ML20093J005
| ML20093J005 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/16/1995 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20093H995 | List: |
| References | |
| H4, NUDOCS 9510230062 | |
| Download: ML20093J005 (197) | |
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ND Pace 2 of 197 TABLE OF CONTENTS Section Title Page OFFSITE DOSE CALCULATION MANUAL INTRODUCTION.............
9 D E FI N ITI O N S......................................................
10 1.0 RADIOLOGICAL EFFLUENT SPECIFICATIONS AND SURVEILLANCE R EQ U I R E M E NTS.............................................
14 1.1 S pecifi catio n s...........................................
14 1.2 Surveillance Requirements...............................
14 2.0 LIQ UI D E FFLU E NTS..........................................
15 C o n ce nt ratio n.................................................
15 Dose........................................................
16 Liquid Radwaste Treatment Systems............................
17 Radioactive Liquid Effluent Monitoring Instrumentation.............
18 Liquid Storag e Tanks..........................................
19 3.0 G AS EO U S E FFLU E NTS.......................................
20 D o s e R at e....................................................
20 D o se - N oble G ase s...........................................
21 Dose - I-131,1-133, Tritium, Long Lived Particulates..............
22 Gaseous Radwaste Treatment Systems..........................
23 Explosive Gas Monitoring Instrumentation........................
25 Radioactive Gaseous Effluent Monitoring Instrumentation..........
26 Atmospheric Steam Dump Monitoring............................
27 4.0 LIQUID EFFLUENT C ALCULATIONS... -.........................
28 4.1 Monitor Alarm Setpoint Determination......................
28 4.2 Compliance With 10CFR20...............................
36 4.3 Liquid Effluent Dose - Compliance with 10CFR50...........
38 4.4 R ef e re n ce s.............................................
42 J
5.0 GASEOUS EFFLUENT CALCULATIONS........................
43 5.1 Monitor Alarm Setpoint Determination......................
43 5.2 Gaseous Effluent Dose Rate - Compliance with 10CFR20....
47 5.3 Gaseous Effluents - Compliance with 10CFR50.............
50 5.4 R e f e re n ce s.............................................
55
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 1
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gn, Paae 3 of 197 TABLE OF CONTENTS Section Title Page 6.0 TOTAL DOSE FROM RADIOACTIVE RELEASES AND URANIUM F U EL SO U R C ES.............................................
56 7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....
58 8.0 R EPORTING REQUIREMENTS................................
62 8.1 Annual Radioactive Effluent Report........................
62 8.2 Annual Radiological Environmental Monitoring Report.......
64 8.3 Annual Summary of Meteorological Data...................
65 8.4 R eco rd R ete ntio n.......................................
65 BASES 2.0 Liq uid Efflu e nt s........................................
66 3.0 G a s e o u s E fflu e nt s.......................................
68 6.0 Tot al D o s e..............................................
71 7.0 Radiological Environmental Monitoring Program.............
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- W Paae 4 of 197 TABLE OF CONTENTS Section Title Page LIST OF TABLES TABLE 1.1 - OP ERATIONAL MOD ES...............................
'/3 TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS P R O G R AM...........................................
74 TABLE 2.2 - RADIOACTIVE LIQUID EFFLUENT MONITORING IN STR U M E NTATION..................................
78 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..
80 TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPt.ING AND AN ALYSIS P ROG R AM.................................
82 TABLE 3.2 - RADIOACTIVE GASEOUS EFFLUENT MONITORING I N STR U M E NTATI O N..................................
87 TABLE 3.3 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..
89 TABLE 4.1 - LIQUID SOURC E TERMS..............................
91 TABLE 4.2-ADULT INGESTION DOSE VALUES (A) FOR THE PRAIRIE i
ISLAND NUCLEAR GENERATING PLANT (M R E M/H R P E R M Cl/M L).............................
92 l
TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992)...............
94 TABLE 5.1 - MONITOR ALARM SETPOINT DETERMINATION FOR PINGP...............................................
108 TABLE 5.2 - GASEOUS SOURCE TERMS...........................
109 TABLE 5.3 - CRITICAL ORGAN DOSE VALUES (P ) FOR CHILD.......
110 i
TABLE 5.4 - DOSE FACTORS FOR NOBLE GASES *.................
111 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GROUND, ALL AGES........
112 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE, ADULT.........
113 9
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Pace 5 of 197 TABLE OF CONTENTS Section Title Page LIST OF TABLES TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE, TEEN..........
114 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE, CHILD.........
115 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT, ADULT...............
116 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT, TEEN................
117 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT, CHILD................
118 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, ADULT..........
119 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, TEEN...........
120 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, CHILD..........
121 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK, INFANT........
122 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, ADULT........
123 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, TEEN..........
124 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, CHILD.........
125 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK, INFANT........
126 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * -INHALATION, ADULT.......
127 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, TEEN........
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- +.MW "Mt Page 6 of 197 TABLE OF CONTENTS Section Title Page LIST OF TABLES TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, CHILD........
129 TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - INHALATION, INFANT.......
130 TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS.................
131 TABLE 7.2 - REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATION IN ENVIRONMENTAL SAMPLES........................
135 TABLE 7.3 - DETECTION CAPABILITIES FOR ENVIRONMENTALSAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(A).......
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TABLE OF CONTENTS Section Title Page LIST OF FIGURES FIGURE 3.1 - PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE BOUNDARY FOR LIQUID EFFLUENTS................
138 FIGURE 3.2 - PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE BOUNDARY FOR GASEOUS EFFLUENTS.............
139 APPENDICES APPENDIX A - METEOROLOGICAL ANALYSES........................
140 TABLE A PRAIRIE ISLAND RELEASE CONDITIONS..............
143 TABLE A DISTANCES (MILES) TO CONTROLLING UNRESTRICTED AREA BOUNDARY LOCATIONS.......................
144 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
145 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
146 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
153 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
160 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
161 TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS.........
169 APPENDIX B - PRAIRIE ISLAND 12.2M WIND AND DT 42.7-12.2M STABILITY JOINT FREQUENCY DISTRIBUT.ONS (4/1/77 - 3/31/78)... 177 APPENDIX C - DOSE PARAMETERS FOR RADIOlODINES, PARTICULATES AND TRITIUM..............................................
185 TABLE C PARAMETERS FOR COW AND GOAT MILK PATHWAYS.
195 TABLE C PARAMETERS FOR THE MEAT PATHWAY.............
196 TABLE C PARAMETERS FOR THE VEGETABLE PATHWAY.......
197
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Pace 8 of 197 RECORD OF REVISIONS Revision No.
Data 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 i
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 i
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 September 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES igg TITLE:
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EMWy 7 Mk Pane 9 of 197 OFFSITE DOSE CALCULATIONS MANUAL INTRODUCTION The Offsite Dose Calculation Manual (ODCM) describes the methodologies and pararieters used in: 1) the calculation of offsite doses resulting from radioactive gaseous and liquid effluent 3; 2) the calculation of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. The methodology stated in this manualis 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 j
implementation of this manual are provided in the Count Room Manual, (Radiation Protection Implementing Procedures 4000 Series).
4 Also included in this manual is information related to the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP). Tables 7.1,7.2 and 7.3 designate specific r,ampia 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:
i
- 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 i
period of the report in which the change in the ODCM was made. Each change SHALL i
be identified by markings in the margin of the affected pages clearly indicating the area of j
the page that was changed. The date (i.e., month and year) of the change SHALL be l
clearly indicated on the " Record of Revision" page.
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Pace 10 of 197 DEFINITIONS e ABNORMAL RELEASE i
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 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, e 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, e CHANNEL CHECK 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.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST consists of injecting a simulated signalinto the channel as close to the primary sensor as practicable to verify that it is OPERABLE, including alarm and/or trip initiating action.
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REV: 13 ik ^f Sedtiott? g%f y 90 gge fh Paae 11 of 197 CHANNEL RESPONSE TEST A CHANNEL RESPONSE TEST consists of injecting a simulated signalinto the channel a 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 ( Ci/ 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 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.
l
. 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, ion exchange or chemical reaction for the purpose of reducing the total radioactivity prior to release to the environment.
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, sc 9e e Pace 12 of 197 LONG TERM RELEASE e
LONG TERM RELEASES are usually airborne CONTINUOUS RELEASES. The term "Long Term" comes from the reference to utilizing the long term dispersion factor (X/0) from Table 5.1.
. MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC means any individual except when that individualis receiving an occupational dose.
. OPERABLE - OPERABILITY As defined in the Technical Specifications, e PURGE - PURGING PURGE - PURGING SHALL be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
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.
SHORT TERM RELEASE SHORT TERM RELEASES usually refers to airborne BATCH RELEASES. The term "Short Term" comes from the reference to utilizing the short term dispersion factor (X/0) l from Table 5.1.
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e SITE BOUNDARY The SITE BOUNDARY SHALL be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. 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 1
An UNRESTRICTED AREA SHALL be an>
2, access to which is neither limited nor controlled by the licensee.
l e UR ANIUM 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 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."
e VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM SHALL be any system designed and installed to reduce gaseous radiciodine 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 lodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered safety feature atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
. 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 gases via sampling equipment or instrumentation is not considered a controlled process.
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Pace 14 of 197 ww 1.0 RADIOLOGICAL EFFLUENT SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS APPLICABILITY AND SURVEILLANCE REQUIREMENTS 1.1 Specifications 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.
1.1.2 Noncompliance with a specification SHALL exist when the requirements of the Control and associated ACTION requirements are not met within the specified time interval. If the Controlis restored prior to expiration of the specified time interval, completion of the ACTION requirements is not required.
1.2 Surveillance Reauirements 1.2.1 Surveillance Requirement SHALL be met during the conditions specified for 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 interval, defined by Specification 1.2.2, SHALL constitute noncompliance with the OPERABILITY requirements for a Control for operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.
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Page is of 197 2.0 LIQUID EFFLUENTS CONCENTRATION SPECIFICATIONS 2.1 In accordance with T.S. 6.5.H the concentration of liquid radioactive material released 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 104 Cl/ml total activity.
4 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 SURVElLLANCE 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.
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u DOSE SPECIFICATIONS 2.3 in accordance with T.S. 6.5.H the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to:
a.
During any calendar quarter to s3 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 organ.
APPLICABILITY At all times.
ACTION
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits,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.
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.
SURVEILLANCE REQUlHEMENTS 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.
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REV: 13
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s bM5MNN aw Paae 17 of 197 w
ws LIQUID RADWASTE TREATMENT SYSTEMS SPECIFICATIONS 2.5 in accordance with T.S. 6.5.H the LIQUID RADWASTE TREATMENT SYSTEM SHALL be used to reduce the radioactive materials in liquid wastes prior to their 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 monthly period.
1 APPLICABILITY a
At all times.
ACTION
- a. With radioactive liquid waste being discharged without treatment and in excess 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 information:
1.
Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent recurrence.
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.
4 2.6.2 The Installed LIQUID RADWASTE TREATMENT SYSTEM SHALL be considered OPERABLE by meeting the Controls specified in 2.1 and 2.3.
s
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
%gg%
TITLE:
NUMBER:
3 l
k Nl$ p 6 ;~4[
OFFSITE DOSE CALCULATION H4 s7 MANUAL (ODCM)
REV: 13 Lse5os A%
%@ # #;ish w s % + si2dt Pace 18 of 197 RADIOACTIVE LLQUID EFFLUENT MONITORING INSTRUMENTATION d
SPECIFICATIONS 2.7 in accordance with T.S. 6.5.H the radioactive liquid effluent monitoring 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 instrumentation channel alarm / trip setpoint 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 CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 2.3.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
",, 5; OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
REV: 13 Pace 19 of 197 LIQUID STORAGE TANKS SPECIFICATIONS 2.9 In accordance with T.S. 6.5.J the quantity of radioactive material contained in each of the following tanks SHALL be limited to 10 curies; excluding tritium and dissolved or entrained gases:
Condensate Storage Tanks Outside Temporary Storage Tanks APPLICABILITY 4
At all times.
ACTION a.
With the quantity of radioactive material contained in any of the above listed tanks exceeding the limit in 2.9 above,immediately suspend all additions of radioactive materials to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the contents to within the limit.
SURVEILLANCE REQUIREMENTS 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 materials are being added to the tank.
i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES gg'ggjig TITLE:
NUMBER:
Y'/
jhb; OFFSITE DOSE CALCULATION H4 peran F
MANUAL (ODCM)
REV: 13
% /Nionh@,
Jh A m 2 ng Jg,
Pace 20 of 197 3.0 GASEOUS EFFLUENTS D_QSE RATE SPECIFICATIONS 3.1 In accordance with T.S.6.5.H the dose rate due to radioactive materials released in 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 At all times.
ACTION
- a. With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above I;mits(s).
b.
Report all deviations in the Annual Radioactive Effluent Report.
3.2 SURVElLLANCE REQUIREMENTS 3.2.1 The dose rate due to noble gases in effluents SHALL be determined to be within 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 within the above limits in accordance with the methodology r.d parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.1.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 6'
< /,
TITLE,
NUMBER:
~ Dr;M@2pmT
- @MS gg" OFFSITE DOSE CALCULATION H4 j@F MANUAL (ODCM)
REV: 13
- Ve
- is4c0W1E pp
+yngg*M Pace 21 of 197 DOSE - NOBLE G ASES SPECIFICATIONS 3.3 in accordance with T.S.6.5.H the air dose due to noble gases released in gaseous 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.
f PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
, / gggjg ~ M
~ ;g TITLE:
NUMBER:
g@F ~
OFFSITE DOSE CALCULATION H4
?#j %
- k,{ h y
~#
MANUAL (ODCM)
REV: 13 h
?llbkk.y w ur e Pace 22 of 197 4
DOSE -IODINE -131. LODINE-133. TRITIUM. AND PARTICULATES SPECIFICATIONS 3.5 in accordance with T.S. 6.5.H the dose to any organ of a MEMBER OF THE PUBLIC 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.
APPLICABILITY At all times.
ACTION
- a. With the calculated dose from the release of Iodine-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.
SURVElLLANCE REQUIREMENTS 3.6 Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, Tritium, and Particulates with half-lives greater than 8 days SHALL be determined monthly in accordance with the methodology and pa ameters in Section 5.0 of the ODCM.
J e
. m
4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
h[gIggjg,yggjpgef$g OFFSITE DOSE CALCULATION H4 27 sN4~
h my MANUAL (ODCM)
REV: 13 M"Cigg~:st'fMM[Q$^
9Mdhi; 1 Peae 23 of 197 GASEOUS RADWASTE TREATMENT SYSTEMS 4
3.7 SPECIFICATIONS 3.7.1 in accordance with T.S. 6.5.H the Waste Gas Treatment System and the VENTILATION EXHAUST TREATMENT SYSTEM 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.J the quantity of radioactivity contained in each gas 4
storage tank SHALL be limited to s78,800 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 t.e 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.
1 AP_EllCABILITY At all times.
ACTION
- 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 e
Commission within 30 days a Special Report that includes the following information.
f 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 3.7.2, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES iOdhM$kh9hde[N!
TITLE:
NUMBER:
M/,. %*dd[!
OFFSITE DOSE CALCULATION H4 y>.
MANUAL (ODCM)
REV: 13
@4 !"s46tisi1xe gt -
- '@W W
Pace 24 of 197 3.8 SURVEILLANCE REQUIREMENTS l
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.Ticnthly. If the inventory of any tank exceeds 10,000 curies, daily sampling when niaking additions SHALL be performed.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
'qyg y/d g TITLE:
NUMBER:
r Me F '
sf OFFSITE DOSE CALCULATION H4 gF
~%
MANUAL (ODCM)
REV: 13
'dNidn3 p @.
g+
4%
Pace 25 of 197 I EXPLOSIVE G AS MONITORING INSTRUMENTATION 3.9 SPECIFICATIONS 3.9.1 in accordance with T.S. 6.5.J the explosive gas monitoring instrumentation channels shown in Table 3.2 SHALL be OPERABLE with their Alarm / Trip Setpoints set to ensure the limits of 3.9.2 are not exceeded.
3.9.2 in accordance with T.S. 6.5.J the concentration of oxygen at the outlet of each operating recombiner SHALL be maintained to s2% by volume.
APPLICABILIII As shown in Table 3.2.
ACTIQH
- a. With an explosive gas monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, declare the channel inoperable 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 unsuccessfu:,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, i
- 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 i
volume within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
F[iy C'M Lg8)
M g**LJjiWEM OFFSITE DOSE CALCULATION H4 I E el M MANUAL (ODCM)
REV: 13 sh
- sectionn" M
~gd a
dwd
%M ^ ! "
.H Pace 26 of 197 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SPECIFICATIONS I
3.11 in accordance with T.S. 6.5.H the radioactive gaseous effluent monitoring 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 the methodology in Section 5.0 of the ODCM.
4 J
APPLICABILITY l
l As shown in Table 3.2.
ACTION
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioatiive 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 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 3.12 Each radioactive gaseous effluent monitoring instrumentation channel SHALL be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 3.3.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
- .h$. 'L,+ @. ;m;y';W i
g TITLE:
NUMBER:
sN@'
OFFSITE DOSE CALCULATION H4 a; #
'?
MANUAL (ODCM)
REV: 13
" issionityz g
p g7 g 97 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.
ACIlON
- 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 utilizing Instrumentation with a minimum lodine-131 detection limit of 1.0 pCl/ml.
3.14 SURVElLLANCE REQUIREMENTS 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g dgMjb '
jgy a @fgq" TITLE:
NUMBER:
OFFSITE DOSE CALCULATION H4 Wmt MANUAL (ODCM)
REV: 13
@ ~;%sioiik g+
s g, g,
~
Pace 28 0f 197 4.0 LIQUID EFFLUENT CALCULATIONS 4.1 Monitor Alarm Setooint Determination This procedure determines the monitor alarm setpoint + hat indicates if the concentration of radionuclides in the liquid effluent released to UNREJ fRICTED 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.
Monthly calculation of setpoints using the methodology of Sections 4.1.1 and 4.1.3.
- b. Calculation of alarm setpoint based 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 Ci/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 will be 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHEhN STATES POWER COMPANY H PROCEDURES 3d][p(l MN) 7'%
TITLE:
NUMBER:
e,7 OFFSITE DOSE CALCULATION H4 7@;g$k'i t N %~
MANUAL (ODCM)
REV: 13 l<Weisection)@Q ma a
Paae 29 of 197 4.1.1 Liauid Effluent Monitor Setooints The following method applies when determining the isolation setpoints for the Waste Effluent Liquid Monitor (R-18), Steam Generator Blowdown Liquid Monitor-Unit 1 (1 R-19), and Steam Generator Blowdown Liquid Monitor -
Unit 2 (2R-19) during all operational conditions when the radwaste discharge flow rate is maintained constant at the maximum design flow rate.
A.
Determine the " mix"(radionuclides and composition) of the liquid effluent.
1.
Determine the liquid source terms that are representative of the " mix" of the liquid effluent. Liquid source terms are the total curies of each isotope released during the previous month. Table 4.1 source terms may be used if there have been no liquid releases.
2.
Determine the activity concentrations (AC ) of all non-gamma emitters i
including H-3, Sr-89, Sr-90, Fe-55, and alpha activity.
3.
Determine NGF (the total fraction of the MPC in the liquid effluent) for all non-gamma emitting nuclides.
AC' NGF = E (4.1-1) 7 MPCi where:
AC =
Activity concentration of nuclide 'i'in the liquid i
effluent ( Ci/ml).
MPC The liquid effluent radioactivity concentration limit for i
radionuclide 'i'( Ci/mi) from Table 4.1 or Reference 3.
i l
l l
l
)
PRAIP'N ;2MND NUCLEAR GENERATING PLANT NORTHERM STATES POWER COMPANY H PROCEDURES
~
if gygg,;
TITLE:
NUMBER:
pf!
Qj$f OFFSITE DOSE CALCULATION H4 sMr
- .A MANUAL (ODCM)
REv: 13 12* TsiiiiMIMM 06hMML%32W Pine 30 of 197 4.
Determine SI (the fraction of the gamma emitting radioacti/ity in the liquid effli:ent comprised by radionuclidos 'i') for each individual radionuclide in the liquid effluent.
S=
At i
l Ai (4.1-2) i where:
Ai
= the radioactivity of gamma emitting radionuclide 'i'in the liquid effluent.
5.
Determine WGF (the sum of fractional activities weighted by the MPC) for the gamma emitting nuclides in the liquid effluent.
S' WGF = E (4.1-3)
MPCj n
where:
MPCi the liquid effluent radioactivity concentration limit
=
for radionuclide 'i' ( Cl/ml) from Table 4.1 or Reference 3.
Determine C (the maximum acceptable total radioactivity concentration of B.
t 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)
=
l l
67,300 gpm from cooling tower blowdown
=
l l
f The maximum attainable discharge flow rate
=
prior to dilution (gpm) 60 gpm from the ADT tank pump
=
100 gpm from the CVCS tank pump
=
60 gpm from the SGBD tank pump
=
-=
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
[hg N6' yg TITLE:
NUMBER:
MS9
'f, g OFFSITE DOSE CALCULATION H4 ig:
MANUAL (ODCM)
REV: 13 q.gisfygg 4 ~
- v<'M-Paae 31 of 197 C.
Determine C.R. (the calculated monitor count rate above background attributed to the 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 ).
t D.
Determine HSP (the monitor high alarm setpoint above background (ncpm)).
HSP = TmC.R.
(4.1-5)
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 i
points.
= 0.90 for the Waste Effluent Liquid Monitor (R-18) 1
= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 1 (1 R-19)
= 0.05 for the Steam Generator Blowdown Liquid Monitor - Unit 2 (2R-19)
Tm values may be revised from the values given above.
The summation of allthe Tm values for active release points SHALL NOT be greater than unity.
E. The monitor high alarm setpoint above background (ncpm), SHALL be set at or below the HSP value.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 4s' TITLE:
NUMBER:
,, Ngd m ; ilh i
1 OFFSITE DOSE CALCULATION H4 h% $em> w[!!E g
%Cgy t MANUAL (ODCM)
REV: 13 g$, ~gg p
$2Wde * ~ 1 4
Page 32 of 197 4.1.2 Setooint Based on Analvsis of Liauid Prior to Discharge (Octional)
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 (1R-19), and Steam Generator Blowdown Liquid Monitor-Unit 2 (2R-19), during all operational conditions.
l A.
Determine f (the maximum acceptable discharge flow rate prior to dilution (gpm)).
f
= 0.8 F Tm iMCi Dilution water flow rate (gpm)
F
=
67,300 gpm from cooling tower blowdown
=
l Concentration of radionuclide "i"in the liquid effluent prior to l
Ci =
dilution ( Ci/ml) from analysis of the liquid effluent to be released.
l l
MPC = The liquid effluent radioactivity concentration limit for radionuclide "i"( Ci/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.
l l
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
g' y, / 'pk@g -
s y
W OFFSITE DOSE CALCULATION H4 61 W
c MANUAL (ODCM)
REV: 13 3 wsesionR;s j~mg Paae 33 of 197 B.
Determine the monitor setpoint based on the radionuclide mix of the liquid effluent.
1.
Determine C.R. (the calculated monitor count rate above background attributed to the 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 point that corresponds to the " adjusted" total radioactivity concentration (C )-
t Total radioactivity concentration of the radionuclides (minus C
=
tritium and other radionuclides that are only beta emitters) in the liquid discharge prior to dilution (pCl/ml) as determined using Equation 4.1-4.
I 2.
Determine HSP (the monitor high alarm setpoint above background (ncpm)).
