above nuclides, SHALL also be identified and reported. '
- d. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than l required, the reasons SHALL be documented in the Annual Radioactive Effluent Report.
s
- e. A CONTINUOUS RELEASE is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume of system that has an input flow during the continuous release.
- f. To be representative of the quantitiet s nd concentrations of radioactive materials in liquid effluents, samples SHALL be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite SHALL be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- g. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch SHALL be isolated, and then thoroughly mixed to assure representative sampling.
- h. Daily grab samples from the turbine building sumps SHALL be collected and analyzed for principal gamma emitters, including 1-131, whenever primary to secondary leakage exceeds 150 gpd in any steam generator. This sampling is provided in lieu of continuous monitoring with automatic isolation.
- i. Grab samples SHALL be collected at least once per 12 hours when steam generator blowdown releases are being made and the specific activity of the secondary coolant is p 20.01 Ci/ gram DOSE EQUlVALENT l-131 or primary to secondary leakage exceeds
'd 150 gpd.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: i.AxHs (Sectlo@ Ud OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 W Pee M M 223 TABLE 2.1 -RADIOACTIVE LIQUID WASTE SAMPL,1NG AND ANALYSIS PROGRAM [ CONT'D] TABLE NOTATIONS [ CONT'D] J. A continuous sample is one in which the sampling media is in place at all times during the release period, with the exception of periods necessary to change sampling media and scheduled short term equipment maintenance. If the sample media is not in place during the entire release period, an explanation of the occurrence, actions taken to restore the sampler and to prevent recurrence, and a summary description to explain the occurrence's effect on the analysis validity SHALL be included in the Annual Radioactive Effluent Report.
- k. Continuous samples of the Turbine B'uilding Sumps are collected via on line composite samplers. These samplers function on timers and collect a predetermined volume of effluent whenever the TBS pumps are in operation. Samples from these compositors are collected daily and saved for the preparation of a weekly composite prepared utilizing volumes proportional to the sample volumes collected daily by the compositor. If the use of a submersible pump is necessary to maintain sump level, that pump should be g-positioned above the normal TBS pump controlling level and include a timer to allow the calculation of the additional release volume.
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. 9 i Page 85 of 223 i TABLE 2.2 - RADIOACTIVE LlOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM , CHANNELS l lNSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. Gross Radioactivity Monitors Providing 4 Automatic Termination of Release
- a. Liquid RadwasteEffluent Line 1 During releases 1 l 1
- b. Steam Generator Blowdown 1/ Unit During releases 2 Effluent Line
- 2. Flow Rate Measurement Devices l a. Liquid RadwasteEffluent Line 1 During releases 4 I requiring throttling of flow
- b. Steam Generator Blowdown Flow 1/ Gen During releases 4 1
- 3. Continuous Composite Samplers
- a. Each Turbine Building Sump 1/ Unit During releases 3 l Effluent Line J
l
- 4. Discharge Canal Monitor 1 At all times 6
- 5. Tank Level Monitor l
- a. Condensate Storage Tanks 1/ Unit When tanks are 5 in use
- b. Temporary Outdoor Tanks Holding 1/ Tank When tanks are 5 Radioactive Liquid in use
- 6. Discharge Canal Flow System (Daily NA At all times O determination and following changes in flow)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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Page 86 of 223 TABLE 2.2 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I_ CONT'D_1 TABLE NOTATIONS i ACTION 1 With the number of channels Operable less than required by the Minimum Channels Operable requirement, effluent releases may continue for up to 14 days provided that prior to each release:
- a. At least two independent samples are analyzed in accordance with Specification 2.2.1, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 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 Ci/ gram:
- 1. At least once per 12 hours when the specific activity of the secondary coolant is 20.01 Ci/ gram DOSE EQUIVALENT l-131, or
- 2. At least once per 24 hours when the specific activity of the secondary coolant is <0.01 Ci/ gram DOSE EQUIVALENT l-131.
ACTION 3 With the numbers 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 12 hours, grab samples are collected and saved for weekly composition and analysis in accordance with Table 2.1. ACTION 4 With the number of channeis 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 hours during actual releases. Pump curves may be used to estimate flow. ACTION 5 With the number of channels Operable less than required by the Minimum Channels Operable requirement, liquid additions to the tank may continue for up to 30 days provided the tank liquid level is estimated during all liquid additions. ACTION 6 With the numbers of channels Operable less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may h continue for up to 30 days provided that, at least once per 12 hours, grab samples are collected and analyzed for gamma emitters.
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l @ % TITLE: NUMBER: H4
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'* Page 87 0f 223 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS I 1
l l l * , gg en !!CHANNEuy ?., SOURCE) j FUNCTIONAL 9 Es j;g.. . ,. .. ,.2_. ,.. ' l 4
~s ...m...x- M r.JCH.ECK Q ,1CHECM s,..jTES R x iC R i.ALIBRATION.1; )
llristrumenti { (Frequency (4)1 iFrequency)i!l iLFrequencyjj Frequencyj l Liquid Radwaste Effluent Daily during Prior to each Quarterly (1) At least once every Line Gross Radioactivity releases release 18 months (3) Monitor Liquid Radwaste Effluent Daily during At least once every Line Flow Instrument releases 18 months Steam Generator Blowdown Daily during Monthly Quarterly (1) At least once every Gross Radioactivity Monitors releases 18 months (3) Steam Generator Blowdown Daily during At least once every Flow releases 18 months
/Q Turbine Building Sump Daily during V Continuous Composite releases Samplers (Includes sample volume check)
Discharge Canal Monitor Daily during Monthly Quarterly (2) At least once every releases 18 months (3) Discharge Canal Daily during At least once every Flow Instruments releases 18 months Condensate Storage Tank Daily Quarterly At least once every Level Monitors 18 months Level Monitors for Daily when in use Quarterly when At least once every Temporary Outdoor Tanks in use 18 months when in Holding Radioactive Liquid use l l V ; 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TRLE: NUMBER: I h
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OFFSITE DOSE CALCULATION _. _. _ M MANUAL (ODCM) REV: 14 Pace 88 of 223 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS [ CONT'D] TABLE NOTATIONS i
- 1. The CHANNEL FUNCTIONAL TEST SHALL also demonstrate that automatic isolation of l this pathway and control room annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
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- b. Circuit failure (if provided).
- c. Instrument indicates a downscale failure (if provided).
- d. Instrument controls not set in operate mode (if provided).
- 2. The CHANNEL FUNCTIONAL TEST SHALL also demonstrate that alarm annunciation occurs if any of the following conditions exists:
g
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure (if provided).
- c. Instrument indicates a downscale failure (if provided).
- d. Instrument controls not set in operate mode (if provided).
- 3. The initial CHANNEL CALIBRATION SHALL be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using sources traceable to NIST standards. These standards SHALL permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATIONS, sources that have been related to the initial calibration SHALL be used.
- 4. The CHANNEL CHECK SHALL consist of verifying indication of flow during periods of release. A CHANNEL CHECK SHALL be made at least once daily on any day on which continuous, periodic, or batch releases are made.
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES y -
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R2 , MANUAL (ODCM) REV: 14
%s . v usect. io. n"i "
Page 89 of 223 TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous..ReleaseTypejj _ / JS.amplingit (Minimum; iType of Activity Lower. Limit **Ji e ,
, y X Fquenc'g" As i (Wggf DWisi 3* 7%' ' ~sisT ^ fofnDetectioni
(:(Freq'uencp] ((LLD)( Cl/ml)j CONTINUOUS RELEASE Weekly b i Weekly Principal Gamma 1 x 10-4 Points: Gas Grab Sample Emitters
- g, i, h Weekly c l-131,1-133 1 x 10-12 Phnt Vents: Continuous Charcoal Sample Unit 1 Aux Bldg. 9 8. h Weekly c Principal Gamma 1 x 10-11 Unit 2 Aux Bldg. Continuous Particulate Emitters
- Radwaste Bldg. Sample Spent Fuel Pool g,i,h Monthly H-3 1 x 10-6 Unit 1 Shield Bldg. Continuous Silica Gel Unit 2 Shield Bldg. Sample g,i,h Monthly d Gross Alpha 1 x 10-11 Continuous Particulate Composite g, e, h Quarterly d Sr-89, Sr-90 1 x 10-11 Continuous Particulate Composite 9 Noble Gas Noble Gases, 1 x 10-4 Continuous Monitor Gross beta and gamma Atmospheric Steam Daily 1 Releases k Grab Sample Each Principal Gamma During Release Sample Emitters
- 5 x 10-7 l-131,1-133 1 x 10-6 l
Daily i Grab Sample Monthly I During Release Composite H-3 1 x 10-5 Gross Alpha 1 x 10-7 Daily i Quarterly 8 Sr-89, Sr-90 5 x 10-8 Grab Sample Composite During Release O
I l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
> 0% s TITLE: NUMBER: i
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H4 & ; W OFFSITE DOSE CALCULATION 9EW i Sect.i.o...n. ~s , MANUAL (ODCM) REV: 14 I 4 Paos 90 of 223 TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 1 JCONT'D1 1 Gaseous Release Typej u jSamplingigj 1 Minimum # Type of Activity; Lower Limit *@ TFrequencp? JAnalysis)p L " +Ahalp" sis 11~ fof.Detectioni!
* *. ^ ~ ~
j Frequency! f(LLD)( Cl/ml)? m Gas Grab Sample Each Principal Gamma 1 x 10-4 Containment Purge Prior to each Purge Sample Emitters
- i (Prior to Release)
Grab 9 h, m Each H-3 1 x 10-6 Prior to Release Sample , and Continuous l Grab g.h, m Charcoal 1-131,1-133 1 x 10-12 Prior to Release Sample 1 1 and Continuous Grab g, h, m Particulate Principal Gamma 1 x 10-11 Prior to Release Sample Emitters
- and Continuous l Grab 9. h, m Monthly d Gross Alpha 1 x 10-11 Prior to Release Particulate and Continuous Composite Grab g, h, m Quarterly d Sr-89, Sr-90 1 x 10-11 Prior to Release Particulate and Continuous Composite Waste Gas Gas Grab Sample Each Principal Gamma 1 x 104 Storage Tanks Prior to each Sample Emitters
- Release (Prior to Release)
Grab Sample Each H-3 1 x 10-6 Prior to each Sample Release (Prior to Release) g O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 9Ag . , TITLE: NUMBER: (] , ?Mi Cj" j m OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 l g iSectionj I Page 91 of 223 ! TABLE 3.1 -RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ! [ CONT'D] TABLE NOTATIONS 4
- a. The LLD is defined, for purposes of these controls, as the smallest concentration of !
radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 sb i LLD = E V 2.22 x 10s . y . exp (- AAt) l where: l LLD = the "a priori" lower limit of detection (microcurie per unit mass or volume. l] sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute). E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22 x 106 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, , 1 A = the radioactive decay constant for the particular radionuclide (sec-1), and At = the elapsed time between the midpoint of sample collection and i the time of counting (sec). Typical values of E, V, Y, and At should be used in the calculation. it should be recognized that the LLD is defined as an a Dios (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: y t OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h m iSe$_lon$ ' - Pace 92 of 223 l TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ICONT'D] TABLE NOTATIONS [ cont'd1
- b. Grab samples taken at the ventilation exhausts are generally below minimum detectable levels for most nuclides with existing analytical equipment. If this is the case, PWR GALE Code noble gas isotopic ratios may be assumed. j
- c. With >1 Ci/gm DOSE EQUIVALENT l-131 in either Unit 1 or Unit 2 reactor coolant system, the iodine and particulate collection devices for all release points SHALL be removed and analyzed daily untilit is shown that a pattern exists which can be used to predict the release rate. Sampling may then revert to weekly. When samples collected for one day are analyzed, the corresponding LLD's may be increased by a factor of 10.
Samples SHALL be analyzed within 48 hours after removal.
- d. To be representative of the average quantities and concentrations of radioactive materials in particulate form in gaseous effluents, samples should be collected in proportion to the -
rate of flow of the effluent streams,
- e. The principal gamma emitters for which the LLD control applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas analysis and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 in lodine and particulate analysis. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, SHALL also be detected and reported.
- f. Nuclides which are below the LLD for analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than reported, the reasons SHALL be documented in the Annual Radioactive Effluent Report.
- g. For continuous samples, the ratio of the sample flow rate to the samples stream flow rate SHALL be known for the time period sampled (Conservative assumptions may be used).
Design flow rates may be used for building exhaust vent flow rates.
- h. A continuous sample is one in which the sampling media is in place at all times during the i release period, with the exception of periods necessary to change sampling media and scheduled short term equipment maintenance of two hours or less. If the sample media !
is not in place during the entire release period (except as described above), an l explanation of the occurrence, actions taken to restore the sampler and to prevent I reoccurrence, and a summary description to explain the occurrence's effect on the analysis validity SHALL be included in the Annual Radioactive Effluent Report. l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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, ICONT'D1 TABLE NOTATIONS Icont'd_1 1.
Releases are made via the shield building vents only during PURGING, or operation of special ventilation systems. When ventilation fans in any vent path are not in service for the entire sample period, in lieu of weekly removal and analysis of iodine and particulate j collection devices, these devices may be removed and analyzed following each release l provided that the release lasts less than one week. Releases made via the plant ' ventilation paths as a result of routine surveillance tests, operational testing or scheduled : short term maintenance activities of 2 hours or less do not require special sampling and I analysis provided that plant conditions do not indicate the completion of these activities 3 would cause an increase in the release of activity. Removal and analysis of collection : devices is not required if releases are not being made. 1 J. Grab samples for atmospheric steam releases are representative liquid grab samples from the respective steam generator. k
- k. Atmospheric steam releases are the timed releases of steam from the steam generators to the atmosphere via either the power operated reliefs, steam dump valves or flash tank vents. It does not include steam dumped via the condenser.
I. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of steam released and in which the method of sampling employed results in a specimen which is representative of the total steam released form the respective steam generator.
- m. Containment Purges includes PURGE releases with either the Inservice Purge or Containment Purge Fans and also VENTING of containment utilizing the Post Loca Vent i
- System. When the release is completed via the Post Loca Vent, the pre-release tritium, i
- particulate and charcoal samples should be used for all analyses, and continuous samples collected during the release are not required. During Cold Shutdown periods, the availability of ventilation systems and the position of containment air-lock doors may require that portions of the required samples be collected with installed continuous monitors or portable sampling equipment.
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l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES mi ^' ' TITLE: NUMBER- 1 H4 4m m:: , OFFSITE DOSE CALCULATION
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MANUAL (ODCM)
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT
;7 NORTHERN STATES POWER COMPANY H PROCEDURES 1 Et ; ng TITLE: NUMBER:
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_. n_ . MANUAL (ODCM) REV: 14 Page 95 of 223 TABLE 3.2 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. Waste Gas Holdup System Explosive 2 During system 2 Gas (Oxygen) Monitors operation
- 2. Effluent Release Points l
Unit 1 Aux Bldg. i Unit 2 Aux Bldg. Rad Waste Bldg. , Spent Fuel Pool l Unit 1 Shield Bldg. Unit 2 Shield Bldg.
- a. Noble Gas Activity Monitor
- 1 During releases 4,5,7
- b. lodine Sampler Cartridge 1 During releases 3 l
!(]~ '
- c. Particulate Sampler Filter
- d. Sampler Flow Integrator 1
1 During releases During releases 3 1 i 3. Air Ejector Noble Gas Monitors 1 During power op- 6 (Each Unit) eration j
- Noble gas activity monitors providing automatic termination of releases (except the Radwaste Building which has no automatic isolation function).
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I l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ; e ~ MW TITLE: NUMBER: I H4 ' OFFSITE DOSE CALCULATION sJ4 MANUAL (ODCM) REV: 14 "b Pace 96 of 223 TABLE 3.2- RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION [ CONT'D1 TABLE NOTATIONS ACTION 1 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 12 hours. 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, operating of this system may continue for up to 14 days. With two channels inoperable, manually isolate the oxygen addition line. ACTION 3 With the numbers 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 samples are collected with auxiliary sampling equipment as required in Table 3.1. ACTION 4 With the number of channels Operable less than required by the Minimum O Channels Operable requirement, effluent releases via this pathway may l continue for up to 30 days provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. I ACTION 5 With the number of channels Operable less than required by the Minimum ; Channels Operable requirement,immediately suspend Purging of radioactive l effluents via this pathway during periods when containment integrity is required or { the primary system is initially opened to the atmosphere. (applicable to Reactor j Building Vents) ' ACTION 6 With the number of channels Operable less than required by the Minimum Channels Operable requirement, air ejector operation may continue for up to 30 days provided grab samples are taken at least once per 24 hours and these samples are analyzed for gross activity within 24 hours. ACTION 7 With the number of channels operable less than required by the Minimum Channels operable requirement, the contents of the waste gas decay tanks 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 lineup; Otherwise, suspend release of radioactive effluents via this pathway (applicable to Unit 2 Auxiliary Building Vent).
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES C
.,w figg-t gib me--
TITLE: NUMBER: . O V A OFFSITE DOSE CALCULATION 94
._ly*%p MANUAL (ODCM) REV:14 s
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,, n. ~"O Page 97 of 223 TABLE 3.3 - RADIOACTIVE G ASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1
4 g gi > LCHANNEL% , LSOURCEP sFUNCTIONAL$ R A& _ _. .. . . _ .
~r '^ '
i . JCHECKs*s ICHECKT NTESTs ICAllBRATION!
!!$ssum$gt ~*;)nh WiNFrequensyb [frasibsnsp! ~N~ fastusrdil ~ iFrehuencpf Waste Gas Holdup System Daily during Monthly (2) Quarterly (5) 4 Explosive Gas (Oxygen) system operation Monitors i Effluent Release Points Unit 1 Aux Bldg.
- Unit 2 Aux Bldg.
Rad Waste Bldg. Spent Fuel Pool l Unit 1 Shield Bldg. Unit 2 Shield Bldg. e o ^ct'vitv o""' ""<'"o " "t"'v- o" <t <'v o> ^t'e t "ce everv 4 CJ M" o'n'itor (4) releases 18 months (3) (Except Radwaste i Building) Noble Gas Activity Monitor Daily during Monthly Quarterly (2) At least once every Radwaste Building (4) releases 18 months (3) lodine and Particulate Weekly
- Samplers i Sampler Flow Rate Monitor Weekly Atleast once every '
18 months Air Ejector Noble Gas Daily during re- Monthly Quarteriy(2) At least once every Monitors (Each Unit) leases 18 months (3)
- A SOURCE CHECK of the applicable nobles gas monitor SHALL be conducted prior to each waste gas decay tank or containment purge release.
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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OFFSITE DOSE CALCULATION REV: 14 iSectiof MANUAL (ODCM)
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Paae 98 of 223 TABLE 3.3 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS ICONT'D] TABLE NOTATIONS
- 1. The CHANNEL FUNCTIONAL TEST SHALL also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following exists.
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure (if provided).
- c. Instrument indicates a downscale failure (if provided).
- d. Instrument controls not set in operate mode (if provided).
- 2. The CHANNEL FUNCTIONAL TEST SHALL also demonstrate that alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure (if provided).
- c. Instrument indicates a downscale failure (if provided).
- d. Instrument controls not set in operate mode (if provided).
- 3. The initial CHANNEL CALIBRATION SHALL be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using sources traceable to NIST standards. These standards SHALL permit calibrating i the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATIONS, sources that have been related to the initial calibration SHALL be used.
- 4. Noble gas monitor in the Radwaste Building vent not provided with automatic isolation trip. !
- 5. The CHANNEL CAllBRATION SHALL include the use of a nitrogen zero gas and an oxygen span gas with a nominal concentration suitable for the range of the instrument.
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Vg ', g , g, TITLE: NUMBER: o yl; OFFSITE DOSE CALCULATION H4 V E .,. .j *J
'4 MANUAL (ODCM) REV:14 Page 99 of 223 TABLE 4.1 -LIQUID SOURCE TERMS !
1 l l R s
' r.. _ . ..>.1. _J.
- . WASTE EFFLUENT ....SGBD 1 RADIONUCLIDE [MPC(ECi/rhnj , l fad (CINrH ffMICINr$.;.,3, l Mo-99 4E-5 6.42E-3 1.415E-2 1-131 3E-7 3.061 E-2 4.11 E-2 l Te-132 2E-5 2.12E-3 3.61 E-3 1-132 8E-6 2.83 E-3 1.88 E-2 1-133 1E-6 2.365E-2 4.856E-2 Cs-134 9E-6 1.464E-1 4.047E-2 1-135 4E-6 4.84E-3 1.792E-2 Cs-136 6E-5 5.743E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69E-2 O i (j All Others 1E-7 0 2E-5 H-3 3E-3 1.89E2 1.41 E2 Noble gases 2E-4 TOTAL 1.894E2 1.412E2 O
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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MANUAL (ODCM) REV: 14
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SMN Page 101 of 223 TABLE 4.2 - ADULT INGESTION DOSE VALUES (Ap) FOR THE i PRAIRIE ISLAND NUCLEAR GENE _ RATING PLANT ' (MREM /HR PER uCl/ml) NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 NA-24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 CR-51 0.00E-01 0.00E-01 1.27E 00 7.61 E-01 2.81 E-01 1.69E 00 3.20E 02 MN-54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 MN-56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 I FE-55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 FE-59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 CO-57 0.00E-01 2.10E 01 3.48E 01 0.00E-01 0.00E-01 0.00E-01 5.32E 02 CO-58 0.00E-01 8.92E 01 2.00E 02 l 0.00E-01 0.00E-01 0.00E-01 1.81E 03 CO-60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81E 03 NI-63 3.11E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 NI-65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51 E 01 0.00E-01 8.50E 02 O CU-64 ZN-65 ZN-69 2.32E 04 4.93E 01 7.37E 04 3.33E 04 0.00E-01 4.03E 04 0.00E-01 4.64E 04 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 BR-83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 BR-84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11 E-04 BR-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 1.01 E-15 RB-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 l RB-88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 RB-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 ' SR-89 2.21 E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 SR-90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 SR-91 4.07E 02 0.00E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 SR-92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03 Y-90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 Y-91M 5.44E-03 0.00E-01 2.11 E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 Y-91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 Y-92 5.06E-02 0.00E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 Y-93 1.60E-01 0.00E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 ZR-95 2.40E-01 7.70E-02 5.21 E-02 0.00E-01 1.21 E-01 0.00E-01 2.44E 02 ZR-97 1.33E-02 2.68E-03 1.22E-03 0.00E-01 4.04 E-03 0.00E-01 8.30E 02 NB-95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51 E 04 NB-97 3.76E 00 9.48E-01 3.46E-01 0.00E-01 1.11E 00 0.00E-01 3.50E 03 M O-99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 TC-99M 8.87E-03 2.51 E-02 3.19E-01 0.00E-01 3.81 E-01 1.23E-02 1.48E 01 TC-101 9.12E-03 1.31 E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95E-14 RU-103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 Os RU-105 3.69E-01 0.00E-01 1.46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 l RU-106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 RH-105 2.92E 00 2.12E 00 1.40E 00 0.00E-01 9.00E 00 0.00E-01 3.38E 02 AG-110M 8.81 E-01 8.15E-01 4.84E-01 0.00E-01 1.60E 00 0.00E-01 2.9E 02
l l l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: 4g ' @s 3' h OFFSITE DOSE CALCULATION O REV: 14 l 20& seek +, c/ s MANUAL (ODCM) I i - < Pace 102 of 223 TABLE 4.2 - ADULT INGESTION DOSE VALUES (Aa) FOR THE l 4 RATING PLANT l (MREM /HR PER uCl/ml) [ CONTINUED] NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG Gl-LLI SB-124 6.74E 00 1.27E-01 2.66E-01 1.63E-02 0.00E-01 5.23E 00 1.91E 02 SB-125 5.34E 00 5.75E-02 1.07E 00 4.74E-03 0.00E-01 5.58E 02 4.72E 01
- SB-126 2.75E 00 5.60E-02 9.94E-01 1.69E-02 0.00E-01 1.69E 00 2.25E 02 TE-125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.02E 04 TE-127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 TE-127 1.05E-02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03 4
TE-129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 TE-129 3.01 E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 TE-131M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 TE-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.00E-01 2.67E 00 STE-132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 I-130 2.71E 01 8.01 E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 1-131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01
- I-132 7.29E 00 1.95E 01 S.82E 00 6.82E 02 3.11E 01 0.00E-01 3.66E 00 -
I-133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 I-134 3.81E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01E-03 1-135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 CS-134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.20E 05 7 61E 04 1.24E 04 CS-136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 CS-137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 CS-138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 BA-139 9.29E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 BA-140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 BA-141 4.51 E-01 3.41 E-0.4 1.52E-02 0.00E-01 3.17E-04 1.93E-04 2.13E-10 BA-142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 LA-140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 LA-142 7.66E-03 3.48E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 CE-141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 CE-143 3.95E-03 2.92E 00 3.23E-04 0.00E-01 1.29E-03 0.00E-01 1.09E 02 CE-144 1.17E 00 4.88 E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 PR-143 5.51 E-01 2.21 E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41E 03 PR-144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 ND-147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2.54E-01 0.00E-01 2.09E 03 W-187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 NP-239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 O
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MANUAL (ODCM) Mhn) ' Page 103 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) l 1 Appendix B - Concentrations in Air and Water Above Natural Background [See footnotes at end of Appendix B) isotope $ Table i Table 11 Element (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 -Water (pCi/ml) (pCi/ml) (pCi/ml) (pCi/ml) Aconium(89) . Ac 227.. S 2x10-12 6x10-3 8x10-'d 2r104 1 3x10-11 9x10-3 9x10-13 3x104 Ac 228. S 8x104 3x104 3x104 9x10-5 1 2x1g.a 3x104 6x10-10 9x10-5 Am 241.. S 6x10-12 ixjo a 2x10-13 4x104 l Amenctum(95).. l 1x10-to 8x104 4x 10-12 3x10-5 Am 242m . . S 6x10-12 1xio4 2x10-13 4x1M l 3x10-10 3x104 9x10-12 gxjo-3 Am 242.. S 4x104 4x10-3 1x10-e 3x30-4 . I 5x104 4x104 2x104 1x10-4 I Am 243.. S 6x10-12 1x10-4 2x10-13 4x10-s 1 1x1740 8x104 4x10-12 3x10-3 b Am 244.. S 1 4x104 2x10-a 1 x10-1 1 x10-1 1 x10-7 8x10-7 5x10-3 5x10-3 Antmony.. _ Sb 122.- S 2x10-7 8x10-4 6x10-8 3x1g-5 1 1x10-7 8x10-4 5x10-8 3x10-5 Sb 124 .. S 2x10-7 7x10-4 5x10-e 2x10-5 1 2x10-a 7xj o-4 7x10-10 2x10-5 Sb 125.. S 5x10-7 3x104 2x104 1x10-4 1 3x10-a 3x10-3 9x10-10 1x10-4 Argon (18). . . A 37. Sub2 6x104 1x10-4 A 41 Sub 2x104 4x10-a l Arsenic (33).. .. As 73.. S 2x104 1 x10-2 7x10* 5x10-4 1 4x10-7 1xig-2 1x1 H 5x10-4 As 74 .. S 3x10-7 2x10-3 1x10-a 5x10-5 1 1x10-7 2x10-3 4x10-0 5x10-5 As 76.. S 1x10-7 6x10-4 4x10-8 2x10-5 l 1x10-7 6x10-4 3x10-0 2x10-5 As 77.. S 5x10-7 2x10-3 2x10-a 8x10-5 1 4x10-7 2x10-3 2x10-s ex3ga Astatine (85). At 211. S 7x10-8 5x10-3 2x10-'O 2x10-6 1 3x104 2x10-8 1 x10-8 7x10-5 Banun(56) - Ba 131. S 1x10-6 Ex1 H 4x10-8 2x10-4 I 4x10-7 5x10-3 1 x10-a 2x10-4 Ba 140 . ... S 1x10-7 8x10-4 4x10-e 3x10-3 1 4x104 7x10-4 1x10-e 2x10-3 Berkelaun(97)... Bk249- S 9x10-10 2x10-2 3x10-11 6x10-4
,._ l 1x10-7 2x10-2 4x10-0 6x10-4 f Bk 250.. S 1x10-7 6x104 5x10-e 2x10-4
\ l 1x10-a 6x10-3 4x10-8 2x10-4 Beryllium (4). Be 7 S 6x104 5x10-2 2x10-7 2x10-3 l 1x10-a 5x10-2 4xto-a 2x10-3 j
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(Section OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 W l l l Page 104 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) (CONT'D] Appendix B - Concentrations in Air and Water Above Natural Background Cont'd ' [See footnotes at end of Appendix B] lsotopei Table i Table 11 Element (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 - Water (pCi/ml) (pCi/ml) (pCi/ml) (pCi/ml) Bismuth (83).. B: 206.. S 2x10-7 1x104 6x104 4x104 1 1x10-7 1x10-3 5x10-e 4xtoa j Bi 207.. S 2x10-7 2x10-3 6x10.e 6x10-5 i 1x104 2x104 5x10-10 8x104 Bi210 S 6x10-8 1x10-3 2x10-10 4x104 i 6x10-e g xio-o 2x10-10 4x104 Bi 212. S 1x10-7
- 1x10-2 3x10-8 4x10-4 I 2x10-7 1x10-2 7xte-o 4x10-4 Bromine (35).. Br 82. S 1x104 8x104 4x104 3x10-4 1 2x10-7 1x10-3 6x10-8 4xig-5 Cidmium(48)... Cd 109. S 5x10-8 5x104 2x10-8 2x10d i 7x10-a Sxt o-3 3x10-8 2x10-4 Cd 115m . S 4x10-8 7x10d 1x10-e 3x104 1 4x10-8 7x104 1x10-e 3x104 '
Cd 115.. S 2x10-7 1x10-3 8x10-8 3x10-5 1 2x10-7 1x104 6x10-8 4xio-5 C:Jcium(20).. Ca 45.. S 3x10-8 3x104 1x10-8 0x10-6 1 1x10-7 5x10-3 4x10-8 2x10-4 CaJ7. S 2x10-7 1x10-3 6x10-8 5x10-5 l 2x10-7 1x10-3 6x1g-o 3x10-5 C:Jifomium(98)... . . . . Cf249 S 2x10-12 1xig-4 5x10-14 4x104 1 1x10-10 7x10-4 3x10-12 2x104 Cf250.. S 5x1g-12 4xj o-4 2x10-13 1x104 1 1 x10-10 7x10-4 3x10-12 3x10-5 Cf 251. S 2x10-12 1xj g-4 6x10-14 4x104 1 1 x10-10 8x10-4 3x10-12 3x104 Cf 252 S 6x1g-12 2x10-4 2x10-13 7x10-e 1 3x10-11 2x10-4 1x10-12 7xt a-6 Cf253.. S 8x10-10 4x104 3x10-11 1x10-4 I 8x10-10 4x10-3 3x10-11 1x1 H Cf 254.. S 5x10-12 4xig4 2x10-13 1x10-7 1 5x10-12 4xto-o 2x10-13 1x10-1 Cirbon(6).- C 14 .... .. S 4x10-6 2x10-2 1xio-7 8x10-4 (CO2) .. Sub 5x10-5 1x104 Cenum(58) Ce 141. S 4x10-7 3x104 2x104 9x104 1 2x10-7 3x104 5x10-8 9x10-5 Co 143. ... S 3x10-7 1x10-3 9x10-e 4x10-3 1 2x10-7 1x10-3 7x10-o 4x104 Ce 144. S 1x104 3x10-4 3x10-10 1x10-3 < 1 6x10-e 3x10-4 2x10-10 1x10-3 i l l l l
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Page 105 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) [ CONT'D] Appendix B - Concentrations in Air and Water Above Natural Background Cont'd 1 [See footnotes at end of Appendix B) l
!sotopei Table i Table it Element (atomic number) Col.1 - Ait Col. 2 - Water Col.1 - Air Col. 2 -Water (pCi/ml) ( Ci/ml) (pCi/ml) (pCi/ml)
Cesium (55).. Os 131. S 1x104 7x10-2 4xio-7 2x104 1 3x104 3x10-2 1xio-7 gxio-4 Cs 134m . S 4x10-5 2x10-1 1x10-8 6x10-3 l 1 6x104 3x10-2 2x10-7 1 x10-3 l Cs 134.. S 4x1 H 3x104 1x10-o gx104 ! I 1x104 1 x10-3 4x10-10 4x10-5 i Cs 135.. S 5x10-7 3x10-3 2x10-a 1xio-4 l 1 3x10-8 7xio-3 3x10-8 2x10-4 Cs 136 S 4x10-7 2x104 1x10 a gxio-5 { l 2x10-7 2x104 6x10-0 6x10-5 j Cs 137.. S 6x104 4x104 2x10-e 2x10-5 l 1x10-8 1xjo-3 5x10-10 4x10-5 Chlonne(17).. Cl 36 .. S 4x10-1 2x10-3 1x10-e 8x10-5 fg i 2x10-a 2x10-3 8x10-10 6x10-5 i kj Cl 38 .. S 3x10-a 1xj p-2 gxj g-a 4x10-4 1 2x104 1x10-2 7xio-a 4xio-4 Chromium (24).. - Cr51. S 1x10-5 5x10-2 4x10-i 2x10-3 1 2x10-6 5x10-2 8x10-8 2x10-3 Cobalt (27).-- Co S7.. S 3x104 2x10-2 1x10-7 5x10-4 1 2x10-7 1x10-2 6x10-8 4x10-4 Co S8m .. S 2x10-5 8x10-2 6x10-7 3x10-3 1 9x10-8 6x10-2 3x10-7 2x104 CoSS- S 8x10-7 4x10-3 3x10-a 1xio-4 1 5x104 3x104 2x10-0 9x10-3 Co 60.. S 3x10-7 1x10-3 1x10-a 5x10-3 l 9x10-e 1xio-3 3x10-10 3x10-5 Copper (29)., Cu 64.. S 2x10-6 1x1g-2 7xjg4 3x10-4 i i 1x104 6x104 4x10-a 2x10-4 : Curium (96).. Cm 242.. S 1x10-10 7x10-4 4x10-12 2x10-6 f i 2x10-10 7x10-4 6x10-12 2x10-5 l Cm 243.. S 6x10-12 1xio-4 2x10-13 5x10-e l 1x10-10 7x10-4 3x10-12 2x10-5 { Cm 244.. S 9x10-12 2x104 3x10-13 7x10-e i 1x10-10 8x10-4 3x10-12 3x10-5 Cm 245.. . S 5x10-12 1x10-4 2x10-13 4x10-e i 1x10-10 8x10-4 4x10-12 3x10-5 , Cm 246 S 5x10-12 1xt o-4 2x10-13 4x10-s ! 1 1x10-10 8x10-4 4x10-12 3x10-5 (xi Cm 247.. S l 5x10-12 1x10-10 1xio-4 6x10-d 2x10-13 4x10-12 4x104 2x10-5 1 Cm 248.. S 6x10-13 1x10-5 2x10-14 4x10-7 l 1x10-11 4x10-5 4x10-13 3 x10-6 )
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MANUAL (ODCM) 1SectionT Page 106 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) ICONT'D1 ~ Appendix B - Concentrations in Air and Water Above Natural Background Cont'd , (See footnotes at end of Appendix B] I isotopet Table i Table il l Element (atomic number) Col.1 - Air Col. 2- Water Col.1 - Air Col. 2 - Water a (pCi/ml) ( Ci/ml) (pCuml) ( Cuml) d Cm 249. S 1x10-6 6x104 4x10-1 2x104 i i 1x10-5 6x10-2 4x10-7 2x104 Dysprosium (66).. Dy 165. S 3x104 1x104 9x10-8 4x104 1 2x104 1x10-2 7x10-8 4xj o-4 Dy 166. S 2x10-7 1x104 8x10-o 4x104 2x10-7 1x104 l l 7x10-e 4xio-5 . Emsteinium(99).. Es 253.. S 8x10-'O 7x10d 3x10-" 2x10-5 i 6x10-10 7x10-4 2x10-H 2x10-5 Es 254m .'. S 5x104 5x10-4 2x10-'O 2x10-5
- I 6x10-0 5x104 2x10-10 2x10-5 Es 254.. S 2x10-" 4x10-4 6x10-13 1x10-5 !
