ML20249C381
| ML20249C381 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/22/1998 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20249C379 | List: |
| References | |
| NUDOCS 9806290162 | |
| Download: ML20249C381 (9) | |
Text
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' - NPL 98-0503
, Attachment 3 l
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ATTACHMENT 3 CORRECTED PAGES TECliNICAL SPECIFICATION CIIANGE REQUEST 174 l
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Environmental Manual (EM) - In order to assure conformance with PBNP GDC 17 and with the guidance of Apnendix I to 10 CFR 50. this manual shall contain the Radiological Environmental Monitoring Program (REMP) methodology. parameters and administrative functions required for monitoring; samnling analyzing and recorting of radiation levels and radionuclides 3 concentrations in the environment around PBNP. The REMP shall require an annual milk survev and shall require that radionnalyses be conducted by a laboratory participating in an Interlaboratory Comparison Program
- b. Radiological Emuent Control Program Manual (RECM) The RECM shall contain the Radiological Emuent Control Program (RECP) parameters and methodologies needed in order to assure conformance with 10 CFR 50.36a for the control of emuents and for maintaining doses to the oublic ALARA and for compliance with 10 CFR 201302. The following RECP items are contained in the RECM:
11 radioactive emuent monitoring instrumentation operability. with actions to be taken if operability requirements are not met. and surveillance requirements:
21 radioactive emuent samnling and analyses requirements:
31 limitations on the concentrations of radioactive materials in liauid emuents to the unrestricted area to 10 times the concentration value in Anpendix B. Table 2. Column 2 to 10CFR20.1001-20.2402:
41 determination of the cumulative and orojected dose contributions from radioactive emuents for the current calendar cuarter and current calendar year in accordance with ODCM methodoloev and narameters at least every 31 days:
- 5) assurance that the appropriate nortions of the liquid and gnseous emuent treatment system are used whenever the projected doses in a ceriod of 31 days would exceed 2 nercent of the 10CFR50 Aopendix I dose guidelines:
- 6) limitations to the release rate of radioactive emuent to the atmosobere in order to assure that the following dose rates would not be exceeded at or bevond the site boundarv:
- a. 500 mrem /vr total body from noble gases.
- b. 3000 mrem /vr. skin from noble gases.
- c. 1500 mrem /vr. any organ from I-131. I-133. H-3 and all radioactive particulate with a half-life greater than 8 days:
Unit 1 - Amendment No. 15.7.8-2 Unit 2 - Amendment No. I
NUCLEAR POWER BUSINESS UNIT RECM
'.' RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.0 RADIOACTIVE EFFLUENT RELEASE LIMITS 5.1 Obiective To ensure controlled releases of radioactive materials in liquid and gaseous effluents to unrestricted areas are within applicable 10 CFR 20 concentration limits and to ensure the quantities of radioactive material released during any calendar year are such that resulting radiation exposures do not exceed the dose objectives of 10 CFR 50, Appendix I.
5.2 Radioactive Liauid Effluent Concentrations 5.2.1 Alarm setpoints for liquid effluent monitors shall be determined and adjusted utilizing the methodologies and parameters given in the ODCM.
5.2.2 The liquid effluent monitor setpoints shall be established to ensure that radioactive materials released as effluents shall not result in concentrations to unrestricted areas in excess of ten times the concentration values specified in Appendix B, Table 2, Column 2, of 10 CFR 20.1001-20.2402.
5.2.3 During release of radioactive liquid effluents, at least one condenser circulating water pump shall be in operation and the service water return header shall be lined up only to the unit whose circulating water pump is operating.
5.3 Radioactive Liauid Effluent Release Limits 5.3.1 The annual calculated total quantity of radioactive material above background released from PBNP in liquid effluents shall not result in an unrestricted area estimated annual dose or dose commitment from all exposure pathways to any individual in excess of 6 millirem to the total body or 20 millirem to any organ. .
5.3.2 For the purpose ofinitiating the use of the liquid effluent treatment system whenever the projected dose for a period of 31 days will exceed 2% of the dose guidelines of Appendix I to 10 CFR 50, the 2% of the Appendix I values, as given in Section 5.3.1, are 0.12 mrem for the whole body and 0.4 mrem for any organ.
5.3.3 Quarterly limits are defined as one-half of the annual limits.
5.3.4 Compliance with these release limits will be demonstrated by periodic dose calculations utilizing the methodology of the ODCM.
I Page 25 of 34 INFORMATION USE j
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NUCLEAR POWER BUSINESS UNIT RECM
".* RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.4 Radioactive Gaseous Emuent Concentrations 5.4.1 Alarm setpoints for the gaseous effluent monitors shall be determined and adjusted utilizing the methodologies and parameters given in the ODCM.
5.4.2 The gaseous effluent monitor setpoints are established to ensure that radioactive materials released shall not result in concentrations to unrestricted areas in excess of the values specified in 10 CFR 20, Appendix B, Table 2.