HSP =.QA (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 Discharge Canal Monitor I
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.
l 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 j
total curies of each isotope released during the previous month.
4 Table 4.1 source terms may be used if there have been no liquid releases.
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES hi{jdf, ' ~ hg $g TITLE:
NUMBER:
l kr/f LE h ;
OFFSITE DOSE CALCULATION H4 MhOIl $[15 '
MANUAL (ODCM)
REv: 13 Thi g[SebtNNk jA Pace 34 of 197 2.
Determine the activity concentrations (AC ) of all non-gamma emitters i
including H-3, Sr-89, Sr-90, Fe-55, and alpha activity.
3.
Determine NGF (the total fraction of the MPC in the liquid released to the discha.;. canal) for all non-gamma emitting nuclides. The volume used to calculate the non-gamma emitting activity concentrations is the volume released via cooling tower blowdown during a one month period at the minimum flow rate of S7,300 gpm.
NGF =
AC:
iMPCi where:
ACi
=
Activity concentration of nuclide 'i' released to the discharge canal
( Cl/ml)
MPC =
The liquid effluent radioactivity concentration limit for i
radionuclide 'i'( Ci/mi) from Table 4.3 or Reference 3.
4.
Determine Si (the fraction of the gamma emitting radioactivity in the liquid released to the discharge canal comprised by radionuclide 'i') for each individual radionuclide released to the discharge canal.
Si
=
Ai Ej Ai where:
A; The radioactivity of gamma emitting radionuclide 'i' released
=
to the discharge canal.
5.
Determine WGF (the sum of fractional activities weighted by the MPC) for the gamma emitting nuclides released to the discharge canal.
WGF = [.
MPCi
= The liquid effluent radioactivity concentration limit for radionuclide 'i' (pCl/ml) from Table 4.3 or Reference 3.
I i
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
5 ^hy p.
s, ~ M r
?
us
- JW W; hda OFFSITE DOSE CALCULATION H4
~ # ^ EtE EN$ hbh@h MANUAL (ODCM)
REV: 13 Pace 35 of 197 Determine C (the maximum acceptable total radioactivity concentration of B.
t gamma emitting nuclides released to the discharge canal ( Cl/ml)).
C=
1--NG F i
WGF C.
Determine C.R. (the calculated monitor count rate above background attributed tot he 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 that corresponds to the " adjusted" total radioactivity concentration (C ).
t D.
The monitor high alarm satpoint 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 l
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 energies.
The cumulative errors associated with the monitor calibration methodology are 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.
)
i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
ikh;$YU[fif*
,W j
OFFSITE DOSE CALCULATION H4 "P e>J*
MANUAL (ODCM)
REV: 13 A Rqg & ?
p mRy g. wy4;mn Paae 36 of 197 4.2 Comollance 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 ll of 10CFR20. For CONTINUOUS RELEASES, the alarm trip setpoints discussed in Section 4.1 will assure that these concentrations are not exceeded. For BATCH RELEASES, concentrations of radioactivity 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 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.
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 radionuclides, the methodologies given in Section 4.2.2 will be applied to the turbine sump weekly releases and the limit in Equation 4.2-2 will be lowered to account for this source term.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES M&-
/x gc TITLE:
NUMBER:
s 3 f 'N OFFSITE DOSE CALCULATION H4 EE
- 1 MANUAL (ODCM)
REV: 13 4
9 IShidn'fwJE' g
,j -
gn Pace 37 of 197 4.2.2 Batch Releases To further show compliance with 10CFR20, the radioactivity content of each BATCH RELEASE will be determined prior to release. The concentration of the various radionuclides in the BATCH RELEASE prior to dilution, is divided by the minimum dilution flow to obtain the concentration at the SITE BOUNDARY. This calculation is shown in the following equation:
Conci=
C; R (4.2-1)
MDF where Conci = concentration of radionuclide i at the site boundary, Ci/ml; Ci
= concentration of radionuclide iin the potential batch release, Ci/ml; 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 in Appendix B, Table 11 of 10CFR20 which are given in Table 4.1. Before a release may occur, Equation 4.2-2 must be met for allisotopes.
{.Conci I
<;; 0.9 (4.2-2)
MPCi f
MPCi=
Maximum permissible concentration of radionuclide i from Table 4.3 or Appendix B, Table ll of 10CFR20. pCl/mi 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.
1
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES gy3gg)@g gi TITLE:
NUMBER:
'A$E_E2 j*
OFFSITE DOSE CALCULATION H4 y Q1 MANUAL (ODCM)
REY: 13
( NSNINk,hk Paae 38 of 197
^
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 Liquid Effluent Dose - Comoliance 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 month.
Since Fe-55, Sr-89, Sr-90, and alpha concentrations are determined from composite samples, the monthly liquid effluent dose calculations and comparisons to quarterly and annual limits should be completed using the most recent available composite sample results. The quarterly and annual dose calculations SHALL be completed usir g the actual composite sample results.
The limits of 10CFR50 are on a per reactor unit basis. The liquid radwaste system at 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 releases from PINGP. Therefore, for compliance with 10CFR50 the releases from both units will be summed at d the limits of Appendix I will be doubled.
l l
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j
%f
- W T{
h ga ; ', f TITLE:
NUMBER:
^
OFFSITE DOSE CALCULATION H4 II MANUAL (ODCM)
REV: 13
- ' ' Q&ny
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Page 39 of 197 1
4.3.1 Determination of Liould Effluent Dilution To determine doses from liquid effluents the near field averaps dilution factor for the period of release must be calculated. This dilution factor must be calculated for each BATCH RELEASE and each CONTINUOUS RELEASE mode. The dilution factor is determined by:
Fk
=
Ry (4.3-1)
X ADFk where:
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 ADF is limited to 1000 cfs (4.5 x 105 k
gpm). Therefore, since blowdown flow in closed c cle is 150 cfs, the denominator of Equation 4.3-1 is always 4.5 x 10 yin closed cycle. In oncei through or helper mode, the value if X is reduced to 1.0.
4.3.2 Dose Calculations 1
The dose contribution from the release of liquid effluents will be calculated monthly. The dose contribution will be calculated using the following:
J where:
Dr II Ax tk Cik Fk (4.3-2)
=
i ki where:
Dr the dose commitment to the total body or any
=
organ t, from the liquid effluents for the period of release, mrem; Cg the average concentration of radionuclide,i, i
=
in undiluted liquid effluent for liquid release k, Ci/ml;
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES W. SWWW ' ap TITLE:
NUMBER:
)
n.
- zgn.
av p
OFFSITE DOSE CALCULATION H4 up$Nggas fy MANUAL (ODCM)
REV: 13 EE
+$ 'g% < m +7..%@%g%
s c
Page 40 of 197 the site related ingestion dose commitment factor Ax i
=
to the total body or any organ t for each identified principal gamma and beta emitter, mrem /hr per Cl/ml; the near field average dilution factor for C x during Fk
=
i liquid effluent release k, the duration of release k, hours.
tk
=
The dose factor Axwas calculated for an adult for each isotope using the i
following equation:
5 1.14 x 10 (21BF DFx]
(4.3-3)
Ax i
i i
=
where:
3 1.14 x 105
= 106 x 10 ml x 1 yr :
pfi Cl I
8760 hr adult fish consumption, Kg/yr; 21
=
bio accumulation factor for radionuclide i in BFi
=
fish from Table A-1 of Regulatory Guide 1.109 Rev.1 (5) pCi/Kg per pCi/l; dose conversion factor for radionuclide i for adults DFg
=
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 forirrigation downstream of the plant.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES N M(,'W TITLE:
NUMBER:
s 14*
- M OFFSITE DOSE CALCULATION H4
~i
. -1@
MANUAL (ODCM)
REV: 13
- W]SS_Ionhw
' W J :
Paae 41 of 197 4.3.3 Cumulation of Doses Doses calculated monthly will be summed for comparison with quarterly and annual limits. 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 for the combined 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 Equation 4.3-6 or 4.3-7, additional components of the liquid radwaste treatment system will be used to process waste. The projected doses will be calculated using Equation 4.3-2. The dilution factor, F, will be calculated by replacing the term k
ADF in Equation 4.3-1 with the term MDF from Equation 4.2-1. The total k
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 coming month.
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
jgfMft{
$ps hg:#
OFFSITE DOSE CALCULATION H4 Ugyp pA MANUAL (ODCM)
REV: 13 ThadectionhM5 WN JFNi
^N Pace 42 of 197 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.
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, /..:endix I," Rev.1,1977.
i 4
9
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
<WW
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TITLE:
NUMBER:
3
[
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OFFSITE DOSE CALCULATION H4 E.....,
G MANUAL (ODCM)
REV: 13
. J ectl.on ? jy S
m Paae 43 of 197 5.0 GASEOUS EFFLUENT CALCULATIONS 5.1 Monitor Alarm Selpoint Determination This procedure determines the monitor alarm setpoint that indicates if the dose rate in 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. Monihty calculation of setpoint using the methodology of Section 5.1.1 for CONTINUOUS RELEASES using previous month releases as source term.
i t'
Prior to each containment PURGE, recalculation of the setpoint using the methodology of Section 5.1.1 based on the cample taken prior to PURGlNG.
1 c.
In lieu of (5.1.a) and (5.1.b) above, alarm setpoints may be establsihed 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 will be 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 gaseous effluent.
1.
Determine the gaseous source terms that are representative of the gaseous effluent. Gaseous source terms are the total curias of each noble gas released during the previous month or a representative 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 detection (LLD).
/
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
gg) ggp2 yn,g" g&u3g OFFSITE DOSE CALCULATION H4 y"% N E E E*d MANUAL (ODCM)
REV: 13 t
y @+ $
r J
4d Pace 44 of 197 Determine S (the fraction of the total radioactivity in the gaseous effluent 2.
i comprised by noble gas radionuclide "i") for each individual noble gas radionuclide in the gaseous effluent.
Si
=
A!
IAi (5.1-1) i The radioactivity of noble gas radionuclide "i"in the Ai
=
gaseous effluent from either the previous months releases or from Table 5.2 If there were no releases during the previous month.
Determine Q (the maximum acceptable total release rate of all noble gas B.
t radionuclides in the gaseous effluent ( Cl/sec)) based upon the whole body exposure limit.
500 (5.1-2)
Og
=
(x /Q) I K Si i
i (x /Q) =
The highest calculated annual average relative concentration of effluents released via the plant vents for any area at or 3
beyond the site boundary for all sectors (sec/m ) from the "x /Q" column in Table 5.1.
Ki
=
The total whole body dose factor due to gamma emissions 3
from noble gas radionuclide "i"(mrem / year /pCi/m ) from i
Table 5.4.
C.
Determine Q based upon the skin exposure limit.
t Q
3000 (5.1-3)
=
t (x /Q) I (L + 1.1 M) Si i
i i
L + 1.1 Mi
=
i The total skin dose factor due to gamma and beta emissions from noble gas radionuclide "i" 3
(mrem / year / Ci/m ) from Table 5.4.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
)b&fLffQ*
TITLE:
NUMBER:
y
$p OFFSITE DOSE CALCULATION H4 enspL ^ioh.jf;j MANUAL (ODCM)
REV: 13 gg$. 8ect _M.,.,E '
3 Determine C (the maximum acceptable total radioactivity concentration of all D.
t noble gas radionuclides in the gaseous effluent (/ Ci/cc)).
2.12 E-3 Ot (5.1-4)
C
=
F j
s@!) <
Use the lower of the Q: values obtained in Section 5.1.1.B "gg; and 5.1.1.C.
3
.m The maximum effluent flow rate at the point of F
=
release (cfm) from the " Effluent Flow Rate" column in Table 5.1.
Unit conversion constant to convert Ci/sec/cfm 2.12 E-3
=
to pCl/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 (nepm)).
Tm C.R.
(5.1-5)
HSP
=
Fraction of the total radioactivity from the site that may be Tm
=
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 j
monitors should be set at or below the HSP values.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHEMN STATES POWER COMPANY H PROCEDURES
( ~ "
4 TITLE:
NUMBER:
($g i
OFFSITE DOSE CALCULATION H4 I
p4
/
MANUAL (ODCM)
REV: 13 Mkhh#vrkkh Pace 46 of 197 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.
These monitors are provided to give rapid indication of steam generator tube leakage. They are not effluent monitors since the air ejectors are vented to the auxiliary building vents during normal plant operation and releases are monitored by the auxiliary building vent monitoring system.
5.1.3 Monitor Calibration 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 that one gas 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 cf calibration is two separate calibration curves for each monitor. One curve to be used when the isotopic mix being monitored 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.
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.
l The cumulative errors associated with the monitor calibration methodology are not accounted for in the determination of the individual monitor setpoints. There is sufficient conservatism built into the selection of the actual monitor setpoint; i
plus the fact that the monitor fractions used in the setpoint determination l
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.
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES W6D #
9 TITLE:
NUMBER:
[q(v[$] } > ^
h OFFSITE DOSE CALCULATION H4 f!
MANUAL (ODCM)
REV: 13 hsection@@%
2" Paae 47 of 197 5.2 Gaseous Effluent Dose Rate -Compliance with 10CFR20 Dose rates resulting from the release of noble gases, and radiciodines 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 cas9 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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 values and critical receptors reported to the USNRC SHALL be calculated using the actual composite results.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g
g TITLE:
NUMBER:
'W i
OFFSITE DOSE CALCULATION H4 3
f MANUAL (ODCM)
REV: 13 y
Pace 48 of 197 n
2%rf '
="
5.2.1 Noble Gases 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 i
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 j
for doses from noble gas releases to show compliance with 10CFR50, Appendix I as discussed in Section 5.3.1.
5.2.2 Radiolodine. Radioactive Particulates. and Other Radionuclides For compliance with 10CFR20, the dose rate at the SITE BOUNDARY resulting i
from the release of radiolodines and particulates with half ' aves greater than 8 j
days is limited to 1500 mrem /yr to any organ. Calculations showing compliance with this dose rate limit will be performed for BATCH RELEASES prior to the release and weekly for all releases. To show compliance, Equations 5.2-1 will be evaluated for 1-131,1-133, tritium, and radioactive particulates with half-lives i
greater than eight days.
I P (x/Q v) O y
< 1500 mrem /yr (5.2-1) i where:
4 child critical organ dose parameter for radionuclide i for the Pi
=
3 i
inhalation pathway, mrem /yr per Cl/m (Table 5.3);
i (X/Ov) =
annual average relative concentration for LONG-TERM release at 3
j the criticallocation, sec/m (Appendix A, Table A-3);
i Ov the total release rate of radionuclide i from all vents form both units i
=
i for the batch or week of interest, Ci/sec; l
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, i
The source terms (O v) will be determined from the results of analysis of vent i
particulate filters and charcoal canisters and vent flow rate. These source terms i
include all gaseous releases from PINGP.
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT i
NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
Sj@@ti * -;fM.
Wy 4 d@?
OFFSITE DOSE CALCULATION H4
' fg gi,bO0nh Mc 9W~
MANUAL (ODCM)
REV: 13 N 6iSe
, in '
? " Wi Pace 49 of 197 Significant short term BATCH RELEASES of long-lived radioactive particulates and tritium will result from containment PURGES. Calculations will be made for s
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 i
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.
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:
1500 -(Dy-D )
(5.2-2)
BL
=
p where:
limiting dose rate for the batch, mrem /yr; BL
=
previous week's dose rate from all continuous and Dv
=
batch releases mrem /yr; previous week's dose rate from all PURGE D
=
p releases mrem /yr.
5.2.3 Critical Receotor Identification i
i Comphance with 10CFR20 radiation dose limits for individual MEMBERS OF l
l THE PUBLIC will be demonstrated by identifying critical receptor locations based on 10CFR50 App I ALARA cesign objectives. Since the doses associated with 4
10CFR50 are more restrictive than the 10CFR20 limits, this method satisfies the i
10CFR20 requirements.
1 a
i i
f
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g" s f g, gyg TITLE:
NUMBER:
p
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W OFFSITE DOSE CALCULATION H4
@ Q.[ W.k MANUAL (ODCM)
REV: 13 pgySection (,3 &
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Pace 50 of 197 5.3 Gaseous Effluents - Comollance with 10CFR50 Doses resulting from the release of noble gases, radiciodines and particulates must be calculated to show compliance with Appendix I of 10CFR50. The calculations will be performed monthly for all gaseous effluents.
The limits of 10CFR50 are on a per reactor unit basis. The GASEOUS RADWASTE TREATMENT SYSTEM and the auxiliary building at 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 contribute a very small portion of the total gaseous releases form PINGP. Therefore, for compliance with 10CFR50 the releases from both units will 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 scheduled short term maintenance / work activities of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 l
ventilation has no filtration.
i l
- b. The lower limit of detection limits specified in Table 3.1 can not be obtaineri on all l
the specified nuclides with normal sample flow and a sample duration of less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- 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.
l Therefore, it is conservative to assume that the auxiliary building normal ventilation l
system would continue to run during the testing / maintenance period. The surveillance l
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 sampled SHALL be sampled and analyzed as described in Table 3.1.
1 l
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
- p 4 4>
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TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
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Paae 51 of 197 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 values and critical receptors reported to the USNRC SHALL be calculated using the actual composite results.
5.3.1 NobleRas A.
Dose Eauations 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 as described in Section 5.3.4.
1 For gamma radiation:
3.17 x 10-8 3 y, I
(x/Q)v Qv + (x/q)vqiv i
< 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 Ov + (x/q)vqiv i
< 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, 3
mrad /yr per Cl/m ;(Table 5.4)
Ni
=
The air dose factor due to beta emissions for each identified noble gas radionuclide i, 3
mrad /yr per Cl/m ;(Table 5.4)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g
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OFFSITE DOSE CALCULATION H4 f g 4 5 # g $g s g
N MANUAL (ODCM)
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a Pace 52 of 197 the annual average relative concentration for areas (x/Q)v
=
at or beyond the restricted area boundary for LONG TERM 3
vent releases (greater than 500 hr/ year), sec/m (Appendix A, Table A--4);
The relative concentration for areas at or beyond the (x/q)y
=
restricted area boundary for SHORT-TERM vent releases 3
(equal to or less than 500 hrs / year), sec/m (Appendix A, Table A-7);
The total release of noble gas radionuclide iin gaseous qiv
=
effluents for SHORT-TERM vent releases from both units (equal to or less than 500 hrs / year), Ci; the total release of noble gas radionuclide i in gaseous Qv i
=
effluents for LONG-TERM vent releases from both units (greater than 500 hrs /yr), Cl; 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.
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 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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Pace 53 of 197 5.3.2 Radiolodine. Particulates. and Other Radionuclides A.
Dose Equations The worst case dose to an Individual from l-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 jak (5.3-3) i ji WyQ v + w qiv i
v
< 15 mrem (per quarter)
< 30 mrem (per calendar year) where:
1 release of radionuclide i for LONG-TERM vent releases from Ov
=
i both units (greater than 500 hrs /yr), pCi; release of radionuclide i for SHORT-TERM purge releases qiv
=
from both units (equal to or less than 500 hrs /yr); pCi; the dispersion parameter for estimating the dose to an Wy
=
individual at the controlling location for LONG-TERM vent releases (greater than 500 hrs /yr);
the dispersion parameter for estimating the dose to an wy
=
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;
=
the dose factor for each identified radionuclide i, Rjak i
=
2 pathway j, age group a, and organ k, m mrem /yr per pCl/sec or mrem /yr per Ci/m.
3
\\
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
W ; 2h'j f@h@g%QQd$P y"
OFFSITE DOSE CALCULATION H4 s i j $%c$
MANUAL (ODCM)
REV: 13 R#
i NSi F ' N$h Pace 54 of 197 The above equation will be applied to each combination of age group and organ. Values of Pyak 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 samo manner as in Section 5.2. The W vabes are in terms of x/Q(sec/m ) for thu inhalation pathways and for tritium (Tables A-4 and 3
A-7) and in terms of D/Q(1/m ) for all other pathways (Tables A-5 and A-8).
2 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 exceeded, a special report showing compliance with 40CFR190 will be submitted.
5.3.3 Prolection 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.
If the projected release of 1-131,1-133, 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 required if not currently in use.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l MifhfM' y?j, TITLE:
NUMBER:
WMQN OFFSITE DOSE CALCULATION H4 r EM < E E A igl MANUAL (ODCM)
REV: 13
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O Pace 55 of 197 5.3.4 Critical Receotor identification For compliance with 10CFR50 App I ALARA design objectives, two critical 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.
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 vent x/O values given in Appendix A, Table A-3. This location will remain the 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 lesfy 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 i
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 Reference.g "NSP-Prairie Island Nuclear Generating Piant, Appendix I Analysis-Supplement No.1
- Docket No. 50-282 and 50-306", Table 2.1-4.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES d @ H % d kpy[ '3 TITLE:
NUMBER:
?8k Skt OFFSITE DOSE CALCULATION H4 p., R 2,
MANUAL (ODCM)
REv: 13 gsscuann Page 56 of 197 few 6c0 TOTAL DOSE FROM RADIOACTIVE RELEASES AND URANIUM FUEL SOURCES SPECIFICATIONS 6.1 In accordance with T.S.6.5.H the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from URANIUM FUEL 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 ir>cluding direct radiation contributions from the reactor units (including outside storage tanks) to determine whether the above limits 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 ali 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 H PROCEDURES TITLE:
NijMBER:
- 943;Wm]fff',.; l' OFFSITE DOSE CALCULATION H4
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SURVEILLANCE REQUIREMENTS 6.2 Cumulative dose contributions from liquid and gaseous effluents SHALL be determined in accordance with Specifications 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.
l l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES y,7?pgfg'g TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4 Gg Enm jff MANUAL (ODCM)
REV: 13 gphisectiom e :
Paae 58 of 197 G-7.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM SPECIFICATIONS 7.1 In accordance with T.S.6.5.I the Radiological Environmental Monitoring Program (REMP) SHALL be conducted as specified in Table 7.1.
APPLICABILITY At all times.
ACTION l
- a. Whenever the Radiological Environmental Monitoring Program is not being conducted as c'c scribed 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, b.
Deviations are permitted from the required sampling schedule if sample are unobtainable due to hazardous conditions, seasonable unavailability, or to malfunctions 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.
l
- c. With the level of radioactivity as the result of plant effluents in an environinental 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 exceeoing the limit (s).
2.
Defines the corrective actions that have been taken to reduce radioactive effluents 1
so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 2.3,3.3, oc 3.5.
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 g@6@@@
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OFFSITE DOSE CALCULATION H4 j
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Pace 59 of 197 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) concentration (2) 1
+
+.. 2 1.0 reporting level (1) reporting level (2) i When nuclides other than those in Table 7.2 are detected and are the result of plant 2
effluents, this report SHALL be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of 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 such an event, the 2
condition SHALL be reported and described in the Annual Radiological Environmental Monitoring Report.
5
- 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 i
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.
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 K!
TITI ':
NUMBER:
F%[$1M3 hpl h
OFFSITE DOSE CALCULATION H4 sc IOR MANUAL (ODCM)
REV: 13
- 9 Wssuidnu,
- W, a " '*u+5" Paae 60 of 197 LAND USE CENSUS SPECIFICATIONS 7.3 in accordance with T.S.6.5.I a Land Use Census SHALL be conducted and SHALL identify:
- a. The location of the nearest milk animal, the nearest residence, and the nearest 2
garden of greater than 500 ft producing fresh leafy vegetation in each of the 16 meteorological sectors within a distance of 5 miles, 2
Fields or gardens of greater than 500 ft producing corn that are irrigated with water b.