l 1x10-10 4x104 4x10-12 1xj o-5 j Es 255.. S 5x10-10 8x10-4 2x10-H 3xiO4
- 1 4x10-1C 8x10-4 1x10-H 3x10-5 j 3
Erbium (68)... . Er 169.. S 6x10-7 3x104 2x10-8 9x104 1 4x10-7 3x104 1x104 9x10-5 Er 171. S 7x10-7 3x104 2x10-a j x1o-4 ; I 6x10-7 3x10-3 2x104 1x104 1 Europium (63)... Eu 152 ........ S 4x10-7 2x104 1x10-8 6x10-5 i (T/2=9.2 hrs) l 3x10-7 2x104 1x10-8 6x104 Eu 152 ... .... S 1x10-s 2x104 4 x10-10 8x10-5 l (T/2=13 yrs) I 2x104 2x10-3 6x10-10 8x10-5 ; 1 Eu 154. S 4x10-8 6x10-4 1x10-10 2x10-5 1 7x104 6x104 2x10-10 2x1g.5 Eu 155. S 9x10-a 6x104 3x10-e 2x10-4 1 7x10-a 6x10-3 3x10-8 2x10-4 Fermium (100)... Fm 254.. S 6x10-e 4x104 2x10-6 1x10-4 1 7x104 4x10-3 2x104 1x10-4 Fm 255.. S 2x104 1x10-3 6x10-10 3x10-5 l l 1x104 1x104 4x10-10 3x10-5 l Fm 256.. S 3x10-e 3x10-5 1x10-10 9x10-7 1 2x10-9 3x10-5 6x10-H 9x10-7 Fluonne(9) F 18.. S 5x104 2x104 2x10-7 8x10-4 ; I 3x104 1x10-2 gxto4 5xio-4 i Gadohnium(64). -- Gd 153., S 2x10-7 6x104 8x10-6 2x104 l l 9x10-8 6x10-3 3x10-8 2x104 Gd159. S 5x10-7 2x104 2x10-8 8x104 1 4x10-7 2x104 1x104 8x104 Galhum(31). Ga 72.. S 2x10-7 1x10-3 8x104 4x10-6 l 1 2x10-7 1x104 6x10-e 4xt o-5 Germanium (32)... Ge 71. S 1x10-6 5x104 4x10-7 2x104 I 6x104 5x10-2 2x10-7 2x104
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- Appendix B - Concentrations in Air and Water Above Natural Background Cont'd I i (See footnotes at end of Appendix B) isotopei Tabic i Table ll Elemorit (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 - W ter 2
( Ci/ml) (pCi/ml) (pCi/mt) (pCL/ml) ; Gold (791-- Au 196.. . S 1x104 5x10-3 4x104 2x104 I 3 l 6x10-7 4x10-3 2x104 1x104 $ Au 198 . S 3x10-7 2x10-3 1x104 5x10-5 ) i 2x10-7 1x10 3 8x104 5x10-5 1 Au 199 .. .. . S 1x104 5x104 4x10-a 2x104 l 8x10-7 4x104 3x10-8 2x10d 3 ' Hafnium (72) Hf181. S 4x104 2x10-3 1x10-8 7x10-3 ! 1 7x10-a 2x10-3 3x104 7x10-3 l l Holmium (67). Ho 166.. S 2x10-7 9x104 7x10-8 3x10-3 1 2x10-7 9x104 6x10-0 3x10-3 Hydrogen (1).. H3 S 5x104 1 x10-1 2x10-7 3x10-3 1 5x10-e j xig-t 2x10-7 3x10-3 Sub 2x10-3 4x10-5 _ O Indium (49). . In 113m .. in 114m ., S 1 d 8x10-4 7x104 1x10-7 4x10-2 4xig-2 5x104 3x104 2x10-7 4x10-e 1x10-3 1 x10-3 2x10-3 1 2x10-a 5x10-4 7x10-10 2x10-3 in 115m .. S 2x104 1x1g-2 8x104 4x10-4 1 2x10-e j xt o-2 6x10-a 4x10-4 in 115. S 2x10-7 3x10-3 9x10-e gxjo-s i 3x10-a 3x10-3 1 x10-e gxto-5 lodine (53)... I125- S 5x104 4x10-3 8x10-H 2x104 1 2x10-7 6x10-3 6x104 2x10-4 1126 S ex10-e 5x10-3 9x10-" 3x10-7 1 3x10-7 3x10-3 1 x10-a gxjo-s 1129 S 2x10-e 1xio-a 2x10-" 6x10-a l 7x10-a 6x10-3 2x10-0 2x10-4 1131. S 9x10-e 6x10-3 1x10-10 3x10-7 1 3x10-7 2x10-3 1x10-a 6x10-5 1132 S 2x10-7 2x10-3 3x104 8x10-e 1 9x10-7 5x10-3 3x10-8 2x10-4 1133- S 3x10-a 2x10-4 4x10-10 1x10-e i 2x10-7 1x10-3 7x10-e 4xio-s 1134 S 5x10 I 4x10-3 6x10-e 2x10-3 1 3.10-8 2x10-2 1x10-7 6x10-4 1135 S 1x10-7 7x10-4 1x10-8 4x10-e 1 4x10-7 2x10-3 1x10-a 7x10-5 Indium (77). tr190 S 1x10-6 6x10-3 4x104 2x10-4 1 4x10-7 5x10-3 1x10-8 2x10-4 tr192- S 1x10-7 1x10-3 4 x10-o 4x10-3
* ' l 3x10-a 1x10-3 9x10-10 4x10-3 16194 S 2x10-7 1x10-3 8x10-e 3x10-3 1 2x10-7 9x104 5x10-e 3x10-3
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 1 TITLE: NUMBER: r<5 s.. M a OFFSITE DOSE CALCULATION MANUAL (ODCM) REY: 14 h m JSecponf %, Page 108 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) ICONT'D1 ~ Appendix B -Concentrations in Air and Water Above Natural Background Cont'd (See footnotes at end of Appendix B] lsotopei Table 1 Table !! Element (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2- Water (pCi/ml) (pCi/ml) (pCi/ml) (pCi/ml) fron(26).. Fe SS- S 9x10-1 2x10-2 3x10-8 8x104 1 1x104 7x10-2 3x104 2x10-2 Fe 59.. S 1x10-7 2x104 5x104 6x104 1 5x104 2x10-3 2x104 5x104 Krypton (36). . . . Kr 85m . Sub 6x104 1x10-1 Kr 85 - Sub 1x10-5 3x10-7 Kr 87. Sub 1x104 _ 2x104 Kr 88 -- Sub 1x10-8 2x10-a Lanthanum (57). La 140 ... .. S 2x10-7 7x10d 5x104 2x10-3 1 1x10-7 7x104 4x10-8 2x104 ; l Lead (82).-- Pb 203.. S 3x104 1x10-2 gxtg4 4xiga l 2x104 1x10-2 6x10-a 4xtoa ; Pb 210.. S 1x1040 4x104 4x10-12 1x t a-7 1 2x10-10 5x10-3 8x10-12 2x104 , Pb 212. S 2x10-s 6x104 6x10-10 2x10-3 1 2x104 5x10-' 7x10-10 2x10-3 Lutetium (71).. Lu 177.. S 6x10-7 3x104 2x104 1x104 1 5x10-7 3x10-3 2x10-8 1x10-4 Manganese (25) . . . Mn 52.. S 2x10-! 1x104 7x10-8 3x104 1 1x10-7 9x10-4 5x10-8 3x10-5 Mn54. S 4x10-7 4x10-3 1x10-8 1x10-4 1 4x10-8 3x10-3 1x10-e 1xtga Mn56. S 8x10-7 4x104 3x104 1x10-4 1 5x10-7 3x104 2x104 1x10-4 i Mercury (00).. . . . . Hg 197m . S 7x10-7 6x104 3x104 2x10-d I 8x10-7 5x10-3 3x10-a 2x10-4 ; Hg 197.. S 1x10-8 9x10-3 4x10-8 3x10-4 I I 3x10-8 1x10-2 gxig-a sxto-4 1 Hg 203. S 7x10-a 5x10-4 2x104 2x10-3 1 1x10-7 3x10-3 4x10-8 1x10d I Molybdenum (42L 5.2.. Mo99. S 7x10-7 5x104 3x10-8 2x10-4 j i 2x10-7 1x104 7x10-e 4x10-5 Neodymium (60) - ... Nd 144 S 8x10-11 2x104 3x10-12 7xica 1 3x10-10 2x10-3 1x10-11 8x104 Nd 147.. S 4x10-7 2x104 1x104 6x10-3 I I 2x10-7 2x10-3 8x10-e 6x10-3 ) Nd 149.. S 2x10-a 8x104 6x10-8 3x104 1 1x10-s Bx104 5x1g-a 3x10-4 Nepturuum(93). .. . . . . . . . . . . . Np 237 S 4x10-12 gxtg4 1x10-13 3x104 l 1x10-10 9x104 4x1942 3x104 Np 239., S 8x10-7 4x10-3 3x10-s j xt o-4 1 7x10-7 4x10-3 2x10-a 1x10-4 Nickel (28).. Ni S9. S 5x10-7 6x174 2x10-6 2x1CT4 I 8x10-7 6x1g.2 3x10-a 2x10-3
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] ?W9}B5 BC* "f]hi H4 OFFSITE DOSE CALCULATION MANUAL (ODCM) REY: 14 e J' NN$b hk Page 109 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) ICONT'D1 ~ ~
Appendix B - Concentrations in Air and Water Above Natural Background Cont'd [See footnotes at end of Appendix B] T lso3ei Table i Table I! i Element (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 - Water ( Ci/ml) (pCi/ml) ( Cl/ml) (gCumi) Ni 63 .. S 6x104 8x10-4 2x10-8 3x10-3 1 3x10-7 2x10-2 1xto4 7xjo-4 Ni 65 .. S 9x10-7 4x10-3 3x104 1x10-4
- I 5x10-1 3x10-3 2x104 1x10-4 Niobium (Columbium)(41).. Nb93m. S 1x10-7 1 x10-2 4xio4 4x10-4
, 1 2x10-7 1x10-2 5x10-8 4x10-4 Nb 95.. S 5x10-7 3x10-3 2x104 1x10-4 1 1x10-7 3x10-3 3x10-e j xj o-4 Nbp? S 6x104 3x1g-2 2x10-7 9x10-4 1 5x104 3x10-2 2x10-7 9x10-4 Osmium (76).. Os 185.. S 5x10-7 2x10-3 2x10-a 7x10-3 1 5x10-a 2x10-3 2x10-e 7x10-8 Os 191m . S 2x10-5 7xio-2 6x10-7 3x10-3 9x104
\(N N,./
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Os 191. i 1x104 7x10-2 3x10-7 2x10-8 S 5x104 4x104 2x10-4 i 4x10-7 5x10-3 1x10 a 2x10-4 Os 193.. S 4x10-7 2x10-3 1x10-s 6x10-3 1 3x10-7 2x10-3 9xtr8 5x10-3 Pa!!adium(46).. Pd 103. S 1x104 1x10-2 6x1g.a 3x10-4 1 7x10-7 8x10-3 3x104 3x10-4 Pd 109.. S 6x10-7 3x10-3 2x10-8 gxio-3 1 4x10-7 2x10-3 1x104 7x10-3 Phosphorus (15) P 32.. S 7x1re 5 x10-* 2x10-8 2x104 1 8x10-8 7x10-4 3x1 78 2x10-3 Platinum (78).. Pt191. . S 8x10-7 4x10-3 3x104 1x174 1 6x10-1 3x10 3 2x10-a j x10-4 Pt 193m .. S 7x104 3x10-2 2x10-7 1x10-3 1 5x104 3x10-2 2x10-7 1x10-3 Pt193.. S 1x10-6 3x10-2 4x104 9x10-4 1 3x10-7 5x10-2 1xto-a 2x10-3 Pt 1G.'m . S 6x10-6 3x10-2 2x10-7 1x10-3 1 5x104 3x10-2 2x10-7 9x10-4 Pt197- S 8x10-7 4 x10-3 3x10-s j x1o-4 1 6x10-7 3x10-3 2x104 1x10-4 PlutoniumW).. Pu 238.. S 2x10-12 1 xj g 7x10-14 5x104 1 3x10-" 8x10-4 1x10-12 3x10-5 Pu 239. S 2x10-12 1 xj o-4 6x10-14 5x10-s 1 4x10-" 8x10-4 1x10-12 3x10-5 m i Pu 240.. S 2x10-12 4x10-H 1x10-4 8x10-4 6x10-14 Ex10-e i I 1x10-12 3x10-5 Pu 241. S 9x10-H 7x10-3 3x10-12 2x10-4 1 4x10-s 4xio-2 1xio-o j xig-3
i PRAlRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l
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MANUAL (ODCM) REV: 14 w._ ^ _ Page 110 of 223 , 1 l TABLE 4.3-OLD 10CFR20 APPENDIX B (APRIL 1992)[ CONT'D] ! Appendix B -Conce.,trations in Air and Water Above Natural Background Cont'd l (See footnotes at end of Appendix B) Isotope 1 Table i Table 11 i Element (atomic number) Col.1 - Air Col. 2- Water Col.1 - Air Col. 2 - Water (pCi/ml) ( Ci/ml) ( Ci/mt) ( Ci/ml) Pu 242.. S 2x1gaa 1x10-4 6x10-14 5x104 1 4x10-" 9x104 1x10-12 3x10-5 j Pu 243.. S 2x104 1x10-2 6x104 3x104 ) 1 2x104 1x1g-2 8x104 3x104 Pu 244.. S 2x1042 3 x t o-4 6x10-14 4x104 1 3x10-" 3x104 1x10-12 1xj o-5 Polonium (84).. Po 210.. S 5x10-'O 2x104 2x10-H 7x10-1 1 2x1040 8x10-4 7x10-12 3x104 Po'.:.ssium(19).. K 42.. S 2x104 9x104 7x104 3x10-4 1 1x104 6x104 4x10-0 2x10-5 Priseodymium(59).. Pr 142.. S 2x10-7 9x10-4 7x10-8 3x104 1 2x104 9x10-4 5x10-e 3x104 Pr 143 . S 3x104 1x104 1x10-8 5x104
- 1 2x104 1x104 6x10-e 5x10-3 PromethnJm(61)... Pm 147.. S 6x10-8 6x104 2x104 2x10-4 1 1x104 6x10-3 3x104 2x10-4 l
Pm 149.. S 3x104 1x104 1x10-8 4xtga j l 2x104 1x10-3 8x10-8 4x10-3 Protoachnium(91)... Pa 230.. S 2x10-8 7x104 6x10-H 2x10-4 1 8x10-10 7x10-3 3x10-" 2x10-4 l Pa 231. S 1x10-12 3x104 4xtrW ?x104 1 1x104 0 8x10-d 410-12 2=10-5 Pa 233.. S 6x104 4x10-3 2x10-8 1x1'M i 2x104 3x104 6x1g-e txt s l Radium (88). Ra 223.. S 2x10-8 2x10-5 6x10-H 7x104 l t 2x10-10 la104 8x10-12 4x 404 ' Ra 224 S 5x10-8 7x10-3 2x10-10 2x104 I 7x10-10 2x10-4 2x10-" 5x104 Ra 226.. S 3x10-" 4x104 3x10-12 3x10-a 1 5x10-11 9x10-4 2x10-12 3x10-6 Ra 228. S 7x10-" 8x104 2x10-12 3x10-e 4x10-" 7x10-4 1 x10-12 3x10-5 Radon (86) Rn 220... S 3x104 . 1x104 Rn 2223 I 3x10-e 3x10-e Rhenium (75) . Re 183.. S 3x104 2x10-2 9x104 6x10-4 l 2x104 8x10-3 5x10-e 3x10-4 Re186..... S 6x104 3x104 Px104 9x10-5 1 2x104 1x104 8x10-e 5x10-5 Re 187.. S 9x10-e 7xj g-2 3x104 3x10-3 1 5x10-7 4x10-2 2x104 2x10-8 Re 188. S 4x10-7 2x10-3 1x10-a 6x104 1 2x104 9x10-4 6x10-0 3x104
PRAIRIE ISLAND NUCLEAR GENERATING PLANT . NORTHERN STATES POWER COMPANY e* / ' H PROCEDURES TITLE: O ^' " ' ^ ' ' " NUMBER:
- 'H_l* Nb5
_ w "S" S" MANUAL (ODCM) REV: 14 Page 111 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) (CONT'D] Appendix B - Concentrations in Air and Water Above Natural Background Cont'd {See footnotes at end of Appendix B] Isotopet Table i Table in Element (atomic number) Col.1 - Air Col. 2- Water Col.1 - Air Col. 2 -Water (pCi/mi) (pCuml) ( Ci/ml) (pCi/mi) Rhodium (45)... Rh 103m . S 8x10-3 4x10-1 3x104 1x10-2 1 6x10-8 3x10-1 2x104 1x10-2 Rh 105. S 8x10-7 4x10-8 3x104 1x104 1 5x10-7 3x104 2x104 1x104 Rubidium (37)... Rb86. S 3x10-7 2x104 1x104 7x10-3 I 7x104 7x104 2x10-o 2x10-3 Rb 87.. S 5x10-7 3x10-3 2x10-a 1x10-4 1 7x10-a gxj o-a 2x10-8 2x10-4 Ruthenium (44).. Ru97. S 2x10-6 1x10-2 8x104 4x10-4 1 2x10-8 1x10-2 6x104 3x10-4 Ru 103. S 5x10-7 2x10-3 2x10-a 8x10-5 1 8x10-8 2x10-3 3x10-8 8x10-5 Ru 105 . S 7x10-7 3x10-3 2x104 1x10-4 1 5x10-7 3x10-3 2x10-8 1x10-4 Ru 106. S 8x10-a 4x10-4 3xig-o jxio-3 1 6x10-e 3x10-d 2x10-10 1x10-3 Samanum(62). Sm 147. S 7x10-11 2x10-3 2x10-i2 6x10-3 ! l 3x10-10 2x17 3 9x10-12 7x10-3 Sm 151. S 6x10-a 1xio-2 2x10-0 4xjg-4 1x10-7 1x10-2 5x1g-e 4xin-4 Sm 153. . S 5x10-7 2x10-3 2x10-a 8x10-3 1 4x10-7 2x10-3 1x10-8 8x10-3 Scandium (21).. . Sc46. S 2x10-7 1x104 8x104 4x10-3 l l 2x104 1x10-3 8x10-10 4x10-3 Sc 47.. S 6x10-7 3x10-3 2x10-8 gxjo-a 1 5x10-7 3x10-3 2x10-8 gxje-3 Sc 48.. S 2x10-7 8x104 6x10-o 3x10-3 i i 1x10-7 8x10-4 5x10-8 3x10-3 ! Selenium (34)... Se 75 - S 1x10-6 9x10-3 4x104 3x10-4 I i 1x10-7 8x10-3 4x10-e 3x10-4 l Silicon (14)- Si 31 - S 6x10-6 3x10-2 2x10-7 9x10-* 1 1x104 6x10-3 3x1 H 2x10-4 Silver (47) Ag 105.. S 6x10-7 3x10-3 2x104 1x10-4 1 8x10-a 3x10-3 3x10-0 1x10-4 Ag 110m .. S 2x10-7 9x10-4 7x10-e 3x10-3 1 1x104 9x10-4 3x10-10 3x10-3 Ag 111 S 3x10-7 1x10-3 1x10-8 4xin-3 1 2x10-7 1 x10-3 8x10-8 4x10 3 q Sodium (11). . Na 22 .. . S 2x10-7 1x104 6x10-8 4x10-3 ' I 9x10-e 9x10-4 3x10-10 3x10-3 Na 24.. S 1x10-e 6x10-3 4xig.a 2x10-4 1 1x10-7 8x10-4 5x10-8 3xl04
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- Page 112 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) [ CONT'D]
Appendix B -Concentrations in Air and Water Above Natural Background Cont'd [See footnotes at end of Appendix B) Isotope 1 Table i Table !! Element (atomic number) col.1 - Air Col 2 - Water Col.1 - Air Col. 2 - Water (pCi/ml) (pCi/ml) ( Cuml; ( Ci/ml) Strontium (38).. Sr 85m . S 4x10-6 2x10-1 1x10d 7x104 1 3x10-5 2x10-1 1x104 7x10-3 Sr 85. S 2x10-7 3x104 8x104 1x104 1 1x10-7 5x10-3 4x104 2x104 Sr 89.. S 3x10-a 3x10d 3x10-10 3x104 1 4x104 8x1 H 1x10-e 3x10-5 Sr 90.. S 1x104 1x104 3x10-11 3x104 1 5x10-8 1x10-3 2x10-10 4x104 Sr 91 S 4x104 2x104 2x10-a 7x104 1 3x104 1x104 9x1g e 5x10-3 Sr 92 . ... .. S 4x104 2x10-3 2x10-a 7x10-3 1 3x104 2x104 1x104 6x104 Sulfur (16).. S 35.. S 3x104 2x104 9x104 6x104 ' 1 3x104 8x10-3 9x10-e 3xj o-4 Tantalum (73).. Ta 182.. S 4x10-8 1x1 H 1x10-6 4 x10-5 1 2x10-8 1xjo-a 7xto-to 4xj o-5 Technetium (43).. Tc 96m .. S 8x10-6 4x10-1 3x104 1 x10-2 1 3x10-5 3x10-1 1x10-8 1 x10-2 Tc96. S 6x10-7 3x10-8 2x104 1x10" I 2x104 1x104 8x104 5x10-5 Tc 97m ., S 2x104 1x10-2 8x10-a 4x3na 1 2x10-7 5x10-3 5x10-0 2x104 Tc97. S 1x10-5 5x10-2 4xto4 2x104 1 3x104 2x10-2 1xio-a 8x104 Tc 09m .. S 4x10-6 2x10-1 1x10-a 6x104 1 1x10-5 8x10-2 5x10-7 3x10-3 Tc 99.. S 2x10-8 1x10-2 7x104 3x10-d i 6x10-a 5x10-3 2x10-8 2x10-4 Tellurium (52). Te 125m .. S 4x104 5x10-3 1x10-a 2x10-4 1 1x104 3x104 4x10-8 1 x10-4 To127m S 1x10-7 2x104 5x104 6x10-5 1 4x104 2x104 1x10-e 5x104 To127.. S 2x10-e 8x10-3 Sx104 3x10 d i 9x104 5x104 3x10-a 2x10-4 To129m.. S 8x10-a 1x104 3x10-e 3x10-5 1 3x104 6x10d 1x10-e 2x10-5 Te129- S 5x10-e 2x10-2 2x104 8x10d i 4x104 2x1g-2 1x104 8x10-4 To131m.. S 4x104 2x104 1x104 6x10-6 1 2x104 1x10-3 6x10-0 4xio-5 To132.. S 2x104 9x10-4 7x104 3x10-5 l 1x104 6x10-4 4x10-0 2x10-5
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES c ik TITLE: NUMBER: (j , f^ 9 , & }Jbve OFFSITE DOSE CALCULATION H4 a
- MANUAL (ODCM) REV: 14
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Page 113 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) (CONT'D] Appendix B -Concentrations in Air and Water Above Natural Background Cont'd (See footnotes at end of Appendix B) Isotopet Table i Table 11 Element (atomic number) Col.1 - Ar Col. 2 - Water Col.1 - Air Col. 2 -Water (pCi/ml) (pCi/ml) ( Ci/ml) (pCi/ml) Terbium (65). . Tb 160. S 1x10-7 1x104 3x104 4x104 1 3x174 1x10-3 1x104 4x10-5 Thallium (81)... Ti200.. S 3x104 1x10-2 gx1e4 4xjo-4 l 1x104 7x10-3 4x10-8 2x10-4 Tl201 S 2x104 9x10-3 7x104 3x104 1 9x10-7 5x104 3x104 2x10-4 Tl202.. S 8x10-7 4x10-3 3x10-8 1 xto-4 1 2x10-7 2x104 8x10-8 7x1g.5 Tl204- S 6x10 3x10-3 2x104 1x10-4 1 3x10-8 2x10-3 9x10-10 6x10-5 Thonum(90).- Th 227.. S 3x10-80 5x10-4 1x10-H 2x10-5 l l 2x10-'O 5x10-4 6x10-12 2x10-5 ,3 Th 228.. S 9x10-12 2x10-4 3x10-13 7x10-e )
) 1 6x10-12 4xt o-4 2x10-13 1x10-5 s Th 230.. S 2x10-12 5x10-5 8x10-14 2x104 1 1x10-H 9x10-4 3x10-13 3x104 Th 231.. S 1x10-e 7xt o-3 5x1g-a 2x10-4 ,
i 1x10-8 7x10-3 4x104 2x10-4 l Th 232 S 3x10-H 5x10-5 1x10-12 2x10-e l l 3x10-H 1x10-3 1x10-12 4xjo-5 j Th natural .. S 6x10-H 6x10-5 2x10-12 2x10-a l I 6x10-H 6x10-4 2x10-12 2x10-5 l Th 234 S 6x10-8 5x10-4 2x10-e 2x10-5 l l 3x10-e 5x10-4 1 x10-e 2x10-5 Thulium (69).. Tm 170.. S 4x10-8 1x104 1x104 5x10-5 1 3x10 a 1x10-3 1x10-0 5x10-5 Tm 171. S 1x10-7 1x10-2 4xto-e 5xt o-4 1 2x10-7 1x10-2 8x10-e 5x10-4 Tin (50).. Sn 113. S 4x10-7 2x104 1x10-8 9x10-5 1 5x104 2x104 2x10-o 8x10-5 Sn 125. S 1x10-7 5x10-4 4x10-8 2x10-5 I 8x10-6 5x10-4 3x10-e gx10-5 Tungsten (Wolfram)(74). W 181 S 2x10-6 1x10-2 8x10-6 4x10-4 1 1x10-7 1x10-2 4xto-o 3x10-4 W 185 S 8x10-7 4x104 3x10-a 1 xio-4 1 1x10-7 3x104 4 x10-0 1x10-4 W 187.. S 4x10-7 2x104 2x10-e 7xio-5 1 3x10-7 2x10-3 1xig-a 6x10-5 U 230.. S 3x10-10 1x10-H 5x104 O Uranium (92) . 1x10-4 1 1x10-10 1x10-4 4x10-12 Sxjo-e
l l I PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER:
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a OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h Page 114 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) ICONT'D1- ~ Appendix B - Concentrations in Air and Water Above Natural Background Cont'd [See footnotes at end of Appendix B] Isotope 1
)
Table i Table il ' Element (atomic number) Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 - Water ( Ci/ml) (pCi/ml) (pCi/ml) ( Ci/ml) U 232.. S 1x10-10 ? 8x104 3x10-12 3x104 1 3x10-11 8x10-4 9x10-13 3x10-5 U 233.. S 5x10-10 9x10-4 2x10-" 3x10-5 j l 1x10-10 9x10-4 4x10-12 3x104 l U 234 S4 6x10-10 9x10-4 2x10-" 3x104 1 1 x10-10 9x10-4 4x10-12 3x10-5 I U235. S4 5x10-10 8x10-4 2x10-" 3x104 1 1 x10-10 8x10-4 4x10-12 3x104 U 236.. S 6x10-10 1x10-8 2x10-" 3x10-5 1 1x10- 0 1x10-3 4x10-12 3x10-5 U 238.. S4 7x10-" 1x10-3 3x10-12 4xto-5 l 1x10-10 1x104 5x10-12 4xt o-5 U 240.. S 2x10-7 1x10-3 8x10-e 3x10-5 l l 2x10-7 1x10-3 6x10-8 3x10-5 i U-natural .. S4 1x10-10 1x10-3 5x10-12 3x104 !
! 1 x10-10 1x10-3 5x10-12 3x10-5 i Vanadium (23).. V 48.. S 2x10-7 9x10-4 6x104 3x104 1 6x104 8x10-4 2x10-0 3x10-5 X:non(54k Xe 131m . Sub 2x10-6 4xio-r I Xe 133 . Sub 1x10-5 3x10-7 j Xe 133m . Sub 1x10-5 3x1&-7 I Xe 135.. Sub 4x10-a j xj o-7 j Yttarbium(70)... Yb 175.. S 7x10-7 3x104 2x10-8 1 x10-4 l 1 6x10-7 3x104 2x10-8 1xio-4 )
Yttnum(39)... Y 90 : . S 1x10-7 6x10-4 4x10-8 2x10-6 l 1x10-7 6x10-4 3x10-8 2x10-5 Y 91m S 2x10-5 t x t o-1 8x10-7 3x10-3 1 2x10-5 1x10-1 6x10-7 3x10-3 Y 91. S 4x10-8 8x10-4 1x10-8 3x10-5 l I 3x10-a 8x10-4 1x10-8 3x10-5 Y 92 - S 4x10-7 2x10-3 1x10-a 6x10-5 j l 3x10-7 2x10-3 1x10-e 6x10-5 i Y 93.. S 2x10-7 8x1G-4 6x10-e 3x10-5 1 1x10-7 8x10-4 5x10-e 3x10-5 Zinc (30). Zn 65 - S 1x10-7 3x104 4x10-6 1x10-4 , I 6x10-a 5x10-3 2x10-e 2x10-4 l Zn 69m .. S 4x10-7 2x104 1x10-a 7xio-5 1 3x10-7 2x104 1x10-a 6x10-5 Zn 69 : S 7x10-4 5x10-2 2x10-7 2x104 1 9x10-a 5x10-2 3x10-7 2x10-3 Zitconium(40) Zr 93. S 1x10-1 2x10-2 4xto4 8x104 1 3x10-7 2xig-2 1xjo-a 8x10-4 a
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES J&._ gig g, TITLE: o ',., NUMBER: V w,' OFFSITE DOSE CALCULATION H4 7 h pESec _d _otD~ ~ x g MANUAL (ODCM) REV: 14
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Page 115 of 223 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 19921ICONT'D] Appendix B - Concentrations in Air and Water Abova Naturd Background Cont'd (See footnotes at end of Appendix B) Isotopei Table i Table 11 Element (atomic number) Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 - Water (pCi/ml) (pCi/ml) ( Ci/ml) (pCi/ml) Zr 95 S 1x10-1 2x104 4x10-8 6x104 1 3x10-a 2x104 1x10-0 6x10-5 Zr 97 -- S 1x10-7 5x10-4 4x10-e 2x104 1 9x10-a 5x10-4 3x10-e 2x10-5 Any single radionuclide not listed above with decay Sub 1x10-a 3x10-8 mode other than alpha emission or spontaneous fission cnd with radioactive half-life less than 2 hours. Any single radionuclide not listed above with decay 3x10-e gxio-5 3xio40 3x10-e mode other than alpha emission or spontaresous fission , tnd with radioactive half-life greater than 2 hours. l I Any single radionudide not listed above, which decays 6x10-13 4x10-7 2x1044 3x10-a l by alpha emission or spontaneous fission. 8 Soluble (S): Insoluble (1). O I 2-Sub" means that values given are for submersion in a semisphericalinfinite cloud of airbome material. 8These radon concentrations are appropriate for protection from radon 222 combined with its short-lived daughters. Attematively, the value in Table 1 rnry be replaced by one third (1/3) " working level.* (A working lewl"is defined as any combination of short-lived radon-222 daughters, polonium 218, lud-214, bismuth 214 and polonium 214, in one litar of air, without regard to the degree of equilibriurn, that will result in the ultimate emission of 1.3 x 105 MeV of alpha particle energy.) The Table ll value may be replaced by one-thirtieth (1/30) of a "worldng level." The limit on radon 222 , concentrations in restncted areas may be based on an annual average. I 4For soluble mixtures of U-238. U-234 and U-235 in air chemical toxicity may be the limiting factor. If the percent by weight enrichment of U-235 is less than 5, the concentration value for a 40-hour workweek, Table Iis 0.2 milligrams uranium per cubic meter of air average. For any enrichment, the i product of the average concentration and time of exposure during a 40-hour workweek SHALL NOT exceed 8 x 103 SA pCi-hr/ml, where SA is the ' specific activity of the uranium inhaled. The concenration value for Table il is 0.007 milligrams uranium per cubic meter of air. The specific activity for nitural uranium is 6.77 x 10 7 curies per gram U. The specific activity for other mixtures of U-238, U-235 and U-234,if not known SHALL be: SA 3.6 x 10-7 curies / gram U U-depleted SA=(0.4 + 0.38 E + 0.0034 Er; 3o-8 Ego.72 where E is the percentage by weight of U-235, expressed as percent. [ i ... in any coes where there le e mirene in air er wetw of more sun one redenucNde,the IlmMin0
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wesues for pwpease of ede Appeeds should be doesnnined so feNews:
- 1. If the identity and concentration of each radionuclide in the mixbre are known, the limiting values should be derived as follows: Determine, for each radonuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radonuclide when not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed 1* (i.e ' unity")
EXAMPLE: If radionuclides A, B, and C are presentin concentrations CA, Ce and Cc. and if the applicable MPC's, are MPCA , and MPCs and MPCcrespectively, then the concentrations SHALL be limited so that the following relationship exists: (CA/MPCA)+(Cs/MPCs)+(Co/MPCC )51 (
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TRLE: NUMBER: H4 & OFFSITE DOSE CALCULATION W
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, TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) [ CONT'D]
Appendix B - Concentrations in Air and Water Above Natural Background Cont'd [See footnotes at end of Appendix B]
- 2. If either the idenhty or the concentration of an{aradionudide in the mixture is not known, the limiting values for purposes of Appendix B SHALL be:
- a. For purposes of Table I, Col.1-6 x 10-
- b. For purposes of Table 1, Col. 2-4 x 10-7
- c. For purposes of Table !!, Col 1-2 x 10-H
- d. For purposes of Table 11, Col 2-3 x 10-e
- 3. If any of the condtions specified below are met, the corresponding values specified below may be used in lieu of those specified in paragraph 2 above.
- a. If the identity of each radionuclide in the mixture is known but the concentraton of one or more of the radionuclides in the mixture is not known the concentrabon limit for the mixture is the limit specified in Appendx *B" for the radionudide in the mixture having the lowest concentration Emit; or
- b. If the identty of each radionudide in the mixturu is known, but it is known that certain radionuddes specified in Appendix "B" are not present in the mixture, the concentration limit for the mixture is the lowest concentration limit specified in Appendix B" for any radionudide which is not known to be absent from the mixture; or Table l Table ll
- c. Element (atomic number) and isotope Col.1 - Air Col 2 - Water Col 1 - Air Col. 2 - Water (pCi/ml) ( Ci/ml) (pCi/ml) (pCi/ml) 11 It is known that Sr 90, i 125, i 126. I 129, i 131 (I 133 Table 11 only) Pb 210 Po 210, At 211, Ra 223, Ra 224. Ra 226, Ac 227, Ra 228 Th 230, Pa 231, Th232.
Th nat, Cm 248 Cf254, and Fm 256 are not present.. 9x10-5 3x10-e if it is known that Sr 90, i 125, i 126, i 129 (I 131, i 133, Table 11 only), Pb 210 Pu 210, Ra 223, Ra 226, Ra 228, Pa 231. Th nat, Cm 248, Cf 254, and Fm 256 2x104 cr2 not present... 6x10-6 If it is known that Sr 90, i 129 (I 125,1126,1131. Table 11 only), Pb 210, Ra 226 Ra 228, Cm 248, and Cf 254 are not present _ _ . . 2x10-5 6x10-7 if it is known that (1129. Table il onty), Ra 226, and Ra 228 are not present ,. 3x104 1x10-7 ff itis known that alpha-emitters and Sr 90,1129, Pb 210, Ac 227, Ra 228, Pa 230, Pu 241,and Bk 249 are not present.. 3x10-o 1x10-2 If it is known that alpha-emitters and Pb 210, Ac 227, Ra 228, and Pu 241 are not present 3x10-2 1x10-" l If it is known that alpha-emitters and Ac 227 are not present .. 3x10-" 1 x10-12 If it is known that Ac 227 Th 230, Pa 231 Pu 238, Pu 239, Pu 240, Pu 242, Pu 244, Cm 248, Cf 249 and Cf 251 are not present - 3x1g-12 1x10-13 l
- 4. If a mixture of radionuclides consists of uranium and its daughters in ore dust prior to chemical separation of the uranium from the ore, the values specified below may be used for uranium and its daughters through radium-226, instead of those from paragraphs 1,2, or 3 above.
- c. For purposes of Table I, Col.1-1x10-MpCi/ml gross alpha activity: or 5x10-H pCi/mi natural uranium or 75 micrograms per cubic meter of air natural uranium.
- b. For purposes of Table 11. Col.1-3x10-12pCi/mi gross alpha activity: 2x10-12pCi/ml natural uranium or 3 micrograms per cubic meter of air natural uranium.
- 5. For purposes of this note, a radionuclide may be considered as not present in a mixture if (a) the rato of the concentration of that radonuclide in the mixture (CA) to the concentration limit for that radonuclide specified in Table 11 of Appendix *B* (MPC A ) does not exceed 1/10 (i.e. AC IMPC A st/10) t.nd (b) the sum of such ratios for all the radionuclides considered a not present in the mixture does not exceed 1/4 i.e.
(CalMPCA + CgIMPCs ..+ S f/4).
IE ISLAND NUCLEAR GENERATING PLANT h ERN STATES POWER COMPANY d H PROCEDURES's y TITLE: NUMBER: H4
"'S" o S5 o^'o"'^ "
l-l '
~
MANUAL (ODCM) REV: 14 isostisM Page 117 of 223 TABLE 5.1 - MONITOR ALARM SETPOINT DETERMINATION FOR PINGP g.; e , , tSOURCE3 . yEFFLUENTS pRFIFASEg
'% - RELEASE SOURCE OF gTERMS (A;) . . . . . c ., s FLOW HATE FRACTION MONITOR ^
POINT < RELEASE f(TABLE 3.1-2)!! FX/Q(sec/m3 1s !?fF) 4 * (cfmi t (TinlM 1R ,30 Aux. Bldg. Aux. Bldg. and Vent-Unit 1 Unit 1 Exhaust Aux. Bldg. 3.38E-5 2.9E+4 0.2 1R47 Air Ejector Air Ejector 3.38 E-5 2.9E+4 Unit 1 2R-30 Aux. Bldg. Aux. Bldg. - and Vent -Unit 2 Unit 2 Exhaust Aux. B:dg. 3.38E-5 4.1 E+4 0.3 2R-37 Gas Decay Xe-133 (100%) 1.32E-4 4.1 E+4 Tanks Air Ejector Air Ejector 3.38E-5 4.1 E+4 Unit 2 1 R-12 and Shield Bldg. Cont. - Units 1R-22 Vent- Unit 1 1&2 Purge, Unit Shield Bldg. 1.32E-4 3.2E+4 0.3 1 (Note 2) Inservice Purge 2R-12 and Shield Bldg. Cont. - Unit 2 Shield Bldg. 1.32E-4 4.6E+3 0.3 2R-22 Vent-Unit 2 Inservice Purge R 35 Radwaste Bldg. Radwaste Bldg. Aux. Eldg. 3.38E-5 6.1 E+3 0.1 Vent Exhaust R-25 and Spent Fuel Pool Spent Fuel Pool Aux. Bldg. 3.38E-5 1.8E+4 0.1 R-31 Air Vent Air Exhaust Values listed for Tm are nominal values only. They may be adjusted as necessary to allow a reasonable _i. mar 9in to the monitor setpoint. Dupilcate values of Tm are assigned to both Sb! eld Build!ng vents YN..
- 1. OT.E*n; F7 g$;g since only one containment will be purged at any one time. The assigned Tmvalues of allactive
- g -
release points SHALL NOT be greater than unity. jg p.. . .. 7.pd 2 s When purging the Unit 1 containment via the Inservice purge system, the monitor setpoints may be based on 4.6E+3 cfm for the duration of the release.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g_ , 04 ~ ~ ,
~
TITLE: NUMBER: OFFSITE DOSE CALCULATION H4
- 'o .
MANUAL (ODCM) REV: 14
. Section,
~' Page 118 0f 223 THIS PAGE IS LEFT INTENTIONALLY BLANK t
J G G G ,
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
^
. TITLE: NUMBER:
(s i
~ qu OFFSITE DOSE CALCULATION H4
' ": . I
.. _f/ MANUAL (ODCM) REV: 14 c section
Paae 119 of 223 l TABLE 5.2 - GASEOUS SOURCE TERMS 1
' !!AUXtBLDG; 1 SHIELD BLDG t , ? AIR EJECTOR 0 RADIONUCLIDE s ' l(A);(Ci/Yi)jj[
i s [(A);(Cl/Yr)]i i & ((Aj)l(Ci/Yr)) Kr-85m 3EO - 2EO Kr-85 2EO 2.2E1 - Kr-87 1EO - - Kr-88 SEO 1EO 3EO i Xe-131m 2EO 2.1 E1 1EO Xe-133m SEO 2E1 3EO Xe-133 3.7E2 2.7E3 2.3E2 Xe-135 8EO 6EO SEO
)
Xe-138 1EO - - TOTAL 3.97E2 2.77E3 2.44E2
" " indicates that the release is less than 1 Ci/yr.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
$f 's TITLE: NUMBER:
O
- g. . a. , a.. ^
H4 x OFFSITE DOSE CALCULATION W
# ' I.__/ %
5
- S.-.e.ctionli.
MANUAL (ODCM) REV: 14 w4= Pace 120 of 223 THIS PAGE IS LEFT INTENTIONALLY BLANK
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I i e
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- NORTHERN STATES POWER COMPANY H PROCEDURES i ,#9f?? -.. J ' <- ' , '
TITLE: NUMBER: O m Ma~ f, 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14
.- Sectiott, <
Pace 121 of 223 i TABLE 5.3 - CRITICAL ORGAN DOSE VALUES (Pid for Child
' ,~ .,y , imram/vr;>
ISOTOPE . (Pdjf", ,
< jpCi/m!!! l 4 1
H-3 1.12 E 3 Cr-51 1.70 E 4 i Mn-54 1.58 E 6 j j Fe-59 1.27 E 6 l Co-58 1.11 E 6
- Co-60 7.07 E 6 Zn-65 . 9.95 E 5 Rb-86 1.98 E 5 Sr-89 2.16 E 6 Sr-90 1.01 E 8 6
Y-91 2.f;3E6 Zr-95 2.2356 Nb-95 6.14 E 5 Ru-103 6.62 E 5 Ru-106 1.43 E 7 Ag-110m 5.48 E 6 Te-127m 1.48 E 6 Te-129m 1.76 E 6 Cs-134 1.01 E 6 Cs-136 1.71 E 5 Cs-137 9.07 E 5 Ba-140 1.74 E 6 Ce-141 5.44 E 5 Ce-144 1.20 E 7 l-131 1.62 E 7 O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES we TITLE: NUMBER:
^ [$" g, g OFFSITE DOSE CALCULATION H4 g 'is 41_y 1,g*
- MANUAL (ODCM) REV: 14 C-Section "'s-
- - - :1.xe - Page 122 of 223 THIS PAGE IS LEFT INTENTIONALLY BLANK O
I i 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ag + TITLE: NUMBER: O ^ d _H_[- OFFSITE DOSE CALCULATION H4 REV: 14 ysecuon? - MANUAL (ODCM)
#^ '~ '
Paae 123 of 223 TABLE 5.4-D_QSE FACTORS FOR NOBLE GASES
- Jotal B.ody, Dose} , _ . .. . . . .; ;Be.ta' Air Doset
!Factorl{ ,
LSkI(.. _ . 6l,e Ds Fsetod iGaitsmalAlfDossi iFshtb6! iKle . iLis Factor l Mis edNIN d~hirehi/r:'pe@ [i(niradlyiped Ilinfad/pEpers: Rnirehi/yfp[urj RAdi_.,on dslidej 3Ci/m3)f" 7{pCilip3) '
~
" 1%Ci/m3)f ' 3 C_i/ m 3) [
Kr-83m 7.56E-02 1.93 E+01 2.88E+02 Kr--85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73 E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 163E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 i Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 l Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- The listed dose factors are for radionuclides that may be detected in gaseous effluents.
All others are 0. O
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: H4 _" , , OFFSITE DOSE CALCULATION REV: 14 iSectione > MANUAL (ODCM) Paae 124 of 223 THIS PAGE IS LEFT INTENTIONALLY BLANK O e!l i
E ISLAND NUCLEAR GENERATING PLANT '- NhKERN STATES POWER COMPANY H PROCEDURES I TITLE: NUMBER: N'}@'C'n3.g[3~ "4 M! ', k&51 QM gg:5 OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM)
;m sseedank:.:3
-W~ ' Pace 125 of 223 1
l TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- l
-GROUND. ALL AGES 1 PATHWAY = GROUND
! NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN l MN54 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.34E 09 1.57E 09 FE 59 2.75E 08 2.75E 08 2.75E 08 2.75E 08 2.75E 03 2.75E 08 2.75E 08 3.23E 08 CO 58 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 3.79E 08 4.44E 08 CO 60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.52E 10 ! SR 89 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.23E 04 2.58E 04 1131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 CS134 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 6.82E 09 7.96E 09 CS137 1.03E 10 1.03E 10 1.03E 1'O 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1-133 2.45E 06 2.45E 06 2.45E 06 2.45E 06 2.45E 06 2.45E 06 2.45E 06 2.98E 06 NB-95 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.36E 08 1.61 E 08 ZR-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.84E 08 i CS-136 1.51 E 08 1.51 E 08 1.51 E 08 1.51 E 08 1.51E 08 1.51E 08 1.51 E 08 1.71E 08 i AG-110M 3.44E 09 3.44E 09 3.44E 09 3.44E 09 3.44E 09 3.44E 09 3.44E 09 4.01 E 09
- R VALUES IN UNITS OF MREM /YR PER pCl/M3FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
, - - , ~ . , , . , - - , - , - <- -~, a . ,e m ,e en,- ~ , ,, + ,
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES mpgisegggf xwi$ TITLE: NUMBER: gdh@ 7 jY J. "4 OFFSITE DOSE CALCULATION 1
,[J
- tsm4 k# [-- MANUAL (ODCM) REV: 14
. m m page 12s of 99 =
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
-VEGETABLE. ADULT PATHWAY = VEGET AGE GROUP EQUALS ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KlDNEY THYROID LUNG SKIN H 3 2.28E 03 2.28E 03 0.00E 00 2.28E 03 2.28E 03 2.28E 03 2.28E 03 2.28E 03 MN54 5.83E 07 9.36E 08 0.00E 00 3.05E 08 9.09E 07 0.00E 00 0.00E 00 0.00E 00 FE 59 1.12E 08 9.75E 08 1.24E 08 2.93E 08 0.00E 00 0.00E 00 8.17E 07 0.00E 00 CO 58 6.71 E 07 6.07E 08 0.00E 00 2.99E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 3.67E 08 3.12E 09 0.00E 00 1.66E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 2.87E 08 1.60E 09 1.00E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.64E 11 1.93E 10 6.70E 11 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 6.61 E 07 3.04E 07 8.07E 07 1.15E 08 1.98E 08 3.78E 10 0.00E 00 0.00E 00 CS134 8.83E 09 1.89E 08 4.54E 09 1.08E 10 3.49E 09 0.00E 00 1.16E 09 0.00E 00 CS137 5.94E 09 1.76E 08 6.63E 09 9.07E 09 3.08E 09 0.00E 00 1.02E 09 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
e O 9
.-_% -..Jm.- . 46._am. .34 ,A . A4 a4+I-.-_61 .e--. %._.-4S--h = - 4 4^+4 *4""- -
% A'* 1-E ISLAND NUCLEAR GENERATING PLANT N ERN STATES POWER COMPANY H PROCEDURES
, TITLE: NUMBER:
[- $hjf. OFFSITE DOSE CALCULATION REV: 14
^
n _._?" (Section? ,:, MANUAL (ODCM) ' Pace 127 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- VEGETABLE. TEEN PATHWAY = VEGET AGE GROUP EQUALS TEEN NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.61 E 03 2.61 E 03 0.00E 00 2.61 E 03 2.61E 03 2.61E 03 2.61 E 03 2.61 E 03 MN 54 8.79E 07 9.09E 08 0.00E 00 4.43E 08 1.32E 08 0.00E 00 0.00E 00 0.00E 00 FE 59 1.60E 08 9.78E 08 1.77E 08 4.14E 08 0.00E 00 0.00E 00 1.30E 08 0.00E 00 CO 58 9.79E 07 5.85E 08 0.00E 00 4.25E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 5.57E 08 3.22E 09 0.00E 00 2.47E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 4.36E 08 1.81 E 09 1.52E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ,
SR 90 2.05E 11 2.33E 10 8.32E 11 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 , i131 5.77E 07 2.13E 07 7.68E 07 1.07E 08 - 1.85E 08 3.14E 10 0.00E 00 0.00E 00 CS134 7.54E 09 2.02E 08 6.90E 09 1.62E 10 5.16E 09 0.00E 00 1.97E 09 0.00E 00 CS137 4.90E 09 2.00E 08 1.06E 10 1.41 E 10 4.78E 09 0.00E 00 1.86E 09 0.00E 00 R VALUES IN UNITS OF MREM /YR PER Cl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER Cl/SEC FOR ALL OTHERS. ______m_ _ _ _ _ . _ _ _ _ - . _ . . _ _ _ _ _ . _ _ - _ . _ _ _ _ _ _ _ _ - _ _ _ - __ ___-__m_-___ _______._______-.________-.-___-__mimr_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - - .______-______._u___ ___._
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES , W TITLE: NUMTER:
"4 OFFSITE DOSE CALCULATION j s,,, ~._
7 hSectiottji s MANUAL (ODCM) REY: 14 we~ 4 -~ Pace 128 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
-VEGETABLE. CHILD PATHWAY = VEGET AGE GROUP EQUALS CHILD NUCLIDE T. BODY GI-TRACT BONE LIVER KlDNEY THYROlD LUNG SKIN H 3 4.04E 03 4.04E 03 0.00E 00 4.04E 03 4.04E 03 4.04E 03 4.04E 03 4.04E 03 MN54 1.73E 08 5.44E 08 0.00E 00 6.49E 08 1.82E 08 0.00E 00 0.00E 00 0.00E 00 FE 59 3.17E 08 6.62E 08 3.93E 08 6.36E 08 0.00E 00 0.00E 00 1.84E 08 0.00E 00 CO 58 1.92E 08 3.66E 08 0.00E 00 6.27E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 1.11 E 09 2.08E 09 0.00E 00 3.76E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 1.03E 09 1.40E 09 3.62E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 3.49E 11 1.86E 10 1.38E 12 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 8.16E 07 1.28E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 0.00E 00 0.00E 00 CS134 5.40E 09 1.38E 08 1.56E 10 2.56E 10 7.93E 09 0.00E 00 2.84E 09 0.00E 00 CS137 3.52E 09 1.50E 08 2.49E 10 2.39E 10 7.78E 09 0.00E 00 2.80E 09 0.00E 00 1-133 1.65E OS 1.76E 06 3.53E 06 4.37E 06 7.28E 06 8.12E 08 0.00E 00 0.00E 00 NB-95 1.12E 05 2.91 E 08 4.04E 05 1.57E 05 1.48E 05 0.00E 00 0.00E 00 0.00E 00 ZR-95 7.35E 05 8.61 E 08 3.75E 06 8.25E 05 1.18E 06 0.00E 00 0.00E 00 0.00E 00 CS-136 1.46E 08 7.95E 06 8.23E 07 2.26E 08 1.21E 08 0.00E 00 1.80E 07 0.00E 00 AG-110M 1.86E 07 2.77E 09 3.45E 07 2.33E 07 4.34E 07 0.00E 00 0.00E 00 0.00E 00 R VALUES IN UNITS OF MREM /YR PER Cl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF
MREM /YR PER pCl/SEC FOR ALL OTHERS.