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 Evait Report, identify the new location (s)in the next Annual Radiological Environmental MorJtoring 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.
2 If fields or gardens larger than 500 ft producing corn are being irrigated with Mississippi c.
River water, appropriate samples SHALL be collected and analyzed per Table 7.1.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4
,jy
?ggf db MANUAL (ODCM)
REv: 13
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SURVEILLANCE 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.
INTERLABORATORY COMPARISON PROGRAM SPECIFICATIONS 7.5 In accordance with T.S.6.5.1 analysis SHALL be performed on radioactive materials, supplied by an NRC approved crosscheck program. This program involves the analyses of samples provided by a control laboratory as well as with other laboratories l
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.
APPLICABILITY At all times.
ACTION
- a. When required analyses are not performed, corrective action SHALL be reported in the Annual Radiological Environmental Monitoring Report.
SURVElLLANCE REQUIREMENTS 7.6 The summary results of analyses performed as part of the above required Interlaboratory Comparison Program SHALL be included in the Annual Radiological Environmental Monitoring Report.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES i M c ': A TITLE:
NUMBER:
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M &L 'Jgf T MANUAL (ODCM)
REV: 13 gg&ony 9 MnOM 6 YNN 3 Paae 62 of 197 8.0 REPORTING REQUIREMENTS 8.1 Annual Radioactive Effluent Report 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 i
SHALL include:
- a. The Annual Radioactive Effluent Report covering the operation of the plant during the previous calendar year SHALL be submitted by May 15 of each calendar year to the Administrator of the appropriate Regional NRC office or designee.
- 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 for inclusion with the report, the report SHALL be submitted noting and explaining the reasons for the missing results. The missing data SHALL be submitted as soon as possible in a supplementary report.
- 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 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., cernent, urea formaldehyde),
- e. The Annual Radioactive Effluent Report SHALL include ABNORMAL RELEASES from the site of rad loactive materials in gaseous and liquid effluents on a quarterly basis.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES yeBF 'M!My dsLe T R E:
NUMBER:
&J OFFSITE DOSE CALCULATION H4
'M MANUAL (ODCM)
REV: 13 0% OS$bl0b{k@'h a =lyyswu- ' gsd v Pace 63 of 197 g
- f. If the calculated dose from the release of radioactive materials in liquid or gaseous sfiluents exceeds twice the limits of 10 CFR 50, Appendix I, the Annual Radioactive l
Ef1Nent Report SHALL also include an assessment of radiation doses to the most likely exposed MEMBER OF THE GENERAL PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show l
compliance with 40CFR190, Environmental Radiation Protection Standards for Nuclear Power l
Operation.
j i
- g. The Annual Radioactive Effluent Report SHALL include a description (including I
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.
1
- 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 i
Tables 2.2 and 3.2.
)
{
l
- 1. The Annual Radioactive Effluent Report SHALL include a description of the i
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.
I k.
The Annuai Radioactive Effluent Report SHALL include an assessment of the radiation doses from radioactive effluents released from the ISFSI during the previous calendar year.
f I. Licensee initiated changes to the ODCM SHALL be submitted to the NRC in the j
form of a complete legible copy of the entire ODCM as a part of or concurrent with l
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 i
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.
i
I PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ggM apy@
TITLE:
NUMBER:
NkJ _. j@%
AF OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
REv: 13 m W secuon F ~
N W ' " DM Pace 64 of 197 8.2 Annual Radiological Environmental Monitoring Report 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:
- a. The Annual Radiological Environmental Monitoring Report covering the operation of the plant during the previous calendar year SHALL be submitted by May 15 of each year to the Administrator of the appropriate Regional NRC office or his designee.
- b. The Annual Radiological Environmental Monitoring Report SHALL include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report SHALL be submitted noting and explaining the reasons for the missing results. The missing data SHALL be submitted as soon as possible in a supplementary report.
- c. The Annual Radiological Environmental Monitoring Report SHALL include summaries, interpretations, and an analysis of trends of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveliiance reports and an assessment of the observed impacts of the plant operation on the environment. The report SHALL also include a summary of the results of the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report SHALL provide an analysis of the problem and a planned course of action to alleviate the problem.
- 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 for all deviations from the REMP sampling program as specified in Table 7.1 and plans for the prevention of a recurrence, if applicable.
f.
The Annual Radiological Environmental Monitoring Report SHALL contain a description of when and why milk or leafy vegetable samples specified in Table 7.1 cannot be obtained from the designated sample locations, and identify the new locations added to and deleted from the monitoring program.
P AAiRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
, / Ml>
TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
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If the level of radioactivity in an environmental sampling medium at a specified location exceeds the reporting levels of Table 7.2 as 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 l
Annual Radiological Environmental Monitoring Report. If the required Interlaboratory Comparison Program analyses are NOT performed, corrective action i
SHALL be reported in the Annual Radiological Environmental Monitoring Report
- i. The Annual Radiological Environmental Monitoring Report SHALL NOT include the Complete Analysis Data Tables. These contain the results of each sample analysis and SHALL be maintained by the licensee.
8.3 Annual Summarv of Meteorological 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES MWE TITLE:
NUMBER:
INN OFFSITE DOSE CALCULATION H4 gf*,Sectj6ti*NM MANUAL (ODCM)
REV: 13 a
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- e $4* J Pace 66 of 197 BASES 2.0 1.lOUID EFFLUENTS 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 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 gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)
Publication 2.
This control applies to the releases of radioactive materials in liquid effluents from all units at the site.
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 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 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 >0.5 gpm).
2.3/2.4 DOSE Provided to implement the requirements of Sections ll.A, Ill.A and IV.A of Appendix I, 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix I. The ACTION statements provide operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents 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 the drinking water that are in excess of the 40CFR141 requirements.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
'Mkh NhjgK TITLE:
NUMBER:
996iMd OFFSITE DOSE CALCULATION H4 gxff*
P MANUAL (ODCM)
REV: 13
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> wg;yr j '^ W Paae 67 of 197 2.5/2.6 LIQUID RADWASTE TREATMENT SYSTEMS Provides assurance that the liquid radwaste treatment system will be avaliable 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.
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 The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during i
actual or potential releases of liquid effluents. The Alarm / Trip Setpoint for these instruments SHALL be calculated and adjusted in accordance with the methodologies i
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 ll, Column 2,in an UNRESTRICTED AREA.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES e
TITLE:
NUMBER:
kgy{gg@, f,Ms? LIE OFFSITE DOSE CALCULATION H4 gy[I] 4dF MANUAL (ODCM)
REV: 13 Miseisf%
l p#M
' M M #
- Pace 68 of 197 3.0 GASEOUS EFFLUENTS 3.1/3.2 DOSE RATE This controlls provided to ensure that the dose rate at any time at the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10CFR Part 20 for UNRESTRICTED AREAS. The annual dose limits are 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 individualin an UNRESTRICTED AREA to annual average concentrations exceeding limits specified in Appendix B, Table 11 of 10CFR Part 20. For individuals who may at times be within the SITE BOUNDARY, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the total body or to less than or 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 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.
3.3/3.4 DOSE FROM NOBLE GAS This controlis provided to implement the requirements of Sections ll.B, Ill.A and IV.A of Appendix I,10CFR Part 50. The Limiting Conditions for Operation implement the 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 Section IV.A of Appendix I to assure that the release of radioactive materialin gaseous effluents will be kept "as low as reasonably achievable".
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
g fgW g Mk } $$g OFFSITE DOSE CALCULATION H4 W*
u e C%
MANUAL (ODCM)
REV: 13 k
ISedkkM7 9
- Mg M&N Paae 69 of 197 3.5/3.6 DOSE FROM IODINE 131. IODINE 133. TRITIUM & PARTICULATES 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 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 caiculations are
- 1)individualinhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and
- 4) deposition on the ground with subsequent exposure of man.
3.7/3.8 GASEOUS RADWASTE TREATMENT SYS TEMS This control provides assurance that the Waste Gas Treatment System and the VENTILATION EXHAUST TREATMENT SYSTEMS will be available for use whenever gaseous wastes are released to the environment. The roquirement 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 10CFR Part 50, and the design objective given in Section ll.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of the 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.
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.
-.m_
PRAIRIE ISLAND NUCLEAR GENERATING PLANT j
NORTHERN STATES POWER COMPANY H PROCEDURES TRLE:
NUMBER:
!M<
L k
OFFSITE DOSE CALCULATION H4 4
MANUAL (ODCM)
REV: 13 i
a w
4AfsE4 -
Pace 70 of 197 l
The cooling towers at Prairie Island are located to the south of the plant and are within
]
500 to 2000 feet. At low wind velocities (below 10 mph) the 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 circulating water in the tower. This j
control minimizes the possibility of releases of gaseous effluents from entering the river from cooling tower scrubbing.
3.9/3.10 EXPLOSIVE GAS MONITORING INSTRUMENTATION To ensure the concentration of potentially explosive gas mixtures contained in the j
waste gas treatment system is maintained below the flammability limits of hydrogen and oxygen. Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. Maintaining the l
concentrations below the flammability limit provides assurance that the releases of I
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 oxygen: 1) oxygen added for recombiner operation, and 2) placing tanks vented for maintenance back on the system. The system is operated through the 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.
t j
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 i
waste gas system. If the required gas analyzers are not operable, the oxygen to the recombiner will be isolated to prevent oxygon from entering the system from this i
source. Tanks that may undergo maintenance are normally purged with nitrogen before placing them in service to eliminate this as a source of oxygen.
l 3.11/3.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING l
lNSTRUMENTATION The radioac'ive gaseous effluent monitoring instrumentation is provided to monitor and j
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 i
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 i
A to 10CFR Part 50.
i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
M DEN {GlM5m!s4@
ig y
OFFSITE DOSE CALCULATION H4 P'l MANUAL (ODCM)
REv: 13 6
4 g 9SktioWV W'7A M [
PaQe 71 of 197 6.0 TOTAL DOSE This controlis provided to meet the dose limitations of 10CFR Part 190 that have been incorporated into 10CFR 20 by 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 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 individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storage tanks, etc.) are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within 40CFR Part 190 limits. For the purposes of the Special Report,it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, 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 requirements of 40CFR Part 190, the Special Report with a request for a variance (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 individualls 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.
7.0 R ADIOLOGICAL ENVIRONMENTAL MONITORING 7.1/7.2 MONITCRING 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 supplements the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels are not higher than expected in the bases of the effluent measurements and modeling of the environmental exposure pathways.
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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Th
%3h Q TITLE:
NUMBER:
MM8i OFFSITE DOSE CALCULATION H4
'M WW MANUAL (ODCM)
REV: 13
' ?fy
$ k" ud isf, ' i' di 4 Page 72 of 197 7.3/7.4 LAND USE CENSUS This controlls 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 survey 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 minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
7.5/7.6 INTERLABORATORY COMPARISON PROGRAM 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 materialin 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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Ryggy,gjfM:g TITLE:
NUMBER:
PM < W 6'lljlg 5:
3pcF iT OFFSITE DOSE CALCULATION H4 EEM MANUAL (ODCM)
REV: 13
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Pane 73 of 197 TABLE 1.1 - OPERATIONAL MODES REACTOR
% RATED AVERAGE VESSEL HEAD REACTIVITY THERMAL COOLANT CLOSURE BOLTS MODE IIILE CONDITION ED M TEMPERATURE FULLY TENSIONED 1
POWER OPERATION Critical
>2%
NA YES 2
HOT STANDBY" Critical s2%
NA YES 3
HOT SHUTDOWN" Suberitical NA 2350*F YES 4
INTERMEDIATE Subcritical NA
< 350 F YES SHUTDOWN" 2200 F 5
COLD SHUTDOWN Subcritical NA
< 200*F YES 6
REFUELING NA*
NA NA NO Boron concentration of the reactor coolant system and the refueling cavity sufficient to ensure that the more restrictive of the following conditions is met:
)
a.
K tr s 0.95, or b.
Boron concentration 2 2000 ppm.
Prairie Island specific MODE title, not consistent with Standard Technical Specification MODE titles.
MODE numbers are consistent with Standard Technical Specification MODE numbers.
l l
1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g@{@C):
ggg@ggApf TITLE:
NUMBER:
fugg9h OFFSITE DOSE CALCULATION H4 d
BEgEdN@h MANUAL (ODCM)
REV: 13 48 M ;Ssctidn b J.
l W pgg% As W
Pace 74 of 197 TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release lypep 3Sampgngy g aMinimum; gType of Activityj slower umitLoff
$h Ib33$M[N$M
< Y[? MAN $ fhhalysisjjy 9]!pnalysi,sif ' '
DetectionT(Lp+)l m
m can gg afrequencyg mm m
((nCyrsi)*t
~
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 b
Composite Gross alpha 1 x 10-7 Each Batch Quarterly Sr-89, Sr-90 5 x 10-8 Composited Fe-55 1 x 10-6 Continuous Release *:
Continuousj.h,k Weekly Principal Gamma 5 x 10-7 f
Turbine Building Composite Emitterso Sumps 1-131 1 x 10-6 Weekly Grab Each Sample Dissolved and 1 x 10-5 Sample Entrained Gases Continuousj k Monthly H-3 1 x 10-5 l
Composite Gross Alpha 1 x 10-7 f
Continuousj.k Quarterly Sr-89, Sr-90 5 x 10-8 Composite' Fe-55 1 x 10-6 Continuous Release *:
Weekly Grab Each Sample Principal Gamma 1 x 10-7 b
Steam Generator Sample During Composite Emitterse Blowdown Releasesi 1-131 1 x 10-6 Grab Sample Each Sample Dissolved and 1 x 10-5 Each Month Entralned Gases During Releases Weekly Grab Monthly H-3 1 x 10-5 Sample During Compositeb Releases' Gross Alpha 1 x 10-7 Weekly Grab Quarteri[
Sr-89, Sr-90 5 x 10-8 Sample During Compositeb Releasesi Fe-55 1 x 10-6
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STALES POWER COMPANY H PROCEDURES gg,g!yp *,' '
TITLE:
NUMBER:
M; WfK OFFSITE DOSE CALCULATION H4
' @ R_f ~
MANUAL (ODCM)
REV: 13
[SoCtionfj %
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Paae 75 0f 197 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 materialin 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 6
E V
2.22 x 10 Y. exp (-AAT) where:
= the "a priori" lower limit of detection (microcurie per unit mass or volume),
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),
i 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 samp!e 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 pdoIl(before the fact) limit representing the capability of a measurement system and not as an a costeriori (after the fact) limit for a particular measurement.
PRAIRIE ISLAND NUCLEAR GENERAT1NG PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j
TITLE:
NUMBER:
s b
OFFSITE DOSE CALCULATION H4
[
.,,_ a T
MANUAL (ODCM)
REv: 13 kir iTM Paae 76 of 197 l
TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGBAM
[ 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 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 required, the reasons SHALL be documented in the Annual Radioactive Effluent Report.
- 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 quantities and 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 0.5 gpm in any steam generator. This sampling is provided in lieu of continuous 3
monitoring with automatic isolation.
- 1. Grab samples SHALL be collected at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when steam generator blowdown releases are being made and the specific activity of the secondary coolant is
- t0.01 pCi/ gram DOSE EQUlVALENT l-131 or primary to secondary leakage exceeds 0.5 gpm.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES s Ef gjgggi.
TITLE:
NUMBER:
$(Sh g1%[x OFFSITE DOSE CALCULATION H4 e' l' E E / ' ' 1 MA?1UAL (ODCM)
REV: 13 h;wdfi$thbtl05 '9SV gyg " g rggd 5 Pace 77 M 197 4
TABLE 2.1 - RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
[CONTD]
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 Building Sumps are collected via on-line composite samplers. These samplers function on timers and collect a predetermined volume of i
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 positioned above the normal TBS pump controlling level and include a timer to allow the calculation of the additional release volume.
I
.- m-
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES f$r:M, TITLE:
NUMBER:
83@@gi- % @$
OFFSITE DOSE CALCULATION H4 OTP' 2 ~$
MANUAL (ODCM)
REv: 13 gn - l- -
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Paae 78 of 197 TABLE 2.2 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
Gross Radioactivity Monitors Providing AutomaticTermination of Release a.
Liquid RadwasteEffluent Line 1
During releases 1
b.
Steam Generator Blowdown 1/ Unit During releases 2
Effluent Line 2.
Flow Rate Measurement Devices a.
Liquid RadwasteEffluent Line 1
During releases 4
requiring throttling of flow b.
Steam Generator Blowdown Flow 1/ Gen During releases 4
3.
Continuous Composite Samplers a.
Each Turbine Building Sump 1/ Unit During releases 3
Effluent Line 4.
Discharge Canal Monitor 1
At all times 6
5.
Tank Level Monitor 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 determination and following changes in flow)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
y q.g,
'M-d; g
?E RDF[k OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
REv: 13
+ 2 Sect l6ni Mdf, ^
Page 79 of 197 IABLE 2.2 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
[ CONT'D]
TABLE NOTATIQNS 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is 20.01 pCi/ gram DOSE EQUlVALENT l-131, or 2.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is <0.01 pCi/ gram DOSE EQUIVALENT 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 i
continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and saved for weekly composition and analysis in accordance with Table 2.1.
ACTION 4 With the number of channels Operable less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. 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 continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and saved for weekly composition and analysis.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES jh @@INf, TITLE:
NUMBER:
@y 7
OFFSITE DOSE CALCULATION H4 hMljj{$
lg MANUAL (ODCM)
REV: 13 4 ; ~-
gyw,;r Pace 80 of 197 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATIOll SURVEILLANCE REQUIREMENTS f g
iQHANNElgsg l SOURCE; (FUNCTIONAL 4 J dii.mf M
'.. JCHECK1.,.. '
i[, Call.BRATi.ONli-
%dinstruments'
)Fre'quenc'y;(4)?
yFrequencyl iFrequencys sFrequencyA '
Liquid Radwaste Effluent Daily during Prior to each QuarterlyO)
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 St::am Generator Blowdown Daily during Monthly QuarterlyO)
At least once every Gross Radioactivity Monitors releases 18 months (3)
Steam Generator Blowdown Daily during At least once every Flow releases 18 months Turbine Building Sump Daily during At least once every Continuous Composite releases 18 months 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
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Mdfb jf%%@gi TITLE:
NUMBER:
1 Ebb 7 ~ %di OFFSITE DOSE CALCULATION H4 wy q gya MANUAL (ODCM)
REV: 13 Nyssisnd$"p g c ;gs -
Pace 81 of 197 TABLE 2.3 - RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS [ CONT'D]
TABLE NOTATIONS
- a. The CHANNEL FUNCTIONAL TEST SHALL also demonstrate that automatic isolation of this pathway and control room 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),
- b. 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).
- c. The initial CHANNEL CAllBRATION SHALL be performed using one or more of the reference standards certified by the National Bureau of Standards or using sources traceable to NBS standards. These standards SHALL permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATIONS, sources that have been related to the initial calibration SHALL be used.
- d. 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.
PRAIP2 ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 00 TITLE:
NUMBER:
2 mjp mdF pn w.
g OFFSITE DOSE CALCULATION H4
- l %.; _ionte 9 MANUAL (ODCM)
REV: 13 fi 4
tsect 1""'
'T Pace 82 0f 197
~
TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit 9
/ pelof'Actlytt ; gof Detectidnj!
1@WsAnalpslii"y' Gaseous Release Type ggSamplingW -
- Minimumi T T ' ' "f* l c^
7Analpals*f fiFrequency/W !Frequets:p]
~ '~ J
~ '
QQO;R f ' v4Ms Jm:q.m:,-
c'.
[(LLD){ Cl/ml)
CONTINUOUS RELEASE Weekly b, h Weekly Principal Gamma 1 x 10-4 Points:
Gas Grab Sample Emitters
- g, i, h Weekly c l-131 1 x 10-12 Plant Vents:
Continuous Charcoal Sample Unit 1 Aux Bldg.
g,i, h Weekly C Principal Gamma 1 x 10-H Unit 2 Aux Bldg.
Continuous Particulate Emitters e 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 Gross Alpha 1 x 10-H d
Continuous Particulate Composite g, i, h Quarterly Sr-89, Sr-90 1 x 10-"
d Continuous Particulate Composite 9
Noble Gas Noble Gases, 1 x 104 Continuous Monitor Gross beta and gamma Atmospheric Steam Daily 1 Releases k Grab Sample Each Principal Gamma 5 x 10-7 During Release Sample Emitters e l-131 1 x 10-6 Daily i 3
Grab Sample Monthly During Release Composite H-3 1 x 10-5 Gross Alpha 1 x 10-7 Daily 1 Quarterly i Sr-89, Sr-90 5 x 10-8 Grab Sample Composite During Release
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES vv
'g
^ M TITLE:
NUMBER:
o
.w,4
.,/...
+jw w ew y, '
OFFSITE DOSE CALCULATION H4
.s m
q!sactioni 9 MANUAL (ODCM)
REV: 13 n my y Pace 83 of 197 TABLE 3.1 -RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
[ CONT'D]
Gaseous. Release $pe e Sampling
- e. Minimum 9 e of Activit 4 Lower Limit *@
g,f j
j ' @jM * ^
, ' Frequency
.}Adalysid;";Typ$nslysisf y*Jof.Dstehtlois
! Frequency!
!;(LLD)( Cl/ml))
'~~
s Gas Grab Sample Each Principal Gamma 1 x 10-4 m
Containment Purge Prior to each Purge Sample Emitters 8 (Prior to Release)
Grab g m Each H-3 1 x 10-6 Prior to Release Sample and Continuous Grab 9 8. m Charcoal 1-131 1 x 10-12 Prior to Release Sample and Continuous Grab g., m Particulate Principal Gamma 1 x 10-11 Prior to Release Sample Emitters 8 and Continuous Grab g,i, m Monthly Gross Alpha 1 x 10-11 d
Prior to Release Particulate and Continuous Composite Grab g.i m Quarterly Sr-89, Sr-90 1 x 10-11 d
Prior to Release Particulate and Continuous Composite Waste Gas Gas Grab Sample Each Principal Gamma 1 x 10-4 Storage Tanks Prior to each Sample Emitters 8 Release (Prior to Release)
Grab Sample Each H-3 1 x 10-6 Prior to each Sample Release (Prior to Release)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
'+
WW TITLE:
NUMBER:
w re W s L E
OFFSITE DOSE CALCUl. ATION H4
, ppWM,
^
MANUAL (ODCM)
REV: 13 W W Section w
a v y
ygg TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
[ CONT'D]
IABLE NOTATIONS
- a. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive materialin 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:
b LLD = E V
2.22 x 10e. y. exp (- AAt) where:
LLD the "a priori" lower limit of detection (microcurie per unit mass or
=
volume.
the standard deviation of the background counting rate or of the sb
=
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,
=
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 DIlod (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.
J
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES gp %
Qpg TITLE:
NUMBER:
tgy 4
OFFSITE DOSE CALCULATION H4 g#Ag5 s E@$7 MANUAL (ODCM)
REV: 13 J W sesii d $ "
~;&M
'/ /
Pace 85 of 197 TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
[ CONT'D]
TABLE NOTATIONS [ cont'd]
- 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.
- 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 one day are analyzed, the corresponding LLD's may be increased by a factor of 10. Samples SHALL be analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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.
i
- e. The principal gamma emitters for which the LLD control applies include the following i
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, j
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).
j Design flow rates may be used for building exhaust vent flow rates.