~
O O O
IE ISLAND NUCLEAR GENERATING PLANT h ERN STATES POWER COMPANY H PROCEDURES
. 1.j!T4 x TITLE: NUMBER:
m n - 94 t s~
~ Ed OFFSITE DOSE CALCULATION a , ,_.,-
MANUAL (ODCM) REV: 14 h I
**x Pace 129 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- MEAT. ADULT PATHWAY = MEAT AGE GROUP EQUALS ADULT ,
NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 3.25E 02 3.25E 02 0.00E 00 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 MN54 9.46E 05 1.52E 07 0.00E 00 4.96E 06 1.47E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 1.14E 08 9.93E 08 1.27E 08 2.98E 08 0.00E 00 0.00E 00 8.32E 07 0.00E 00 CO 58 1.99E 07 1.80E 08 0.00E 00 8.90E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 l COEO 9.37E 07 7.98E 08 0.00E 00 4.25E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 4.21 E 06 2.35E 07 1.47E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.86E 09 2.19E 08 7.57E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ; i131 4.34E 06 2.00E 06 5.30E 06 7.58E 06 1.30E 07 2.48E 09 0.00E 00 0.00E 00 CS134 7.04E 08 1.51 E 07 3.62E 08 8.61 E 08 2.79E 08 0.00E 00 9.25E 07 0.00E 00 CS137 4.57E 08 1.35E 07 5.10E 08 6.98E 08 2.37E 08 0.00E 00 7.88E 07 0.00E 00 , i
- R VALUES IN UNITS OF MREM /YR PER Cl/M 3FOR INHALATION AND TRITIUM, AND IN UNITS OF l M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
l .
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
^'r ^ "
TITLE: NUM2ER:
' H4 OFFSITE DOSE CALCULATION
'N
. I MANUAL (ODCM) REV: 14
, SGCtl00m .~
RR 2M Page 130 of 972 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- MEAT. TEEN PATHWAY = MEAT AGE GROUP EQUALS TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 l 1.94E 02 1.94E 02 0.00E 00 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 MN 54 7.50E 05 7.75E 06 0.00E 00 3.78E 06 1.13E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 9.13E 07 5.59E 08 1.01 E 08 2.36E 08 0.00E 00 0.00E 00 7.46E 07 0.00E 00 CO 58 1.58E 07 9.45E 07 0.00E 00 6.86E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 7.42E 07 4.29E 08 0.00E 00 3.30E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 !
SR 89 3.55E 06 1.47E 07 1.24E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.21 E 09 1.37E 08 4.90E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 3.31 E 06 1.22E 06 4.40E 06 6.16E 06 1.06E 07 1.80E 09 0.00E 00 0.00E 00 CS134 3.14E 08 8.42E 06 2.88E 08 6.77E 08 2.15E 08 0.00E 00 8.22E 07 0.00E 00 CS137 1.96E 08 8.02E 06 4.24E 08 5.64E 08 1.92E 08 0.00E 00 7.46E 07 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCI/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS. O O O
IE ISLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY O)
'N./ H PROCEDURES IiM n TITLE: NUMBER:
- %MMwa,3-94
~f_,
y ;.v .difF
%J OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM) ~ MSectionhW!i wg mme - -
y* Pace 131 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- MEAT. CHILD PATHWAY = MEAT AGE GROUP EQUALS CHILD NUCLIDE T. BODY Gl-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.34E 02 2.34E 02 0.00E 00 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 MN54 1.15E 06 3.63E 06 0.00E 00 4.33E 06 1.21E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 1.45E 08 3.03E 08 1.80E 08 2.91 E 08 0.00E 00 0.00E 00 8.43E 07 0.00E 00 CO 58 2.45E 07 4.67E 07 0.00E 00 8.01 E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 1.15E 08 2.17E 08 0.00E 00 3.91 E 07 0.00E 00 0.00E 00' O.00E 00 0.00E 00 SR 89 6.69E 06 9.07E 06 2.34E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.60E 09 8.52E 07 6.33E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 4.66E 06 7.31 E 05 8.16E 06 8.21 E 06 1.35E 07 2.71 E 09 0.00E 00 0.00E 00 CS134 1.76E 08 4.49E 06 5.07E 08 8.33E 08 2.58E 08 0.00E 00 9.26E 07 0.00E 00 CS137 1.10E 08 4.68E 06 7.81 E 08 7.47E 08 2.43E 08 0.00E 00 8.76E 07 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
PRAIRIE ISLAND SiUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
~ ~
TITLE: NUMBER:
~ H4 FFSITE DOSE CALCULATION
- M_li.m tSecthmm;l 3M MANUAL (ODCM) REV: 14 Paae 132 of ??3 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
-COW MILK. ADULT PATHWAY = COW MILK AGE GROUP EQUALS ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 7.63E 02 7.63E 02 0.00E 00 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 MN54 8.67E 05 1.39E 07 0.00E 00 4.54E 06 1.35E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 1.27E 07 1.10E 08 1.41 E 07 3.31 E 07 0.00E 00 0.00E 00 9.26E 06 0.00E 00 CO 58 5.15E 06 4.6SE 07 0.00E 00 2.30E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 2.04E 07 1.74E 08 0.00E 00 9.27E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 2.00E 07 1.12E 08 6.99E 08 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 6.99E 09 8.22E 08 2.85E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 1.19E 08 5.50E 07 1.46E 08 2.08E 08 3.57E 08 6.83E 10 0.00E 00 0.00E 00 CS134 6.05E 09 1.30E 08 3.11 E 09 7.40E 09 2.40E 09 0.00E 00 7.95E 08 0.00E 00 CS137 3.87E 09 1.14E 08 4.32E 09 5.91 E 09 2.01 E 09 0.00E 00 6.67E 08 0.00E 00 R VALUES IN UNITS OF MREM /YR PER Cl/M3FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
O O O
m N. AEERN ISLAND STATES POWER NUCLEAR COMPANY GENERATING ] PLANT H PROCEDURES
; / N^ TITLE: NUMBER:
"4
- OFFSITE DOSE CALCULATION
' :' ' MANUAL (ODCM) REV: 14
' 'secuan a
> +
Pace 133 0f 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- COW MILK. TEEN PATHWAY = COW MILK AGE GROUP EQUALS TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 9.94E 02 9.94E 02 0.00E 00 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 MN54 1.50E 06 1.55E 07 0.00E 00 7.57E 06 2.26E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 2.22E 07 1.36E 08 2.46E 07 5.74E 07 0.00E 00 0.00E 00 1.81 E 07 0.00E 00 CO 58 8.91 E 06 5.33E 07 0.00E 00 3.87E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 3.54E 07 2.05E 08 0.00E 00 1.57E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 3.69E 07 1.53E 08 1.29E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 9.93E 09 1.13E 09 4.02E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00
~ l131 1.99E 08 7.32E 07 2.64E 08 3.70E 08 6.37E 08 1.08E 11 0.00E 00 0.00E 00 CS134 5.90E 09 1.58E 08 5.40E 09 1.27E 10 4.04E 09 0.00E 00 1.54E 09 0.00E 00 CS137 3.63E 09 1.48E 08 7.83E 09 1.04E 10 3.55E 09 0.00E 00 1.38E 09 0.00E 00 t
- R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER Cl/SEC FOR ALL OTHERS.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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TITLE: NUMBER:
"4 '
1 ~ OFFSITE DOSE CALCULATION REV: 14
~
,i ' !~5 MANUAL (ODCM)
; section -
^
Page 134 of 992 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- COW MILK. CHILD PATHWAY = COW MILK AGE GROUP EQUALS CHILD NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.57E 03 1.57E 03 0.00E 00 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 MN 54 3.02E 06 9.50E 06 0.00E 00 1.13E 07 3.17E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 4.60E 07 9.61 E 07 5.70E 07 9.23E 07 0.00E 00 0.00E 00 2.68E 07 0.00E 00 CO 58 1.81 E 07 3.45E 07 0.00E 00 5.91 E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 7.19E 07 1.35E 08 0.00E 00 2.44E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 9.10E 07 1.23E 08 3.19E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.72E 10 9.15E 08 6.80E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 3.66E 08 5.74E 07 6.41 E 08 6.45E 08 1.06E 09 2.13E 11 0.00E 00 0.00E 00 CS134 4.13E 09 1.10E 08 1.25E 10 2.04E 10 6.34E 09 0.00E 00 2.27E 09 0.00E 00 ;
CS137 2.67E 09 1.13E 08 1.89E 10 1.81 E 10 5.89E 09 0.00E 00 2.12E 09 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS. O O O
1 N E ISLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY H PROCEDURES d h s . TITLE: NUMBER: . M~ "4 h OFFSITE DOSE CALCULATION en ~, 11 1 (90Ctl043@9 MANUAL (ODCM) REV: 14 4 ma -- Pace 135 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- COW MILK. INFANT ,
PATHWAY = COW MILK AGE GROUP EQUALS INFANT NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 2.38E 03 2.38E 03 0.00E 00 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 MN 54 4.77E 06 7.73E 06 0.00E 00 2.11E 07 4.67E 06 0.00E 00 0.00E 00 0.00E 00 FE 59 7.33E 07 8.88E 07 1.06E 08 1.86E 08 0.00E 00 0.00E 00 5.50E 07 0.00E 00 CO 58 2.95E 07 2.94E 07 0.00E 00 1.18E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 1.18E 08 1.18E 08 0.00E 00 4.98E 07 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 1.74E 08 1.25E 08 6.06E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.88E 10 9.23E 08 7.40E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 i131 6.93E 08 5.63E 07 1.34E 09 1.58E 09 1.84E 09 5.18E 11 0.00E 00 0.00E 00 CS134 3.78E 09 1.02E 08 2.01E 10 3.74E 10 9.64E 09 0.00E 00 3.95E 09 0.00E 00 CS137 2.50E 09 1.10E 08 3.01 E 10 3.53E 10 9.46E 09 0.00E 00 3.83E 09 0.00E 00
- R VALUES IN UNITi.Jr: MREM /YR PER pCl/M 3FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER Cl/SEC FOR ALL OTHERS. .
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MTHERN STATES POWER COMPANY _ -. .,vutcan utneHATING PLANT _ o sg * *M$ '
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TITLE: '
.- H PROCEDURES 48 '
' NUMBER: R e ' ^ secom, p$
> OFFSITE DOSE CALCULATION H4 g w w q MANUAL (ODCM)
REV: 14 i p,o, 3 38 o, ,,,, TABLE 5.5-12-B VALUES FOR EAR _ THE PRAIRIE ISLANENUCL GENERATING PLANT
- _ GOAT MILK. ADUE PATHWAY = GOATMILK AGE GROUP EQUALS ADULT
_ NUCLIDE T. BODY GI-TRACT BONE H 3 LIVER 1.56E 03 f 1.56E 03 KIDNEY THYROID 0.00E 00 1.56E 03 LUNG SKIN MN54 1.04E 05 ' 1.56E 03 1.67E 06 ' 1.56E 03 1.56E 03 0.00E 00 5.45E 05 ' 1.56E 03 FE 59 1.65E 05 1.62E 05 1.44E 06 0.00E 00 0.00E 00 1.83E 05 4.31E 05 0.00E 00 _ CO 58 6.18E 05 0.00E 00 5.59E 06 0.00E 00 1.20E 05 0.00E 00 2.76E 05 CO 60 0.00E 00 2.45E 06 2.09E 07 0.00E 00 0.00E 00 0.00E 00 } 0.00E 00 1.11E 06 0.00E 00 SR 89 4.21E 07 0.00E 00 2.35E 08 0.00E 00 0.00E 00 1.47E 09 0.00E 00 ~ [ SR 90 1.47E 10 1.73E 09 0.00E 00 0.00E 00 0.00E 00 I131 5.98E 10 0.00E 00 0.00E 00 0.00E 00 \ -. 1.43E 08 6.60E 07 0.00E 00 0.00E 00
! 1.75E 08 2.50E 08 0.00E 00 CS134 4.29E 08 i
1.82E 10 3.89E 08 8.20E 10 0.00E 00 0.00E 00 } 9.33E 09 2.22E 10 0.00E 00 CS137 1.16E 10 7.19E 09
- 3.43E 08 0.00E 00 2.39E 09 1.30E 10 1.77E 10 0.00E 00 _
6.02E 09 0.00E 00 i 2.00E 09 0.00E 00
- R VALUES IN UNITS OF MREM /YR PER pCl/M3M2-MREM .
O 9 9
E ISLAND NUCLEAR GENERATING PLANT N ERN STATES POWER COMPANY H PROCEDURES NUMBER:
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- s TITLE:
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H4
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OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM)
. sectiorin, :J > '
Pace 137 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- GOAT MILK. TEEN PATHWAY = GOATMILK AGE GROUP EQUALS TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKil H 3 2.03E 03 2.03E 03 0.00E 00 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 MN54 1.80E 05 1.86E 06 0.00E 00 9.08E 05 2.71 E 05 0.00E 00 0.00E 00 0.00E 00 FE 59 2.88E 05 1.76E 06 3.20E 05 7.46E 05 0.00E 00 0.00E 00 2.35E 05 0.00E 00 CO 58 1.07E 06 6.40E 06 0.00E 00 4.64E 05 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 4.24E 06 2.45E 07 0.00E 00 1.88E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 7.74E 07 3.22E 08 2.70E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 2.09E 10 2.37E 09 8.45E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 2.39E 08 8.79E 07 3.17E 08 4.44E 08 7.65E 08 1.30E 11 0.00E 00 0.00E 00 CS134 1.77E 10 4.74E 08 1.62E 10 3.81 E 10 1.21E 10 0.00E 00 4.63E 09 0.00E 00 CS137 1.09E 10 4.45E 08 2.35E 10 3.13E 10 1.06E 10 0.00E 00 4.13E 09 0.00E 00 ,
t R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
- , TITLE: NUMBER:
^
J H4 OFFSITE DOSE CALCULATION
-^
MANUAL (ODCM) REV: 14
'^ ' Pane 138 0f ??2 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- GOAT MILK. CHILD PATHWAY = GOATMILK AGE GROUP EQUALS CHILD NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 3.20E 03 3.20E 03 0.00E 00 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03
~
MN54 3.62E 05 1.14E 06 0.00E 00 1.36E 06 3.81E 05 0.00E 00 0.00E 00 0.00E 00 FE 59 5.98E 05 1.25E 06 7.42E 05 1.20E 06 0.00E 00 0.00E 00 3.48E 05 0.00E 00 CO 58 2.17E 06 4.14E 06 0.00E 00 7.09E 05 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 8.63E 06 1.62E 07 0.00E 00 2.93E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 1.91 E 08 2.59E 08 6.69E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 3.62E 10 1.92E 09 1.43E 11 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 4.40E 08 6.89E 07 7.70E 08 7.74E 08 1.27E 09 2.56E 11 0.00E 00 0.00E 00 CS134 1.29E 10 3.31 E 08 3.74E 10 6.13E 10 1.90E 10 0.00E 00 6.82E 09 0.00E 00 CS137 8.00E 09 3.39E 08 5.66E 10 5.42E 10 1.77E 10 010E 00 6.35E 09 0.00E 00 R VALUES IN UNITS OF MREM /YR PER Cl/M3FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS. 9 O O
h IE ISLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY s H PROCEDUREbd h
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TITLE: NUMBER:
' ~ "4
' : OFFSITE DOSE CALCULATION
^
~
~'.
MANUAL (ODCM) REV: 14
^
section, Pace 139 of 223 TABLE 5.5 R VALUES FOR THE FRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- GOAT MILK. INFANT PATHWAY = GOATMILK l AGE GROUP EQUALS INFANT l NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 4.86E 03 4.86E 03 0.00E 00 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 I
MN54 5.73E 05 9.28E CF 0.00E 00 2.53E 06 5.60E 05 0.00E 00 0.00E 00 0.00E 00 FE 59 9.53E 05 1.15E 06 1.38E 06 2.42E 06 0.00E 00 0.00E 00 7.15E 05 0.00E 00 CO 58 3.54E 06 3.53E 06 0.00E 00 1.42E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 1.41 E 07 1.42E 07 0.00E 00 5.97E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 3.65E 08 2.62E 08 1.27E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 3.95E 10 1.94E 09 1.55E 11 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 8.32E 08 6.76E 07 1.61 E 09 1.89E 09 2.21E 09 6.22E 11 0.00E 00 0.00E 00 CS134 1.13E 10 3.05E 08 6.02E 10 1.12E 11 2.89E 10 0.00E 00 1.19E 10 0.00E 00
^
CS137 7.50E 09 3.31 E 08 9.04E 10 1.06E 11 2.84E 10 0.00E 00 0.00E 00 l 1.15E 10
- R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES , TITLE: NUMBER: $.=;-N,: de gI#
~
2 d" - OFFSITE DOSE CALCULATION H4 REV: 14 MANUAL (ODCM)
~<Iil a]M J a,sec, tion
' ~
p ,,3 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
-INHALATION. ADULT PATHWAY = INHAL AGE GROUP EQUALS ADULT NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.26E 03 1.26E 03 0.00E 00 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 MN54 6.29E 03 7.72E 04 0.00E 00 3.95E 04 9.83E 03 0.00E 00 1.42E 06 0.00E 00 FE 59 1.05E 04 1.88E 05 1.17E 04 2.77E 04 0.00E 00 0.00E 00 1.01 E 06 0.00E 00 CO 58 2.07E 03 1.06E 05 0.00E 00 1.58E 03 0.00E 00 0.00E 00 9.27E 05 0.00E 00 CO 60 1.48E 04 2.84E 05 0.00E 00 1.15E 04 0.00E 00 0.00E 00 5.96E 06 0.00E 00 SR 89 8.71 E 03 3.49E 05 3.04E 05 0.00E 00 0.00E 00 0.00E 00 1.40E 06 0.00E 00 SR 90 6.09E 06 7.21 E 05 9.91 E 07 0.00E 00 0.00E 00 0.00E 00 9.59E 06 0.00E 00 :
1131 2.05E 04 6.27E 03 2.52E 04 3.57E 04 6.12E 04 1.19E 07 0.00E 00 0.00E 00 CS134 7.27E 05 1.04E 04 3.72E 05 8.47E 05 2.87E 05 0.00E 00 9.75E 04 0.00E 00 CS137 4.27E 05 8.39E 03 4.78E 05 6.20E 05 2.22E 05 0.00E 00 7.51 E 04 0.00E 00 i R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS. O O O
to IE ISLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY ) H PROCEDURES ( C
/ '
~- u n.E: NUM ' ER:
~
~
b'2 OFFSITE DOSE CALCULATION H4
- ~
MANUAL (ODCM) REV: 14
:Secdon -
~ >
Page 141 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING.P_LANT*
-INHALATION. TEEN PATHWAY = INHAL AGE GROUP EQUALS TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.27E 03 1.27E 03 0.00E 00 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 MN54 8.39E 03 6.67E 04 0.00E 00 5.10E 04 1.27E 04 0.00E 00 1.98E 06 0.00E 00 FE 59 1.43E 04 1.78E 05 1.59E 04 3.69E 04 0.00E 00 0.00E 00 1.53E 06 0.00E 00 CO 58 2.77E 03 9.51 E 04 0.00E 00 2.07E 03 0.00E 00 0.00E 00 1.34E 06 0.00E 00 CO 60 1.98E 04 2.59E 05 0.00E 00 1.51 E 04 0.00E 00 0.00E 00 8.71 E 06 0.00E 00 SR 89 1.25E 04 3.71 E 05 4.34E 05 0.00E 00 0.00E 00 0.00E 00 2.41 E 06 0.00E 00 SR 90 6.67E 06 7.64E 05 1.08E 08 0.00E 00 0.00E 00 0.00E 00 1.65E 07 0.00E 00 1131 2.64E 04 6.48E 03 3.54E 04 4.90E 04 8.39E 04 1.46E 07 0.00E 00 0.00E 00 CS134 5.48E 05 9.75E 03 5.02E 05 1.13E 06 3.75E 05 0.00E 00 1.46E 05 0.00E 00 CS137 3.11 E 05 8.47E 03 6.69E 05 8.47E 05 3.04E 05 0.00E 00 j 1.21 E 05 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - NORTHERN STATES POWER COMPANY H PROCEDURES r') TITLE: NUMBER:
^
H4 2
'A OFFSITE DOSE CALCULATION 11_d ~ ^ ; MANUAL (ODCM) REV: 14 iSection? ',
~ 34 ' " - -
Page 142 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
-INHALATION. CHILD PATHWAY = INHAL AGE GROUP EQUALS CHILD NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.12E 03 1.12E 03 0.00E 00 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 MN54 9.50E 03 2.29E 04 0.00E 00 4.29E 04 1.00E 04 0.00E 00 1.57E 06 0.00E 00 FE 59 1.67E 04 7.06E 04 2.07E 04 3.34E 04 0.00E 00 0.00E 00 1.27E 06 0.00E 00 CO 58 3.16E 03 3.43E 04 0.00E 00 1.77E 03 0.00E 00 0.00E 00 1.10E 06 0.00E 00 CO 60 2.26E 04 9.61E 04 0.00E 00 1.31E 04 0.00E 00 0.00E 00 7.06E 06 0.00E 00 SR 89 1.72E 04 1.67E 05 5.99E 05 0.00E 00 0.00E 00 0.00E 00 2.15E 06 0.00E 00 SR 90 6.43E 06 3.43E 05 1.01 E 08 0.00E 00 0.00E 00 0.00E 00 1.47E 07 0.00E 00 ,
i131 2.72E 04 2.84E 03 4.80E 04 4.80E 04 7.87E 04 1.62E 07 0.00E 00 0.00E 00 CS134 2.24E 05 3.84E 03 6.50E 05 1.01 E 06 3.03E 05 0.00E 00 1.21 E 05 0.00E 00 CS137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.32E 05 0.00E 00 1.04E 05 0.00E 00 1-133 7.70E 03 5.48E 03 1.66E 04 2.03E 04 3.38E 04 3.85E 06 0.00E 00 0.00E 00 NB-95 6.55E 03 3.70E 04 2.35E 04 9.18E 03 8.62E 03 0.00E 00 6.14E 05 0.00E 00 ZR-95 3.70E 04 6.11 E 04 1.90E 05 4.18E 04 5.96E 04 0.00E 00 2.23E 06 0.00E 00 CS-136 1.16E 05 4.18E 03 6.51 E 04 1.71 E 05 9.55E 04 0.00E 00 1.45E 04 0.00E 00 AG-110M 9.14E 03 1.00E 05 1.69E 04 1.14E 04 2.12E 04 0.00E 00 5.48E 06 0.00E 00 R VALUES IN UNITS OF MREM /YR PER pCl/M3 FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER Cl/SEC FOR ALL OTHERS. O 6 9
i E ISLAND NUCLEAR GENERATING PLANT N ERN STATES POWER COMPANY H PROCEDURES
< + TITLE: NUMBER:
;i H4 OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14
, ; gg v
' ~
Pace 143 of 223 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT *
- INHALATION. INFANT PATHWAY = INHAL AGE GROUP EQUALS INFANT NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 6.46E 02 6.46E 02 0.00E 00 6.46E 02 6.46E 02 6.46E 02 6.46E 02 6.46E 02 MN 54 4.98E 03 7.05E 03 0.00E 00 2.53E 04 4.98E 03 0.00E 00 9.98E 05 0.00E 00 FE 59 9.46E 03 2.47E 04 1.35E 04 2.35E 04 0.00E 00 0.00E 00 1.01 E 06 0.00E 00 CO 58 1.82E 03 1.11 E 04 0.00E 00 1.22E 03 0.00E 00 0.00E 00 7.76E 05 0.00E 00 CO 60 1.18E 04 3.19E 04 0.00E 00 8.01E 03 0.00E 00 0.00E 00 4.50E 06 0.00E 00 SR 89 1.14E 04 6.39E 04 3.97E 05 0.00E 00 0.00E 00 0.00E 00 2.03E 06 0.00E 00 SR 90 2.59E 06 1.31 E 05 4.08E 07 0.00E 00 0.00E 00 0.00E 00 1.12E 07 0.00E 00 1131 1.96E 04 1.06E 03 3.79E 04 4.43E 04 5.17E 04 1.48E 07 0.00E 00 0.00E 00 CS134 7.44E 04 1.33E 03 3.96E 05 7.02E 05 1.90E 05 0.00E 00 7.95E 04 0.00E 00 CS137 4.54E 04 1.33E 03 5.48E 05 6.11E 05 1.72E 05 0.00E 00 7.12E 04 0.00E 00 R VALUES IN UNITS OF MREM /YR PER Cl/M3FOR INHALATION AND TRITIUM, AND IN UNITS OF M2-MREM /YR PER pCl/SEC FOR ALL OTHERS.
. _ _ - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ ___-____-__-.___-__-___-__--_____________-__-_____-___-__m- _ _ _ - - . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES w < c> ~ ' ~ < TITLE: NUMBER: H4 is - LE ~ J '. OFFSITE DOSE CALCULATION REV: 14 ds W ,5 5, g ' MANUAL (ODCM) M ? SectlOn "'
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MANUAL (ODCM) Pace 145 of 223 TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS Page 1 of 4 OI ip6sdriPittivE E ~' ~~ 7"INu~~itiei~df5shipiisE" n "Zi5ssiplinjiiB}"E "Ufjp5*sidf~~iHE 735] f' and Sample L :: . nn/or, su m ~ ~ s Tand Santpis Locations **f . u s w w w m u x osus m ad awa ICollestion:FrsquenspL uma w uammmmaama ^ ~ "Mof! Anal seasawwun maamaat R$* " e
- 1. AIRBORNE Samples from 5 locations: Continuouc hmpler operation Radiolodine analysis weekly Radioiodine and 3 samples from offsite locations (in with sampic ollection weekly for 1-131 Particulates different sectors) of the highest calculated annual average ground level Particulate:
D/O, Gross beta activity on each filter 1 sample from the vicinity of a weekly *. Analysis SHALL be community having the highest calculated performed more than 24 hours annual average ground-level D/O, nnd 1 following filter change. Perform sample from a control location specified gamma isotopic analysis on in the ODCM composite (by location) sample quarterly.
- 2. DIRECT RADIATION 32 TLD stations established with Quarterly Gamma dose duplicate dosimeters placed at the quarterly following locations:
- 1. Using the 16 meteorological wind sectors as guidelines, an inner ring of stations in the general area of the site boundary is established and an outer ring of stat lons in the 4 to 5 mile distance from the plant site is established. Because of inaccessibility, seven sectors in the inner and outer rings are not covered j If Gross beta activity in any indictor sample exceeds 10 times the yearly average of the control sample, a gamma isotopic analysis is required.
** Sample locations are further described by the REMP.
1
.- -. ~
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
-n TITLE:
- - NUMBER:
c' H4 OFFSITE DOSE CALCULATION x;'. ,' I
' Secth '~ MANUAL (ODCM) REV: 14 Page 146 of 991 TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS [ CONT'D]
Page 2 of 4 [,~~~ExjiIoidriPatliway ^'~~ M"ONUihissif~df Siidpiks{"T ""'l TSiispijny'lsndI"g" SiggsiiniiMyys*fWsy'gg s and/or Sample' > A mammuwum.nax;, uau.1and Sampletocations**4 iCollectioh ~ ':li 'lof AnslyslE ' Fredsericyi m'aziggwamagg,sAj w- w~a- a .- ma, x; _muumaaaugug
- 2. DIRECT RADIATION
[ Cont'd]
- 2. Seven dosimeters are established at specialinterest areas and a control station.
- 3. WATERBORNE
- a. Surface Upstream & downstream locations Monthly Composite of weekly Gamma isotopic analysis of samples (water & ice conditions each monthly composite permitting)
Tritium analysis of quarterly composites of monthly composites
- b. Ground 3 samples from wells within 5 miles of Quarterly Gamma isotopic and tritium the plant site and 1 sample from a well analyses of each sample greater than 10 miles for the piant site
- c. Drinking 1 sample from the City of Red Wing Monthly Composite of weekly 1-131 Analysis and Gross beta water supply samples and gamma isotopic analyses of each monthly composite Tritium analysis of quarterly composites of monthly composites Sample locations are further described by the REMP.
O O' O
h IE ISLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY (9
\/ H PROCEDURES (_/
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~ OFFSITE DOSE CALCULATION
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?Sectionse
~
k Pace 147 of 223 TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAR SAMPLE COLLECTION AND ANALYSIS [ CONT'D] Page 3 of 4 j35EIEs@ssieMisirsyjiW" ""]Niis6sfo[Sirdplisl(~~" ~ ~ ' ~ Sampling'ind""" "T~ ~ ~^' T5se id(FredUe'n"c~y~] W: and/or Sample T ~ ~ ' ~Jand Sample Loc Collection Frequency of Analysis 1 wwwawaaaamwwd>e&w aamm.a manausaa:ations**2 auussamma . ~ - - > , ~ - .. - ~ ~ :- ~ - - - ~; '
- 3. WATERBORNE
[ Cont'd]
- d. Sediment from One sample upstream of plant, one Semiannually Gamma isotopic analysis of shoreline sample downstream of plant, and one each sample from shoreline of recreational area.
- 4. INGESTION
- a. Milk One sample from dairy farm having Monthly or biweekly if animals Gamma isotopic and 1-131 highest D/Q, one sample from each of are on pasture analysis of each sample three dairy farms calculated to have doses from I-131 >
1 mrem /yr, and one sample from 10-20 miles
- b. Fish and One sample of one game specie of fish Semiannually Gamma isotopic analyses on invertebrates located upstream and downstream of the each sample (edible portion only plant site on fish)
One sample of Invertebrates upstream and downstream of the plant site Sample locations are further described by the REMP.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER:
- H4
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- s . OFFSITE DOSE CALCULATION REV: 14
. . . .. 3 -
MANUAL (ODCM) y is.cison;^ Page 148 of 993 TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS [ CONT'D] Page 4 of 4 nn.,,, - ~ - - - - - - - - - - - ,
- - ~ . . - nn._ ,- .
- t. . ' ~ ~- Type and Frequency-g,,sExposure..Pathwayf - ' % 7:3 Ndmbn ,,Sampl.ing,and3,a,ge,n, e erofn~~Samisest R _.
3 of Analysis tand Samplelocations** 4 ; !? and Lanamas/or,Samplei? .1,Collection me: -me~awa Frequency)a,m sa w as a h - anamaeas.usax m.maa.aauame&s. mc _-_-_-~s s~ a
- 4. INGESTION
[ Cont'd]
- c. Food Products One sample of com from any field that is At time of harvest Gamma isotopic analysis of irrigated by water into which liquid plant edible portion of each sample wastes have been discharged *"
One sample of broad leaf vegetation At time of harvest 1-131 analyses of edible portion from highest D/O garden and one of each sample sample from 10-20 miles
- Sample locations are further described by the FEMP.
" As determined by methods outlined in the ODCM.
O O O
IE ISLAND NUCLEAR CENERATING PLANT h ERN STATES POWER COMPANY H PROCEDUREb
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@JH ~ OFFSITE DOSE CALCULATION REV: 14 A MANUAL (ODCM) jsectioni V 2
W Page 149 of 223 TABLE 7.2- REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATION IN ENVIRONMENTAL SAMPLES WATER AIRBORNE PAR- FISH MILK FOOD PROD-ANALYSIS (pCill) TICULATE OR (pCl/kg, wet) (pCl/I) UCTS (pCilkg, GASES (pCl/m3) wet) H-3 30,000(a) Mn-54 1,000 30,000 Fe-59 400 10,000' Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400@) 1-131 20(a) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200@) 300@) (a) No drinking water pathway exists. (b) Total for parent and daughter.
.1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY Mye% >
TITLE: H PROCEDURES
+ n NUMBER:
OFFSITE DOSE CALCULATION H4 as _ l -
- !3 sections , : MANUAL (ODCM) REY: 14 Pace 150 of 293 THIS PAGE IS LEFT INTENTIONALLY BLANK l
O O O
I IE ISLAND NUCLEAR GENERATING PLANT [(,/ [) H PROCEDURES w./ ERN STATES POWER COMPANY ? TITLE: NUMIER: m ;W*: - 1.u .f ^ . 94 mm f w OFFSITE DOSE CALCULATION REV: 14 ~in 2.Jfl_.. secuan.. s MANUAL (ODCM) p TABLE 7.3 - DETECTION CAPABILITIES FOR ENVIRONMENTALSAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(a) , WATER AIRBORNE FISH MILK FOOD PROD- SEDIMENT ANALYSIS (pCill) PARTICULATE (pCilkg, wet) (pCl/1) UCTS (pCi/kg, (pCi/kg, dry) OR GASES wet) (pCl/m3) Gross Beta 4 0.01 30,000(a) H-3 3,000@) Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15(c) 1-131(d) 15@) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15(c) 15(c)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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H4
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~> ll y MANUAL (ODCM) REV: 14 Js.csson; J
' ~ Paae 152 of 772 TABLE 7.3-TABLE NOTATION a - The LLD is the smallest concentration of radioactive materialin a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66s. Lto - E . V. 2.22 . Y. exp {mt A t) Where: LLD is the apriori lower limit of detection as defined above (as picocurie per unit mass or volume), so is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background SHALL include the typical contributing of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y and At SHALL be used in the calculations. E is the counting efficiency (as counts per transformation), 2.22 is the number of transformation per minute per picocurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and . At is the elapsed time between sample coIIection (or end of the sample collection period) and time of counting. b - No drinking water pathway exists. c - Total for parent and daughter d - These LLDs apply only where "1311 analysis"is specified. e - Where " Gamma Isotopic Analysis"is specified, the LLD specification applies to the following radionuclides: 54Mn, 59pg, 58Co, 60Co, 65Zn, 95Zr-Nb,137Cs,134Cs, and 140Ba-La. Other peaks which are measurable and identifiable, bgether with the above nuclides, SHAl ' also be identified and reported. O O O
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT H PROCEDURES NORTHERN STATES POWER COMPANY .. NUMBER: H4 I OFFSITE DOSE CALCULATION V' E TITLE: MANUAL (ODCM) APPENDIX A-METEOROLOGICAL ANALYSES REV: 14 Page 157 of 223 Table A-1 Release Conditions Table A-2 Unrestricted Area Boundaries Table A-3 Long Term - Ground Level- Unrestricted Area Boundary-x/O and D/O Table A-4 Long Term - Ground Level- Standard Distances - x/O Table A-5 Long Term - Ground Level- Standard Distances - D/O Table A-6 Short Term - Ground Level- Unrestricted Area , Boundary-x/q and D/q , O Table A-7 Short Term - Ground Level - Standard Distances - x/q Table A-8 Short Term - Grcund Level - Standard Distances - D/q l O
i 1 PRAIRIE ISLAND NUCLEAR @ENERATING PLANT 1 l NORTHERN STATES POWER COMPANY H PROCEDURES 9 ii: L.E: NUMBER: f A OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h h+ e ss . Pace 158 of 223 l l l l ! THIS PAGE IS LEFT INTENTIONALLY BLANK i 1 i l O
1 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY H PROCEDURES l 7 P.O *f ..1 + TITLE: NUMBER: o c a.vyy uwyWDD 94 i'j , OFFSITE DOSE CALCUl # TION P p .:3 4. fR c ;,I
~
MANUAL (ODCM) REY: 14 hf;j QM ' bli.bv Page 159 of 223 APPENDIX - A Summarv of Dispersion Calculational Procedures l
- Undepleted, undecayed dispersion parameters were computed using the computer program
.XOODOQ (Sagendorf and Goll,1977). Specifically, sector average x/O and D/O values
. were obtained for a sector width of 22.5 degrees. Building wake corrections were used to adjust calculations for ground-level releases. Standard open terrain recirculation conection factors were also applied as available as default values in XOODOO. Dispersion calculations were based on ground level releases for the shield buildings, turbine buildings, and auxiliary building (hereafter referred to as the plant complex). A summary of release conditions used as input to XOODOQ is presented in Table A-1 and controlling unrestricted boundary distances are defined in Table A-2. Computed x/O and D/O values for unrestricted area boundary locations (relative to release points) and for standard distances Q b (to five miles from the source in 0.1 mile increments) are presented in Tables A-3 through A-8. Onsite meteorological data for the period April 1,1977 through March 31,1978 (as presented in Appendix B) were used as input to XOODOO. Data were collected and AT stability classes were defined in conformance with NRC Regulatory Guide 1.23. Dispersion calculations for the plant complex were based on AT 42.7-12.2m and 12.2 meter wind data (joint data recovery of 96 percent). O v
.l
PRAIRIE ISLAND NUCLEAR GENERATIN3 PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
- TITLE:
NUMBER: Na OFFSITE DOSE CALCULATION d, REV: 14 6 MANUAL (ODCM) E6i pwe Page 160 of 223 BEFERENCF,S
- 1. Sagendorf, J.F. and Goll, J.T., XOODOO Program for the Evaluation of Rcutine Efflueul Releases at Nuclear Power Stations, NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977.
O
o P ISLAND NUCLEAR GENERATING PLANT NO ERN STATES POWER COMPANY H PROCEDURES () _
, TITLE: NUMBER:
I
- H4 OFFSITE DOSE CALCULATION C - ~ REV: 14
~~
.h MANUAL (ODCM)
_i Ik Page 161 of 223 TABLE A PRAIRIE ISLAND RELEASE CONDITIONS Shield Buildings Auxiliary Building Turbine Building Type Release Ground Level Ground Level Ground Level (Long Term and Short Term) (Long Term) (Long Term) Release Point Height (m) 56.4 24.4 33.6,12.2 Adjacent Building Height 62.2 62.2* 62.2* Relative Location to Adjacent Struc- Adjacent to Adjacent to Adjacent to tures Auxiliary Building Auxiliary Building Auxiliary Building Exit Velocity (m/sec) N.A. N.A. N.A. Intemal Stack Diameter (m) N.A. N.A. N.A. Building Cross-Sectional Area (m2) 2,170 2,170** 2,170** Purge Frequency *** (times /yr) 20 N.A. N.A. Purge Duration *** (hours / release) 5 N.A. N.A.
- Height of Shield Buildings
" Shield Building cross-sectional area
"* Applied to short-term calculations only
PRAIRIE ISLAND NUCLEAR GENERATIN2 PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j""f 3CfJ.f51 SschJ m LE: NUMBER: 3 H4 ! 0 W l 1 1 1. Wf j.1.][. l OFFSITE DOSE CALCULATION
- j. i.i, .= :,c f f[Ligig,';.. ": : J '; REV: 14 MANUAL (ODCM) eg 7 .. ..
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rgu TITLE: NUMBER: w$$pLewer2 y* OFFSITE DOSE CALCULATION H4 M MANUAL (ODCM) REV: 14 b: Efe w ax - Page 163 of 223 TABLE A DISTANCES (MILES) TO CONTROLLING UNRESTRICTED AREA BOUS!DARYLOCATIONS As Measured from Edge of Plant Comolex Sant91 DlS101199 N 0.28 NNE 0.26 NE 0.84* ENE 0.62* E 0.69* ESE 0.61* SE 0.67 SSE 0.43 S 0.43 SSW 0.40 SW 0.40 WSW 0.37 W 0.36 WNW 0.36 NW 0.43 NNW 0.48
*Over-water distances e
(
I PRAIRIE ISLAND NUCLEAR GENERATING PLANT ; NORTHERN STATES POWER COMPANY H PROCEDURES l TITLE: NUMBER- l Ma-
- OFFSITE DOSE CALCULATION MANUAL (ODCM) REY: 14
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. IE ISLAND NUCLEAR CENERATING PLANT .
N ERN STATES POWER COMPANY %> H PROCEDURET
- ?.s W w. E :.f( " 9 / TITLE:
NUMBER: 7ty ;j H4 At: M. 3* : u%. ;.s -[ OFFSITE DOSE CALCULATION _ g f: :- 7dU MANUAL (ODCM) REv: 14
- 3 si'n 1. -J.~'-
L J.. R;, *jN1 Page 165 of 223 TABLE A-3-EBA_lRIE ISLAND DISPERSION PARAMETERS Prairie Island Dispersion Parameters for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Unrestricted Area Boundary Locations (identified in Table A-2)
Unrestricted Area yfQ (sec/m3) D/O (1/m2) Boundary Sector N 1.82E-05 1.18E-07 NNE 1.52E-05 8.55E-08 NE 1.83E-06 7.74E-09 ENE 3.25E-06 1.84E-08 E 1.05E-05 4.23E-08
- ESE 1.86E-05 7.30E-08 SE 1.67E-05 6.80E-08
- SSE 1.95E-05 6.81 E-08 S 8.12E-06 3.19E-08 l SSW 7.08E-06 2.55E-08 SW 7.66E-06 2.77E-08 WSW 1.13E-05 3.53E-08 l
t W 2.66E-05 7.63E-08 WNW 3.38E-05 1.42E-07 NW 2.13E-05 9.02E-08 l NNW 1.11 E-05 5.43E-08 \ Period of Record: 4/1/77 - 3/31/78 - i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES M1 Y[Vgl; . $:;- TITLE: NUMBER: Q . g 1.a p - }~.L S $ OFFSITE DOSE CALCULATION H4 i L g.D. . DJ J 5 MANUAL (ODCM) REY: 14
. _..1, . ? .Eji . " 'i 7,.;; f :. ; . . , .
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- j y7ij;;g 42% J J~D _4:i"~;% Page 167 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS Prairie Island Dispersion Parameters (X/Q), SEC/M3, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M D2 DJ Dd DJ Da D,Z N 1.20E-04 3.44E-05 1.66E-05 1.02E-05 7.04E-06 5.29E-06 4.13E-06 NNE 8.53E-05 2.44E-05 1.18E-05 7.20E-06 4.93E-06 3.67E-06 2.83E-06 NE 8.18E-05 2.35E-05 1.14E-05 6.87E-06 4.69E-06 3.49E-06 2.69E-06 ENE 7.88E-05 2.26E-05 1.10E-05 6.70E-06 4.62E-06 3.46E-06 2.69E-06 E 2.40E-04 6.89E-05 3.34E-05 2.02E-05 1.38E-05 1.02E-05 7.88E-06 ESE 4.52E-04 1.30E-04 6.28E-05 3.80E-05 2.59E-05 1.92E-05 1.48E-05 SE 4.85E-04 1.39E-04 6.74E-05 4.07E-05 2.77E-05 2.04E-05 1.56E-05 SSE 2.59E-04 7.44E-05 3.60E-05 2.17E-05 1.48E-05 1.10E-05 8.44E-06 S 1.08E-04 3.09E-05 1.46E-05 9.06E-06 6.20E-06 4.62E-06 3.58E-06 SSW 8.60E-05 2.46E-05 1.19E-05 7.19E-06 4.91 E-06 3.66E-06 2.83E-06 SW 9.19E-05 2.62E-05 1.26E-05 7.72E-06 5.31E-06 3.98E-06 3.09E-06 WSW 1.17E-04 3.35E-05 1.61 E-05 9.80E-06 6.70E-06 4.97E-06 3.83E-06 W 2.64E-04 7.56E-05 3.66E-05 2.22E-05 1.51 E-05 1.12E-05 8.61 E-06 WNW 3.42E-04 9.80E-05 4.75E-05 2.88E-05 1.98E-05 1.47E-05 1.14E-05 NW 2.91 E-04 8.35E-05 4.05E-05 2.46E-05 1.68E-05 1.25E-05 9.67E-06 NNW 1.76E-04 5.04E-05 2.45E-05 1.50E-05 1.03E-05 7.70E-06 5.99E-06 Period of Record: 4/1/77 - 3/31/78 l _ --- __ - -
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATE] POWEE COMPANY H PROCEDURES TID.E: NUMBER: gs.(i W ;7. 5- - - y. s . .wi. p.nlC H4
.--T M OFFSITE DOSE CALCULATION nM j f 3.y i REV: 14 MANUAL (ODCM)
. ;gege e n
. M E 3a .j. Page 168 of 223 TABLE A PRAIRIEISLANG DISPERSION PARAMETERS [ CONT'D]
Prairie Island Dispersion Parameters (x/Q), SEC/M3, for Long Term Ground Level Releases '
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector Da Da LQ 11 12 M M N 3.18E-06 2.39E-06 1.87E-06 1.51 E-06 1.24E-06 1.04E-06 8.80E-07 NNE 2.17E-06 1.62E-06 1.27E-06 1.02E-06 8.33E-07 6.95E-07 5.90E-07
~
NE 2.06E-06 1.54E-06 1.20E-06 9.60E-07
- 7.86E-07 6.56E-07 5.56E-07 ENE 2.07E-06 1.55E-06 1.21 E-06 9.72E-07 7.98E-07 6.66E-07 5.65E-07 E 6.02E-06 4.51 E-06 3.52E-06 2.82E-06 2.31 E-06 1.93E-06 1.64E-06 ESE 1.13E-05 8.44E-06 6.58E-06 5.28E-06 4.33E-06 3.62E-06 3.07E-06 SE 1.19E-05 8.92E-06 6.96E-06 5.58E46 4.58E-06 3.82E-06 3.2SE-06 SSE 6.45E-06 4.82E-06 3.76E-06 3.01 E-06 2.47E-06 2.06E-06 1.75E-06 S 2.74E-06 2.06E-06 1.61 E-06 1.29E-06 1.06E-06 8.88E-07 7.54E-07 SSW 2.17E-06 1.63E-06 1.27E-06 1.02E-06 8.36E-07 6.99E-07 5.93E-07 SW 2.38E-06 1.78E-06 1.39E--06 1.12E-06 9.17E-07 7.66E-07 6.50E-07 WSW 2.93E-06 2.19E-06 1.71 E-06 1.37E-06 1.12E-06 9.35E-07 7.93E-07 W 6.57E-06 4.91 E-06 3.83E-06 3.07E-06 2.51 E-06 2.10E-06 1.78E-06 WNW 8.77E-06 6.58E-06 5.14E-06 4.13E-06 3.39E-06 2.83E-06 2.41 E-06 NW 7.40E-06 5.56E-06 4.35E-06 3.50E-06 2.88E-06 2.41 E-06 2.05E-06 NNW 4.60E-06 3.46E-06 2.71E-06 2.18E-06 1.79E-06 1.50E-06 1.28E-06 Period of Record: 4/1/77 - 3/31/78 O O O
N IE ISLAND NUCLEAR CENERATING PLANT ERN STATE 3 POWER COMPANY O H PROCEDURES NUMBER:
/ g ;;./ H4 4 y;-f OFFSITE DOSE CALCULATION REV: 14
'.p L
wgj MANUAL (ODCM)
'..' ~' .~ T~~ ~~ M Page 169 0f 223 i TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D]
Prairie Island Dispersion Parametera (x/Q), SEC/M3, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M M LI M M 24 2d N 7.57E-07 6.59E-07 5.79E-07 5.13E-07 4.59E-07 4.14E-07 3.76E-07 NNE 5.07E-07 4.41E-07 3.87E-07 3.43E-07 3.07E-07 2.77E-07 2.52E-07 NE 4.77E-07 4.15E-07 3.64E-07 3.23E-07 2.89E-07 2.61 E-07 2.38E-07 ENE 4.86E-07 4.23E-07 3.71 E-07 3.29E-07 2.94E-07 2.65E-07 2.41 E-07 E 1.41 E-06 1.23E-06 1.08E-06 9.55E-07 8.56E-07 7.75E-07 7.05E-06 , ESE 2.64E-06 2.30E-06 2.02E-06 1.79E-06 1.61 E-06 1.46E-06 1.32E-06 SE 2.79E-06 2.43E-06 2.14E-06 1.90E-06 1.70E-06 1.54E-06 1.40E-06 SSE 1.50E-06 1.31E-06 1.15E-06 1.02E-06 9.12E-07 8.25E-07 7.51 E-07 S 6.49E-07 5.65E-07 4.97E-07 4.41 E-07 3.95E-07 3.56E-07 3.24E-07 SSW 5.10E-07 4.44E-07 3.90E-07 3.46E-07 3.10E-07 2.80E-07 2.54E-07 SW 5.59E-07 4.87E-07 4.27E-07 3.79E-07 3.39E-07 3.06E-07 2.78E-07 WSW 6.82E-07 5.93E-07 5.21E-07 4.61 E-07 4.13E-07 3.74E-07 3.40E-07 i W 1.53E-06 1.33E-06 1.17E-06 1.04E-06 9.29E-07 8.40E-07 7.64E-07 WNW 2.07E-06 1.80E-06 1.59E-06 1.41 E-06 1.26E-06 1.14E-06 1.03E-06 NW 1.76E-06 1.54E-06 1.35E-06 1.20E-06 1.08E-06 9.72E-06 8.83E-07 NNW 1.10E-06 9.59E-07 8.43E-07 7.47E-07 6.69E-07 6.04E-07 5.49E-07 Period of Record: 4/1/77 - 3/31/78
+ - o ,
PRAIRIE ISLAND NUCLEAR GENERATIN3 PLANT NORTHERN STATE 3 POWER COMPANY
- 1. )g i M p.
IIII E: H PROCEDURES NUMBER:
;I R E-A OFFSITE DOSE CALCULATION H4
- f. h O r3, [ ] MANUAL (ODCM) REY: 14
- (( Nh Page 170 of 223 TABLE A- PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 Pmirie Island Dispersion Parameters (x/Q), SEC/M3, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /OTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 2.2 23 24 25 24 2.I 24 i N 3.42E-07 3.14E-07 2.89E-07 2.67E--07 2.47E-07 2.30E-07 ' NNE 2.30E-07 2.15E-07 2.11E-07 1.94E-07 1.80E-07 1.67E-07 1.56E-07 1.45E-07 NE 2.17E-07 1.99E-07 1.84E-07 1.70E-07 1.58E-07 1.47E-07 1.38E-07 ENE 2.20E-07 2.01E-07 1.85E-07 1.71E-07 1.59E-07 1.48E-07 1.38E-07 E 6.44E-07 5.92E-07 5.46E-07 5.05E-07 4.70E-07 4.38E-07 4.09E-07 ESE 1.21E-06 1.11E-06 1.03E-06 9.51 E-07 8.84E-07 8.25E-07 7.71E-07 SE 1.28E-06 1.18E-06 1.09E-06 1.01E-06 9.37E-07 8.74E-07 8.17E-07 SSE 6.86E-07 6.31E-07 5.82E-07 5.39E-07 5.01E-07 4.67E-07 4.37E--07 S 2.96E-07 2.71 E-07 2.50E-07 2.31 E-07 2.15E-07 2.00E-07 SSW 1.87E-07 2.32E-07 2.13E-07 1.96E-07 1.82E-07 1.69E-07 1.57E-07 1.47E-07 SW 2.53E-07 2.32E-07 2.14E-07 1.98E-07 1.83E-07 1.71 E-07 1.59E-07 WSW 3.11E-07 2.85E-07 2.63E-07 2.43E-07 2.26E-07 2.11 E-07 1.97E-07 W 6.99E-07 6.42E-07 5.93E-07 5.49E-07 5.10E-07 4.76E-07 4.45E-07 WNW 9.44E-07 8.67E-07 7.99E-07 7.39E-07 6.86E-07 6.39E-07 5.97E-07 NW 8.07E-07 7.41E-07 6.83E-07 6.32E-07 5.87E-07 5.47E-07 5.12E-07 NNW 5.01 E-07 4.59E-07 4.23E-07 3.91 E-07 3.63E-07 3.38E-07 3.15E-07 l Period of Record: 4/1/77 - 3/31/78 O O O
- ,e i IEISLAND NUCLEAR CENERATING PLANT ERN STATE] POWER COMPANY (Q H PROCEDURE pi ' yfp TITLE: NUMBER:
gy .. m OFFSITE DOSE CALCULATION MKI g,J t.. IIO p; 5 * / r. MANUAL (ODCM) REV: 14 112..1. L.S. ..a J1 Page 171 of 223 TABLE A PE'Ja;E ISLAND DISPERSION PARAMETERS [ CONT'D1 Prairie Island Dispersion l arameters (x/Q), SEC/M 3, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 23 aa 3,1 M M 3A 3a , N 2.01 E-07 1.88E--07 1.77E-07 1.67E-07 1.58E-07 1.49E-07 1.42E-07 NNE 1.36E-07 1.28E-07 1.20E-07 1.14E-07 1.07E-07 1.02E-07 9.65E-08 NE 1.29E-07 1.21 E-07 1.14E-07 1.08E-07 1.02E-07 9.69E-08 9.20E-08 ENE 1.29E-07 1.21 E-07 1.14E-07 1.07E-07 1.01 E-07 9.60E-08 9.11 E-08 E 3.84E-07 3.61 E-07 3.40E-07 3.21 E-07 3.04E-07 2.88E-07 2.74E-07 - ESE 7.23E-07 6.80E-07 6.41 E-07 6.05E-07 5.73E-07 5.43E-07 5.16E-07 SE 7.67E-07 7.21 E-07 6.80E-07 6.42E-07 6.08E-07 5.77E-07 5.48E-07 SSE 4.10E-07 3.85E-07 3.63E-07 3.43E-07 3.24E-07 3.08E-07 2.92E-07 S 1.75E-07 1.64E-07 1.55E-07 1.46E-07 1.38E-07 1.31 E-07 1.24E-07 SSW 1.38E-07 1.29E-07 1.22E-07 1.15E-07 1.09E-07 1.03E-07 9.77E-08 , SW 1.49E-07 1.40E-07 1.32E-07 1.24E-07 1.17E-07 1.11 E-07 1.05E-07 WSW 1.85E-07 1.74E-07 1.64E-07 1.54E-07 1.46E-07 1.39E-07 1.32E-07 W 4.17E-07 3.92E-07 3.70E-07 3.49E-07 3.30E-07 3.13E-07 2.98E-07 WNW 5.60E-07 5.26E-07 4.95E-07 4.67E-07 4.42E-07 4.19E-07 3.98E-07 NW 4.79E-07 4.50E-07 4.24E-07 4.00E-07 3.79E-07 3.59E-07 3.41 E-07 , NNW 2.95E-07 2.77E-07 2.61 E-07 2.46E-07 2.32E-07 2.20E-07 2.09E-07 Period of Record: 4/1/77 - 3/31/78 _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ - _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ __________._______________..m_ _ _ _ _ _ _ _ _ _ . _ _ . _
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: EpE H4 OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM) Page 172 of 223 l . TABLE A- PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D_] Prairie Island Dispersion Pa%neters (x/Q), SEC/M3, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QT'A for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M al M M LQ il 12 N 1.35E-07 1.28E-07 1.22E-07 1.16E-07 1.11 E-07 1.07E-07 1.02E-07 NNE 9.18E-08 8.74E-08 8.34E-08 7.975-08 7.62E-08 7.30E-08 7.00E-08 NE 8.75E-06 8.34E-08 7.96E-08 7.61 E-08 7.28E-08 6.98E-08 6.70E-08 ENE 8.66E-48 8.24E-08 7.86E-08 7.50E-08 7.17E-08 6.86E-08 6.58E-08 E 2.60E-07 2.48E-07 2.37E-07 2.26E-07 2.17E-07 2.08E-07 1.99E-07 ESE 4.91 E-07 4.68E-07 4.47E-07 4.27E-07 4.09E-07 3.92E-07 3.76E-07 SE 5.22E-07 4.97E-07 4.75E-07 4.54E-07 4.35E-07 4.17E-07 4.00E-07 SSE 2.78E-07 2.65E-07 2.53E-07 2.42E-07 2.32E-07 2.22E-07 2.13E-07 S 1.18E-07 1.12E-07 1.07E-07 1.02E-07 9.79E-08 9.38E-08 8.99E-08 SSW 9.29E-08 8.85E-08 8.44E-08 8.07E-08 7.72E-08 7.39E-08 7.09E-08 SW 1.00E-07 9.54E-08 9.10E-08 8.69E-08 8.31E-08 7.95E-08 7.62E-08 WSW 1.25E-07 1.19E-07 1.14E-07 1.09E-07 1.04E-07 9.98E-08 9.57E-08 W 2.83E-07 2.70E-07 2.58E-07 2.47E-07 2.36E-07 2.26E-07 2.17E-07 WNW 3.78E-07 3.60E-07 3.44E-07 3.28E-07 3.14E-07 3.01 E-07 2.89E-07 NW 3.24E-07 3.09E-07 2.95E-07 2.82E-07 2.70E-07 2.58E-07 2.48E-07 NNW 1.99E-07 1.89E-07 1.80E-07 1.72E-07 1.65E-07 1.58E-07 1.51 E-07 Period of Record: 4/1/77 - 3/31/78 O O O
i NO lSLAND NUCLEAR GENERATING PLANT ERN STATES POWER COMPANY v
)
H PROCEDURES [d .' m -; , d TITLE: NUMBER:
' g y.%v,n% ' .M i H4 sh D.~ OFFSITE DOSE CALCULATION REV: 14 NM .fl
); l Q: .2 * %[ MANUAL (ODCM) n .t.. i . '
.r.C Page 173 of P23 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D]
Piair;0 Island Dispersion Parameters (x/Q), SEC/M3, for Long Term Ground Level Releases
> 500 Hrtffr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M M M M .4,I M M LQ N 9.79E-08 9.41 E--08 9.04E-08 8.71 E-08 8.39E-08 8.09E-08 7.81 E-08 7.54E-08 NNE 6.72E-08 6.46E-08 6.22E-08 5.99E-08 5.77E-08 5.57E-08 5.38E-08 5.20E-08 NE 6.43E-08 6.18E-08 5.95E-08 5.74E-08 5.53E-08 5.34E-08 5.16E-08 4.99E-08 ENE 6.31E-08 6.06E-08 5.83E-08 5.62E-08 5.41 E-08 5.22E-08 5.04E-08 4.87E-08 E 1.91 E- 07 1.84E-07 1.77E-07 1.71 E-07 1.65E-07 1.59E-07 1.54E-07 1.49E-07 ESE 3.62E-07 3.48E-07 3.35E-07 3.23E-07 3.11 E-07 3.01 E-07 2.91 E-07 2.81 E-07 SE 3.85E-07 3.70E-07 3.56E-07 3.44E-07 3.31 E-07 3.20E-07 3.09E-07 2.99E-07 SSE 2.05E-07 1.97E-07 1.90E-07 1.83E-07 1.76E-07 1.70E-07 1.65E-07 1.59E-07 S 8.63E-08 8.30E-08 7.98E-08 7.69E-08 . 7.41 E-08 7.15E-08 6.91 E-08 6.68E-08 SSW 6.81 E-08 6.55E-08 6.30E-08 6.07E-08 5.85E-08 5.65E-08 5.46E-08 5.27E-08 SW 7.32E-08 7.03E-08 6.76E-08 6.51 E-08 6.28E-08 6.06E-08 5.85E-08 5.65E-08 WSW 9.19E-08 8.84E-08 8.51 E-08 8.20E-08 7.91 E-08 7.64E-08 7.38E-08 7.14E-08 W 2.09E-07 2.01 E-07 1.93E-07 1.86E-07 1.80E-07 1.73E-07 1.68E-07 1.62E-07 WNW 2.77E-07 2.66E-07 2.56E-07 2.47E-07 2.38E-07 2.30E-07 2.22E-07 2.15E-07 NW 2.38E-07 2.29E-07 2.20E-07 2.12E-07 2.05E-07 1.97E-07 1.91 E-07 1.84E-07 NNW 1.45E-07 1.39E-07 1.34E-07 1.29E-07 1.24E-07 1.20E-07 1.16E-07 1.12E-07 Period of Record: 4/1/77 - 3/31/76
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ,
~
NUMBER: % :g ":pj; ti.(':,, . .;. ..;.;f TITLE: ire:.g4 - H4
! OFFSITE DOSE CALCULATION REY: 14 w.,, % . %[ .f,cf - . .