[
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
ps@@%& @:
AW LJgdA OFFSITE DOSE CALCULATION H4 qMip < =A MANUAL (ODCM)
REV: 13 isW@M a E A %
Pace 86 of 197 TABLE 3.1 - RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
[ CONT'D]
TABLE NOTATIONS [ cont'd]
- h. Releases are made via the shield building vents only during PURGING, or operation of the shield building ventilation system, or operation of the auxiliary building special ventilation system in lieu of weekly removal and analysis of iodine and particulate collection devices, these devices may be removed and analyzed following each release provided that the release lasts less than one week. Releases made via the shield building vents as a result of routine surveillance tests or scheduled short term maintenance activities (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or less) do not require sampling and analysis of the shield building vent. Removal and analysis of collection devices is not required if releases are not being made.
- i. 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.
J. Grab samples for atmospheric steam releases are representative liquid grab samples from the respective steam generator.
- 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 fiash tank vents, it does not include steam dumped via the condenser.
- l. 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 Fanc and also VENTING of containment utilizing the Post Loca Vent System. When the rele.6e is completed via the Post Loca Vent, the pre-release tritium, particulate and charcoal samples should be used for all analyses, and continuous samples collected during the releasu are not required. During Cold Shutdown periods, the availability of ventilation systems and the position of containment air-lock doo:s may require that portions of the required samples be collected with installed continuous monitors or portable sampling equipment.
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES y
TITLE:
NUMBER:
i f',
g '.3
^
OFFSITE DOSE CALCULATION H4 as@/% 1 *'*9d' MANUAL (ODCM)
REV: 13
- "< ? & Q ;%f
^
G4Clm ' /W@
Pace 87 of 197 TABLE 3.2 - RADIOACTIVE G ASEOUS 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 Unit 1 Aux Bldg.
Unit 2 Aux Bldg.
Rad Waste Bldg.
Spent Fuel Pool 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
c.
Paniculate Sampler Filter 1
During releases 3
- d. Sampler Flow Integrator 1
During releases 1
- 3. Air Ejector Noble Gas Monitors 1
During power op-6 (Each Unit) eration
- Noble gas activity monitors providing automatic termination of releases (except the Radwaste Building which has no automatic isolation function).
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j
TITLE:
NUMBER:
w+
n &>.a
+
- 4 7
OFFSITE DOSE CALCULATION H4
,l-g,m MANUAL (ODCM)
REv: 13 WN; ' >
Pace 88 of 197 TABLE 3.2 - RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1
JCONT'D_
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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 2 With the number of channels Operable less than required by the Minimum Channelo 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 Channels Operable requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 5 With the number of channels Operable less than required by the Minimum Channels Operable requirement,immediately suspend Purging of radioactive effluents via this pathway (applicable to Reactor Building vents).
i ACTION 6 With the number of channels Opera. le less than required by the Minimum Channels Operable requirement, air ejector operation may continue for up to 30 days provded grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and these samples as analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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).
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES s@
Rbr Wa TITLE:
NUMBER:
gp@$55%"j@$@$aaM" {
y OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
REV: 13 y, k@ m :Onf$;n vr n
1 W
1
<m Pace 89 of 197 j
TABLE 3.3 -BAD 1QACIlYJLGASEQL9 EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1
4
+ LCHANNEtts 4
sitSOURCEl 4 FUNCTIONAL 3
..g...... ug N.d$ l8%g' j%gge._#...
y _LIBRATIONF 4
edCHECK R JC.HE.C.K?
- f-
$ TEST 6 M ICA
%qgghyMeggs%$iNstruinentifmP%
dF$illOensp(4)?_ fF.requensp!
!!FfM0sti$p@@
3Frequsncy1[f l
Waste Gas Holdup System Daily during Monthly (2)
Quarterly (5)
Explosive Gas (Oxygen) system operation Monitors i
Effluent Release Points Unit 1 Aux Bldg.
Unit 2 Aux Bldg.
Rad Waste Bldg.
2 Spent Fuel Pool Unit 1 Shield Bldg.
Unit 2 Shield Bldg.
Noble Gas Activity Daily during Monthly
- Quarterly (1)
At least once every Monitor (d) releases 18 months (3)
(Except Radwaste Building) 4 Noble Gas Activity Monitor Daily during Monthly Quarterly (2)
At least once every Radwaste Building (d) releases 18 months (3) i lodine and Particulate Weekly Samplers i
Sampler Flow Rate Manitor Weekly At least once every 18 months Air Ejector Noble Gas Daily during re-Monthly Quarterly (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 of containment purge release.
I k
2 5
i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Nk'djf gg g'~
TITLE:
NUMBER:
k E * @gf, OFFGITE DOSE CALCULATION H4 p;@
Wa MANUAL (ODCM)
REv: 13
% 1. section 4^
Paae 90 of 197 3mg IABLE 3.3 - RADIOACTIVE G ASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS [ CONT'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 Bureau of Standards or using sources traceable to NBS 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.
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.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g' - W TITLE:
NUMBER:
, ;;g.:;Y!p,,,;dgg[
A l@r OFFSITE DOSE CALCULATION H4 m
%W MANUAL (ODCM)
REV: 13 h:ts,[Sebt%g/2, as Sn.
Page 91 of 197 4.
TABLE 4.1 - LIQUID SOURCE TERMS a
yn WASTE EFFLUENT '
SGBD m
RADIONUCLIDE,
{MP6iddjI5l$7 1(ANCl/Yr)) '
' $((A N Cl/Y N3 '
I Mo-99 4E-5 6.42E-3 1.415 E-2 1-131 3E-7 3.061 E-2 4.11 E-2 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 5.743 E-2 1.862E-2 Cs-137 2E-5 8.214E-2 2.69 E-2 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
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES p
- gp TITLE:
NUMBER:
[?
OFFSITE DOSE CALCULATION H4 Wh Ef MANUAL (ODCM)
REV: 13 ff Jsset:+ #s 6
E M Paae 92 of 197 TABLE 4.2 - ADULT INGESTION DOSE VALUES (Ap) FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MREM /HR PER uCl/ml)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GhLLI 1H 3
0.00E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 6C 14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 11NA 24 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 4.07E 02 24CR 51 0.00 E-01 0.00E-01 1.27E 00 7.61 E-01 2.81 E-01 1.69E 00 3.20E 02 25MN 54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 25MN 56 0.00 E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.51E 03 26FE 55 6.58E 02 4.55E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61 E 02 26FE 59 1.04E 03 2.44E 03 9.36E 02 0.00E-01 0.00E-01 6.82E 02 8.14E 03 27C0 58 0.00 E-01 8.92E 01 2.00E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 27CO 60 0.00E-01 2.56E 02 5.65E 02 0.00E-01 0.00E-01 0.00E-01 4.81 E 03 28NI 63 3.11 E 04 2.16E 03 1.04E 03 0.00E-01 0.00E-01 0.00E-01 4.50E 02 28NI 65 1.26E 02 1.64E 01 7.49E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 29CU 64 0.00E-01 9.97E 00 4.68E 00 0.00E-01 2.51E 01 0.00E-01 8.50E 02 30ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 30ZN 69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 35BR 83 0.00E-01 0.00 E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 35BR 84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11 E-04 35BR 85 0.00 E-01 0.00 E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 1.01 E-15 37RB 86 0.00E-01 1.01 E 05 4.71 E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 37RB 88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 37RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 38SR 89 2.21 E 04 0.00E-01 6.35E 02 0.00E-01 0.00E-01 0.00E-01 3.55E 03 38SR 90 5.44E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.57E 04 38SR 91 4.07E 02 0.00 E-01 1.64E 01 0.00E-01 0.00E-01 0.00E-01 1.94E 03 l
38SR 92 1.54E 02 0.00E-01 6.68E 00 0.00E-01 0.00E-01 0.00E-01 3.06E 03 39Y 90 5.76E-01 0.00E-01 1.54E-02 0.00E-01 0.00E-01 0.00E-01 6.10E 03 39Y 91M 5.44E-03 0.00E-01 2.11 E-04 0.00E-01 0.00E-01 0.00E-01 1.60E-02 39Y 91 8.44E 00 0.00E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 4.64E 03 39Y 92 5.06E-02 0.00 E-01 1.48E-03 0.00E-01 0.00E-01 0.00E-01 8.86E 02 39Y 93 1.60E-01 0.00 E-01 4.43E-03 0.00E-01 0.00E-01 0.00E-01 5.09E 03 40ZR 95 2.40 E-01 7.70E-02 5.21 E-02 0.00E-01 1.21 E-01 0.00E-01 2.44E 02 40ZR 97 1.33 E-02 2.68 E-03 1.22E-03 0.00E-01 4.04E-03 0.00E-01 8.30E 02 41NB 95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 42MO 99 0.00E-01 1.03E 02 1.96E 01 0.00E-01 2.34E 02 0.00E-01 2.39E 02 43TC 99M 8.87E-03 2.51 E-02 3.19E-01 0.00E-01 3.81 E-01 1.23E-02 1.48E 01 43TC 101 9.12 E-03 1.31 E-02 1.29E-01 0.00E-01 2.37E-01 6.72E-03 3.95 E-14 44RU 103 4.43E 00 0.00E-01 1.91E 00 0.00E-01 1.69E 01 0.00E-01 5.17E 02 44RU 105 3.69 E-01 0.00E-01 1.46E-01 0.00E-01 4.76E 00 0.00E-01 2.26E 02 l
44RU 106 6.58E 01 0.00E-01 8.33E 00 0.00E-01 1.27E 02 0.00E-01 4.26E 03 I
47AG 110M 8.81 E-01 8.15E-01 4.84E-01 0.00E-01 1.60E 00 0.00E-01 3.33E 02 52TE 125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.02E 04 52TE 127M 6.48E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 52TE 127 1.05 E-02 3.78E 01 2.28E 01 7.80E 01 4.29E 02 0.00E-01 8.31E 03
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
- Q &q < W~ WT6; g TITLE:
NUMBER:
p y m.
yg gr3f OFFSITE DOSE CALCULATION H4 zu E E ' r h MANUAL (ODCM)
REv: 13 W yQQ*y 96 ~
p Pace 93 of 197 TABLE 4.2 - ADULT INGESTION DOSE VALUES (Ap) FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT (MREM /HR PER uCl/ml)[ CONT'D]
NUCLlDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 52TE 129M 1.10E 04 4.11 E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.54E 04 52TE 129 3.01 E 01 1.13E 01 7.33E 00 2.31 E 01 1.26E 02 0.00E-01 2.27E 01 52TE 131M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.04E 04 52TE 131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.26E 01 0.00E-01 2.67E 00 52TE 132 2.41 E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.38E 04 531 130 2.71 E 01 8.01 E 01 3.16E 01 6.79E 03 1.25E 02 0.00E-01 6.89E 01 531 131 1.49E 02 2.14E 02 1.22E 02 7.00E 04 3.66E 02 0.00E-01 5.64E 01 53I 132 7.29E 00 1.95E 01 6.82E 00 6.82E 02 3.11 E 01 0.00E-01 3.66E 00 531 133 5.10E 01 8.87E 01 2.70E 01 1.30E 04 1.55E 02 0.00E-01 7.97E 01 53I 134 3.81 E 00 1.03E 01 3.70E 00 1.79E 02 1.64E 01 0.00E-01 9.01 E-03 53I 135 1.59E 01 4.17E 01 1.54E 01 2.75E 03 6.68E 01 0.00E-01 4.70E 01 55CS 134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 55CS 136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.38E 03 1.40E 04 1
55CS 137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01 E 04 55CS 138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 56BA 139 9.29 E-01 6.62E-04 2.72E-02 0.00E-01 6.19E-04 3.75E-04 1.65E 00 56BA 140 1.94E 02 2.44E-01 1.27E 01 0.00E-01 8.30E-02 1.40E-01 4.00E 02 56BA 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 56BA 142 2.04E-01 2.10E-04 1.28E-02 0.00E-01 1.77E-04 1.19E-04 2.37E-19 57LA 140 1.50E-01 7.54E-02 1.99E-02 0.00E-01 0.00E-01 0.00E-01 5.54E 03 57LA 142 7.66E-03 3.48 E-03 8.68E-04 0.00E-01 0.00E-01 0.00E-01 2.54E 01 58CE 141 2.24E-02 1.52E-02 1.72E-03 0.00E-01 7.04E-03 0.00E-01 5.79E 01 58CE 143 3.95 E-03 2.92E 00 3.23E-04 0.00E-01 1.29E-03 0.00E-01 1.09E 02 58CE 144 1.17E 00 4.88E-01 6.27E-02 0.00E-01 2.90E-01 0.00E-01 3.95E 02 59PR 143 5.51 E-01 2.21 E-01 2.73E-02 0.00E-01 1.27E-01 0.00E-01 2.41 E 03 59PR 144 1.80E-03 7.48E-04 9.16E-05 0.00E-01 4.22E-04 0.00E-01 2.59E-10 60ND 147 3.76E-01 4.35E-01 2.60E-02 0.00E-01 2.54 E-01 0.00E-01 2.09E 03 74W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 93NP 239 2.85E-02 2.80E-03 1.54E-03 0.00E-01 8.74E-03 0.00E-01 5.75E 02 t
i PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
NORTHERN STATES POWER COMPANY H PROCEDURES Op TITLE:
NUMBER:
wlg.g.$ #ptf; %MS OFFSITE DOSE CALCULATION H4
+
'9' f a fa MANUAL (ODCM)
REV: 13
' L 'isectiostg Pace 94 of 197 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) 1 Appendix B - Concentrations in Air and Water Above Natural Background
[See footnotes at end of Appendix B]
Isotope Table 1 l
Table ll l
Element (atomic number)
Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2-Water (pCi/ml)
(pCi/ml)
(pCi/ml)
(pCi/ml)
Achnium(89)..
Ac 227..
S 2x10-12 6x104 8x10-14 2x104 1
3x10-H 9x10-3 9x10-13 3x10-4 Ac 228...
S 8x10-8 3x1 H 3x10-8 9x10-5 1
2x104 3x104 6x10-10 9x10-5 Amencium(95)..
Am 241..
S 6x10-12 1 x10-*
2x10-13 4x104 1
1x10-10 8x10-4 4x10-12 3x1g-5 Am 242m..
S 6x10-12 1xjoa 2x10-13 4x1.s 4
1 3x1040 3y10-3 9x10-12 gxio-3 Am 242..
S 4x104 4x104 1x10-e j x j o-4 1
5x104 4x104 2x10-e 1 x10-4 Am 243..
S 6x10-12 j x10-4 2x10-13 4x10-e I
1x10-10 8x10-4 4x10-12 3x10-3 Am 244.
S 4x10-e 1x10-1 1x10-7 5x10-3 1
2x10-a j x10-1 8x10-7 5x10-3 Anbmony..
Sb 122.
S 2x10-7 8x10-4 6x104 3x10-6 1
1x10-7 8x10-4 5x10-e 3x10-5 Sb 124..
S 2x10-7 7x10-4 5xig-e 2x10-5 1
2x10-8 7x10-4 7x10-10 2x10-5 Sb 125..
S 5x10-7 3x104 2x10-a jxjo-4 I
3x10-a 3x104 9x1040 1x10-4 Argon (18)..
A 37 -
Sub2 6x104 1x10-4 A 41.
Sub 2x10-e 4xin-a Arsenic (33)..
As 73..
S 2x10-8 1x10-2 7x104 5x10-4 1
4x10-7 1 x10-2 j xt e-a 5xio-4 i
As 74..
S 3x10-7 2x10-3 1x104 5x10-5 1
1x10-7 2x10-3 4x104 5x104 As 76..
S 1x10-7 6x10-4 4 x10-8 2x10-5 l
1x10-7 6x10-4 3x10-0 2x10-5 As 77..
4x10-7 2x10-3 2x10-8 8x1g-5 Astatne(85)..
At211.
S 7x10-8 5x104 2x10-10 2x10-8 1
3x10-8 2x10-3 1x10-e 7xjo-5 Banun(56)..
Da 131.
S 1x10-8 5x104 4x10-8 2x10-4 1
4x10-7 5x10-3 1x104 2x10-4 Ba 140..
S 1x10-7 8x10-4 4x104 3x10-3 1
4x104 7x10-4 1x10-0 2x104 Berkebun(97)..
Bk 249_..
S 9x10-10 2x10-2 3x10-11 6x10-4 l
1x10-7 2x10-2 4xj o-o 6x10-4 Bk 250..
S 1x10-7 6x104 5x10-8 2x10-4 1
1x10-6 6x10-3 4x10-8 2x10-4 BeryDium(4)..
Be 7 S
6x1 H 5x10-2 l
2x10-7 2x104 1
1x10-8 5x1g-2 l
4x1H 2x104
l l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l
@Mdggggjg TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4
?1 MANUAL (ODCM)
REV: 13
$ ' $fssti6n;Qg e
vu Pace 95 of 197 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) isotopel Table i Table II Element (atomic number)
Col.1 - Air Col. 2 -Water Col.1 - Air Col. 2 -Water
( Ci/ml)
(pCi/ml)
( Ci/mf)
(pCi/ml)
Bismuth (83).-
Bi 206 S
2x104 1x104 6x10-8 4x10-5 l
1x104 1x10-3 5x10-e 4xio-5 Bi 207..
S 2x104 2x10-3 6x10-e 6x10-5 i
Bi 210.
S 6x10-e j xto-s 2x10-10 4x10-a i
6x10-8 1 x10-3 2x10-10 4x10-a 1
Bi 212..
S 1x104 1x10-2 3x10-e 4xjga l
2x104 1 x10-2 7 c104 4xj o-4 I
Bromine (35)--
Br 82..
S 1x10-8 8x104 4x10-8 3x10-4 1
Cadmium (48). _
Cd 109.
S 5x10-e 5x104 2x10-8 2x10-4 I
7x104 5x10-3 3x104 2x10-4 Cd 115m..
S 4x10-a 7x10-d 1x10-e 3x10-5 1
4x10-8 7xj o-4 j xto-o 3x10-5 Cd 115.,
S 2x10-1 1x10-3 8x10-e 3x10-5 1
2x104 1x10-3 6x10-0 4xjo-5 Calcium (20)..
Ca 45..
S 3x10-8 3x10-4 1x1 H 9x10-8 1
1x104 5x10-3 4x10-8 2x10-4 Ca 47..
S 2x104 1x104 6x10-e
$xto-5 1
2x104 1x104 6x10-8 3x10-5 Californium (98)...
Cf249.
S 2x10-12 1xiga 5x10-14 4x10-8 i
l 1x10-10 7x10-4 3x10-12 2x10-5 Cf 250..
S 5x1g-12 4xjoa 2x10-13 1x10-5 1
1x10-10 7x104 3x10-12 3x10-5 Cf 251.
S 2x10-12 t xiga 6x10-14 4x10-e 4
l 1 x10-10 8x104 3x10-12 3x10-5 Cf 252.
S 6xig-12 2x10-4 2x10-13 7x10-6 I
3x10-11 2x10-4 1x10-12 7x10-6 Cf253.
S 8x1010 4x10-3 3x10-"
1x10-4 I
8x10-10 4x10-3 3x10-"
1x10-4 i
Cf254.
S 5x10-12 4xto-o 2x10-13 1x10-7 1
5x10-12 4xjo-o 2x10-13 1x104 Carbon (6).
C 14....
S 4x104 2x10-2 1xjg4 8x10-4 (CO )..
Sub 5x10-5 1x10-6 2
Cenum(58)..
Ce 141.
S 4x104 3x104 2x104 9x104 1
2x104 3x10-3 5x10-e gx10-5 Ce 143..
S 3x104 1x10-3 9x10-8 4x10-3 1
2x104 1x104 7x10-e 4 xj o-3 Ce 144..
S 1x104 3x10-4 3x10-IO 1x10-3 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES gAJ gyr$y%
TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4 j'ij MW 4880@AN MANUAL (ODCM)
REv: 13 m gdy5 b
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Pace 96 of 197 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]
l lsotope Table 1 Table ll Element (atomic number)
Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 -Water
( Ci/ml)
(pCi/ml)
( Cl/ml)
( Ci/mi)
Cislum(55)..
Cs 131..
S 1x104 7x10-2 4x10-7 2x104 1
3x104 3x10-2 1xt o-7 gxto4 Cs 134m S
6x104 3x10-2 2x10-7 1x10-3 Cs 134..
1x10-a j xio-3 4xj o-10 4xio4 Cs 135..
S 5x10-7 3x10-3 2x104 1x10-4 1
9x104 7x10-3 3x10-e 2x104 Cs136..
S 4x10-7 2x10-3 1x10-8 9x10-5 1
2x10-7 2x104 6x1g-9 6x10-5 Cs 137..
S 6x10-8 4xj o-4 2x10-8 2x10-5 l
1x10-8 j xjo-3 5x10-M 4x10-5 Chlonne(17)..
Cl36 S
2x104 2x10-3 8x10-10 6x10-5 Cl 38..
S 3x10-s j xj o-2 gxio4 4xto-4 1
2x104 1x10-2 yx1o-a 4xig.4 Chromium (24)..
Cr 51..
S 1x104 5x10-2 4x1g-7 2x104 1
2x10-8 5x10-2 8x10-a 2x10-3 Csbalt(27)..
Co S7..
S 3x10-6 2x10-2 1 xio-7 5x10-4 1
2x10-7 1x10-2 6x10-e 4xio-4 Co S8m..
S 2x104 8x10-2 6x10-7 3x10-3 1
Co SS..
S 8x10-7 4x10-3 3x104 1x10-4 l
l 5x10-8 3x104 2x10-8 9x10-3 Co 60..
9x10-8 1x104 3x10-10 3x10-5 Copper (29)..
Cu64.
S 2x10-6 1 x1g-2 7x10-8 3x10-4 1
1x10-6 6x10-3 4x10-8 2x10-4 Curium (96)..
Cm 242.
S 1x1g-tu 7x10-4 4x10-12 2x104 1
2x10-10 7x104 6x10-12 2x10-5 Cm 243.....
S 6x10-12 j xt o-4 2x10-13 5x10-e I
1x10-10 7x10-4 3x10-12 2x10-5 C m 244..
S 9xjg-12 2xj04 3x1o-13 7gj0-6 l
1 x10-10 8x10-4 3x10-12 3x10-5 Cm 245..
S 5x10-12 1x104 2x10-13 4x10-8 l
1x10-2 8x10-4 4x10-12 3x WS Cm 246..
S 5x1g-12 1xjoa 2x10-13 4x10-e i
1x10-10 8x10-4 4x10-12 3x10-5 Cm 247..
S 5x10-12 3xto-4 2x10-13 4x104 1
1x10-10 6x10-4 4x10-12 2x10-5 Cm 248..
S 6x10-13 1x104 2x10-14 4x10-7 1
1x10-11 4x10-5 4x1o-13 1x10-6 i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT l
NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
7 M G M $p d$i OFFSITE DOSE CALCULATION H4 g v: ?
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MANUAL (ODCM)
REV: 13 l
M iWh%M
+ Y vd Page 97 of 197 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) ICONT'D1
~
i Appendix B - Concentrations in Air and Water Above Natural Background Cont'd
[See footnotes at end of Appendix B]
lsotope Table i Table 11 i
I Element (atomic number)
Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 -Water (pCi/ml)
(pCl/ml)
(pCi/ml)
(pCI/ml)
Cm 249..
S 1x104 6x10-2 4xt o-i 2x104 l
1x10-5 6x10-2 4xjg4 2x10-3 Dysprostum(66) -
Dy 165 S
3x10-6 1xio-2 gxina agina 1
2x104 1x10-2 7x104 4x104 Dy 166..