MANUAL (ODCM)
;f- . .
Page 174 of 223 i THIS PAGE IS LEFT INTENTIONALLY BLANK t [ t i I i 1 i O O O
p I- E ISLAND NUCLEAR GENERATING PLANT ( N ERN STATES POWER COMPANY H PROCEDURES '-) 7P TITLE: NUMBER: ! q%nj9% ,m t
.e -
KW D OFFSITE DOSE CALCULATION H4 J REV: 14 M.y V..e.[. .
; MANUAL (ODCM) 4 2 7. * .il?1 "..f
; Page 17s of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS Prairie Island Dispersion Parameters (D/Q),1/m 2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector Da 02 M M M M D.Z N 5.38E-07 2.01 E-07 1.09E--07 6.97E-08 4.87E-08 3.62E-08 2.81 E-08 NNE 3.39E-07 1.27E-07 6.87E-08 4.39E-08 3.07-08 2.28E-08 1.77E-08 NE 2.21 E-07 8.28E-08 4.49E-08 2.87E-08 2.01E-08 1.49E-08 1.16E-08 ENE 2.88E-07 1.08E-07 5.85E-08 3.73E-08 2.61 E-08 1.94E-08 1.51E-08 E 6.15E-07 2.30E-07 1.25E-07 7.97E-08 5.57E-08 4.14E-08 3.22E-08 ESE 1.12E-06 4.19E-07 2.27E-07 1.45E-07 1.02E-07 7.54E-08 5.86E-08 SE 1.22E-06 4.55E-07 2.47E-07 1.58E-07 1.10E-07 8.19E-08 6.36E-08 SSE 5.81 E-07 2.17E-07 1.18E-07 7.53E-08 5.27E-08 3.91 E-08 3.04E-08 S 2.72E-07 1.02E-07 5.53E-08 3.53E-08 2.47E-08 1.83E-08 1.42E-08 SSW 2.00E-07 7.47E-08 4.06E-08 2.59E-08 1.81 E-08 1.34E-08 1.04E-08 SW 2.16E-07 8.06E-08 4.38E-08 2.79E-08 1.95E-08 1.45E-08 1.13E-08 WSW 2.39E-07 8.93E-08 4.85E-08 3.09E-08 2.16E-08 1.61 E-08 1.25E-08 W 5.00E-07 1.87E-07 1.01 E-07 6.47E-08 4.53E-08 3.36E-08 2.61E-08 WNW 9.50E-07 3.55E-07 1.93E-07 1.23E-07 8.60E-08 6.39E-08 4.96E-08 NW 7.95E-07 2.97E-07 1.61E-07 1.03E-07 7.20E-08 5.35E-08 4.15E-08 NNW 5.54E-07 2.07E-07 1.12E-07 7.17E-08 5.02E-08 3.72E-08 2.89E-08 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISt.AND NUCLEAR C ENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES J-y g %y j y[ tiiLE: NUMBER: ii M 'Q OFFS!TE DOSE CALCULATION H4 i - T: "gg- b &pp 7 , MANUAL (ODCM) REY: 14 W 7 J.1,s.2 a.gj Page 176 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS ICONT'D1 Prairie Island Dispersion Parameters (D/Q),1/m 2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M M M M 12 M M N 2.13E-08 1.56E-08 1.19E-08 9.32E-09 7.47E-09 6.10E-09 5.07E-09 NNE 1.34E-08 9.84E-09 7.49E-09 5.87E-09 4.70E-09 3.84E-09 3.19E-09 NE 8.76E-09 6.43E-09 4.90E-09 3.83E-09 3.07E-09 2.51E-09 2.09E-09 ENE 1.14E-08 8.37E-09 6.37E-09 4.99E-09 4.00E-09 3.27E-09 2.72E-09 E 2.43E-08 1.79E-08 1.36E-08 1.07E-08 8.54E-09 6.98E-09 5.80E-09 ESE { 4.43E-08 3.26E-08 2.48E-08 1.94E-08 1.56E-08 1.27E-08 1.06E-08 SE 4.81 E-08 3.54E-08 2.69E-08 2.11E-08 1.69E-08 1.38E-08 1.15E-08 SSE 2.30E-08 1.69E-08 1.29E-08 1.01 E-08 8.07E-09 6.59E-09 5.48E-09 S 1.08E-08 7.92E-09 6.03E-09 4.72E-09 3.78E-09 3.09E-09 2.57E-09 . SSW 7.91 E-09 5.81E-09 4.42E-09 3.46E-09 2.77E-09 2.27E-09 1.88E-09 . SW 8.53E-09 6.26E-09 4.77E-09 3.73E-09 2.99E-09 2.45E-09 2.03E-09 WSW 9.45E-09 6.94E-08 5.28E-09 4.14E-09 3.32E-09 2.71E-09 2.25E-09 W 1.98E-08 1.45E-08 1.10E-08 8.65E-09 6.93E-09 5.67E-09 4.71E-09 WNW 3.76E-08 2.76E-08 2.10E-08 1.64E-08 1.32E-08 1.08E-08 8.95E-09 NW 3.14E-08 2.31E-08 1.76E-08 1.38E-08 1.10E-08 9.02E-09 7.49E-09 NNW 2.19E-08 1.61E-08 1.22E-08 9.59E-09 7.68E-09 6.28E-09 5.22E-09 Period of Record: 4/1/77 - 3/31/78 9 9 e
^
! ,~ ~ l I- EISLAND NUCLEAR GENERATING PLANT l N ERN STATES POWER COMPANY H PROCEDURE 3 - TITLE: NUMBER: -
~~5 H4 OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM)
Page 177 of 223 i TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] l Prairie Island Dispersion Parameters (D/O),1/m 2, for Long Term Ground Level Releases l > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles l l Sector M M 1,Z M M 24 2,1 N 4.27E-09 3.65E-09 3.14E-09 2.73E 2.40E-09 2.12E--09 1.89E-09 1.72E-09 1.33E-09 1.19E-09 NNE 2.69E-09 2.30E-09 1.98E-09 1.51 E-09 NE 1.76E-09 1.50E-09 1.29E-09 1.13E-09 9.87E-10 8.72E-10 7.76E-10 ! ENE 2.29E-09 1.95E-09 1.68E-09 1.46E-09 1.28E-09 1.14E-09 1.01 E-09 - E 4.88E-09 4.17E-09 3.59E-09 3.13E-09 2.74E-09 2.42E-09 2.16E-09 ESE 8.90E-09 7.59E-09 6.54E-09 5.69E-09 4.99E-09 4.41 E-09 3.93E-09 SE 9.66E-09 8.25E-09 7.11 E-09 6.18E-09 5.43E-09 4.79E-09 4.27E-09 SSE 4.61 E-09 3.94E-09 3.39E-09 2.95E-09 2.59E-09 2.29E-09 2.04E-09 S 2.16E-09 1.85E-09 1.59E-09 1.38E-09 1.21 E-09 1.07E-09 9.55E-10 SSW 1.59E-09 1.35E-09 1.17E-09 1.02E-09 8.91 E-10 7.87E-10 7.00E-10 SW 1.71 E-09 1.46E-09 1.26E-09 1.10E-09 9.61 E-10 8.49E-10 7.56E-10 WSW 1.90E-09 1.62E-09 1.40E-09 1.21E49 1.06E-09 9.41E-10 8.37E-10 W 3.97E-09 3.39E-09 2.92E-09 2.54E-09 2.23E-09 1.97E-09 1.75E-09 WNW 7.54E-09 6.44E-09 5.55E-09 4.83E-09 4.23E-09 3.74E-09 3.33E-09 NW 6.31 E-09 5.39E-09 4.64E-09 4.04E-09 3.54E-09 3.13E-09 2.79E-09 NNW 4.40E-09 3.75E-09 3.23E-09 2.81E-09 2.47E-09 2.18E-09 1.94E-09 Period of Record: 4/1/77 - 3/31/78
--- __ _ _--___----_---------_ _ - -----.___- - - _--_.______ _----ta
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY
H PROCEDURES g p , .y; A - . sJ TITLE: NUMBER:
QfI D .'i A 1 D
^LQ OFFSITE DOSE CALCULATION H4 MANUAL (ODCM) REY: 14 skkM Page 178 si223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D]
Prairie Island Dispersion Parameters (D/O),1/m 2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 2.2 24 2d 24 24 2.Z 24 N 1.69E-09 1.52E-09 1.37E-09 1.25E-09 1.14E-09 1.04E-09 9.58E-10 NNE 1.06E-09 9.56E-10 8.65E-10 7.86E-10 7.17E-10 6.57E-10 6.03E-10 NE 6.95E-10 6.25E-10 5.65E-10 5.13E-10 4.69E-10 4.29E-10 3.94E-10 ENE 9.40E-10 8.14E-10 7.36E-10 6.68E-10 6.10E-10 5.59E-10 5.13E-10 E 1.93E-09 1.74E-09 1.57E-09 1.43E-09 1.30E-09 1.19E-09 1.10E-09 ESE 3.51 E-09 3.16E-09 2.86E-09 2.60E-09 2.37E-09 2.17E-09 2.00E-09 SE 3.82E-09 3.44E-09 3.11 E-09 2.82E-09 2.58E-09 2.36E-09 2.17E-09 SSE 1.82E-09 1.64E-09 1.48E-09 1.35E-09 1.23E-09 1.13E-09 1.04E-09 8 8.55E-10 7.69E-10 6.95E-10 6.32E-10 5.77E-10 5.28E-10 4.85E-10 SSW 6.27E-10 5.64E-10 5.10E-10 4.63E-10 4.23E-10 3.87E-10 3.56E-10 SW 6.76E-10 6.09E-10 5.50E-10 5.00E-10 4.56E-10 4.18E-10 3.84E-10 WSW 7.49E-10 6.74E-10 6.10E-10 5.54E-10 5.06E-10 4.63E-10 4.26E-10 W 1.57E-09 1.41 E-09 1.28E-09 1.16E-09 1.06E-09 9.68E-10 8.90E-10 WNW 2.98E-09 2.68E-09 2.42E-09 2.20E-09 2.01 E-09 1.84E-09 1.69E-09 NW 2.49E-09 2.24E-09 2.03E-09 1.84E-09 1.68E-09 1.54E-09 1.42E-09 NNW 1.74E-09 1.56E-09 1.41 E-09 1.28E-09 1.17E-09 1.07E-09 9.86E-10 Period of Record: 4/1/77 - 3/31/78 O O O
l 6 E ISLAND NUCLEAR GENERATING PLANT I NO ERN STATES POWER COMPANY H PROCEDURE 3 l TITLE: NUMBER:
!g H4 OFFSITE DOSE CALCULATION
.1 REY: 14 MANUAL (ODCM)
~~~~~~
5 i _2[ Page 179 of 223 1 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (D/Q),1/m 2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector 2a 3a M 32 3.2 ad 35 N 8.84E-10 8.17E-10 7.58E-10 7.05E-10 6.57E-10 6.14E-10 5.75E-10 NNE 5.56E-10 5.15E-10 4.77E-10 4.44E-10 4.14E-10 3.87E-10 3.62E-10 , NE 3.64E-10 3.36E-10 3.12E-10 2.90E-10 2.70E-10 2.53E-10 2.37E-10 ENE 4.73E-10 4.38E-10 4.06E-10 3.78E-10 3.52E-10 3.29E-10 3.08E-10 E 1.01 E-09 9.34E-10 8.67E-10 8.06E-10 7.51 E-10 7.02E-10 6.57E-10 ESE 1.84E-09 1.70E-09 1.58E-09 1.47E-09 1.37E-09 1.28E-09 1.20E-09 SE 2.00E-09 1.85E-09 1.71 E-09 1.59E-09 1.49E-09 1.39E-09 1.30E-09 SSE 9.55E-10 8.83E-10 8.19E-10 7.61 E-10 7.10E-10 6.63E-10 6.21 E-10 S 4.47E-10 4.14E-10 3.84E-10 3.57E-10 3.33E-10 3.11 E-10 2.91 E-10 SSW 3.28E-10 3.04E-10 2.82E-10 2.62E-10 2.44E-10 2.28E-10 2.14E-10 SW 3.54E-10 3.27E-10 3.04E-10 2.82E-10 2.63E-10 2.46E-10 2.30E-10
- WSW 3.92E-10 3.63E-10 3.37E-10 3.13E-10 2.92E-10 2.73E-10 2.55E-10 W 8.20E-10 7.59E-10 7.04E-10 6.54E-10 6.10E-10 5.70E-10 5.34E-10 WNW 1.56E-09 1.44E-09 1.34E-09 1.24E-09 1.16E-09 1.08E-09 1.01E-09 l NW 1.31 E-09 1.21 E-09 1.12E-09 1.04E-09 9.71 E-10 9.07E-10 8.49E-10 ;
NNW 9.09E-10 8.41 E-10 7.80E-10 7.25E-10 6.76E-10 6.32E-10 5.92E-10 Period of Record: 4/1/77 - 3/31/78 _ . _ _ _ _ - . _ _ -- __ .n
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES (.{ f si LE: NUMBER: B -N [..E R?Q ' @$ ;
.. ._ , -.. .. _ : l .
OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REY: 14 Page 180 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (D/Q),1/m2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M AZ 34 33 da 4,1 d.2 N 5.40E-10 5.07E-10 4.78E-10 4.51 E-10 4.26E-10 4.03E-10 3.82E-10 NNE 3.40E-10 3.19E-10 3.01 E-10 2.84E-10 2.68E-10 2.F'5-10 2.41 E-10 NE 2.22E-10 2.09E-10 1.97E-10 1.86E-10 1.75E-10 1.66E-10 1.57E-10 ENE 2.89E-10 2.72E-10 2.56E-10 2.42E-10 2.28E-10 2.16E-10 2.05E-10 E 6.17E-10 5.80E-10 5.46E-10 5.16E-10 4.87E-10 4.61 E-10 4.37E-10 ESE 1.12E-09 1.06E--09 9.95E-10 9.39E-10 8.87E-10 8.40E-10 7.96E-10 SE 1.22E-09 1.15E-09 1.08E-09 1.02E--09 9.64E-10 9.12E-10 8.65E-10 SSE 5.83E-10 5.48E-10 5.16E-10 4.87E-10 4.60E-10 4.36E-10 4.13E-10 S 2.73E-10 2.57E-10 2.42E-10 2.28E-10 2.16E-10 2.04E-10 1.94E-10 SSW 2.00E-10 1.88E-10 1.78E-10 1.67E-10 1.58E-10 1.50E-10 1.42E-10 SW 2.16E-10 2.03E-10 1.92E-10 1.81E-10 1.71E-10 1.62E-10 1.53E-10 WSW 2.40E-10 2.25E-10 2.12E-10 2.00E-10 1.89E-10 1.79E-10 1.70E-10 W 5.01E-10 4.71E-10 4.44E-10 4.19E-10 3.96E-10 3.75E-10 3.55E-10 WNW 9.53E-10 8.96E-10 8.44E-10 7.96E-10 7.52E-10 7.12E-10 6.75E-10 NW 7.97E-10 7.50E-10 7.06E-10 6.66E-10 6.29E-10 5.96E-10 5.65E-10 NNW 5.55E-10 5.22E-10 4.92E-10 4.64E-10 4.38E-10 4.15E-10 3.93E-10 Period of Record: 4/1/77 - 3/31/78 O O O
F EISLAND NUCLEAR GENERATING PLANT bh H PROCEDURES v) h N ERN STATES POWER COMPANY _g< TITLE: NUMBER: ,g " :;g:y.. v . ; f. d. 94 . Z.* 1 H-M OFFSITE DOSE CALCULATION gW.e , REY: 14
,..- .: h MANUAL (ODCM) 8:L W.;.c4:L% J% Page 181 of 223
. 42!
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (D/O),1/m 2, for Long Term Ground Level Releases
> 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Sector M M M M M M M 5A N 3.63E-10 3.45E-10 3.28E-10 3.13E-10 2.99E-10 2.85E-10 2.73E-10 2.61 E-10 NNE 2.29E-10 2.17E-10 2.07E-10 1.97E-10 1.88E-10 1.80E-10 1.72E-10 1.64E-10 t NE 1.49E-10 1.42E-10 1.35E-10 1.29E-10 1.23E-10 1.17E-10 1.12E-10 1.07E-10 ENE 1.94E-10 1.85E-10 1.76E-10 1.68E-10 1.60E-10 1.53E-10 1.46E-10 1.40E-10 E 4.15E-10 3.94E-10 3.75E-10 3.58E-10 3.41 E-10 3.26E-10 3.12E-10 2.98E-10 ESE 7.56E-10 7.18E-10 6.84E-10 6.52E-10 6.22E-10 5.94E-10 5.68E-10 5.43E-10 , SE 8.21 E-10 7.80E-10 7.45E-10 7.08E-10 6.75E-10 6.45E-10 6.17E-10 5.90E-10 i SSE 3.92E-10 3.73E-10 3.55E-10 3.38E-10 3.23E-10 3.08E-10 2.94E-10 2.82E-10 S 1.84E-10 1.75E-10 1.66E-10 1.58E-10 .1.51 E-10 1.44E-10 1.38E-10 1.32E-10 SSW 1.35E-10 1.28E-10 1.22E-10 1.16E-10 1.11 E-10 1.06E-10 1.01 E-10 9.69E-11 SW 1.45E-10 1.38E-10 1.32E-10 1.25E-10 1.20E-10 1.14E-10 1.09E-10 1.05E-10 WSW 1.61 E-10 1.53E-10 1.46E-10 1.39E-10 1.33E-10 1.27E-10 1.21 E-10 1.16E-10 W 3.37E-10 3.20E-10 3.05E-10 2.91 E-10 2.77E-10 2.65E-10 2.53E-10 2.42E-10 WNW 6.41 E-10 6.09E-10 5.80E-10 5.52E-10 5.27E-10 5.03E-10 4.81 E-10 4.61 E-10 NW 5.36E-10 5.10E-10 4.85E-10 4.62E-10 4.41 E-10 4.21 E-10 4.03E-10 3.85E-10 NNW 3.75E-10 3.55E-10 3.38E-10 3.22E-10 3.07E-10 2.93E-10 2.80E-10 2.68E-10 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY H PROCEDURES 4 n. y . s. .; I e"W TITLE: NUMBER: 3
- i. - ..: ga n j Mg. o ..f. . U D f.N::.:
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@ O O
F E ISLAND NUCLEAR GENERATING PLANT j NO ERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: + v,(;.. c:: 43;; h.;- j ._c.:s? c.y ' 94
. G .: 2 '? . OFFSITE DOSE CALCULATION REV: 14
((1[fM MANUAL (ODCM)
.j /,I,[ .[.$.k Page 183 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS Prairie Island Dispersion Parameters for Short Term Ground Level Releases s 500 Hrs /Yr or s 150 Hrs /QTR for Unrestricted Area Boundary Locations (identified in Table A-2)
Unrestricted Area B9EDdary Sector Sector xlg_(pec/m3) D/a (1/m2) N 7.09E-05 4.60E-07 NNE 7.32E-05 4.11 E-07 NE 1.60E-05 6.77E-08 ENE 1.97E-05 1.11 E-07 - E 4.92E-05 1.99E-07 ESE 6.40E-05 2.52E-07 SE 5.98E-05 2.43E-07 SSE 8.79E-05 3.08E-07 S 5.18E-05 2.04E-07 SSW 5.26E-05 1.89E-07 SW 5.25E-05 1.90E-07 WSW 7.83E-05 2.44E-07 W 1.32E-04 3.78E-07 WNW 1.10E-04 4.61 E-07 NW 7.67E-05 3.25E-07 NNW 4.79E-05 2.34E-07 Period of Record: 4/1/77 - 3/31/78 ;
PRAIRIE ISLAND NUCLEAR EENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
~ j. p p. . . - .- -- a b TITLE:
NUMBER:
.z. .
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P. ISLAND NUCLEAR GENERATING PLANT j NORTRERN STATES POWER COMPANY v HPROCEDURES J 3 g :. < P 2:: ; TITLE: NUMBER: g$:x-yxj ?. 94 W 7: w[ . : ; v; *: OFFSITE DOSE CALCULATION REV: 14 j NJ . ?I MANUAL (ODCM) , 4 . Wm. .x Page 185 of 223 2 !.i . 1 . .; 1 TAB E A-7-PRAIRIE ISLAND DISPERSION PARAMETERS . Prairie Island Dispersion Parameters (x/q), sec/m3, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M M M M M M N 3.76E-04 1.13E-04 6.59E-05 4.39E-05 3.15E-05 2.47E-05 1.90E-05 NNE 3.35E-04 1.05E-04 5.94E-05 3.93E-05 2.77E-05 2.19E-05 1.65E-05 NE 4.38E-04 1.33E-04 7.71 E-05 4.94E-05 3.39E-05 2.68E-05 2.12E-05 ENE 3.27E-04 1.02E-04 5.93E-05 4.01 E-05 2.80E-05 2.19E-05 1.69E-05 E 8.12E-04 2.43E-04 1.39E-04 8.80E-05 6.16E-05 4.84E-05 3.78E-05 ESE 1.17E-03 3.52E-04 1.98E-04 1.27E-04 8.80E-05 6.84E-05 5.32E-05 SE 1.27E-03 3.85E-04 2.06E-04 1.31 E-04 9.32E-05 7.34E-05 5.67E-05 SSE 5.30E-04 2.82E-04 1.57E-04 9.85E-05 6.75E-05 5.39E-05 4.30E-05 S 5.01 E-04 1.57E-04 8.75E-05 5.74E-05 3.97E-05 3.11 E-05 2.51 E-05 2.85E-05 2.31 E-05 SSW 4.54E-04 1.43E-04 8.26E-05 5.34E-05 3.60E-05 l SW 4.46E-04 1.44E-04 8.25E-05 5.30E-05 3.58E-05 2.85E-05 2.35E-05 WSW 6.10E-04 1.95E-04 1.08E-04 6.78E-05 4.59E-05 3.67E-05 3.05E-05 W 1.00E-03 3.10E-04 1.74E-04 1.10E-04 7.59E-05 6.07E-05 4.89E-05 WNW 8.70E-04 2.65E-04 1.50E-04 9.70E-05 6.86E-05 5.33E-05 4.17E-05 NW 8.41 E-04 2.50E-04 1.38E-04 8.89E-05 6.37E-05 4.97E-05 3.84E-05 NNW 5.69E-04 1.71E-04 9.73E-05 6.28E-05 4.54E-05 3.55E-05 2.78E-05 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISI.AND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES P4f,.g R@@gg.l.; TITLE: NUMBER: My l1$C OFFSITE DOSE CALCULATION H4 WR : JCT;.;: MANUAL (ODCM) REV: 14 lO TU&& .R$Q f 14 <fj:; Page 186 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'DJ Prairie Island Dispersion Parameters (x/q), sec/m 3, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles L Sector M M LQ 11 12 la M N 1.57E-05 1.26E-05 1.06E-05 8.97E-06 7.73E-06 6.76E-06 5.91E-06 NNE 1.35E-05 1.11 E-05 9.26E-06 7.87E-06 6.81 E-06 5.96E-06 5.27E-06
~
NE 1.74E-05 1.44E-05 1.21 E-05 1.02E-05 8.57E-06 7.50E-06 6.63E-06 ENE 1.39E-05 1.14E-05 9.46E-06 8.04E-06 6.83E-06 5.97E-06 5.27E-06 E 3.11 E-05 2.51 E-05 2.11 E-05 1.80E-05 1.53E-05 1.33E-05 1.18E-05 ESE 4.35E-05 3.58E-05 2.98E-05 2.54E-05 2.19E-05 1.91E-05 1.71 E-05 SE 4.65E-05 3.79E-05 3.18E-05 2.71 E-05 2.32E-05 2.03E-05 1.81 E-05 SSE 3.53E-05 2.87E-05 2.41 E-05 2.05E-05 1.72E-05 1.51 E-05 1.35E-05 S 2.05E-05 1.66E-05 1.38E-05 1.17E-05 1.01 E-05 8.83E-06 7.81 E-06 SSW 1.89E-05 1.54E-05 1.29E-05 1.10E-05 9.05E-06 7.93E-06 7.02E-06 SW 1.95E-05 1.54E-05 1.30E-05 1.12E-05 9.19E-06 8.05E-06 7.21 E-06 WSW 2.51 E-05 2.05E-05 1.72E-05 1.47E-05 1.21 E-05 1.06E-05 9.41E-06 i W 4.01 E-05 3.24E-05 2.70E-05 2.30E-05 1.89E<-05 1.65E-05 1.46E-05 WNW 3.44E-05 2.75E-05 2.31 E-05 1.96E-05 1.68E-05 1.48E-05 1.31 E-05 NW 3.15E-05 2.57E-05 2.17E-05 1.85E-05 1.60E-05 1.40E-05 1.24E-05 NNW 2.28E-05 1.86E-05 1.54E-05 1.31 E-05 1.12E-05 9.85E-06 8.82E-06 Period of Record: 4/1/77 - 3/31/78 O O O
F ISLAND NUCLEAR GENERATING PLANT H PROCEDURES V b NO ERN STATES POWER COMPANY
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TITLE: NUMBER: y44pi + A 'f/ ,7.;(ig n ng a? ~ 0. .. i.a OFFSITE DOSE CALCULATION REY: 14 JJ '.L:13 MANUAL (ODCM) _[Q$QJQ Page 187 of 223 _ . 2 .i .. .~7:A TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (yfq), sec/m3, for Short Term Ground Level Releases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M LZ M M 24 2d i N 5.27E-06 4.74E-06 4.30E-06 3.91 E-06 3.59E-06 3.32E-06 3.07E-06 NNE 4.70E-06 4.22E-06 3.82E-06 3.47E-06 3.18E-06 2.97E-06 2.75E-06 . NE 5.89E-06 5.30E-06 4.80E-06 4.37E-06 4.01 E-06 3.69E-06 3.42E-06 ENE 4.67E-06 4.21 E-06 3.80E-06 3.45E-06 3.16E-06 2.91 E-06 2.70E-06 E 1.06E-05 9.52E-06 8.66E-06 7.90E-06 7.25E-06 6.74E-06 6.25E-06 ESE 1.52E-05 1.38E-05 1.25E-05 1.13E-05 1.04E-05 9.72E-06 9.03E-06 SE 1.62E-05 1.46E-05 1.33E-05 ~ 1.21 E-05 1.11 E-05 1.03E-05 9.59E-06 SSE 1.20E-05 1.09E-05 9.84E-06 8.96E-06 8.23E-06 7.58E-06 7.04E-06 S 6.97E-06 6.27E-06 5.68E-06 5.18E-06 4.75E-06 4.36E-06 4.04E-06 , SSW 6.28E-06 5.66E-06 5.14E-06 4.69E-06 4.31 E-06 3.92E-06 3.64E-06 SW 8.43E-06 5.78E-06 5.24E-06 4.77E-06 4.37E-06 3.90E-06 3.62E-06 WSW 8.41 E-06 7.58E-06 6.87E-06 6.27E-06 5.77E-06 5.17E-06 4.80E-06 W 1.30E-05 1.17E-05 1.06E-05 9.62E-06 8.83E-06 8.33E-06 7.73E-06 WNW 1.17E-05 1.05E-05 9.65E-06 8.80E-06 8.08E-06 7.42E-06 6.89E-06 NW 1.11 E-05 1.00E-05 9.09E-06 8.30E-06 7.63E-06 7.13E-06 6.62E-06 NNW 7.89E-06 7.11 E-06 6.47E-06 5.89E-06 5.41 E-06 5.01E-06 4.64E-06 i Period of Record: 4/1/77 - 3/31/78
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PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 6,g
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.UU 3.7 14 7;ti.Hds 1 L i MANUAL (ODCM) REW 14 CM- . . . 5. OnJ Page 18f, of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (x/q), sec/m3, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 2.2 22 2d 24 24 2.Z 2A N 2.87E-06 2.67E-06 2.50E-06 2.32E-06 2.27E-06 1.94E-06 1.84E-06 NNE 2.56E-06 2.39E-06 2.24E-06 2.09E-06 2.03E-06 1.76E-06 1.66E-06 NE 3.19E-06 2.98E-06 2.79E-06 2.63E-06 2.57E-06 2.24E-06 2.11 E-06 ENE 2.51 E-06 2.34E-06 2.19E-06 2.05E-06 1.97E-06 1.74E-06 1.64E-06 E 5.82E-06 5.44E-06 5.10E-06 4.89E-06 4.75E-06 4.14E-06 3.92E-06 ESE 8.41 E-06 7.87E-06 7.38E-06 7.16E-05 7.09E-06 6.11 E-06 5.78E-06 SE 8.93E-06 8.35E-06 7.82E-06 7.70E-05 7.60E-06 6.62E-06 6.26E-06 ' SSE 6.56E-06 6.14E-06 5.76E-06 5.55E-06 5.36E-06 4.73E-06 4.47E-06 S 3.76E-06 3.51 E-06 3.29E-06 3.18E-06 3.06E-06 2.73E-06 2.59E-06 SSW 3.39E-06 3.16E-06 2.96E-06 2.89E-06 2.75E-06 2.42E-06 2.28E-06 SW 3.37E-06 3.15E-06 2.95E-06 2.84E-06 2.70E-06 2.44E-06 2.30E-06 WSW 4.47E-06 4.18E-06 3.92E-06 3.85E-06 3.67E-06 3.28E-06 3.10E-06 W 7.21 E-06 6.74E-06 6.32E-06 6.45E-06 6.03E-06 5.30E-06 5.02E-06 WNW 6.42E-06 6.00E-06 5.65E-06 5.32E-06 5.23E-06 4.55E-06 4.30E-06 NW 6.16E-06 5.76E-06 5.40E-06 5.16E-06 5.03E-06 4.37E-06 4.13E-06 NNW 4.31 E-06 4.02E-06 3.76E 3.57E-06 3.46E-06 3.00E-06 2.83E-06 Period of Record: 4/1/77 - 3/31/78 O O O
EISLAND NUCLEAR GENERATING PLANT } , ERN STATES POWER COMPANY H PROCEDURES [V TITLE: NUMBER:
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TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (x/q), sec/m3, for Short Term Ground Level Releases s 500 Hrs /Yr or s 150 Hrs /OTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 2a M M M M M M N 1.74E-06 1.66E--06 1.58E-06 1.50E-06 1.43E-06 1.37E-06 1.31E-06 NNE 1.57E-06 1.50E-06 1.43E-06 1.36E-06 1.30E-06 1.24E-06 1.19E-06 , NF 2.00E-06 1.90E-06 1.81 E-06 1.73E-06 1.65E-06 1.58E-06 1.51 E-06 ENE 1.55E-06 1.48E-06 1.40E-06 1.33E-06 1.27E-06 1.21 E-06 1.16E-06 E 3.71 E-06 3.51 E-06 3.34E-06 319E-06 3.04E-06 2.91 E-06 2.79E-06 l ESE 5.48E-06 5.18E-06 4.93E-06 4.70E-05 4.49E-06 4.29E-06 4.11 E-06 SES 5.93E-06 5.63E-06 5.36E-06 5.11 E-05 4.87E-06 4.66E-06 4.46E-06 , SSE 4.24E-06 3.97E-06 3.78E-06 3.60E-06 3.44E-06 3.29E-06 3.15E-06 S 2.45E-06 2.25E-06 2.14E-06 2.04E-06 1.94E-06 1.85E-06 1.77E-06 SSW 2.16E-06 1.96E-06 1.87E-06 1.78E-06 1.70E-06 1.63E-06 1.56E-06 SW 2.18E-06 2.03E-06 1.93E-06 1.84E-06 1.75E-06 1.67E-06 1.60E-06 WSW 2.94E-06 2.70E-06 2.57E-06 2.45E-06 2.34E-06 2.24E-06 2.14E-06 W 4.76E-06 4.34E-06 4.13E-06 3.95E-06 3.77E-06 3.61 E-06 3.47E-06 WNW 4.07E-06 3.86E-06 3.67E-06 3.50E-06 3.34E-06 3.20E-06 3.06E-06 NW 3.92E-06 3.69E-06 3.51 E-06 3.35E-06 3.20E-06 3.06E-06 2.94E-06 NNW 2.68E-06 2.53E-06 2.40E-06 2.28E-06 2.18E-06 2.08E-06 1.99E-06 Period of Record: 4/1/77 - 3/31/78
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I PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: Q:14%D Q" ,[ Y ;. j Mi OFFSITE DOSE CALCULATION H4 hlRN.$;b' h.:M MANUAL (ODCM) REY: 14 u [ [. '[ Page 190 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS ICONT'D1 Prairie Island Dispersion Parameters (y/q), sec/m3, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M 3Z M M M 4.1 4.2 N 1.25E-06 1.20E-06 1.15E-06 1.10E-06 1.06E-06 1.02E-06 9.88E--07 NNE 1.14E-06 1.09E-06 1.05E-06 1.01 E-06 9.73E-07 9.37E-07 9.04E-07 NE 1.45E-06 1.39E-06 1.34E-06 1.29E-06 1.24E-06 1.20E-06 1.16E-06 ENE 1.11 E-06 1.07E-06 1.02E-06 9.83E-07 9.46E-07 9.11 E-07 8.79E-07 E 2.67E-06 2.57E-06 2.47E-06 2.38E-06 2.29E-06 2.21 E-06 2.13E-06 ESE 3.94E-06 3.78E-06 3.64E-06 3.50E-06 3.38E-06 3.26E-06 3.15E-06 SES 4.27E-06 4.10E-06 3.94E-06 3.79E-06 3.65E-06 3.52E-06 3.39E-06 SSE 3.02E-06 2.90E-06 2.79E-06 2.68E-06 2.59E-06 2.50E-06 2.41 E-06 S 1.70E-06 1.63E-06 1.57E-06 1.51 E-06 1.45E-06 1.40E-06 1.35E-06 SSW 1.50E-06 1.44E-06 1.38E-06 1.33E-06 1.29E-06 1.24E-06 1.20E-06 SW 1.53E-06 1.47E-06 1.41 E-06 1.36E-06 1.29E-06 1.25E-06 1.20E-06 WSW 2.06E-06 1.98E-06 1.90E-06 1.83E-06 1.76E-06 1.70E-06 1.64E-06 W 3.33E-06 3.20E-06 3.08E-06 2.97E-06 2.87E-06 2.77E-06 2.68E-06 WNW3 2.93E-06 2.81E-06 2.70E-06 2.60E-06 2.51 E-06 2.42E-06 2.33E-06 NW 2.82E-06 2.71E-06 2.60E-06 2.50E-06 2.41 E-06 2.32E-06 2.24E-06 NNW 1.91 E-06 1.83E-06 1.76E-06 1.69E-06 1.63E-06 1.57E-06 1.52E-06 Period of Record: 4/1/77 - 3/31/78 O O O
F IE ISLAND NUCLEAR C ENERATING PLANT f') [ N ERN STATES POWER COMPANY L/ H PROCEDURESs w 4 -. ; i j J. m LE: NUMBER: yy /=; w" w c ', - , .
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OFFSITE DOSE CALCULATION 94 Mp ((. . MANUAL (ODCM) REV: 14 bah 2 ~ . -,[. ' . . .:: Page 191 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 Prairie Island Dispersion Parameters (x/q), sec/m3, for Short Term Ground Level Releases s 500 HrsNr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M M M M M M N 9.59E- 07 9.27E-07 8.97E-07 8.68E-07 8.41 E-07 8.16E-07 7.92E-07 NNE 8.73E-07 8.44E-07 8.16E-07 7.90E-07 7.65E-07 7.42E-07 7.20E-07 NE 1.12E-06 1.08E-06 1.05E-06 1.01 E-06 9.18E-07 9.51 E-07 9.23E-07 ENE 8.4 /E-07 8.18E-07 7.91 E-07 7.66E-07 7.41 E-07 7.18E-07 6.97E-07 E 2.06E-06 2.00E-06 1.93E-06 1.87E-06 1.82E-06 1.76E-06 1.71 E-06 ESE 3.04E-06 2.94E-06 2.85E-06 2.76E-06 2.67E-06 2.60E-06 2.52E-06 l SE5 3.27E-06 3.16E-06 3.06E-06 2.97E-06 2.88E-06 2.79E-06 2.70E-06 ! SSE 2.34E-06 2.26E-06 2.19E-06 2.12E-06 2.07E-06 2.01E-06 1.95E-06 S 1.30E-06 1.26E-06 1.22E-06 1.18E-06 1.15E-06 1.11 E-06 1.08E-06 SSW 1.16E-06 1.12E-06 1.09E-06 1.05E-06 1.02E-06 9.94E-07 9.66E-07 SW 1.16E-06 1.12E-06 1.09E-06 1.05E-06 1.02E-06 9.91E-07 9.62E-07 WSW 1.59E-06 1.54E-06 1.49E-06 1.44E-06 1.39E-06 1.35E-06 1.31 E-06 W 2.59E-06 2.51 E-06 2.43E-06 2.36E-06 2.29E-06 2.23E-06 2.17E-06 WNW3 2.25E-06 2.18E-06 2.11 E-06 2.04E-06 1.98E-06 1.92E-06 1.86E-06 NW 2.16E-06 2.09E-06 2.01 E-06 1.95E-06 1.89E-06 1.84E-06 1.79E-06 NNW 1.46E-06 1.41 E-06 1.36E-06 1.32E-06 1.28E-06 1.24E-06 1.20E-06 Period of Record: 4/1/77 - 3/31/78 '_ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _- __m__ -- _ _ _ _ _ _ __ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: ' NUMBER: %ges'T:?
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e Page 192 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] , Prairie Island Dispersion Parameters (x/q), sec/m 3, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles , Sector 5& N 7.67E-07 NNE 6.99E-07 NE 8.97E-07 ENE 6.76E-07 E 1.67E-06 ESE 2.45E-06 SE 2.62E-06 SSE 1.89E-06 S 1.05E-06 SSW 9.39E-07 SW 9.35E-07 WSW 1.27E-06 W 2.11 E-06 WNW 1.81 E-06 NW 1.74E-06 NNW 1.17E-0(< Period of Record: 4/1/77 - 3/31/78 O O O
F EISLAND NUCLEAR CENERATING PLAK1' NO ERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: EgE H4 OFFSITE DOSE CALCULATION REV: 14 MANUAL (ODCM) Page 193 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS Prairie Island Dispersion Parameters (D/q),1/m2, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles t Sector 01 D2 Da DA D1 D& D2 N 1.68E-06 6.63E-07 4.32E-07 3.00E-07 2.18E-07 1.69E-07 1.20E-07 NNE 1.33E-06 5.43E-07 3.46E-07 2.40E-07 1.72E-07 1.36E-07 1.03E-07 NE 1.19E-06 4.68E-07 3.05E-07 2.06E-07 1.45E-07 1.14E-07 9.10E-08 ENE 1.20E-06 4.86E-07 3.17E-07 2.23E-07 1.58E-07 1.236-07 9.49E-08 E 2.08E-06 8.09E-07 5.21E-07 3.46E-07 2.49E-07 1.96E-07 1.54E-07 ESE 2.90E-06 1.14E-06 7.17E-07 4.85E-07 3.45E-07 2.69E-07 2.11 E-07 SE 3.20E-06 1.26E-06 7.54E-07 5.08E-07 3.71 E-07 2.94E-07 2.31 E-07 SSE 2.09E-06 8.24E-07 5.16E-07 3.41 E-07 2.40E-07 1.92E47 1.55E-07 S 1.27E-06 5.18E-07 3.24E-07 2.23E-07 1.58E-07 1.23E-07 1.00E-07 SSW 1.06E-06 4.33E-07 2.82E-07 1.92E-07 1.33E-07 1.05E-07 8.51E-08 SW 1.05E-06 4.42E-07 2.85E-07 1.91 E-07 1.31 E-07 1.04E-07 8.55E-08 WSW 1.24E-06 5.19E-07 3.24E-07 2.14E-07 1.48E-07 1.19E-07 1.94E-08 W 1.90E-06 7.65E-07 4.83E-07 3.22E-07 2.27E-07 1.82E-07 1.48E-07 WNW 2.42E-06 9.62E-07 6.10E-07 4.14E-07 2.99E-07 2.31 E-07 1.81E-07 NW 2.30E-06 8.91 E-07 5.49E-07 3.72E-07 2.73E-07 2.12E-07 1.65E-07 NNW 1.79E-06 7.01 E-07 4.46E-07 3.01 E-07 2 21E-07 1.72E-07 1.34E-07 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: {g
#p Wg]d g jj OFFSITE DOSE CALCULATION H4 REV.- 14 j;g{ g fjy MANUAL (ODCM)
' 3" 4 iixM Page 194 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D]
Prairie island Dispersion Parametera (D/q),1/m 2, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 04 Da 1Q 11 12 la 14 N 1.05E--07 8.25E-08 6.73E-08 5.55E-08 4.66E-08 3.99E-08 3.41 E-08 NNE 8.35E-08 6.76E-08 5.48E-08 4.55E-08 3.85E-08 3.29E-08 2.85E-08 NE 7.39E-08 5.99E-08 4.95E-08 4.08E-08 3.35E-08 2.87E-08 2.49E-08 ENE 7.67E-08 6.15E-08 4.97E-08 4.13E-08 3.42E-08 2.93E-08 2.53E-08 E 1.25E-07 9.96E-08 8.17E-08 6.79E-08 5.63E-08 4.82E-08 4.18E-08 ESE 1.71 E-07 1.38E-07 1.12E-07 9.32E-08 7.87E-08 6.71 E-08 5.86E-08 SE 1.88E-07 1.50E-07 1.23E-07 1.02E-07 8.55E-08 7.34E-08 6.38E-08 SSE 1.26E-07 1.01E-07 8.26E-08 6.86E-08 5.63E-08 4.83E-08 4.22E-08 S 8.06E-08 6.40E--09 5.16E-08 4.29E-08 3.60E-08 3.07E-08 2.66E-08 i SSW 6.87E-08 5.49E-08 4.50E-08 3.73E-08 3.00E-08 2.57E-08 2.23E-08 SW 7.00E-08 5.41 E-08 4.47E-08 3.73E-08 3.00E-08 2.57E-08 2.25E-08 WSW 8.11E-08 6.49E-08 5.32E-08 4.44E-08 3.59E-08 3.08E-08 2.67E-08 W 1.21 E-07 9.57E-08 7.80E-08 6.48E-08 5.22E-08 4.46E-08 3.86E-08 I WNW 1.47E-07 1.15E-07 9.45E-08 7.80E-08 6.54E-08 5.61E-08 4.86E-08 l NW 1.34E-07 1.07E-07 8.78E-08 7.30E-08 6.13E-08 5.23E-08 4.53E-08 NNW 1.08E-07 8.62E-08 6.96E-08 5.74E-08 4.82E-08 4.12E-08 3.60E-08 Period of Record: 4/1/77 - 3/31/78 O O O
> E ISLAND NUCLEAR CENERATING PLANT l NO ERN STATE 3 POWER COMPANY H PROCEDURES C C C O i~ g u TITLE: NUMBER:
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- H4 OFFSITE DOSE CALCULATION l
[- TiL.M'il Sd[h MANUAL (ODCM) REV: 14 Page 195 of 223 i TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (D/q),1/m 2, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M LI M M 2a 2d N 2.98E-08 2.62E-08 2.33E-08 2.08E-08 1.87E-08 1.70E-08 1.54E-08 l NNE 2.49E-08 2.20E-08 1.95F '.;8 1.74E-08 1.56E-08 1.43E-08 1.30E-08 NE 2.17E-08 1.92E-08 1.70E-08 1.52E-08 1.37E-08 1.23E-08 1.12E-08 ENE 2.20E-08 1.94E-08 1.72E-08 1.54E-08 1.38E-08 1.25E-08 1.13E-08 E 3.66E-08 3.24E-08 2.89E-08 2.58E-08 2.32E-08 2.11 E-08 1.91 E-08 l ESE 5.12E-08 4.53E-08 4.03E-08 3.60E-08 3.23E-08 2.95E-08 2.68E-08 l SE 5.61 E-08 4s96E-08 4.41 E-08 3.95E-08 3.55E-08 3.21 E-08 2.92E-08 SSE 3.70E-08 3.27E-08 2.91 E-08 2.60E-08 2.34E-08 2.10E-08 1.91 E-08 S 2.32E-08 2.05E-08 1.82E-08 1.63E-08 1.46E-08 1.31 E-08 1.19E-08 SSW 1.95E-08 1.73E-08 1.54E-08 1.38E-08 1.24E-08 1.10E-08 1.00E-08 SW 1.97E-08 1.74E-08 1.54E-08 1.38E-08 1.24E-08 1.08E-08 9.86E-09 WSW 2.34E-08 2.07E-08 1.84E-08 1.65E-08 1.49E-08 1.30E-08 1.18E-08 W 3.37E-08 2.97E-08 2.64E-08 2.36E-08 2.12E-08 1.95E-08 1.77E-08 WNW 4.26E-08 3.76E-08 3.38E-08 3.02E-08 2.72E-08 2.44E-08 2.22E-08 NW 3.97E-08 3.51E-08 3.12E-08 2.80E-08 2.52E-08 2.30E-08 2.09E-C8 NNW 3.15E-08 2.78E-08 2.48E-08 2.22E-08 1.99E-08 1.81E-08 1.64E-00 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES P ==.==%T SQ :: .E: NUMBER: s th OFFSITE DOSE CALCULATION H4 j- [Q[M[([h Dd MANUAL (ODCM) REY: 14 Page 196 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS ICONT'D1 Prairie Island Dispersion Parameters (D/q),1/m 2, for Sho.4 Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured frcm Edge of Plant Complex) Miles Sector 2,2 2a 24 25 24 2,Z 24 N 1.41 E-08 1.29E-08 1.19E-08 1.09E48 1.05E-08 8.80E-09 8.23E-09 NNE 1.18E-08 1.08E-08 9.96E-09 9.12E-09 8.70E-09 7.42E-09 6.90E-09 NE 1.02E-08 9.34E-09 8.58E-09 7.92E-09 7.61 E-09 6.51 E-09 6.05E-09 ENE 1.03E-08 9.45E-09 8.69E-09 7.99E-09 7.58E-09 6.56E-09 6.10E-09 E 1.74E-08 1.60E-08 1.47E-08 1.38E-08 1.32E-08 1.13E-08 1.05E-08 ESE 2.44E-08 2.24E-08 2.05E-08 1.96E-08 1.90E-08 1.61 E-08 1.50E-08 SE 2.66E-08 2.43E-08 2.24E-08 2.16E-08 2.09E-08 1.79E-08 1.66E-08 SSE 1.74E-08 1.60E-08 1.47E-08 1.39E-08 1.32E-08 1.14E-08 1.06E-08 S 1.09E-08 9.97E-09 9.17E-09 8.70E-09 8.23E-09 7.22E-09 6.73E-09 SSW 9.14E-09 8.37E-09 7.70E-09 7.37E-09 6.91 E-09 5.96E-09 5.54E-09 SW 9.00E-09 8.25E-09 7.60E-09 7.18E-09 6.72E-09 5.98E-09 5.56E-09 WSW 1.08E-08 9.89E-09 9.09E-09 8.77E-09 8.21 E-09 7.20E-09 6.69E-09 W 1.62E-08 1.48E-08 1.36E-08 1.36E-08 1.25E-08 1.08E-08 1.00E-08 WNW 2.02E-08 1.86E-08 1.71 E-08 1.59E-08 1.53E-08 1.31 E-08 1.22E-08 NW 1.90E-08 1.74E-08 1.60E-08 1.51 E-08 1.44E-08 1.23E-08 1.14E-08 NNW 1.50E-08 1.37E-08 1.26E-08 1.17E-08 1.12E-08 9.53E-09 8.86E-09 Period of Record: 4/1/77 - 3/31/78 O O O
- IEISLAND NUCLEAR GENERATING PLANT N ERN STATES POWER COMPANY H PROCEDURES' g.gy3a <!. ' '
-; TITLE: NUMBER:
- w; u.- H4 OFFSITE DOSE CALCULATION 5.
.E, LCs Y' MANUAL (ODCM) REY: 14 i h. J Page 197 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairie Island Dispersion Parameters (D/q),1/m 2, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 2a M M 12 M M M N 7.68E-09 7.22E-09 6.76E-09 6.35E-09 5.97E-09 5.63E-09 5.31E-09 NNE 6.44E-09 6.04E-09 5.66E-09 5.32E-09 5.00E-09 4.72E-09 4.46E-09 NE 5.64E-09 5.27E-09 4.94E-09 4.64E-09 4.36E-09 4.11E-09 3.89E-09 ENE 5.69E-09 5.33E-09 5.00E-09 4.69E-09 4.41 E-09 4.16E-09 3.92E-09 E 9.78E-09 9.10E-09 8.52E-09 8.00E-09 7.52E-09 7.09E-09 6.69E-09 ESE 1.39E-08 1.30E-08 1.21 E-08 1.14E-08 1.07E-08 1.01 E-08 9.53E-09 SE 1.55E-08 1.44E-08 1.35E-08 1.27E-08 1.19E-08 1.12E-08 1.06E-08 SSE 9.88E-09 9.11 E-09 8.52E-09 8.00E-09 7.52E-09 7.08E-09 6.69E-09 i S 6.27E-09 5.67E-09 5.31 E-09 4.98E-09 4.68E-09 4.41 E-09 4.16E-09 SSW 5.16E-09 4.61E-09 4.32E-09 4.06E-09 3.82E-09 3.61 E-09 3.41 E-09 SW 5.18E-09 4.74E-09 4.45E-09 4.17E-09 3.93E-09 3.70E-09 3.50E-09 WSW 6.24E-09 5.64E-09 5.28E-09 4.96E-09 4.67E-09 4.40E-09 4.16E-09 W 9.36E-09 8.39E-08 7.87E-09 7 40E-09 6.97E-09 6.58E-09 6.22E-09 WNW 1.13E-08 1.06E-08 9.92E-09 9.31 E-09 8.76E-09 8.27E-09 7.81 E-09 NW 1.07E-08 9.88E-09 9.26E-09 8.70E-09 8.19E-09 7.72E-09 7.31 E-09 NNW 8.26E-09 7.66E-09 7.17E-09 6.73E-09 6.33E-09 5.97E-09 5.63E-09 Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 1 TITLE: NUMBER: Sfir$.%y.-:;f.M. q . -- - Ni OFFSITE DOSE CALCULATION H4 n:7 Jp 7 ; [ MANUAL (ODCM) REV: 14
]GEOJ- p TABLE A PRAlRIE ISLAND DISPERSION PARAMETERS ICONT'D_1 -
Prairie Island Dispersion Parameters (D/q),1/m 2, for Short Term Ground Level Releases s E00 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M 3.,Z 3a M _44 _4,1 .4.,2 N 5.01 E-09 4.75E-09 4.50E-09 4.28E-09 4.07E-09 3.88E-09 3.70E-09 NNE 4 22E-09 4.00E-09 3.79E-09 3.60E-09 3.42E-09 3.26E-09 3.11 E-09 l NE 3.68E-09 3.49E-09 3.31 E-09 3.15E-09 3.00E-09 2.85E-09 2.72E-09 ENE 3.71E-09 3.51 E-09 3.33E-09 3.17E-09 3.01 E-09 2.87E-09 2.74E-09 E 6.33E-09 6.00E-09 5.69E-09 5.41 E-09 5.15E-09 4.91 E-09 4.68E-09 ESE 3.02E-09 8.54E-09 8.10E-09 7.70E-09 7.32E-09 6.98E-09 6.66E-09 SE 9.99E-09 9.46E-09 8.96E-09 8.51 E-09 8.09E-09 7.70E-09 7.33E-09 SSE 6.33E-09 5.99E-09 5.68E-09 5.40E-09 5.14E-09 4.90E-09 4.67E-09 ! S 3.94E-09 3.73E-09 3.54E-09 3.36E-09 3.20E-09 3.05E-09 2.91 E-09 SSW 3.23E-09 3.06E-09 2.91 E-09 2.77E-09 2.64E-09 2.51 E-09 2.40E-09 SW 3.31 E-09 3.14E-09 2.98E-09 2.83E-09 2.66E-09 2.53E-09 2.42E-09 WSW 3.94E-09 3.73E-09 3.54E-09 3.37E-09 3.21 E-09 3.06E-09 2.92E-09 W 5.89E-09 5.59E-09 5.31 E-09 5.05E-09 4.81 E-09 4.59E-09 4.38E-09 WNW 7.39E-09 7.00E-09 6.64E-09 6.31 E-09 6.00E-09 5.72E-09 5.45E-09 NW 6.93E-09 6.56E-09 6.23E-09 5.92E-09 5.63E-09 5.36E-09 5.11 E-09 NNW 5.33E-09 5.05E-09 4.79E-09 4.58E-09 4.34E-09 4.13E-09 3.94E-09 i Period of Record: 4/1/77 - 3/31/78 O O O
. E ISLAND NUCLEAR GENERATING PLANT N ERN STATE 3 POWER COMPANY H PROCEDURES
- OF af; N.4:. s: 9 difj TITLE: NUMBER:
# H4
<1.'. L >w' OFFSITE DOSE CALCULATION N w% P ?.fJ3l...