S 2x104 1x104 8x10-e 4xto-5 1
2x104 1x104 7x10-e 4xjg4 i
j Einsteinium (99)--
Es 253..
~
l 6x10-10 7x104 2x10-H 2x10-5 Es 254m.
S 5x104 5x104 2x10-i0 2x10-5 1
6x10-8 5x10d 2x10-10 2x10-5 Es 254..
S 2x10-"
4x1H 6x10-13 1x10-5 1
1x10-10 4x104 4x10-12 1x10-5 Es 255..
S 5x10-10 8x1 H 2x10-"
3x10-5 l
1 4x10-10 8x17-4 1x10-H 3x10-5 Erbium (681-Er169.
S 6x10-7 3x104 2x104 9x104 1
4x104 3x10-3 1 x10-8 gx10-5 Er171.
S 7x104 3x10-3 2x10-a 1x10-4 1
6x104 3x104 2x10-a 1x10d Europium (63)...
Eu 152........
S 4x10-7 2x10-3 1xt o-a 6x10-5 (T/2=9.2 hrs) l 3x104 2x10-8 1x10-a 6x10-5 Eu 152...
S 1x10-a 2x104 4x10-10 8x10-5 (T/2=13 yrs)
I 2x10-a 2x10-3 6x10-10 8x10-5 l
Eu 154..
S 4x104 6x104 1x10-10
.2x104 1
Eu155.
S 9x10-8 6x10-3 3x10-8 2x10d j
l 7x10-8 6x104 3x10-e 2x10-4 Fermium (100)...
Fm 254..
S 6x104 4x104 2x104 1 x10-4 j
i 7x10-8 4xto-3 2x10-0 3 xio-4 Fm 255..
S 2x10-a 1x104 6x10-10 3x10-5 i
i 1x10-a j xjo-3 4xjo.io 3x10-5 Fm 256...
S 3x10-o 3x10-5 1x10-10 9x104 i
2x10-e 3x10-5 6x10-11 9x104 Fluorine (9)...
F 18.-
S 5x104 2x10-2 2x10-7 8x10-4 i
3x10-8 1xio-2 gxto-a 5x10-4 Gadolinium (64).
Gd 153..
l 9x10-a 6x104 3x10-e 2x10-4 Gd 159..
S 5x104 2x104 2x10-6 8x10-5 1
4x104 2x104 1x10-8 8x10-5 Gallium (31)...
Ga 72.,
S 2x10-7 1x104 8x10-8 4x10-5 1
2x10-7 1x104 6x10-8 4x10-5 Germanium (32)...
Ge 71..
S 1x10-5 5x10-2 4xt o-i 2x104 I
-n
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
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MANUAL (ODCM)
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~~ y,, y Pace 98 of 197 TABLE 4.3 - OLD 100FR20 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]
isotopei Table 1 l
Table 11 Element (alomic number)
Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2-Water
( Cl/ml)
(pCi/ml)
(pCi/ml)
(pCi/ml)
Gold (79).
Au 196.....
S 1x104 5x104 4x104 2x10-4 1
6x1 F 4x10-3 2x104 1x104 Au 198......
S 3x10-7 2x104 1x104 5x104 i
1 2x10-7 1x10-3 8x104 5x104 l
Au 199..
S 1x1 H 5x104 4x10-a 2x10-4 1
8x10-7 4x104 3xtra 2x104 Hitnium(72)..
Hf181.
S 4x104 2x104 1x104 7x104 1
7x104 2x104 3x10-e 7x1g4 Holmium (67).
Ho 166..
S 2x10-7 9x1 H 7x104 3x104 1
2x10-7 9x10-4 6x10-o 3x10-3 Hydrogen (1)..
H3 S
5x104 1x10-1 2x10-7 3x104 1
5x104 1x10-1 2x10-7 3x10-3 Sub 2x10-3 4x10-5 Indium (49)
In 113m..
S 8x104 4x10-2 3x10-1 1x10-3 1
7x104 4x10-2 2x10-7 1x10-3 in 114m..
S 1x10-7 5x10-4 4x10-8 2x10-3 1
2x10-a 5x10-4 7x10-10 2x10-3 in 115m.
S 2x104 1x10-2 8x10-8 4xjo-4 1
2x10-a t xto-2 6x10-8 4xio-4 in 115.
S 2x10-7 3x104 9x10-0 gxio-5 1
3x10-8 3x104 1x10 8 9x10-5 lodnt(53).
1125.....
S 5x10-8 4x104 8x10-H 2x10-7 1
2x10-7 6x10-3 6x10-8 2x10-4 1126..
S 8x10-e 5x104 9x10-H 3x10-7 I
3x10-7 3x10-3 1x10-8 gx104 1129..
S 2x104 1 x10-3 2x10-H 6x10-8 7x104 6x10-3 2x10-e 2x10-4 1131..
S 9x10-0 6x10-3 1x10-10 3x10-7 1
3x10-7 2x10-3 1x104 6x10-5 1132..
9x10-7 5x10-3 3x10-s 2x10-4 1133-S 3x104 2x10-4 4x10-10 1x19 a i
2x10-7 1x104 7x10-e 4x10-5 1134..
S 5x10-7 4x10-3 6x10-e 2x104 1
3x104 2x10-2 1xj o-7 6x10-4 1135--
S 1x10-7 7x10-4 1 xig-o 4xjo-a 1
4x10-7 2x104 1x10-8 7xjoa indom(77)
Ir190:
S 1x104 6x104 4x10-8 2x10-4 1
4x10-7 5x10-3 1 x10-e 2x10-4 It192 S
3x10-a 1 x10-3 9x10-10 4x10-3 tr 194..
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 1gg gj@ggy TITLE:
NUMBER:
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OFFSITE DOSE CALCULATION H4 Wi Ws$..
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,a Pace 99 of 197 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRll 1992) [ CONT'D]
Appendix B - Concentrations in Air and Water Above Natural Background Cont'd l
(See footnotes at end of Appendix B]
Isotope Table i Table II A
i Element (atomic number) col.1 - Air Col. 2 - Water Col 1 - Air Col. 2 -Water
( Ci/ml)
(pCi/ml)
( Ci/ml)
(pCi/ml)
Iron (261--
Fe 55..
S 9x10-1 2x10-2 3x10-8 8x10-4 l
1x104 7x10-2 3x104 2x10-3 Fe 59 S
Krypton (36)....
Kr 85m..
Sub 6x104 1x10-7 Kr 85 -
Sub 1x10-5 3x10-7 Kr 87..
Sub 1x104 2x104 ffr 88..
Sub 1x10-e 2x10-8 Lanthanum (57)..
La 140..
S 2x10-7 7x10-4 5x104 2x10-3 1
1x10-7 7x104 4x10-8 2x104 Lead (82)..
Pb 203.
S 3x10-6 ixj g-2 gxjo-a 4x10-4 1
2x10-8 1x10-2 6x10-8 4xj o-4 Pb 210.
S 1x10- 0 4x104 4x10-12 1xio-7 1
2x10-10 5x10-3 8x10-12 2x10-4 Pb 212.
S 2x10-8 6x10d 6x10-10 2x10-3 I
2x10-8 5x10-4 7x10-10 2x10-3 Lutetium (71)..
Lu 177 S
6x10-7 3x10-3 2x10-8 i x to-4 1
5x10-7 3x10-3 2x104 1x10-4 Manganese (25)...
Mn 52..
S 2x10-7 1x10-3 7x10-8 3x104 i
1x104 9x10-4 5x10-e 3x104 Mn 54.
S 4x10-7 4x10-3 1x104 1x10-4 1
4x10-8 3x10-3 1x10-0 1xio-4 Mn56.
S 8x10-7 4x10-3 3x104 1x10-4 1
5x10-7 3x10-3 2x10-a 1 x10-4 Mercury (80)...
Hg 197m.
{
l 8x10-7 5x10-3 3x10-a 2x10-4 j
Hg197.
S 1x10-e gxj g-s 4xig-e 3x10-4 I
3x10-e 1x10-2 gxj o-a 5x10-4 Hg 203.
S 7x104 5x10-4 2x10-e 2x10-3 I
i 1x10-7 3x104 4x10-0 1x10-4 Molybdenum (42).-
Mo99.
S 7x10-1 5x104 3x1g-e 2x10-4 1
2x104 1x10-3 7x10-0 4x10-5 Neodymium (60)..
Nd144.
S 8x10-"
3x10-10 2x10-3 1x10-H 8x10-3 Nd 147.
S 4x104 2x10-3 1x10-8 gxio-3 I
2x10-7 2x10-3 8x10-8 6x10-3 Nd 149.
S 2x10-e 8x104 6x10-8 3x10-4 1
1x104 ex104 5x104 3x10-4 Neptunium (93) -
Np 237..
S 4x10-12 gxio-a ix10-13 3x10-6 1
1x10-10 9x10-4 4x10-12 3x10-5 Np 239.
7x104 4x104 2x10-a 1x10-4 Nickel (28)...
Ni 59 S
PRAIRIE ISLAND NUCLEAR GENERATING PLANT H PROCEDURES NORTHERN STATES POWER COMPANY
? TITLE:
NUMBER:
- j OFFSITE DOSE CALCULATION
_ qh ?
MANUAL (ODCM)
REv: 13 g@ J.. Msw w &,reactionAQ Pace 100 of 197 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) ICONT'D]
Appendix B - Concentrations in Air and Water Above Natural Background Cont'd (See footnotes at end of Appendix B]
lsotopei Table i Table ll Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 -Water Element (alomic number)
( Ci/ml)
( Cl/ml)
( Ci/ml)
(pCi/ml)
Ni 63_
S 6x104 8x10-4 2x10-e 3x104 1
3x10-7 2x10-2 jx1g4 7x104 Ni 65...
S 9x10-7 4x10-8 3x19.a j xto-4 I
Niobium (Columbium)(41).;
Nb 93m.
S 1x10-7 1x10-2 4xio-e 4x to-4 1
2x10-7 1x10-2 5x10-e 4x10-4 Nb95.
1x10-7 3x10-3 3x10-e j xto-4 Nb 97 S
5x10-e 3x10-2 2x10-7 0x10-d Osmium (76)...,
Os 185 S
6x10-a 2x10-3 2x104 7x10-3 Os191m..
S 2x10-5 7xto-2 6x10-7 3x10-3 1
9x10-6 7xjo-2 3x10-7 2x10-3 Os 191.
S 1x10-e 5x10-3 4x10-a 2x10-4 1
4x10-7 5x10-3 1x10-a 2x10-4 Os 193..
S 4x10-7 2x104 1x10-a 6x10-3 1
3x10-7 2x10-3 9x10-8 5x10-3 Palladium (46)..,
Pd103.
7x10-7 8x10-3 3x10-8 3x10-4 Pd 109..
S 6x10-7 3x104 2x10-a gxjo-3 1
4x10-7 2x10-3 1x10-e 7x10-3 Phosphorus (15)._--
P 32.
S 7x104 5x10-4 2x10-8 2x104 I
8x10-8 7x10-4 3x10-o 2x104 Piaunum(78).....
Pt191.
S 8x10-7 4 x10-3 3x10-8 1x10-4 1
6x10-7 3x10-3 2x10-8 ixjo-4 Pt 193m.
S 7x10-8 3x10-2 2x10-7 1x10-3 1
5x10-e 3xj o-2 2x10-7 1x10-3 Pt193..
S 1x10-6 3x10-2 4x104 9x10-4 1
3x10-7 5x10-2 1xj o-a 2x104 Pt 197m.
S 6x10-8 3x10-2 2x10-7 1x10-3 1
5x10-8 3x10-2 2x10-7 9x10-4 Pt197..
S 8x10-7 4x10-3 3x104 1x10-4 1
6x10-7 3x10-3 2xig-a 1x10-4 Plutonium (94)..
Pu 238.
S 2x1g-t a 1x10-4 7x10-14 5x104 1
3x10-"
S 2x10-12 1x10-4 6x10-14 5x10-8 1
4x10-11 8x10-4 1x10-12 3x10-5 Pu 240..
S 2x10-12 1x10-4 6x10-14 5x10 e 1
4x10-"
S 9x10-"
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES gs TITLE:
NUMBER:
qq q g _ [4 s@L OFFSITE DOSE CALCULATION H4 S?h[C[d[E&[
MANUAL (ODCM)
REv: 13 3.SectlOn
%MIME ' "# W Pane 101 of 197 TABLE 4.3 - OLD 10CFR20 APPENDlX B (APRIL 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 (pCuml)
(pCi/ml)
(pCi/ml)
( CVml)
Pu 242..
S 2x10-12 1xtoa 6x10-14 5x10-6 1
I Pu 243.
S 2x104 1x10-2 6x10-8 3x10-4 i
2x104 1 x10-2 8x10-a 3x10-4 Pu 244.
S 2x1012 1x1o-4 6x10-14 4x104 1
3x10-H 3x10-4 1x10-12 1xto-5 Polonium (84)...
Po 210..
S 5x10-80 2x10-3 2x10-H 7x10-7 1
2x10-10 8x10-4 7x10-12 3x10-5 Potassium (19).
K 42.
S 2x104 9x10-3 7x10-8 3x10-4 l
1x10-7 6x10-4 4x10-0 2x10-5 Praseodymium (59).
Pr 142..
S 2x10-7 9x10d 7x10-8 3x10-3 l
2x10-7 9x10-4 5x104 3x10-3 Pr 143..
S 3x10-7 1x10-3 1x10-a 5x10-3 1
2x10-7 1x10-3 6x10-e 5x10-3 Promethium (61).
Pm 147..
S 6x104 6x10-3 2x10-8 2x10-4 1
1x10-7 6x10-3 3x10-0 2x10-4 Pm 149..
S 3x10-7 1x10-3 1x10-8 4x1o-o I
2x10-7 1 x10-3 8x10-e 4x10-3 Protoacanium(91)...
Pa 230..
S 2x10-8 7x10-3 6x10-H 2x10-4 I
8x10-10 7x10-3 3x10-H 2x10-4 Pa 231.
S 1x10-12 3x10-5 4x10-14 9x10-7 1
1x10-10 8x10-4 4x10-12 2x10-5 Pa 233..
S 6x10-7 4x10-3 2x10-a j xig-4 1
2x10-7 3x10-3 6x10-e j x jo-4 Radum(88)..
Ra 223..
S 2x10-8 2x10-3 6x10-H 7x10-i l
2x10-10 1x10-4 8x10-12 4xjo-a Ra 224.
S 5x104 7x10-3 2x10-10 2x10-8 1
7x10-10 2x10-4 2x10-H 5x10-8 Ra 226..
S 3x10-H 4x10-7 3x10-12 3x10-a 1
5x10-H 9x10-4 2x10-12 3x10-5 Ra 228..
S 7x10-H 8x10-7 2x10-12 3x10-8 4x10-H 7x10-4 1x10-12 3x10-5 Radon (86) :
Rn 220...
S 3x10-7 1x104 Rn 2223..
Re 183..
S 3x104 2x10-2 gxio-a 6x10-4 1
2x10-7 8x10-3 5x10-0 3x10-4 Re 186.
S 6x10-7 3x10-4 2x10-a gx10-5 t
2x10-7 1 x10-3 8x10-9 5x10-5 Re 187..
S 9x104 7x10-2 3x10-7 3x10-3 t
5x10-7 4x10-2 2x10-a 2x10-3 Re 188.
S 4x10-7 2x10-3 1x10-8 6x10-3 1
7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE:
NUMBER:
$M$hSyndgg,
H4 OFFSITE DOSE CALCULATION FW$ 2 k 4;flg f@M@$(kgg"}.%p MANUAL (ODCM)
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Page 102 of 197 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]
lsotopel Table i Table 11 i
Element (atomic number)
Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 -Wr.ter (pCi/ml)
( Ci/ml)
(pCl/ml)
(pCVml)
I l
[
Rhodum(45).
Rh 103m S
6x104 3x10-1 2x104 1x10-2 Rh 105,.
S 8x10-7 4x104 3x104 1x10d i
5x10-7 3x104 2x10-8 1x10-d Rubidum(37).
Rb 86.,
S 3x10-7 2x10-3 1x10-a 7x jo-a i
7x10-a 7xj o-4 2x19-9 2x10-3 Rb 87..
S 5x10-7 3x10-3 2x10-s 1x104 1
7x10-a 5x104 2x1g o 2x10-4 Ruthenium (44)...
Ru 97..
2x10-8 1 xt o-2 6x10-a 3x10-4 Ru 103..
Ru 105..
S 7x10-7 3x104 2x10-8 1x10 4 1
5x t 0-7 3x10-3 2x10-s 1x10-4 Ru 106....
S 8x10-8 4x10-4 3x10-0 1xio-3 1
6x10-8 3x10-d 2x10-10 1x10-3 Samarium (62)-
Sm 147..
S 7x10-H 2x10-3 2x10-12 6x104 l
1 3x10-10 2x104 9x10-12 7x10-3 Sm 151.
S 6x10-8 1x10-2 2x10-e 4xjo-4 1
1x10-7 1x10-2 5x10-e 4x jo-4 Sm 153.
S 5x10-7 2x104 2x10-8 8x10-8 1
4x10-7 2x104 1x104 8x10-3 Scandum(21)..
Sc 46 -
2x10-8 1 x10-3 8x10-10 4x10-3 Sc 47..
Sc 48..
S 2x10-7 8x10-4 6x10-8 3x10-3 l
l 1x10-7 8x10-4 5x10-0 3x104 Selenium (34)
Se 75..
S 1x1&4 9x104 4x104 3x10-4 l
l Sdicon(14)...
Si 31.
S 6x10-e 3x10-2 2x10-7 9x10-4 i
i Silver (47)..
Ag 105..
S 6x10-1 3x10-3 2x10-8 1x10-4 l
l 8x10-8 3x104 3x10-e j x jo-4 Ag 110m..
S 2x10-7 9x10-4 7x104 3x10-3 1
1x104 9x10-4 3x10-10 3x104 l
Ag III.
2x10-7 1x10-3 8x10-e 4xjo-3 Sodum(11)..
Na 22.
S 2x10-1 1x10-3 6x10-8 4x10-3 1
0x10-8 9x10-4 3x10-10 3x10-3 l
Na 24.
S 1x104 6x104 4x10-a 2x10-4 l
l 1x10-7 8x10-4 5x10-e 3x10-5 l
l l
I
l PRAIRIE ISLAND NUCLEAR GENERATING PLANT i
NORTHERN STATES POWER COMPANY H PROCEDURES gg jpi@ g
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NUMBER:
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OFFSITE DOSE CALCULATION H4 ff;
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M Pace 103 of 197 TABLE 4.3 - OLD 10CFR20 APPENDIX B (APRIL 1992) ICONT'D1 i
~
Appendix B - Concentrations in Air and Water Above Natural Background Cont'd
[See footnotes at end of Appendix B]
lsotopet Table i Table 11 Element (atomic number)
Col.1 - Air Col. 2 - Water Col.1 - Air Col 2-Water
( Ci/ml)
(pCl/ml)
( CIAnl)
(pCi/ml)
Strontum(38)..--
Sr 85m..
S 4x10-6 2x104 1x104 7x104 1
3x10-8 2x101 1x104 7x10-3 Sr 85..
S 2x10-7 3x10-3 8x104 1x10-4 1
1x10-7 5x10-3 4x10-8 2x10-4 Sr 89.
S 3x104 3x10-4 3x10-10 3x10-e 3
Sr 90......
S 1x10-e j xto-s 3x10-11 3x10-7 1
5x10-e j xt o-3 2x10-10 4x10-5 Sr 91.
S 4x10-7 2x10-8 2x104 7x104 1
3x10-7 1 x10-3 9x10-0 5x10-3 Sr92; S
3x10-7 2x10-3 1x104 6x10-3 Sulfur (16).-
S 35.
S 3x10-7 2x104 9x104 6x104 1
3x10-7 8x104 9x10-o 3x10-4 Tantalum (73)...
Ta 182.,
2x10-a 1xio4 7xio-to 4x104 Technetium (43).--
Tc 96m.
Tc 96..
S 6x10-7 3x10-3 2x10-a j x j o-4 1
2x10-7 1x104 8x10-8 5x104 Tc 97m.
S 2x10-8 1 x10-2 8x10-a 4xto-4 I
2x10-7 6x10-3 5x104 2x10-4 Tc07..
S 1x10-5 5x10-2 4 x10-7 2x10-3 1
3x10-7 2x10-2 1 x10-a 8x10-4 Tc 99m..
S 4x10-5 2x10-1 1x104 6x10-3 1
1x10-5 8x10-2 5x10-7 3x10-3 Tc 99.
S 2x10-e jxjo-2 7xio4 3x10-4 I
6x104 5x104 2x10-0 2x10-4 Teilunum (52)..
Te 125m.
S 4x10-7 5x10-3 1x10-8 2x10-4 1
1x10-7 3x104 4x10-e t x10-4 Te 127m.
S 1x10-7 2x10-3 5x104 6x104 1
4x104 2x10-3 1x10-8 5x10-5 To127..
9x10-7 6x10-3 3x10-a 2x10-4 Te 129m...
S 8x10-8 1xj g-3 3x10-8 3x10-5 1
3x10-a 6x10-4 1x10-8 2x104 Te 129...
S 5x10-e 2x10-2 2x10-7 8x10-4 1
4x10-6 2x10-2 1 xio-7 8x10-4 To131m.
S 4x10-7 2x10-3 1 x10-8 6x10-5 1
2x10-7 1x10-3 6x10-e 4x10-5 Te132..
S 2x10-7 9x10-4 7x10-8 3x10-5 l
1x10-7 6x10-4 4 x10-8 2x10-5 i
1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES l
sum bW h
TITLE:
NUMBER:
@e c $ b @\\ %n FnWA OFFSITE DOSE CALCULATION H4 l
Di E E C b MANUAL (ODCM)
REW 13 1
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7 M M
Paae 104 of 197 l
t 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]
lsotope Teble i Table ll i
Element (atomic number)
Col.1 - Air Col. 2 - Water Col.1 - Air Col. 2 -Water
( Ci/ml)
(pCi/ml)
( Ci/ml)
(pCi/ml)
Terbium (65)..
Tb 160..
S 1x104 1x104 3x10-8 4x104 l
1 3x10-a j xjg4 jxio4 4xto-s l
Thalbum(81). -
Tl200 S
3x10-e j xjo-a gxina 4xjoa 1
1x104 7x10-3 4x10-a 2x104 Tl201 S
9x10-7 5x10-3 3x10-a 2x104 T1202..
S 8x10-7 4x10-3 3x104 1x10-4 i
Tl204..
S 6x10-7 3x10-3 2x10-a j x 3g-4 l
3x104 2x104 9x10-10 6x10-5 Thorium (90)
Th 227..
S 3x10-10 5x10-4 1x10-"
2x10-6 d
6x10-12 2x10-5 l
2x10-10 5x1C Th 228.
S 9x10-12 2x10-4 3x10-13 7x10-a i
6x10-12 4xj o-4 2x10-13 1x104 Th 230 S
2x10-12 5x10-5 8x10-14 2x10-a l
1x10-11 9x10-4 3x10-13 3x104 l
Th 231..
S 1x10-s 7xto-s 5x10-a 2x10-4 1
1x104 7x104 4x1g-a 2x10-4 Th 232..
S 3x10-H 5x10-5 1x10-12 2x10-a 1
3x10-H 1 x10-3 1x10-12 4x1o-5 Th natural..
S 6x10-H 6x104 2x10-12 2x10-a 6x10-H 6x10-4 2x10-12 2x10-5 Th 234..
S 6x10-a 5x10-4 2x10-e 2x10-5 1
3x10-8 6x10-4 1 x10-0 2x10-5 Thuhum(69).
Tm 170..
S 4x104 1x104 1x104 5x10-6 1
3x104 1x104 1x10-8 5x10-5 Tm 171..
S 1x10' 1 x10-2 4xto-e 5x10-4 1
2xR 1x10-2 8x104 5x10-4 Yin (50)
Sn 113..
S 4x10-1 2x104 1x10-8 9x10-5 1
5x10-a 2x104 2x10-e 8x10-5 Sn 125..
S 1x10-7 5x10-4 4x10-0 2x10-5 I
8x10-8 5x10d 3x10-8 2x10-5 Tungsten (Wolfram)(74)..
W 181.
S 2x104 1x10-2 8x10-8 4x10-4 1
1x10-7 1x10-2 4xto-o 3x10-4 W 185.
S 8x10-7 4x10-3 3x104 1x104 i
i 1x10-7 3x104 4x104 1x10-4 W 187..
S 4x10-7 2x104 2x10-a 7xjo-5 l
l 3x10-7 2x104 1 x10-a 6x104 Uranium (92)
U 230.
S 3x10-10 1x10-4 1x10-H 5x10-6 l
1 x10-10 1x10-4 4x10-12 5x10-a t
I
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES N g : g gjp g TITLE:
NUMBER:
g - go@d OFFSITE DOSE CALCULATION H4 Wh b
MANUAL (ODCM)
REV: 13
,ifihhhlbbIs
' up ~ -
'O Pace 105 of 197 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) 1 Isotope Table 1 Table 11 Element (alomic number)
Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 -Water
( Cl/ml)
(pCi/ml)
(pCl/ml)
(pCi/mi)
U 232..
S 1x10-10 8x10-4 3x10-12 3x10-6 1
3x10-"
8x104 9x10-13 3x10-5 U 233..
S 5x10-10 9x10-4 2x10-"
3x10-5 i
1x10-10 9x10-4 4x10-12 3x1g-5 U 234.
S4 6x10-10 9x10-4 2x10-"
3x10-5 1
1x1040 9x10d 4x10-12 3x10-5 U 235-S4 5x10-10 8x10-4 2x10-"
3x10-5 l
1x10-10 8x104 4x10-12 3x10-5 U 236.
S 6x1040 1 x10-3 2x10-"
3x10-5 l
1x10-10 1x10-3 4x10-12 3x10-5 U 238.....-.
S4 7x10-"
1x10-10 1x10-3 5x10-12 4x1o-5 U240 S
2x10-7 1x10-3 6x10-0 3x10-5 U natural..
S4 1x10-10 1x104 5x10-12 3x10-5 l
1x10-10 1x104 5x10-12 3x10-5 Vanadium (23)..
V 48.
S 2x10-7 9x10-4 6x10 e 3x10-5 1
6x104 8x10-4 2x10-e 3x10-5 Xenon (54)...
Xe 131m..
Sub 2x10-6 4xig-7 Xe 133..
Sub 1x10-5 3x10-7 Xe 133m..
Sub 1x10-5 3x10-7 Xe 135..
Sub 4x104 1x10-7 Ytterbium (70)...
Yb 175..
S 7x10-1 3x104 2x10-8 j xig-4 1
6x10-7 3x104 2x10-a jxjo-4 Yttrium (39) -
Y 90..
S 1x10-7 6x10-8 4x10-8 2x10-6 1
1x10-7 6x10-4 3x10-e 2x10-5 Y 91m.
S 2x10-5 ixj g-1 8x10-7 3x10-3 1
2x19-5 1xj o-1 6x10-7 3x10-3 Y 91.
S 4x10-8 8x10-4 1x10-o 3x10-5 1
3x10-a 8x10-4 1x10-e exjo-5 Y 92.
3x10-7 2x10-3 1x10-a 6x10-5 Y 93.
S 2x10-7 8x10-4 6x10-8 3x10-5 1
1x10-7 8x104 5x10-0 3x10-5 2snc(30)
Zn 65.
S 1x10-1 3x104 4 x10-8 1x10-4 1
6x10-8 5x104 2x10-e 2x104 Zn 69m..
S 4x10-7 2x10-3 1x10-8 7xjo-5 1
3x10-7 2x104 1 x10-8 6x10-5 Zn 69.
S 7x10-a 5xto-2 2x10-7 2x10-3 I
9x10-8 5x10-2 3x10-7 2x10-3 3rconium(40)..
Zr 93..
S 1x10-'
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
&W
@ R $ y. j M TITLE:
NUMBER:
[j Q L @M @ a p 3.m hg h
OFFSITE DOSE CALCULATION H4 MANUAL (ODCM)
REv: 13
' g" W
- M @ Nsectieah Pace 106 of 197 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]
lsotopet Table i Table 11 Element (atomic number)
Col.1 - Air Col. 2-Water Col.1 - Air Col. 2 -Water (pCi/ml)
(pCi/ml)
( Cl/ml)
(pCi/ml)
Zr 95..
S 1x10-7 2x10-3
~ 4x104 6x10-5 1
3x104 2x10-3 1x104 6x10-5 Zr o7.
S 1x10-7 5x10-4 4x10-8 2x10-5 l
9x104 5x10-4 3x10-e 2x10-5 Any single radionuclido not listed above with decay Sub 1x10-6 3x10-8 mode other than alpha emissloa or spontaneous fiwlon and with radioactive half life less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Any single radionuclide notlisted above with decay 3x10-8 9x10-5 jx10-10 3x10-e mode other than alpha emission or spontaneous fission cnd with radioactive half-life gmter it an 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Any single radionuclide not bled above, which decays 6x10-13 4x10-7 2x10-14 3x10-8 by (Ipha emission or spontaneous fission.
' Soluble (S): Insoluble (1).
2 Sub' means that values given are for submersion in a semisphedcalinfinite cloud of airbome material.
3These radon concentrations are appropriate for protection from radon.222 combined with its short lived daughters. Altematively, the value in Table 1 miy be replaced by one-third (1/3) " working level.' (A " working level
- is defined as any combination of short lived radon 222 daughters, polonium 218, lead-214, bismuth 214 and polonium 214, in one liter of air, without regard to the degree of equilibrium, that will result in the ultimate emission of 1.3 x 105 MeV of alpha partlcle energy.) The Table ll value may be replaced by one-thirtieth (1/30) of a " working level.* The limit or radon 222 concentrations in restricted areas may be based on an annual average.
dFor 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 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> workweek, Table Iis 0.2 milligtams uranium per cubic meter of air average. For any enrichment, the 3
product of the average concentration and time of exposure during a 40-hour workweek SHALL NOT, exceed 8 x 10 SA pCi-hr/ml, where SA is the specific activity of the uranium inhaled. The concentratico value for Table 11 is 0.007 milligrams uranium per cubic meter of air. The spe:ific activity for nituril 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<lepleted 2
SA=(0.4 + 0.38 E + 0.0034 E ) 1o-e E 0.72 2
where E is the percentage by weight of U-235, expressed as percent.
I g's.w.gmesa
- e. ~.
e -. ~.- -
I E._ G...Ud. dN_ p
""". l., PWPease ewe Apewuss dem M as leNews:
i 1.
If the identity and concentration of each radionudide in the mixture are known, the limiting values should be derived as follows: Determine, for each radonuclide in the mixture, the rstio between the quantity present in the mixture and the Emit otherwise established in Appendix B for the specific radonucide when not in a mixture. The sum of such ratbs for all the radionuclides in the mixture may not exceed *1'(i.e., Nnity")
EXAMPLE: If radionuclides A. B, and C are presentin concentrations C, O 8Md Oc, and if the applicable MPC's, are MPC, and MPCs and A B A
MPCc respectively, then the concentrations SHALL be limited so that the following relationship exists:
(C /MPC )+(OWPCs)+(Cc/MPCc)s1 A
A l
l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Q%p: < m.oWWigs@p:
TITLE:
NUMBER:
n p
..w g y:
sh OFFSITE DOSE CALCULATION H4 7$R m'; '?,
MANUAL (ODCM)
REV: 13 iSedion f suA
- 4!n
s~~ in of all active release points SHALL NOT be greater than unity. _q wg-v', (fy;pyipa$@@"When purging the Unit 1 containment via the Inservice purge system, the monitor setpoints may be g jJ gpg based on 4.6E+3 cfm for the duration of the release. t u tb 2 2 EyA 3a cm t,a l O i j .'.s 1
PR AIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES I pl7 TITLE: NUMBER: l ?gqly ]l7;+ w OFFSITE DOSE CALCULATION H4 J(9 Misiing '@h MANUAL (ODCM} REV: 13 fa p,g, g g g7 v
- gy ;
-s TABLE 5.2 - G ASEOUS SOURCE TERMS a u.. ,e m .? W.;;:AUXcBLDGB 3 SHIELD.BLDGn; y
- rAIRJEJECTOS2 f(A);(Cl/Yr)@ '
(((Aj)(Cl/Yr))! ~ RADIONUCLIDEF a ' i(A);(Cl/Yr)M i i 2EO Kr-85m 3EO Kr-85 2EO 2.2E1 Kr-87 1EO Kr-88 SEO 1EO 3EO 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 Cl/yr. 1 i, 4
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: , ?,ni > '.n.. C /gs e1 m-u. m. e ~ g ; pg ^ ' OFFSITE DOSE CALCULATION H4 iii MANUAL (ODCM) REV: 13 j[$}4, mMENE& % l-[%. y;; Page 110 of 197 TABLE 5.3 - CRITICAL ORG AN DOSE VALUES (Pn) for Child m imrem/vrf -4$f QV assOBh% '. JM ' - ?lSOTOREinn sPO ipCl/m3r H-3 1.12 E 3 Cr-51 1.70 E 4 Mn-54 1.58 E 6 Fe-59 1.27 E 6 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 Y-91 2.63 E 6 Zr-95 2.23 E 6 Nb-95 6.14 E 5 Ru-103 6.62 E 5 l Ru-106 1.43 E 7 Ag-110m 5.48 E 6 Te-127m 1.48 E 6 t Te-129m 1.76 E 6 l Cs-134 1.01 E 6 Cs-136 1.71 E 5 Cs-137 9.07 E 5 Ba-140 1.74 E 6 l Ce-141 5.44 E 5 Ce-144 1.20 E 7 l l-131 1.62 E 7 l l l l
d PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ' MID$$MfM$ 3. TITLE: NUMBER: $.3,df OFFSITE DOSE CALCULATION H4 o;M, dM m ~ ' -._n g MANUAL (ODCM) REV: 13 ' ' !Secti cKm: q< i pp m<< x,. Ve Page 111 of 197 TABLE 5.4-DOSE FACTORS FOR NOBLE GASES
- 1 I
stBeta' Air Dosei s Total. Body.Dosel gJ[b$NFb<6fl S, c; < 1 - s~ $p w w %w
- F ifs,ho?&va gii s2l e c idis
- Skl Gamma Air Dose % S[Fsst6R s 0
- aNhen im n no.. vglijg.g..g ' Facto,r Ml;' .~ u g g y g gj O ~ < ' *% g$,"lm;;;g ,e g(mrem /yr:pern (mradlyr per , i, _ dlyr p_er.a d per!
- ~mra P
2 ]$Cl/ni3)f fjlO.. _)jiQ 'I Mi/m8)jy' pCi/m8) ' ^ I 5$sied6ddf x Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 a 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 1 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 I 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 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 2
- The listed dose factors are for radionuclides that may be detected in gaseous effluents.
All others are 0. 3 e J
~ TABLE 53 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - -GROUND. ALL AfaES PATHWAY = GROUND NUCLIDE T. B O D Y GI-TRACT BONE LIVER ' KIDNEY THYROID ~ LUNG SKIN MN 54 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 08 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 l' 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 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 l I ( 3
- R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M2 -MREM /YR PER pCl/SEC FOR ALL OTHERS.
t + 5- <h I GG e.
TABLE 5.5 B_YALU.ES.EQBltfE_P_Bal -VEGETABLE. ADULT PATHWAY = VEGET - AGE GROUP EQUALS ADULT NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN f 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 i 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 l 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 i 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 l f 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 I131 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 i 3 2 R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS. i e i 0'C e.
........ - -. - ~ . -..-.._... -_ - - -=_ TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - VEGETABLE. TEEN PATHWAY = VEGET AGE GROUP EQUALS TEEN NUCLIDE T. BODY GI-TRACT BONE LIVER KlDNEY THYROID LUNG SKIN H 3 2.61E 03 2.61 E 03 0.00E 00 2.61E 03 2.61 E 03 2.61 E 03 2.61 E 03 2.61 E 03 l 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 4.145 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 1131 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 t CS137 4.90E 09 2.00E 08 1.06E 10 1.41E 10 4.78E 09 0.00E 00 1.86E 09 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER C1/SEC FOR ALL OTHERS.
Eb R
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * -VEGETABLE. CHILQ. 4 L PATHWAY = VEGET AGE GROUP EQUALS CHILD NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN l 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 t l 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 f 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 j l131 8.16E 07 1.28E 07 1.43E 08 1.44E 08 2.36E 08 4.75E 10 0.00E 00 0.00E 00 t I 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
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M2 -MREM /YR 3
PER Cl/SEC FOR ALL OTHERS. l $I !h = l J
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 i 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 l 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 CO 60 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 l 3 2
- R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER Cl/SEC FOR ALL OTHERS.
I i l l l l l ii h e. i
~ _. TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT. TEEN PATHWAY = MEAT AGE GROUP EQUALS TEEN NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN - H 3 1.94E 02 1.94E 02 0.00E 00 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 MN54 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 r 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 l 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 t i131 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 t 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER Cl/SEC FOR ALL OTHERS.
i 7 L nC a \\
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - MEAT. CHILD PATHWAY = MEAT AGE GROUP EQUALS CHILD NUCLIDE T. BODY GI-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 1.21 E 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 8.01E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 1.15E 08 2.17E 08 0.00E 00 3.91E 07 0.00E 00 0.00E 00 0.00E 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 8.21E 06 1.35E 07 2.71E 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 t 3 2 R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER Cl/SEC FOR ALL OTHERS. i l l
- 5. ? ?
i TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * -COW MILK. ADULT PATHWAY = COW MILK AGE GROUP EQUALS ADULT NUCLIDE T. B O D Y 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 3.31E 07 0.00E 00 0.00E 00 9.26E 06 0.00E 00 CO 58 5.15E 06 4.66E 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 1 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 f 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 t CS137 3.87E 09 1.14E 08 4.32E 09 5.91E 09 2.01 E 09 0.00E 00 6.67E 08 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER pCI/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS.
i. o r c1s ee e. a
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 MN 54 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 1131 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 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. sb e.
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - COW MILK. CHILD r i PATHWAY = COW MILK AGE GROUP EQUALS CHILD NUCLIDE T. BODY 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 l MN54 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 5.91E 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 I131 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 l 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 I 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR l
PER pCl/SEC FOR ALL OTHERS. i f i n 1
== a a
TABLE 55 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 MN54 4.77E 06 7.73E 06 0.00E 00 2.11 E 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 l131 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 2.01 E 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 3 2 R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS. =c s. a
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * -GOAT MILK. ADULT PATHWAY = GOATMILK AGE GROUP EQUALS ADULT NUCLlDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN H 3 1.56E 03 1.56E 03 0.00E 00 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.56E 03 MN 54 1.04E 05 1.67E 06 0.00E 00 5.45E 05 1.62E 05 0.00E 00 0.00E 00 0.00E 00 FE 59 1.65E 05 1.44E 06 1.83E 05 4.31E 05 0.00E 00 0.00E 00 1.20E 05 0.00E 00 CO 58 6.18E 05 5.59E 06 0.00E 00 2.76E 05 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO 60 2.45E 06 2.09E 07 0.00E 00 1.11 E 06 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 89 4.21 E 07 2.35E 08 1.47E 09 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR 90 1.47E 10 1.73E 09 5.98E 10 0.00E 00 0.00E 00 0.00E 00 0.00E 00 0.00E 00 1131 1.43E 08 6.60E 07 1.75E 08 2.50E 08 4.29E 08 8.20E 10 0.00E 00 0.00E 00 CS134 1.82E 10 3.89E 08 9.33E 09 2.22E 10 7.19E 09 0.00E 00 2.39E 09 0.00E 00 I CS137 1.16E 10 3.43E 08 1.30E 10 1.77E 10 6.02E 09 0.00E 00 2.00E 09 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS.
l ~
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK. TEEN i l PATHWAY = GOATMILK AGE GROUP EQUALS TEEN NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROID LUNG SKIN 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 l 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 3.81E 10 1.21 E 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 3 2 R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M --MREM /YR l PER Cl/SEC FOR ALL OTHERS. 5?I 1 a-"
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK. CHILD PATHWAY = GOATMILK AGE GROUP EQUALS CHILD i NUCLIDE T. B O D Y GI-TRACT BONE LIVER KIDNEY THYROlD 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 3.81 E 05 0.00E OG 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 217E 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 i 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 l l131 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 0.00E 00 6.35E 09 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER Cl/SEC FOR ALL OTHERS.
=c 3 5
TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT * - GOAT MILK. INFANT PATHWAY = GOATMILK AGE GROUP EQUALS INFANT 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 MN 54 5.73E 05 9.28E 05 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 2.21 E 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 1.15E 10 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS.
sb 5
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 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER Cl/SEC FOR ALL OTHERS.
l e e Gh e.
r TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLAHI* -INHALATION. TEEN PATHWAY = INHAL AGE GROUP EQUALS TEEN NUCLIDE T. B O D Y 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 1.51E 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 2.41E 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 i l t CS137 3.11 E 05 8.47E 03 6.69E 05 8.47E 05 3.04E 05 0.00E 00 1.21E 05 0.00E 00 i
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M2 -MREM /YR 3
l PER pCl/SEC FOR ALL OTHERS. l =a a m 1 m
TABLE 5.5 R VALUES FOR THE PRAIRIE.lSLAND 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 MN 54 9.50E 03 2.29E 04 0.00E 00 4.29E 04 1.00E 04 0.00E 00 1.57E 06 0.00E 00 I 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 j CO 60 2.26E 04 9.61 E 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 l SR 90 6.43E 06 3.43E 05 1.01E 08 0.00E 00 0.00E 00 0.00E 00 1.47E 07-0.00E 00 i 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 1.01E 06 3.03E 05 0.00E 00 1.21E 05 0.00E 00 CS137 1.28E 05 3.61E 03 9.05E 05 8.24E 05 2.82E 05 0.00E 00 1.04E 05 0.00E 00 3 2
- R VALUES IN UNITS OF MREM /YR PER Cl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS.
I j = r 'S
~ TABLE 5.5 R VALUES FOR THE PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- l
-INHALATION. INFANT l f PATHWAY = INHAL AGE GROUP EOUALS 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 6.11 E 05 1.72E 05 0.00E 00 7.12E 04 0.00E 00 l l 3 2
- R VALUES IN UNITS OF MREM /YR PER pCl/M FOR INHALATION AND TRITIUM, AND IN UNITS OF M -MREM /YR PER pCl/SEC FOR ALL OTHERS.
l sa E 5
TABLE 7.1 - FtADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS Page 1 of 4 Exposure Pathway; lNurnbeE of Ssmpies; . JSantpling'andf... 1Typeland Frikidencyli% ~ Pand/pr Samply i, 'and Sample Locations ** ^(Collection Frequencyj l } ~ lof Analysisgg)jf
- 1. AIRBORNE Samples from 5 locations:
Continuous Sampler operation Radiciodine analysis weekly Radiciodine and 3 samples from offsite locations (in with sample collection weekly for 1-131 Particulates different sectors) of the highest calculated annual average ground Particulate: level D/O, Gross beta activity on each filter 1 sample from the vicinity of a weekly *. Analysis SHALL be community having the highest performed more than 24 hours calculated annual average following filter change. Perform ground-level D/O, and 1 sample gamma isotopic analysis on from a controllocation specified in composite (by location) sample the ODCM quarterly.
- 2. DIRECT RADIATION 32 TLD stations established with Quarterly Gamma dose duplicate dosimeters placed at the quarterly following locations:
l
- 1. Using the 16 meteorological wind sectors as guidelines, an inner l
ring of stations in the general area of the site boundary is established and an outer ring of stations 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
- 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.
sb a to y
TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS [ CONT'D] Page 2 of 4 I ExposOre PattiWdy!; ~ /Nuin6dof sam'plAs577^ - ,.jSimpildi5 rid 7% T { STEAniWiNkbiBbCf5 h a , LaQSample Locations **?. . JCellection F_requencyn1 %s'~ ?of Analy, sis ( u, 'Wii
- " m, and/or. Sample'; l m
~ - _ _ - . u m. #m m umsm. .wa
- 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 i
- b. Ground 3 samples from wells within 5 miles Quarterly Gamma isotopic and tritium of the plant site and 1 sample from analyses of each sample a well greaterthan 10 miles for the plant site
- c. Drinking 1 sample from the City of Red Wing Monthly Composite of weekly I-131 Analysis and Gross beta water supply samples and gamma isotopic analyses of each monthly composite Tritium analysis of quarterly composites of monthly-composites L
" Sample locations are further described by the REMP. Im1 1: 3* $b a e~
TABLE 7.1 - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLE COLLECTION AND ANALYSIS [ CONT'D] Page 3 of 4 ' JEir$sure~ Pathway'
- Numbeof Sampibss. '~
^[(. Ssinplinglsndi "" "~ lyse add FrequMy"j 1 and/or Sample; and Sample' Locations **Q iCollection Frgueng 4 j]lof Analysis]pwg ?,l
- 3. WATERBORNE
[ Cont'd]
- d. Sediment from One sample upstream of plant, one Semiannually Gamma isotopic analysis of shoreline sample downstream of plant, and each sample one 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/O, one sample from each are on pasture analysis of each sample of 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 Semiannually Gamma isotopic analyses on Invertebrates fish located upstream and each sample (edible portion downstream of the plant site only on fish)
One sample of Invertebrates upstream and downstream of the plant site
- Sample locations are further described by the REMP.
sb a e~
SAMPLE COLLECTION AND ANALYSIS TCONT'D] Page 4 of 4 $" Exposure PathMiiy I * ' ]N0mlNFOf'Sem#es : l. I ~.._.fSaEsIS5hdf[" W'Waind FAA Uehicil"9 ~ I l {and/or Sample; and Sample Locationsy iCollection.Frequeng (yAnalysisfgg]
- 4. INGESTION
[ Cont'd]
- c. Food Products One sample of corn from any field At time of harvest Gamma isotopic analysis of that is irrigated by water into which edible portion of each sample liquid plant wastes have been discharged *"
One sample of broad leaf At time of harvest 1-131 analyses of edible portion ~ vegetation from highest D/O garden of each sample and one sample from 10-20 miles Sample locations are further described by the REMP. "* As determined by methods outlined in the ODCM. 1: $* $b a as
TABLE 7.2-REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATION IN ENVIRONMENTAL SAMPLES WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS 3 ANALYSIS (pCl/1) OR GASES (pCl/m ) (pC1/kg, wet) (pCl/1) (pCi/kg, 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-Nt>-95 400(b) 1-131 20( ) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 i Ba-La-140 200(b) 300(b) l (a) No drinking water pathway exists. l (b) Total for parent and daughter. l l l ac e.