. M MANUAL (ODCM) REY: 14
....;_. ' .. ? Page 199 of 223 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 Prairie Island Dispersion Parameters (D/q),1/m 2, for Short Term Ground Level Releases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)
Miles Senior M M M M _42 M M N 3.55E-09 3.40E-09 3.26E-09 3.12E-09 2.99E-09 2.87E-09 2.76E-09 NNE 2.97E-09 2.84E-09 2.71 E-09 2.60E-09 2.49E-09 2.39E-09 2.30E-09 NE 2.60E-09 2.48E-09 2.37E-09 2.27E-09 2.18E-09 2.09E-09 2.01 E-09 ENE 2.61 E-09 2.49E-09 2.39E-09 2.29E-09 2.19E-09 2.10E-09 2.02E-09 E 4.48E-09 4.28E-09 4.10E-09 3.93E-09 3.77E-09 3.62E-09 3.47E-09 ESE 6.35E-09 6.07E-09 5.81 E-09 5.57E-09 5.34E-09 5.13E-09 4.92E-09 SE 6.99E-09 6.68E-09 6.38E-09 6.12E-09 5.86E-09 5.62E-09 5.38E-09 SSE 4.48E-09 4.28E-09 4.10E-09 3.93E-09 3.78E-09 3.63E-09 3.48E-09 S 2.78E-09 2.65E-09 2.54E-09 2.43E-09 2.34E-09 2.24E-09 2.15E-09 SSW 2.30E-09 2.20E-09 2.11 E-09 2.02E-09 1.94E-09 1.86E-09 1.79E-09 SW 2.31E-09 2.21E-09 2.12E-09 2.03E-09 1.95E-09 1.87E-09 1.80E-09 , WSW 2.79E--09 2.67E-09 2.55E-09 2.45E-09 2.33E-09 2.24E-09 2.15E-09 W 4.19E-09 4.01E-09 3.84E-09 3.69E-09 3.54E-09 3.40E-09 3.27E-09 WNW 5.20E-09 4.98E-09 4.76E-09 4.57E-09 4.38E-09 4.21 E-09 4.04 E-09 NW 4.88E-09 4.66E-09 4.44E-09 4.25E-09 4.08E-09 3.92E-09 3.77E-09 NNW 3.76E-09 3.60E-09 3.43E-09 3.29E-09 3.16E-09 3.03E-09 2.9-1 E-09 , Period of Record: 4/1/77 - 3/31/78
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: M' OFFSITE DOSE CALCULATION MANUAL (ODCM) TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 NUMBER: REV: 14 H4 Page 200 of 223 Prairie Island Dispersion Parameters (D/q),1/m 2, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector SA N 2.65E-09 NNE 2.21 E-09 NE 1.93E-09 ENE 1.94E-09 E 3.34E-09 ESE 4.73E-09 l SE 5.17E-09 SSE 3.35E-09 S 2.07E-09 ! SSW 1.73E-09 SW 1.73E-09 WSW 2.07E-09 W 3.15E-09 WNW 3.89E-09 NW 3.63E-09 NNW 2.80E-09 i Period of Record: 4/1/77 - 3/31/78 O O O
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES _ TITLE: NUMBER: H4 O oresire oose CALCULATION M'l_
- ) MANUAL (ODCM) REV: 14 Page 201 of 223 APPENDIX B - PRAIRIE 13 LAND 12.2m WIND AND AT42.7-12.2M STABILITY JOINT FREQUENCY DISTRIBUTIONS (4/1/77 - 3/31/78)
~
O l l O
PRAIRIE ISLAND NUCLEAR CENERATIN3 PLANT NORTHERN STATES POWER COMPANY 2 ' " "' H PROCEDURES TITLE: NUMBER: b (! OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h
'3/lle h m e Page 202 of 223 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLAN SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS A ELEVATION 40 FT.
WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO_3 4TO7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL l N 7 22 29 11 0 0 69 NNE 13 19 20 4 0 0 56 NE 11 35 16 0 0 1 63 ENE E 11 14 33 37 20 24 0 0 0 0 0 0 64 75 g , ESE 4 45 49 7 2 0 107 SE 4 10 22 13 1 0 50 SSE 1 7 19 12 2 0 41 S 2 23 45 27 0 0 97 SSW 1 22 39 14 0 0 76 SVV 2 17 30 3 0 0 52 WSW 0 21 25 11 0 0 57 W 1 29 46 18 2 0 96 WNW 6 34 64 56 20 1 181 NW 12 42 72 55 20 0 199 NNW 11 43 49 20 2 0 'i25 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS HOURS OF CALM THIS CLASS 1408 0 g PERCENT OF ALL DATA THIS CLASS 16.81
PRAIRIE ISLAND NUCLEAR GENERATING PLANT H PROCEDURES NORTHERN STATES POWER COMPANY NUMBER:
' "4 O OFFSITE DOSE CALCULATION REV: 14 E TITLE:
MANUAL (ODCM)
" Page 203 of 223 i
NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERAT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS B ELEVATION 40 FT. WIND SPEED (MPH) AT 40 FT LEVEL ) 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL DIRECTION 0 3 5 1 0 0 9 N 2 1 0 0 5 , NNE 1 1 2 0 0 0 0 2 NE O ENE 0 3 2 0 0 0 5 , E O 1 1 0 0 0 2 ESE 1 5 10 6 1 0 23 SE 2 2 8 4 0 0 16 SSE 0 3 4 3 0 0 10 S 1 0 7 9 0 0 17 SSW 0 1 7 0 0 0 8 SW 0 4 1 0 0 0 5 WSW 1 2 5 1 0 0 9 W 0 8 7 3 0 0 18 WNW 1 5 8 6 3 0 23 , NVV 2 4 11 10 1 0 28 NNW 1 5 3 1 0 1 11 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 191 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 2.28
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY Mi TITLE: H PROCEDURES NUMBER: OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 Page 204 of 223 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR SITE METEOROLOGY- FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS C ELEVATION 40 FT. WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION _1 T O 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 2 4 4- 1 0 0 11 NNE 2 3 1 0 0 0 NE 6 1 5 1 0 0 0 7 ENE O 3 1 0 0 0 E 4 - 1 8 3 0 0 0 12 ESE O 7 11 2 0 0 SE O 20 2 5 6 0 0 13 SSE O 2 6 7 1 0 16 S 0 2 10 4 0 0 16 SSW 1 6 4 0 0 0 SW 11 2 2 3 2 0 0 WSW 9 1 6 5 1 2 0 W 0 2 11 4 15 1 0 18 WNW 1 3 6 7 NW 1 0 18 2 7 11 16 6 NNW 3 1 43 5 7 3 3 0 21 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 240 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS2.87
l PRAIRIE ISLAND NUCLEAR CENERATING PLANT H PROCEDURES NUMBER: TITLE: r H4 OFFSITE DOSE CALCULATION V' m_N_ORTHERN S MANUAL (ODCM) NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT REV: 14 Page 205 of 223 SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS D ELEVATION 40 FT. WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 IQIAL N 9 24 11 8 0 0 52 NNE 6 22 9 0 0 0 37 NE 16 26 4 0 0 0 46 ENE 11 41 ~4 0 0 0 56 E 11 95 27 0 0 0 133 l ESE 8 57 154 19 0 0 238 SE 10 30 90 38 5 0 173 SSE 8 40 59 51 10 0 168 l S 1 51 72 17 4 0 145 SSW 5 29 30 12 0 0 76 l SW 4 15 17 4 0 0 40 WSW 5 23 31 21 3 4 87 VV 6 53 61 28 6 1 155 WNW 14 57 76 75 21 0 243 NW 14 44 72 110 41 0 281 NNW 16 22 41 25 13 0 117 l VAR 0 0 0 0 0 0 0 i TOTAL HOURS THIS CLASS 2061 OURS OF CALM THIS CLASS 4 PERCENT OF ALL DATA THIS CLASS 24.49
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY jj? Q f f ' 7 TITLE: H PROCEDURES NUMBER: N OFFSITE DOSE CALCULATION k MANUAL (ODCM) REV: 14 IN -ww Page 206 of 223 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERA SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS E ' ELEVATION 40 FT. l WIND SPEED (MPH) AT 40 FT LEVEL DlHECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL t N 22 30 9~ 11 1 0 73 NNE 18 29 7 0 0 ' 0 54 NE 22 26 7 0 1 0 56 l ENE 19 30 5 0 1 0 55 E 25 96 10 0 0 0 131 l ESE 28 144 140 27 0 0 ' 349 SE 24 107 125 41 2 0 299 SSE 21 67 74 23 0 0 185 S 11 56 73 29 0 1 170 SSW 3 26 29 40 1 0 99 SW 14 22 17 12 0 0 65 WSW 14 24 24 11 1 0 74 VV 26 73 48 18 1 0 166 WNW 46 136 127 44 4 0 357 NVV 46 98 101 62 8 0 315 NNW 43 53 48 10 3 0 157 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS HOURS OF CALM THIS CLASS 2612 7 g PERCENT OF ALL DATA THIS CLASS 31.18
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY M" H PROCEDURES TITLE: NUMBER: O OFFSITE DOSE CALCULATION H4 [ MANUAL (ODCM) REY: 14 b mr Page 207 of 223 NORTHERN STATES POWER COMPANY PRA!RIE ISLAND NUCLEAR GENERATING PL SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS F ELEVATION 40 FT. WIND SPEED (MPH) AT 40 FT LEVEL DIRECTIOR 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 18 8 3 0 0 0 29 NNE 11 6 0 1 0 0 18 NE 11 5 2 0 0 0 18 ENE 13 7 0 0 0 0 20 E 29 33 2 0 0 0 64 ESE 39 61 9 1 0 0 110 SE 38 69 36 3 0 0 146 SSE 27 32 17 2 1 0 79 S 12 16 21 7 0 0 56 SSW 6 11 17 6 0 0 40 SW 5 3 9 4 0 0 21 WSW 8 8 8 0 0 0 24 W 25 39 12 2 0 0 78 WNW 56 63 12 0 0 0 131 NW 66 71 16 3 0 0 156 NNW 29 19 6 2 0 0 56 VAR 0 0 0 0 0 0 0 1053 CTOTAL
' HOURS OFHOURS THIS CLASS CALM THIS CLASS 7 PERCENT OF ALL DATA THIS CLASS 12.57
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES NUMBER: P ,4.p 7.tVf. TITLE: A r H4 W n 1 W@Nx;;;lOFFSITE DOSE CALCULATION
^ REV: 14 MANUAL (ODCM) k.eur.;;er=ms M Page 208 of 223 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 STABILITY CLASS G ELEVATION 40 FT.
WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 14 5 0 0 0 0 19 NNE 13 2 1 0 0 0 16 NE 12 2 1 0 0 0 15 ENE E 22 52 1 8 2 2 0 0 0 0 0 0 25 62 g ESE 50 17 1 0 0 0 68 SE 37 23 8 1 0 0 69 SSE 18 8 7 2 0 0 35 S 11 4 4 0 0 0 19 SSW 13 2 2 0 0 0 17 SW 15 5 1 0 0 0 21 WSW 10 1 1 0 0 0 12 W 41 19 1 0 0 0 61 WNW 75 50 0 0 0 0 125 NVV 80 66 3 0 0 0 149 NNW 47 19 5 0 0 0 71 VAR 0 0 0 0 0 0 0 l TOTAL HOURS THIS CLASS HOURS OF CALM THIS CLASS 821 37 g PERCENT OF ALL DATA THIS CLASS 9.80
PRAIRIE ISLAND NUCLEAR CENERATIN3 PLANT H PROCEDURES NORTHERN STATES POWER COMPANY TITLE: NUMBER: H4 O - OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 f Page 209 of 223 APPENDIX C - DOSE PARAMETERS FOR RADIOlODINES. PARTICULATES AND TRITlUM This appendix contains the methodology which was used to calculate the dose parameters for radiolodines, particulates, and tritium to show compilance with 10CFR20 and Appendix 1 of 10CFR50 for gaseous effluents. These dose parameters, Pi and Ri, were calculated using the methodology outlines in NUREG-0133 along with Regulatory Guide 1.109 Revision 1. The following sections provide the specific methodology which was utilized in calculating the Pi and R i values for the various exposure pathways. C.1 Calculation of Pi The parameter, Pi , contained in the radiolodine and particulates portion of Section 5.2, includes pathway transport parameters of the ith radionuclide, the receptor's usage of the pathway media and the dosimetry of the exposure. Pathway usage rates and the intemal dosimetry are functions of the receptor's age: however, the child age group, will always receive the maximum dose under the exposure conditions assumed. C.1.1 inhalation Pathway Pi , = K' (BR) DFA, (C.1-1) where: P,i = dose parameter for radionuclide i for the inhalation pathway, mrem /yr per cl/m3; K' = a constant of unit conversion:
= 10epCl/ Cl-BR = the breathing rate of the child age group, m3/yr, DFA i= the maximum organ inhalation dose factor for the child age group for radionuclide i, mrem /pCl.
O
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY
" H PROCEDURES TITLE: NUMBER:
L H4 OFFSITE DOSE CALCULATION j MANUAL (ODCM) REV: 14 l b n Page 210 of 223 l The age group considered is the child group. The child's breathing rate is taken as 3700 m3/yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the child DFA,i are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem /pCl. The total body is considered as an organ in the selection of DFA.i The incorporation of breathing rate of the child and the unit conversion factor results in the following: 8 Pi , = 3.7 x 10 DFA (C.1-2) C.2 fddaulation of R3 The radiolodine and particulate specification is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs. The inhalation and ground plane exposure pathways SHALL be considered to exist at all locations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are
'g l
considered based on their existence at the various locations. Ri values have been calculated for the adult, teen, child, and infant age groups for the ground plane, cow milk, goat milk, vegetable and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below. C.2.1 inhalation Pathway R,i = K'(BR)a (DFA )a i (C.2-1) where: R,i = dose factor for each identified radionuclide i of the organ of interest, mrem /yr per Cl/m3; K' = a constant of unit conversion:
= 10epCi/pCi; (BR)a = breathing rate of the receptor of age group a, m3/yr; (DFA)ai = organ inhalation dose factor for radionuclide i for the receptor of age group a, mrem /pCi.
e
PRAIRIE ISLAND NUCLEAR CENERATIN3 PLANT NORTHERN STATES POWER COMPANY H PROCEDURES E gjgry - . v- ., . TITLE: NUMBER: sw: . 94 Q,, Q :. g7 . ..,? OFFSITE DOSE CALCULATION
@ja n: .: MANUAL (ODCM) REV: 14 begc;f G ,,.k?g-Qt m?/r._ -- - Page 211 of 223 I The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109 Revision 1.
l Age Grouo (a) Breathing Rate (m3/vr) Infant 1400 Child 3700 Teen 8000 Adult 8000 inhalation dose factors (DFA)a i for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1. C.2.2 Ground Plane Pathway l l R,i = l i K'K"(SF)DFG i (1-e*')/Ai (C.2-2) where: '
,q R ,"
= dose factor for the ground plane pathway for -
l
'y/ each identified radionuclide i for the organ of l
interest, m2-mrem /yr per pCl/sec per; , 4 l K' = a constant of unit conversion; ;
= 106 pCl/ Ci; K" = a constant of unit conversion;
= 8760 mr/ year; Ai = the radiological decay constant for i radionuclide i, sec-1 l
t = the exposure time, sec;
= 4.73 x 108sec (15 years)'
DFGi
= the ground plant dose conversion factor for radionuclide i; mrem /hr per pCi/m2; SF = the shielding factor (dimensionless)
O li = factor to account for fractional deposition of radionuclidei.
~
PRAIRIE ISLAND NUCLEAR CENERATIND PLANT NORTHERN STATES POWER COMPANY H PROCEDURES N ' TITLE: NUMBER: OFFSITE DOSE CALCULATION k MANUAL (ODCM) REV: 14 NOV mes L Page 212 of 223 For radionuclides other than iodine, the factor il is equal to one. For radioiodines, the value of li may vary. However, a value of 1.0 was used in calculating the R values in Table 5.5-1. A shielding factor of 0.7 from Table E-15 of Regulatory Guide 1.109 Revision 1 is used. A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1. C.2.3 Grass-Cow or Goat-Milk Pathwav_
- fpf, 'r(1-e-AE i tap) + B w (1--e*) ~
Ri , = l K'O i pUapF m (DFL),ei y + PN ,
~
i g (1-fps f) ' r(1 e-AE tes) + PA B (1-e9b) " e -A tih (C.2-3) YA, sE i , R io = dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, m2-mrem /yr per Ci/sec; K' = a constant of unit conversion; 1
= 106 pCl/ Ci; I Op = the cow's or goat's feed consumption rate, kg/ day (wet weight);
I
= I Uap the receptor's milk consumption rate for age group a, l liters /yr; l
Yp = the agricultural productivity by unit area of pasture feed grass, kg/m2; l Y, = the agricultural productivity by unit area of stored l feed, kg/m2; i Fm = the stable element transfer coefficients, ; pCi/ liter per pCi/ day;
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATE 7 POWER COMPANY H PROCEDURES TITLE: () OFFSITE DOSE CALCULATION NUMBER: H4 REV: 14 MANUAL (ODCM) OMIdWO" Pace 213 of 223 r = fraction of deposited activity retained on cow's feed ' grass; (DFl)ai = the organ ingestion dose factor for radionuclide i for the receptor in age group a, mrem /pCi; Ae = 4 +A:
=
4 the radiological decay constant for radionuclide 1, ;
- sec-1; I
i 4 = the decay constant for removal of activity on leaf and plant surfaces by weathering, sec-1; l
= 5.73 x 10-7 sec-1 (corresponding to a 14 day 4
half-life); t, = the transport time from feed to cow or goat to milk, to receptor, sec; th = the transport time from harvest, to cow or goat, to j consumption, sec' to = period of time that activity builds up in soll, sec; Bv i
= concentration factor for uptake of radionuclide i from the soil by the edible parts of crops, pCi/kg (wet weight) per pCl/kg (dry soil);
P = effective surface density for soil, (dry weight) kg/m2; fp = fraction of the year that the cow or goat is on pasture; f, = fraction of the cow feed that is pasture grass while the cow is on pasture; i top = period of pasture grass exposure during the growing ! season, sec; v
)
PRAIRIE ISLAND NUCLEAR CENERATIN3 PLANT NORTHERN STATES POWER COMPANY H PROCEDURES k tgSf.';.(ff?%:p TITLE: NUMBER: l;;w we H4 A e.V : 3. OFFSITE DOSE CALCULATION W [O . U i h A $;4; M S $ ? J MANUAL (ODCM) __ REV: 14 Paae 214 of 223 t,= period of crop exposure during the growing season, sec; li = factor to account for fractional deposition of radionuclide 1. For radionuclides other than iodine, the factor i l is equal to one. For radiolodines, the value of li may vary. However, a value of 1.0 was used in calculating the R values Tables 5.5-8 through 5.5-15. Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of fs was considered unity in lieu of site-specific information. The value of fp was 0.5 based upon a 6-month grazing period. Table C-1 contains the appropriate parameter values and their source in , Regulatory Guide 1.109 Revision 1. The concentration of tritium in milk is based on the airbome concentration rather than the deposition. Therefore, the Ri is based on X/Q: Ry, = K'K" ' FmOgUap (DFL), i 0.75 (0.5/H) (C.2-4) where: R Tu = dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem /yr per Ci/m3 ; K"' = a constant of unit conversion;
= 103 gm/kg; H = absolute humidity of the atmosphere, gm/m3; 1 0.75 = the fraction of total feed that is water; 0.5 = the ratio of the specific activity of the feed grass tv !
the atmospheric water. ' and other parameters and values are given below. A value of H of 8 grams / meter3 , was used in lieu of site-specific information. l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES i I TITLE: NUMBER: l H4 ('~ OFFSITE DOSE CALCULATION ) f_, MANUAL (ODCM) REV: 14 l
$72Uf/At,:2m Paos 215 of 223 i
C.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway, therefore: U pF, (DFL i ),e *'8 ffs 'r(1-e-AEi t ep) + B g (1-e-'i'b) ~
+
Ri , = l K'Op i p y PA i ,
' ~
r(1-e-AE, tes) + Bg(1-ei'b) ~ e -A i 'h (C.2-5) (1-fpf ) YA, sE PA, where: R,i = dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, m2 - n mrem /yr per Ci/sec; - \.y Ff = the stable element transfer coefficients, pCi/Kg per pCi/ day; Uap = the receptor's meat consumption rate for age group a, kg/yr; ts = the transport time from slaughter to consumption, sec; th = the transport time from harvest to animal consumption, sec; tep = period of pasture grass exposure during the crowing season, sec; to, = period of creo exposure during the growing season, sec; li = factor to account for fractional deposition of radionuclide 1. b) '" For radionuclides other than iodine, the factor il is equal to one. For radiolodines, the value of li may vary. However, a value of 1.0 was used in calculating the R values in Tables 5.5-5 through 5.5-7.
PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
' "~" I TITLE: NUMBER: (
cM!, i OFFSITE DOSE CALCULATION MANUAL (ODCM) H4 REV: 14 Page 216 of 223 W i All other terms remain the same as defined in Equation C.2-3. Table C-2 l contains the values which were used in calculating Ri for the meat pathway. l The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R4 is based on X/Q. Rr , = K'K" ' F,O Uap p (DFl),i 0.75 (0.5/H) (C.2-6) I where: l R,7
= dose factor for the meat ingestion pathway for tritium )
for any organ of interest, mrem /yr per Cl/m3.
)
All other terms are defined in Equation C.2-4 and C.2-5, above. l l 1 I l O
l PRAIRIC !SLAND NUCLEAR CENERATIN2 PLANT I NORTHERN STATES POWER COMPANY H PROCEDURES Page 2 7 f 23 C.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore: r(1--e-lE, te) + Bg(1-e*'b) ~+ R;, = 1 K'(DFL 3 j ), U!ft e* y Py ,
~
+ N( (C.2-7)
Usfge*'h YvAE, PA i where:
~
O a r" = e ee recte< <er vesete8ie get" ev rer reoiee ciioe i for the organ of interest, m2 - mrem /yr per Ci/sec; i K' = a constant of unit conversion;
= 106 pCl/ Ci; Uh = the consumption rate of fresh leafy vegetation by the receptor in age group a, kg/yr; Us = the consumption rate or stored vegetation by the I receptor in age group a, kg/yr; IL = the fraction of the annualintake of fresh leafy vegetation grown locally; fo = the fraction of the annualintake of stored vegetation grown locally; i tt = the average time between harvest of leafy
! vegetation and its consumption, sec; !O
1 PRAIRIEEDLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY 24J/. [ il& TITLE: H PROCEDURES p{ M f . Wc
.gr . .
NUMBER: H4 & l f@$ . 4?! OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 W i tfly%dggl%V Paae 218__of 223 i th = the average time between harvest of stored \ vegetation and its consumption, sec; { Yv = the vegetation areal density, kg/m2; t, = period of leafy vegetable exposure during growing season, see; Il = factor to account for fractional deposition of radionuclide i. For radionuclides other tflan iodine, the factor il is equal to one. For I radioiodines. the value of 11 may vary. However, a value of 1.0 was used in calculating the R values in tables 5.5--2 through 5.5-4. All other factors were defined above. g Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1. In lieu of site-specific data default values for tf and fg,1.0 and 0.76, respectively were used in the calculation of Ri . These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1. The concentration of tritium in vegetation is based on the airbome concentration rather than the deposition. Therefore, the Ri is based on X/Q: R Ty = K'K"' 'U$t + Usf g, (DFL ), 0.75 (0.5/H) i (0.2-8) where: R, T = dose factor for the vegetable pathway for tritium for any organ of interest, me- mrem /yr per Cl/m3. All other terms remain the same as those in Equations C.2-4 and C.2-7.
l PRAIRIE ISLAND NUCLEAR CENERATING PLANT H PROCEDURES NORTHERN STATES POWER COMPANY Wf TITLE: NUMBER: Q OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 Page 219 of 223 56 +m _ . 1 TABLE C PARAMETERS FOR COW AND GOAT MILK PATHWAYS Parameter Value Beference (Reg. Guide 1.109 Rev.1) Op (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 Yp (kg/m2) 0.7 Table E-15 tg (seconds) 1.73 x 105 (2 days) Table E-15 r 1.0 (radiolodines) Table E-15 0.2 (particulates) Table E-15 (DFl)ai (mrom/pCl) Each radionuclide Tables E-11 to E-14 Fm (pCl/ day per pCi/ liter) Each stable element Table E-1 (cow) Table E-2 (goat) g o(seconds) t 4.73 x 108 (15 yr) Table E-15 V Ys (kg/m 2) 2.0 Table E-15 Yp (kg/m2) 0.7 Table E-15 in (seconds) 7.78 x 108 (90 days) Table E-15 Uap (liters /yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 tep (seconds) 2.59 x 10e (30 days) Table E-15 tes (seconds) 5.18 x 108 (60 days) Table E-15 Bi v (pCl/Kg (wet weight) Each stable element Table E-1 per pCi/Kg (dry soil)) P(Kg/m2(dryweight)) 240 Table E-15 l l
/
l l PRAIRIE ISLAND NUCLEAR CENERATIN2 PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
; f;j 7:,;; :f W:.t TITLE: !
NUMBER: j 1 1,$ !h((; ! a+- - x :: - .;
$ g 5 .i, Ts h i' l; OFFSITE DOSE CALCULATION MANUAL (ODCM) REV: 14 h! l Paa.22 m 2n I l
l l THIS PAGE IS LEFT INTENTIONALLY BLANK
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I O
PRAIRIE ISLAND NUCLEAR CENERATIN2 PLANT , NORTHERN STATES POWER COMPANY H PROCEDURES I TITLE: NUMBER: O W$ OFFSITE DOSE CALCULATION MANUAL (ODCM) TABLE C PARAMETERS FOR THE MEAT PATHWAY H4 REV: 14 Page 221 of 223 1 j Parameter Yalun Reference (Reg. Guide 1.109 Rev.1) r 1.0 (radiolodines) Table E-15 0.2 (particulates) Table E-15 F (pCl/Kg per pCi/ day) Each stable element Table E-1 Uap (Kg/yr) 0 infant Table E-5 41 child Table E 65 teen Table E-5 110 adult Table E-5 (DFl)ai (mrem /pCi) Each radionuclide Tables E-11 to E-14 Yp (kg/m2) 0.7 Table E-15 Y (kg/m2) 2.0 Table E-15
- tb(seconds) 4.73 x 108 (15 yr) Table E-15 ts (seconds) 1.73 x 106 (20 days) Table E-15 th(seconds) 7.78 x 106 (90 days) Table E-15 tep (seconds) 2.59 x 10e (30 days) Table E-15 tes (seconds) 5.18 x 10s (60 days) Table E-15 Or (kg/ day) 50 Table E-3 Bi y (pCi/Kg (wet weight) Each stable element Table E-1 l per pCl/Kg (dry soll)) 1 P(Kg/m2(dryweight)) 240 Table E-15 i
l O !
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l PRAIRIE ISLAND NUCLEAR CENERATIN2 PLANT l NORTHERN STATES POWER COMPANY
^' H PROCEDURES
"'! .,.j::. ;; ; r.. . . TITLE:
NUMBER: 1/]Qh - 7.1 :' ~ ' OFFSITE DOSE CALCULATION h REV: 14
. ~
+ , . i:_
^:yy .K.' [ ) .
.. MANUAL (ODCM)
% niw 2; n ' _ _
Page 222 of 223 l THIS PAGE IS LEFT INTENTIONALLY BLANK
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PRAIRIE ISLA. "C1W.R CENERATIN3 PLANT NORTHERN STAYE : _"!ER COMPANY H PROCEDURES l NUMBER:
- b.i5:
H4 h OFFSITE DOSE CALCULATION l { MANUAL (ODCM) REV: 14 l e ,
%m ! Page 223 of 223 TABLE C PARAMETERS FOR THE VEGETABLE PATHWAY Parameter Value Reference (Reg. Guide 1.109 Rev.1) r (dimensionless) 1.0 (radiolodines) Table E-1 2.0 (particulates) Table E-1 (DFL)a i (mrem /pCl) Each radionuclide Tables E-11 to E-14 Ual(kg/yr) -Infant 0 Table E-5
- Child 26 Table E-5
- Teen 42 Table E-5
- Adult 64 Table E-5 Uas (kg/yr) -Infant 0 Table E-5
- Child 520 Table E-5
- Teen 630 ' Table E-5
- Adult 520 Table E-5 t t(seconds) 8.6 x 104 (1 day) Table E-15 ;
th(seconds) 5.18 x 108 (60 days) Table E-15 Yy (kg/m2) 2.0 Table E-15 t, (seconds) 5.18 x 108 (60 days) Table E-15 tb(seconds) 4.73 x 108 (15 yr) Table E-15 P(Kg/m2 (dryweight)) 240 Table E-15 Bi g (pCl/Kg (wet weight) Each stable element Table E-1 per pCl/kg (dry soil)) O}}