TABLE 7.3 - DETECTION CAPABILITIES FOR ENVIRONMENTALSAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)(:) WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT 3 ANALYSIS (pCi/1) OR GASES (pCl/m ) (pCi/kg, wet) (pCi/1) _ (pCi/kg, wet) (pCl/kg, dry) Gross Beta 4 0.01 30,000(a) H-3 3,000(b) 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(b) 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) =c 'S
t 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. l For a particular measurement system (which may include radiochemical separation): LLD = E. V. 2.22. Y. exp (,1 A f) Where: LLD is the apriori lower limit of detection as defined above (as picocurie per unit mass or volume), sb s the standard deviation i 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 I 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), i lis the radioactive decay constant for the particular radionuclide, and At is the elapsed time between sample collection (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, 59Fe, 58Co, 60Co,65Zn,95Zr-Nb, 337Cs,134Cs, and 140Ba-La. Other peaks which are measurable and identifiable, l together with the above nuclides, SHALL also be identified and reported. t $b = S
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES 4'- eg TITLE: NUMBER: % :::e Q'g ~ MANUAL (ODCM) REV: 13 OFFSITE DOSE CALCULATION H4
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- FIGURE 3.2-PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE BOUNDARY FOR GASEOUS EFFLUENTS N __ / 3i
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: Wy g!lfSQqqsgyjt 'thg e g_ D b 4 OFFSITE DOSE CALCULATION H4 p;Wh flpj;% MANUAL (ODCM) REV: 13 4f4iMeeeich! a %Mi%ff?X"s"" Pace 140 of 197 APPENDIX A-METEOROLOGICAL ANALYSES Table A-1 Release Conditions Table A-2 Unrestricted Area Boundaries Table A-3 Long Teim - Ground Level-Unrestricted Area Boundary--x/O and D/O Table A-4 Long Term - Ground Level-Standard Distances - y/Q 3 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 Table A-7 Short Term - Ground Level - Standard Distances - x/q ~ Table A-8 Short Term - Ground Level-Standard Distances - D/q
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES $$!fy"Ej@WM T R E: NUMBER: c, ; Th ,gdjg OFFSITE DOSE CALCULATION H4
- EskiW@p 7 MANUAL (ODCM)
REV: 13 i p q?r @ w uss ' @~ dit ' ' Pace 141 of 197 APPENDIX - A Summarv of Dispersion Calculational Procedures 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 correction factors were also applied as available as default values in XOODOQ. Dispersion calculations were based on ground level releases for the shield buildings, turbine 4 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 (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 XOODOQ. Data were collected and AT i stability classes were defined in conformance with NRC Regulatory Guide 1.23. Dispersion i 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). i r f
1 PRAIRIE ISLAND NUCLEAR GENERATING PLA>!T NORTHERN STATES POWER COMPANY H PROCEDURES !$u@j{% leM[$(isin @$3 TITLE: NUMBER: k h OFFSITE DOSE CALCULATION H4
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MANUAL (ODCM) REY: 13 %pi:j:$/ ( Pace 142 of 197 REFERENCES 1. Sagendorf, J.F. and Golf, J.T., XOODOO Program for the Evaluation of Routine Effluent Releases at Nuclear Power Stations. NUREG-0324, U.S. Nuclear Regulatory Commission, September 1977. l l t i 1 l l t i l l t 1
TABLE A PRAIRIE ISLAND REI FAM CONDIT'9NS 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 Structures Adjacent to Adjacent to Adjacent to Auxiliary Building Auxiliary Building Auxiliary Building Exit Velocity (m/sec) N.A. N.A. N.A. Internal Stack Diameter (m) N.A. N.A. ' N.A. Building Cross-Sectional Area (m ) 2,170 2,170** 2,170** 2 Purge Frequency *** (times /yr) 20 N.A. N.A. l Purge Duration *** (hours / release) 5 N.A. N.A. l l Height of Shield Buildings Shield Building cross-sectional area Applied to short-term calculations only EI m:.< Dg ~ a iss
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: j 3@ A,g;./yi,(h., 'l OFFSITE DOSE CALCULATION H4 f5fp - f' MANUAL (ODCM) REv: 13 m':jesecu,an?- m .WM Page 144 of 197 TABLE A DISTANCES (MILES) TO CONTROLLING UNRESTRICTED AREA BOUNDARY LOCATIONS As Measured from Edge of Plant Complex Sector Dhtaura N 0.28 NNE 0.26 NE 0.84* ENE 0.62* E 0.59* 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 l l l l I l l l 1 l
TABLE A-3-N!QtLPABAMEIEBS Prairie Island Dispersion Parameters for Long Tenn Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /OTR for Unrestricted Area Boundary Locations (identified in Table A-2) Unrestricted Area y/O (sec/mh D/Q (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 SSW 7.08E-06 2.55E-08 SW 7.66E-06 2.77E-08 WSW 1.13E-05 3.53E-08 W 2.66E-05 7.63E-08 WNW 3.38E-05 1.42E-07 NW 2.13E-05 9.02E-08 NNW 1.11 E-05 5.43E-08 Pariod of Record: 4/1/77 - 3/31/78 t as &C e.
TABLE A PRAIRIE ISLAND DISEERSION PARAMETERS 3 Prairia Island Dispersion Parametars (x/O), SEC/M, for Long Term Ground Lcvel R: leases ( > 500 HrsNr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles l l Sector DA Q,2 M QA M Q& Q1 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 l E 2.40E-04 6.89E-05 3.34E-05 2.02E-05 1.38E-05 1.02E-05 7.88E-06 l ESE 4.52E-04 1.30E-04 6.28E-05 3.80E-05 2.59E-05 1.92E-05 1.48E-05 1 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 1 l 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 5.31 E-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 EI 1s
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TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 3 Prairie Island Dispersion Parameters (x/Q), SEC/M, for Long Term Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles S99_t91 Q& QS 10 11 12 13 14 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 5.58E-06 4.58E-06 3.82E-06 3.25E-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 7.54E47 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 l 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 2.71 E-06 2.18E-06 1.79E-06 1.50E-06 1.28E-06 Period of Record: 4/1/77 - 3/31/78 i G. $L E"
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] Prairia Island Dispersion Paramet rs (x/Q), SEC/Ma, for Long Tcrm Ground Level R leases > 500 Hrs /Yr or > 150 Hrs /OTR for Standard Distances (As Measured from Edge of Plant Complex) l Miles i Sector M 14 .LI la la 2a 2.1 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 4.41 E-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 1.31 E-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 3.24E47 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 l WSW 6.82E-07 5.93E-07 5.21 E-07 4.61 E-07 4.13E-07 3.74E-07 3.40E-07 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 EI 33 e.
TABLE A PRAIRIE ISLAND DISPERSION PARAMFTERS [ CONT'D] l Prairia Island Dispersion Parametars (X/0), SEC/M3, for Long Term Ground Lcv;l R: leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) ( Miles l l Sector 2,2 2a 2d 24 24 2.I 2a N 3.42E-07 3.14E-07 2.89E-07 2.67E-07 2.47E-07 2.30E-07 2.15E-07 NNE 2.30E-07 2.11 E-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 i ENE 2.20E-07 2.01 E-07 1.85E-07 1.71 E-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 1.21 E-06 1.11 E-06 1.03E-06 9.51 E-07 8.84E-07 8.25E-07 7.71 E-07 SE 1.28E-06 1.18E-06 1.09E-06 1.01 E-06 9.37E-07 8.74E-07 8.17E-07 SSE 6.86E-07 6.31 E-07 5.82E-07 5.39E-07 5.01 E-07 4.67E-07 4.37E-07 i S 2.96E-07 2.71 E-07 2.50E-07 2.31 E-07 2.15E-07 2.00E-07 1.87E-07 SSW 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 3.11 E-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 7.41 E-07 6.83E-07 6.32E-07 5.87E-07 5.47E-07 5.12E-07 NNW 5.01E-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 l hk cis eo a i g ~
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 3 Prairia Island Dispersion Paramet:rs (x/O), SEC/M, for Long Term Ground Level R: leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)- Miles Sector 2a M 3.1 3,2 3,3 M 35 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 1.02E47 9.65E-08 NE 1.29E 1.21 E-07 1.14E-07 1.08E 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 1.24E47 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 l 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 2.46E-07 2.32E-07 2.20E-07 2.09E-07 l k Period of Record: 4/1/77 - 3/31/78 @s I 3G r S j f
W TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 3 Prairis Island Dispersion Paramet:rs (x/O), SEC/M, for Long Term Ground Lcv::t R: leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 24 a.I 3a 3a da L1. 12 N 1.35E-07 1.28E-07 1.22E-07 1.16E-07 1.11 E-07 1.07E--07 1.02E-07 l NNE 9.18E-08 8.74E-08 8.34E-08 7.97E-08 7.62E-08 7.30E-08 7.00E-08 NE 8.75E-08 8.34E-08 7.96E-08 7.61 E-08 7.28E-08 6.98E-08 6.70E-08 ENE 8.66E-08 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 2.78E47 2.65E-07 2.53F-07 2.42E-07 2.32E-07 2.22,E-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 8.31 E-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 'N 2.83E-07 2.70E47 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 II o!.< an e.
Prairia Island Dispersion Parameters (x/Q), SEC/Ma, for Long Term Ground Level R leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles - Sector M M M M LZ M 11 EQ l 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 6.31 E-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 2.9 i 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 6.68E48 - 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 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 - 3/31/78 $E 1s
- a 9.
3s
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS l 2 l Prairie Island Dispersion Parameters (D/O),1/m, 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 DJ Q,2 DJ Qa DJ Q& D.I. N 5.38E-07 2.01 E-07 1.09E-07 6.97E-08 4.87E-08 3.62E-08 2.81 E-08 i 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 2.01 E-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 1.51 E-08 i E 6.15E-07 2.30E-07 1.25E-07 7.97E-08 5.57E-08 4.14E-08 3.22E-08 i ESE 1.12E-06 4.19E-07 2.27E-07 1.45E-07 1.02E-07 7.54E-08 5.86E-08 l SE 1.22E-06 4.55E-07 2.47E-07 1.58E-07 1.10E-07 8.19E-08 6.36E-08 l 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 .4.06 E-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 l W 5.00E-07 1.87E-07 1.01 E-07 6.47E-08 4.53E-08 3.36E-08 2.61 E-08 l 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 1.61 E-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 1 Period of Record: 4/1/77 - 3/31/78 $ ?I I 1.< aC s. 3
TABLE A PRAIRIE ISLAND DISPERSION PARAMETE13S [ CONT'D] 2 Prairia Island Dispersion Parameters (D/Q),1/m, for Long Term Ground Lev:1 R: leases > 500 HrsNr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M 10 .L1 .t2 M 14 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 2.51 E-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 2.11 E-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 5.81 E-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 2.71 E-09 2.25E-09 W 1.98E-08 1.45E-08 1.10E-08 8.65E-09 6.93E-09 5.67E-09 4.71 E-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 2.31 E-08 1.76E-08 1.38E-08 1.10E-08 9.02E-09 7.49E-09 NNW 2.19E-08 1.61 E-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 EI 1s 2G e.
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairie Island Dispersion Parameters (D/Q),1/m, 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 2a 2.1 N 4.27E-09 3.65E-09 3.14E-09 2.73E-09 2.40E-09 2.12E-09 1.89E-09 NNE 2.69E-09 2.30E49 1.98E-09 1.72E-09 1.51 E-09 1.33E-09 1.19E-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 t 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 1.21 E-09 1.06E-09 9.41 E-10 8.37E-10 W 3.97E-09 3.39E-09 2.92E-09 2.54E-09 2.23E-09 1.97E 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 2.81 E-09 2.47E-09 2.18E-09 1.94E-09 Period of Record: 4/1/77 - 3/31/78 t f l;' ** = S
TABLE A PRAIRIE ISLAND DISPERSION PARAM> 1 ERS [ CONT'D1 Prairia Island Dispersion Parametars (D/O),1/m, for Long Turm Ground Level R:: leases 2 > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles -- Sector 2,2 22 24 25 2& 22 21 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 S 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 EI o 1.< aG e. a
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairia Island Dispersion Parameters (D/Q),1/m, for Long Tcrm Ground Lev:1 R ; leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 2a M M 12 M M M 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 l 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 I 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 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 l SW 3.54E-10 3.27E-10 3.04E-10 2.82E-10 2.63E-10 2.46E-10 2.30E-10 i 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 1.01 E-09 i 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 i 1 e1s e O A S l
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 2 Prairia Island Dispersion Param:;tcrs (D/Q),1/m, for Long Tcrm Ground Lev;l R:: leases > 500 Hrs /Yr or > 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M LI M M M M M 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 2.54E-10 2.41 E-10 l NE 2.22E-10 2.09E-10 1.97E-10 1.86E-10 1.75E-10 1.66E-10 1.57E-10 i 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 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 1.81 E-10 1.71 E-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 5.01 E-10 4.71 E-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 l 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 l l !.< E E aG e. 1
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT *D] 2 Prairia Island Dispersion Pararnet::rs (D/O),1/m, for Long Term Ground Lov:1 R:leses > 500 Hrs /Yr or > 150 Hrs /OTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M M M 4.Z M 4A M 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 i NNE 2.29E-10 2.17E-10 2.07E-10 1.97E-10 1.88E 1.80E-10 1.72E-10 1.64E-10 l NE 1.49E-10 1.42E-10 1.35E-10 1.29E-10 1.23E-10 1.17E-10 1.12E 1.07E-10 ENE 1.94E-10 1.85E-10 1.76E-10 1.68E-10 1.60E 1.53E 1.46E-10 1.40E-10 l 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 o 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 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 i 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 l 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 i 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 i ~ I 2=2 ii 3
- h:
0
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS l Prairie Island Dispersion Paramet::rs for Short Term Ground LGvel Releases s 500 Hrs /Yr or s 150 Hrs /QTR for Unrestricted Area Boundary Locations (identified in Table A-2) l l Unrestricted Area l Boundary Sector 3 2 Sector yjg (sec/m ) D/q (1/m ) N 7.09E-05 4.60E-07 NNE 7.32E-05 4.11 E-07 l NE 1.60E-05 6.77E-08 l ENE 1.97E-05 1.11 E-07 E 4.92E-05 1.99E-07 l 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 l A l'I i.< 8C e. a
TABLE A 3 Prairie Island Dispersion Param:,ters (x/q), sec/m, for Short Tcrm Ground Lev:1 R; teases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector D,1 D,2 D2 QA M Q& D1 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 SSW 4.54E-04 1.43E-04 8.26E-05 5.34E-05 3.60E-05 2.85E-05 2.31 E-05 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 1.71 E-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 EI 1s ?G e. Os
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D1 / 3 Prairia Island Dispersion Paramet:;rs (X q), sec/m, for Short T;rm Ground Lcvel R: leases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles 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 5.91 E-06 l 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 l ESE 4.35E-05 3.58E-05 2.98E-05 2.54E-05 2.19E-05 1.91 E-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 l SSW 1.89E-05 1.54E-05 1.29E-05 1.10E-05 9.05E-06 7.93E-06 7.02E-06 l 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 9.41 E-06 W 4.01 E-05 3.24E-05 2.70E-05 2.30E-05 1.89E-05 1.65E-05 1.46E45 l WNW 3.44E-05 2.75E-05 2.31 E-05 1.96E-05 1.68E-05 1.48E-05 1.31 E-05 l NW 3.15E-05 2.57E-05 2.17E-05 1.85E-05 1.60E-05 1.40E-05 1.24E-05 i 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 L i I i.< an e. e y
TABLE A PRAIRIE ISLAND DISPERSION PARAMUERS ICONT'D] / 3 Prairie Island Dispersion Parameters (X q), sec/m, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)~ i Miles l-Sector 14 14 LZ 14 11' 2a 2.1. f N 5.27E-06 4.74E-06 4.30E-06 3.91 E-06 3.59E-06 3.32E-06 3.07E-06 ~ f NNE 4.70E-06 4.22E-06 3.82E-06 3.47E 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 7.25E46 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 t 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 I WSW 8.41 E-06 7.58E-06 6.87E-06 6.27E-06 5.77E-06 5.17E-06 4.80E-06 i l W 1.30E-05 1.17E-05 1.06E-05 9.62E-06 8.83E-06 8.33E-06 7.73E-06 i WNW 1.17E-05 1.05E-05 9.65E-06 8.80E-06 8.08E-06 7.42E-06 6.89E-06 l NW 1.11 E-05 1.00E45 9.09E-06 8.30E-06 7.63E46 7.13E-06 6.62E-06 { NNW 7.89E-06 7.11 E-06 6.47E-06 5.89E-06 5.41 E-06 5.01 E-06 4.64E-06 j Period of Record: 4/1/77 - 3/31/78 j i ? t 8C e. t 2 ~ - - - - ^ ^ ^ ~ ^ ^ ^ ^ - ^ ^ ^ ^ ^ ^ ^ ^ ^ '
TABLE A PRAIRIE ISLAND DISPERSION PARAh-tRS [ CONT'D1 3 Prairia Island Dispersion Paramsters (x/q), sec/m, for Short Tcrm Ground Lcvel R leases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex)- Miles Sector 2.2 2.2 2a 24 24 2.I .24 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 8.35E46 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 5.02E46 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-06 3.57E-06 3.46E-06 3.00E-06 2.83E-06 Period of Record: 4/1/77 - 3/31/78 @I o i s 3 5
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [CONTD] 3 Prairia Island Dispersion Paramst:rs (x/q), sec/m, for Short Term Ground Lcv:1 R: leases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) t c Miles Sector 2a 3a M 3.2 M M M l N 1.74E-06 1.66E-06 1.58E-06 1.50E-06 1.43E-06 1.37E-06 1.31 E-06 NNE 1.57E-06 1.50E-06 1.43E-06 1.36E-06 1.30E-06 1.24E-06 1.19E-06 NE-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 3.19E-06 3.04E-06 2.91 E-06 2.79E-06 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 l 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 3.47E46 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
- ?I a
aG e. 13s
TABLE A PRAIRIE ISLAND DISPER31hl PARAMETERS [ CONT'DJ / 3 Prairia Island Dispersion Parametsrs (X q), sec/m, for Short Term Ground Lev:1 Rr. leases s 500 Hrs /Yr ors 150 Mrs/QTR for Standard Distances (As Measured from Edge of Plant Conplex) Miles Sector 34 2.Z 32 M da il 12 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 j ENE 1.11 E-06 1.07E-06 1.02E-06 9.83E-07 3.46E-07 9.11 E47 8.79E-07 l E 2.67E-06 2.57E-OS 2.47E-06 2.38E-06 k29E-06 2.21 E-06 2.13E-06 l ESE 3.94E-06 3.785-06 3.64E-06 3.50E-06 0.38E-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-63 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 2.81 E-06 2.70E-06 2.60E-06 2.51 E-06 2.42E-06 2.33E-06 NW 2.82E-06 2.71 E-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 !E i 5 8G e. -4 N
.=. I i TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 3 Prairie Island Dispersion Parameters (x/q), sec/m, for Short Term Ground Level Releases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) i Miles l Sector M M M .41 M M j N 9.59E-07 9.27E-07 8.97E-07 8.68E-07 8.41 E--07 8.16E-07 7.92E-07 l 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 8.47E-07 8.18E-07 7.91 E-07 7.66E-07 7.41 E-07 7.18E-07 6.97E-07 l E 2.06E-06 2.00E-06 1.93E-06 1.87E-06 1.82E-06 1.76E-06 1.71 E-06 i 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 2.01 E-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 l 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-OS 1.12E-06 1.09E-06 1.05E-06 1.02E-06 9.91 E-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 I i.< 0C S 4
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS TCONT'D1 3 Prairia Island Dispersion Param;t:rs (x/q), sec/m, for Short Term Ground Lcvel R:le:ses s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector LQ N 7.67E-07 NNE 6.99E-07 NE 8.97E--07 ENE 6.76E-07 E 1.67E-06 l ESE 2.45E-06 S 9 S 1.05E-06 l SSW 9.39E-07 i SW 9.35E-07 l WSW 1.27E-06 W 2.11 E-06 WNW 1.81 E-06 l NW 1.74E-06 NNW 1.17E-06 l Period of Record: 4/1/77 - 3/31/78 l r C \\ 1s l E$ 9. Os + m
TABLE A PRAIRIE ISLAliD DISPERSION PARAMETERS 2 Prairie Island Dispersion Param:t:rs (D/q),1/m, for Short Turm Ground Level R: leases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) i Miles I c l Sector M M M M M M DJ N 1.68E-06 6.63E-07 4.32E-07 3.00E-07 2.18E-07 1.69E-07 1.29E-07 NNE 1.33E-06 5.43E-07 3.46E-07 - 2.40E-07 - 1.72E-07 1.36E-07 1.03E-07 l NE 1.19E-06 4.68E-07 3.05E-07 2.06E-07 1.45E-07 1.14E-07 9.10E-08 l ENE 1.20E-06 4.86E-07 3.17E-07 2.23E-07 1.58E-07 1.23E-07 9.49E-08 .i E 2.08E-06 8.09E-07 5.21 E-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 1.92E-07 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 8.51 E-08 SW 1.05E-06 4.42E-07 2.85 E-07 1.91 E-07 1.31 E-07 1.04E-07 8.55E-08 WSW 1.24E-06 5.19E-07 3.24 E-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 1.48E47 WNW 2.42E-06 9.62E-07 6.10E-07 4.14E-07 2.99E-07 2.31 E-07 1.81 E-07 I 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 2.21 E-07 1.72E-07 1.34E-07 i Period of Record: 4/1/77 - 3/31/78 l $ ?E s S$ 2. 3 i
l l TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS TCONT*D1 l Prairia Island Dispersion Param:t::rs (D/q),1/m, for Short Term Ground Lcv;l Rt. leases 2 l s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M 1Q 11 12 1,2 Id N 1.05E-07 8.25E-08 6.73E-08 5.55E-08 4.66E48 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 l 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 i SSE 1.26E-07 1.01 E-07 8.26E-08 6.86E-08 5.63E-08 4.83E-08 4.22E-08 S 8.06E-08 6.40E-08 5.16E-08 4.29E-08 3.60E-08 3.07E-08 2.66E-08 ~ 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 8.11 E-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 WNW 1.47E-07 1.15E-07 9.45E-08 7.80E-08 6.54E-08 5.61 E-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 l l h
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TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 1 2 Prairie Island Dispersion Parameters (D/q),1/m, 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) i l Miles Sector M M LZ. M M 24 2J. N 2.98E-08 2.62E-08 2.33E-08 2.08E-08 1.87E-08 1.70E-08 1.54E-08 NNE 2.49E-08 2.20E-08 1.95E-08 1.74E-08 1.56E-08 1.43E-08 1.30E-08 i 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 -l E 3.66E-08 3.24E-08 2.89E-08 2.58E-08 2.32E-08 2.11 E-08 1.91 E-08 j ESE 5.12E-08 4.53E-08 4.03E-08 3.60E-08 3.23E-08 2.95E-08 2.68F:-08 SE 5.61 E-08 4.96E-08 4.41 E-08 3.95E-08 3.55E-08 3.21 E-08 2S2E-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 f 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 l WSW 2.34E-08 2.07E-08 1.84E-08 1.65E-08 1.49E-08 1.30E-08 1.18E-08 l W 3.37E-08 2.97E-08 2.64E-08 2.36E-08 2.12E-08 1.95E-08 1.77E-08 l WNW 4.26E-08 3.76E-08 3.38E-08 3.02E-08 2.72E-08 2.44E-08 2.22E-08 i NW 3.97E-08 3.51 E-08 3.12E-08 2.80E-08 2.52E-08 2.30E-08 2.09E-08 l NNW 3.15E-08 2.78E-08 2.48E-08 2.22E48 1.99E-08 1.81 E-08 1.64E-08 i Period of Record: 4/1/77 - 3/31/78 i t en i s =' C 1 6 f =
... = TABLE A-a - PR41RIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairia island Dispersion Parameters (D/q),1/m, far Short Tcrm Ground Level R: leases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 22 22 24 25 24 2.I 22 N 1.41 E-08 1.29E-08 1.19E-08 1.09E-08 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 i 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 i l 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 l 80 S Jh
- ! is e.
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairia Island Dispersion Param;t:rs (D/q),1/m, for Short Term Ground Lcv;l R: leases s 500 Hrs /Yr ors 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector 22 M 11 12 M M M N 7.68E-09 7.22E-09 6.76E-09 6.35E-09 5.97E-09 5.63E-09 5.31 E-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 4.11 E-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 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. 61 E-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 I i.< I a 23 l S. 1
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairia Island Dispersion Param; tars (D/q),1/m, for Short Term Ground Lcv;l Rsleases s 500 Hrs /Yr ors 150 Hrs /OTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M M M M da il .4.2 N 5.01E-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 NE 3.68E-09 3.49E-09 3.31 E-09 3.15E-09 3.00E-09 2.85E-09 2.72E-09 ENE 3.71 E-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 9.02E-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 2.91EM9 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 I 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 Period of Record: 4/1/77 - 3/31/78 I 2 22 e. I
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D] 2 Prairia Island Dispersion Param ters (D/q),1/m, for Short Term Ground Ltvil R; leases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector M 4.4 M M 4.7 M M N 3.55E-09 3.40E-09 3.26E-09 3.12E-09 2.99E-09 2.87E-09 2.76E-0 i 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 2.31 E-09 2.21 E-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 4.01 E-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 4.04E-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 . EI N -k E"
TABLE A PRAIRIE ISLAND DISPERSION PARAMETERS [ CONT'D_1 l 2 Prairia Island Dispersion Parameters (D/q),1/m, for Short Tcrm Ground Level R: leases s 500 Hrs /Yr or s 150 Hrs /QTR for Standard Distances (As Measured from Edge of Plant Complex) Miles Sector EQ 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 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 Period of Record: 4/1/77 - 3/31/78 l !I e aG a
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES %g glffs tjg gg, glt TITLE: NUMBER: I jyspg c wedW OFFSITE DOSE CALCULATIONS H4 w; j y4 MANUAL (ODCM) REv: 13
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- - ' gi,,SM Page 177 of 197 I l l t APPENDlX B - PRAIRIE ISLAND 12.2m WIND AND AT 42.7-12.2M STABILITY JOINT FREQUENCY DISTRIBUTIONS (4/1/77 - 3/31/78) i l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: pj[$gL1 (({.l/;f$<- ' $ ODE ;if iva; OFFSITE DOSE CALCULATIONS H4 [j/c-,4["]g;ge;*- g MANUAL (ODCM) REv: 13 enegj ' ANfh M 2 )$$ Page 178 of 197 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREOUENCY 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_TDJ 4 TO 7 8 TO 12 13 TO 18 19 TO 24 ABOVE 24 TOTAL N 7 22 29 11 0 0 69 NNE 13 19 20 4 0 0 56 NE 11 35 16 1 0 0 63 ENE 11 33 20 0 0 0 64 E 14 37 24 0 0 0 75 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 SW 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 NVV 12 42 72 53 20 0 199 NNW 11 43 49 20 2 0 125 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 1408 HOURS OF CALM THIS CLASS 0 PERCENT OF ALL DATA THIS CLASS 16.81
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES q ;M jpM,gg< TITLE: NUMBER: sp gr > g/4 <; OFFSITE DOSE CALCULATIONS H4 MANUAL (ODCM) REv: 13 i s..iG.. hes; #. f E 4 c, e Page 179 of 197 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT SITE METEOROLOGY - FREOUENCY DISTRIBUTION TABLES HOURS AT EACH WIND SPEED AND DIRECTION PERIOD: 4/1/77 THROUGH 3/31/78 l STABILITY CLASS B l ELEVATION 40 FT. WIND SPEED (MPH) AT 40 FT LEVEL DIRECTION 1TO3 4TO7 8 TO 12 13 TO 18 19 TO 24 ASOVE 24 TOTAL N 0 3 5 1 0 0 9 I NNE 1 2 1 1 0 0 5 NE O 2 0 0 0 0 2 ENE 0 3 2 0 0 0 5 l E 0 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 i 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 NW 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
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Ig@h@pl!%dp MLE: NUMBER: n Iita R Af OFFSITE DOSE CALCULATIONS H4 b; l ' MANUAL (ODCM) REv: 13 ? d. )f"ifffh-Q.. g [h ' n, j kf[M g a Page 130 of 197 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING FLANT SITE METEOROLOGY-FREOUENCY 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 plRECTION 1 TO 3 4 TO 7 8 TO 12 13 TO 18 j9 TO 24 ABOVE 24 TOTAL N 2 4 4 1 0 0 11 NNE 2 3 1 0 0 0 6 NE 1 5 1 0 0 0 7 ENE O 3 1 0 0 0 4 E 1 8 3 0 0 0 12 ESE 0 7 11 2 0 0 20 SE O 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 11 SVV 2 2 3 2 0 0 9 WSW 1 6 5 1 2 0 15 W 0 2 11 4 1 0 18 WNW 1 3 6 7 1 0 18 NW 2 7 11 16 6 1 43 NNW 3 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 CLASS 2.87
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: g{pjp~ 2pfy@,@t ' T&g yl$l OFFSITE DOSE CALCULATIONS H4 sg MANUAL (ODCM) REv: 13
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Page 181 of 197 / 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 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 TOTAL 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 ESE 8 57 154 19 0 0 238 SE 10 30 90 38 5 0 173 SSE 8 40 59 51 10 0 168 S 1 51 72 17 4 0 145 SSW 5 29 30 12 0 0 76 SW 4 15 17 4 0 0 40 WSW 5 23 31 21 3 4 87 W 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 VAR 0 0 0 0 0 0 0 TOTAL HOURS THIS CLASS 2051 HOURS OF CALM THIS CLASS 4 PERCENT OF ALL DATA THIS CLASS 24.49
1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES A dhsi$$%#gy; TITLE: NUMBER: er q,we OFFSITE DOSE CALCULATIONS H4 g / kk{ MANUAL (ODCM) REv: 13 gg, gg y.6h, 'd?J$ by,,p (6 Page 182 of 197 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 E 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 22 30 9 11 1 0 73 NNE 18 29 7 0 0 0 54 NE 22 26 7 1 0 0 56 ENE 19 30 5 1 0 0 55 E 25 96 10 0 0 0 131 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 1 0 170 SSW 3 26 29 40 1 0 99 SVV 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 NW 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 2612 HOURS OF CALM THIS CLASS 7 PERCENT OF ALL DATA THIS CLASS 31.18
4 PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ,gy's syyy? TITLE: NUMBER: J%
- yta, OFFSITE DOSE CALCULATIONS H4 k
!';g j% MANUAL (ODCM) REv: 13 %iffpps .;;<.E ' s Page 183 of 197 i NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT l SITE METEOROLOGY - FREQUENCY DISTRIBUTION TABLES j 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 QlRECTION 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 1 0 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 NVV 66 71 16 3 0 0 156 NNW 29 19 6 2 0 0 56 VAR 0 0 0 0 0 0 0 i TOTAL HOURS THIS CLASS 1053 HOURS OF CALM THIS CLASS 7 PERCENT OF ALL DATA THIS CLASS 12.57
I PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j 1 TITLE: NUMBER: . Apk Jg("gm /% g< + :'3p1 OFFSITE DOSE CALCULATIONS H4
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MANUAL (ODCM) REv: 13 y, Se ? q Page 184 of 197 jn ~~ 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 0 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 22 1 2 0 0 0 25 E 52 8 2 0 0 0 62 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 TOTAL HOURS THIS CLASS 821 HOURS OF CALM THIS CLASS 37 PERCENT OF ALL DATA THIS CLASS 9.80
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES bgg;n @t fggy TITLE: NUMBER: ~ ,, 'P ' M' ' OFFSITE DOSE CALCULATIONS H4 $2i 'y 4 MANUAL (ODCM) REv: 13 ' y'ggI hn;
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' + Page 185 of 197 APPENDIX C-DOSE PARAMETERS FOR RADIOIODINES. PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radiciodines, particulates, and tritium to show compliance with 10CFR20 and Appendix I of 10CFR50 for gaseous effluents. These dose parameters, P and R, were calculated using i i 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 P and R values for the various exposure patnways. i i C.1 Calculation of Pi The parameter, P, contained in the radiciodine and particulates portion of Section 5.2, i 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 internal 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 P, = K' (BR) DFA; (C.1-1) i j where: P, dose parcmeter for radionuclide i for the i = 3 inhalation pathway, mrem /yr per ci/m ; K' a constant of unit conversion: = 6 10 pCi/ Cl- = the breathing rate of the child age group, BR = 1 3 m /yr; DFA the maximum organ inhalation dose factor i = for the child age group for radionuclide i, mrem /pCl.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES
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NUMBER: - 3 M; OFFSITE DOSE CALCULATIONS H4 2Mh,g$hk# 'E E MANUAL (ODCM) REv: 13 YAdg*gg ygg % a m;%y a '; 3 Page 186 of 197 The age group considered is the child group. The child's breathing rate is taken as' 3 3700 m /yr from Table E-5 of Regulatory Guide 1.109 Revision 1. The inhalation dose factors for the child DFA, are presented in Table E-9 of Regulatory Guide 1.109 i in units of mrem /pCl. The total body is considered as an organ in the selection of DFA. The incorporation of breathing rate of the child and the unit conversion factor i results in the following: 9 P, = 3.7 x 10 DFA; (C.1-2) i C.2 Calculation of Ri The radiciodine 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 alllocations. The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their existence at the various locations. R values have been i 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, = K'(BR)a (DFA;)a (C.2-1) i where: R, dose factor for each identified radionuclide i of i = 3 the organ of interest, mrem /yr per pCi/m ; K' a constant of unit conversion: = 6 10 pCi/ Cl; = (BR)a breathing rate of the receptor of age group = 3 a, m /yr; (DFA)a = organ inhalation dose factor for radionuclide i i for the receptor of age group a, mrem /pCi.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES <.... ~ TITLE: NUMBER: g i OFFSITE DOSE CALCULATIONS H4 3 ; e% MANUAL (ODCM) REv: 13 $ ';l ige h[ NMh Page 187 of 197 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. 3 Age Grouc (a) Breathino Rate (m /vri Infant 1400 Child 3700 Teen 8000 Adult 8000 inhalation dose factors (DFA)a for the various age groups are given in Tables E-7 i through E-10 of Regulatory Guide 1.109 Revision 1. C.2.2 Ground Plane Pathway (1-e*)/A (C.2-2) i !;K'K"(SF)DFGi R, = i dose factor for the ground plane pathway for R = i each identified radionuclide i for the organ of interest, m2-mrem /yr per pCi/sec per; a constant of unit conversion; K' = 6 10 pCi/ Cl- = a constant of unit conversion; K" = 8760 mr/ year; = 11 = the radiological decay constant for radionuclide i, sec-1; the exposure time, sec; t = 8 4.73 x 10 sec (15 years)' = the ground plant dose conversion factor for DFGi = 2 l radionuclide i; mrem /hr per pCi/m ; SF the shielding factor (dimensionless) = factor to account for fractioral deposition li = of radionuclide i.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES TITLE: NUMBER: fpQ[ 2?Dl;pgM WWf WB6 OFFSITE DOSE CALCULATIONS H4 Ed' a UNN MANUAL (ODCM) REv: 13
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%ggw w Page 188 of 197 For radionuclides other than iodine, the factor l is equal to one. For i radiolodines, the value of l may vary. However, a value of 1.0 was used in i 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 DFG values is presented in Table E-6 of i Regulatory Guide 1.109 Revision 1. C.2.3 Grass-Cow or Goat-Milk Pathway 'r(1-e-AE t ep) + B (1-ewb) ' i iy y = l K'O Uap m (DFL),e
- f f.
F + R i p i p y PN (1-f f.) r(1-e-AE tes) + B (1gb) ' i iy e -A tih (C.2-3) p YA PA; s E; where: R dose factor for the cow milk or goat milk pathway, for iu = each identified radionuclide i for the organ of interest, 2 m - mrem /yr per Ci/sec; a constant of unit conversion; K' = 6 10 pCi/ Ci; = QF = the cow's or goat's feed consumption rate, kg/ day (wet weight); Uap the receptor's milk consumption rate for age group a, = liters /yr; the agricultural productivity by unit area of pasture Yp = 2 feed grass, kg/m ; the agricultural productivity by unit area of stored Y = 3 feed, kg/m2; the stable element transfer coefficients, Fm = pCi/ liter per pCi/ day;
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES je Mt9Qg/DR,y TITLE: NUMBER: M@y WM OFFSITE DOSE CALCULATIONS H4
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NE MANUAL (ODCM) REv: 13 g e d Page 189 of 197 q > gpu
- Jyv s fraction of deposited activity retained on cow's feed r
= grass; (DFL)a = the organ ingestion dose factor for radionuclide i for i the receptor in age group a, mrem /pCi; A +b; AE l = the radiological decay constant for radionuclide i, li = sec-1; the decay constant for removal of activity on leaf Aw = and plant surfaces by weathering, sec-1; 5.73 x 10-7 sec-1 (corresponding to a 14 day = half-life); the transport time from feed to cow or goat to milk, t, = to receptor, sec; th = the transport time from harvest, to cow or goat, to consumption, sec' period of time that activity builds up in soil, sec; tb = concentration factor for uptake of radionuclide i from Bjy = the soil by the edible parts of crops, pCi/kg (wet weight) per pCi/kg (dry soll); 2 P effective surface density for soil, (dry weight) kg/m ; = fraction of the year that the cow or goat is on f = p pasture; fraction of the cow feed that is pasture grass while f = 3 the cow is on pasture; period of pasture grass exposure during the growing top = season,sec;
r-1 i PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES j TITLE: NUMBER: Q$$dd4%'#[ OFFSITE DOSE CALCULATIONS H4 M@'5 9[ggs d W MANUAL (ODCM) Rev: 13 $nc h q$ g$ dIdNMOm " Page 190 of 197 period of crop exposure during the growing tes = season, sec; factor to account for fractional deposition of I, = radionuclide 1. For radionuclides other than lodine, the factor l is equal to one. For i radiciodines, the value of I; 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 f was considered unity in lieu of 3 site-specific information. The value of f was 0.5 based upon a 6-month p 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 airborne concentration rather than the deposition. Therefore, the R is based on X/Q: i = K'K" ' FmO Uap (DFL ), 0.75 (0.5/H) (C.2-4) R F i Tu where: R dose factor for the cow or goat milk pathway for Tu = 3 tritium for the organ of interest, mrem /yr per pCl/m ; K"' a constant of unit conversion; = 3 10 gm/kg; = 3 absolute humidity of the atmosphere, gm/m ; H = 0.75 the fraction of total feed that is water; = the ratio of the specific activity of the feed grass to 0.5 = the atmospheric water.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES g$hh$'D5Ikh@g;ghf ; N ' % W M-TITLE: NUMBER: E OFFSITE DOSE CALCULATIONS H4 4 MANUAL (ODCM) REv: 13 [, y yy !W " r' ,~ Page 191 of 197 and other parameters and values are given below. A value of H of 8 3 grams / meter, was used in lieu of site-specific information. 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: 'r(1-e-AE, t ep) + B (1-e-niib) ' r iy Uap, (DFL),e ff. F i'8 R, I;K'Op + i i p y Py /n w ~ r(1-e-AE tes) + B (1-e 'b) ' e -A tlh (C.2-5) i iy (1-f f.) p A e Ys E, PA t i u b r v where: p3 h)i(3 O dose factor for the meat ingestion pathway for a = radionuclide i for any organ of interest, m' mrem /yr per Cl/sec; Ff = the stable element transfer coefficients, pCi/Kg per pCi/ day; Uap the receptor's meat consumption rate for age = group a, kg/yr; the transport time from slaughter to ts = consumption, sec; K the transport time from harvest to animal = consumption, sec; top period of pasture grass exposure during the = growing season, sec; period of crop exposure during the growing tes = season, sec; li = factor to account for fractional deposition of radionuclide i.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES MP - g "W TITLE: NUMBER: [ : nog If OFFSITE DOSE CALCULATIONS H4 '$sWRi
- 1 MANUAL (ODCM)
REv: 13 % $ @fm e yw -,f @ T !sann F%g Page 192 of 197 For radionuclides other than lodine, the factor l is equal to one. For i radiciodines, the value of l may vary. However, a value of 1.0 was used in i calculating the R values in Tables 5.5-5 through 5.5-7. 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 R for the meat pathway. i The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R is based on X/O. i R, = K'K" ' F,OpUap (DFL ), 0.75 (0.5/H) (C.2-6) 7 i where: dose factor for the meat ingestion pathway for tritium R = 7* 3 for any organ of Interest, mrem /yr per Ci/m. All other terms are defined in Equation C.2-4 and C.2-5, above.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES Kg TITLE: NUMBER: C _#q g y + D" OFFSITE DOSE CALCULATIONS H4
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4 MANUAL (ODCM) REv: 13 N P M ss$ & I* ? W M Mt"'"' s Page 193 of 197 C.2.5 Vegetation Pathwav 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: = l K'(DFL ), Uhf e"i,' r(1-e-AE te) + B,y(1gb) ' i + R i i t y PN iy Usf e 'h ' r(1-e4E, te) 4 B;y(1-owb) ' ' 4i (C.2-7) g YvA, PA E j where: dose factor for vegetable pathway for radionuclide i R = 7* 2 for the organ of interest, m - mrem /yr per Ci/sec; a constant of unit conversion; K' = I 6 10 pCi/ Cl; = Uh the consumption rate of fresh leafy vegetation by the = receptor in age group a, kg/yr; the consumption rate or stored vegetation by the Us = receptor in age group a, kg/yr; IL the fraction of the annualintake of fresh leafy = vegetation grown locally; the fraction of the annualintake of stored vegetation f = g grown locally; the average time between harvest of leafy tt = vegetation and its consumption, sec;
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES yp$p~?g~g$4Mk !!$$$ f ~ gp g TITLE: NUMBER: OFFSITE DOSE CALCULATIONS H4 j[ Q{ MANUAL (ODCM) REv: 13 %[dq5i$ectlen?!g4;5 6? ym gewg;p gg n Page 194 of 197 th = the average time between harvest of stored vegetation and its consumption, sec; Yv 2 the vegetation areal density, kg/m ; = period of leafy vegetable exposure during t. = growing season, sec; 11 = factor to account for fractional deposition of radionuclide 1. For radionuclides other than lodine, the factor l is equal to one. For i radiolodines, the value of l may vary. However, a value of 1.0 was used in i calculating the R values in tables 5.5-2 through 5.5-4. All other factors were defined above. Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1. In lieu of site-specific data default values for f and f,1.0 and 0.76, t g respectively were used in the calculation of R. These values '. vere obtained i from Table E-15 of Regulatory Guide 1.109 Revision 1. The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R is based on X/Q: i R, = K'K"' 'Uhft + Usy (DFL ), 0.75 (0.5/H) (C.2-8) 7 g, i where: R, dose factor for the vegetable pathway for T = 2 tritium for any organ of interest, m - mrem /yr per 3 pCi/m. All other terms remain the same as those in Equations C.2-4 and C.2-7. i i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ' i$ ; TITLE: NUMBER:
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(;/ f OFFSITE DOSE CALCULATIONS H4 m wg 3, %w MANUAL (ODCM) REv: 13 g ' ggij gM' ( x ec,7 M Page 195 of 197 TABLE C PARAMETERS FOR COW AND GOAT MILK PATHWAYS Parameter Value Reference (Reg. Guide 1.109 n9 val Op (kg/ day) 50 (cow) Table E-3 6 (goat) Table E-3 Yp (kg/m ) 0.7 Table E-15 2 5 tg (seconds) 1.73 x 10 (2 days) Table E-15 r 1.0 (radiciodines) Table E-15 0.2 (particulates) Table E-15 (DFL)a (mrem /pCi) Each radionuclide Tables E-11 to E-14 i Fm (pCi/ day per pCi/ liter) Each stable element Table E-1 (cow) Table E-2 (goat) t (seconds) 4.73 x 10 (15 yr) Table E-15 8 b 2 Y, (kg/m ) 2.0 Table E-15 2 Y (kg/m ) 0.7 Table E-15 p 6 t (seconds) 7.78 x 10 (90 days) Table E-15 h Uap (liters /yr) 330 infant Table E-5 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 6 top (seconds) 2.59 x 10 (30 days) Table E-15 6 tos (seconds) 5.18 x 10 (60 days) Table E-15 B v (pCi/Kg (wet weight) Each stable element Table E-1 i per pCl/Kg (dry soll)) 2 P (Kg/m (dry weight)) 240 Table E-15 l.-
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES ggg,,JgQg TITLE: NUMBER: j ag ma% OFFSITE DOSE CALCULATIONS H4 p$dWM 5 3 Iseittas" 4 ak MANUAL (ODCM) REv: 13 d-e nyggpggg Page 196 of 197 TABLE C PARAMETERS FOR THE MEAT PATHWAY Parameter Yalue Reference (Reg. Guide 1.109 Rev.1) r 1.0 (radiciodines) Table E-15 0.2 (particulates) Table E-15 Fr (pCl/Kg per pCl/ day) Each stable element Table E-1 Uap (Kglyr) 0 infant Table E-5 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL)a (mrem /pCi) Each radionuclide Tables E-11 to E-14 i 2 Y (kg/m ) 0.7 Table E-15 p 2 Ys (kg/m ) 2.0 Table E -15 8 t (seconds) 4.73 x 10 (15 yr) Table E-15 b 8 ts (seconds) 1.73 x 10 (20 days) Table E-15 6 in (seconds) 7.78 x 10 (90 days) Table E-15 6 t,p (seconds) 2.59 x 10 (30 days) Table E-15 6 tas (seconds) 5.18 x 10 (60 days) Table E-15 Or (kg/ day) 50 Table E-3 B v (pCi/Kg (wet weight) Each stable element Table E-1 i per pCi/Kg (dry soil)) 2 P (Kg/m (dry weight)) 240 Table E-15
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY H PROCEDURES y; ggW TITLE: NUMBER: g$g j$ iLE ld OFFSITE DOSE CALCULATIONS H4 f 427,,[ E MANUAL (ODCM) REv: 13 Page 197 of 197 TABLE C PARAMETERS FOR THE VEGETABLE PATHWAY Parameter .Value Reference (Reg. Guide 1.109 Rev.1) r (dimensionless) 1.0 (radiciodines) Table E-1 2.0 (particulates) Table E-1 (DFL)a (mrem /pCl) Each radionuclide Tables E-11 to E-14 i 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 4 t (seconds) 8.6 x 10 (1 aay) Table E-15 t 6 t (seconds) 5.18 x 10 (60 days) Table E-15 h 2 Yv (kg/m ) 2.0 Table E-15 6 ta (seconds) 5.18 x 10 (60 days) Table E-15 6 t (seconds) 4.73 x 10 (15 yr) Table E-15 b 2 P(Kg/m (dry weight)) 240 Table E-15 B v (pCl/Kg (wet weight) Each stable element Table E-1 i per pCi/kg (dry soil))
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