5.4.3 During the release of radioactive gaseous effluents from the gas decay tanks through the auxiliary building vent, at least one auxiliary building exhaust fan shall be in operation.
5.5 Radioactive Gaseous Effluent Release Limits 5.5.1 The annual calculated total quantity of radioactive materials above background released from PBNP to the atmosphere shall not result in an unrestricted area estimated annual dose or dose commitment from all exposure pathways to any individual in excess of the following:
- a. 10 millirem to the total body or 30 millirem to the skin from gaseous effluents near ground level;
- b. 30 millirem to any organ from all I-131, I-133, H-3 and radioactive materials in particulate form whose half-life is >8 days; and -
- c. Furthermore, the annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals in unrestricted areas shall not exceed 20 millirads for gamina radiation or 40 millirads for beta radiation.
.5.5.2 For the purpose ofinitiating the use of the atmospheric effluent treatment system whenever the projected dose for a period of 31 days will exceed 2% of the dose guidelines of Appendix 1 to 10 CFR 50, the 2% of the Appendix I values, as given in Section 5.5.1, are:
- a. 0.2 mrem to the total body and 0.6 mrem to the skin, and l 1
- b. 0.6 mrem to any organ. i l
5.5.3 Quarterly limits are defined as or sai: of 6 .muallimits.
i 5.5.4 Compliance with these - F : . demonstrated by periodic dose calculations utihzmg te e med + e .
' .he ODCM. i i
INFORMATION USE Pa 4
NUCLEAR POWER BUSINESS UNIT RECM
'.' RADIOLOGICAL EFFLUENT CONTROL MAJOR MANUAL Revision 0 DRAFT November 25,1997 RADIOLOGICAL EFFLUENT CONTROL MANUAL 5.6 Atmospheric Release Rate Limitations The rate of release of radioactive effluents to the atmosphere from the site, which if continued for one year, shall not result in dose rates at or beyond the site boundary that exceed the following values.
5.6.1 For noble gases:
- a. 500 mrem /yr to the total body
- b. 3000 mrem /yr to the skin 5.6.2 For I-131, I-133, H-3, and all particulate form radionuclides with a half-life
>8 days:
1500 mrem /yr to any organ 5.6.3 The instantaneous, limiting release rates for the above annual rates, are calculated in Section 3.10 of the ODCM for various release types. Below are default values for various releases. Check the ODCM for the methodology to calculate release rates for more specific radionuclides mixtures or contact the cognizant Radiological Engineer,
- a. For noble gases, the whole body dose is limiting yielding a rate of 8.73E-02 Ci/sec.
- b. For particulate, radioiodines and H-3, as described above, the release rates are 1.14E-06 Ci/sec for radiciodines 1.30E-06 Ci/sec for cesiums 2.16E-05 Ci/sec for cobalts 3.62E-01 Ci/see for H-3 As a conservative measure, the limiting release rate should be applied to the whole radionuclides mixture based upon the presence or absence of the above major dose contributors.
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NUCLEAR POWER BUSINESS UNIT ODCM
. OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL 3.10 Determination of Maximum Release Rates Technical specifications restrict the rate of release (Ci/sec) of radionuclides to the atmosphere to that value, which if continued for one year, would result in the following annual dose rates at or beyond the site boundary: 500 mrem /yr to the whole body and 3000 mrem /yr to the skin from noble gases; and,1500 mrem /yr to any organ from I-131, I-133, H-3, and particulate with a half-life >8 days.
3.10.1 Noble gas release rate The release rate for noble gases are calculated using the Reg. Guide 1.109 dose factors and the annual average isotopic noble gas release for the years 1985 - 1991 as shown in Table B-1. The calculated annual skin dose from the average 1985 - 1991 isotopic mixture with a total of 4.51E+01 curies is 4.12E-03 mrem. Therefore the maximum release rate is calculated from the formula Ci/sec = total Ci
- dose limit / (sec/yr
- dose from total Ci).
Based on skin dose, the release rate formula Ci/sec = 4.51E+01 Ci
- 3000 mrem /yr/ (4.12E-03 mrem
- 3.15E+07 sec/yr) yields a release rate of 1.04E+00 Ci/sec.
Using the same total curies with the same isotopic mixture but with the whole body dose of 8.21E-03 mrem /yr and the whole body dose limit of 500 mrem /yr, the release rate becomes 8.72E-02 Ci/sec.
Therefore the whole body dose rate is limiting and the maximum allowable PBNP noble gas release rate is 8.72E-02 Ci/sec. This rate is at higher than any PBNP noble gas release rate from 1985 - 1991 based on the highest reported hourly average release rates of approximately 4.3E-02 Ci/sec.
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,, ', NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision i1 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL l Table 3.10-4 MREM from all radionuclides except H-3 and radiciodines (2.15E-03 Ci) ;
MREM from all radionuclides except H-3 and radiciodines
)
Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 1.65E-02 2.53 E-02 4.59E-02 2.08E-09 8.49E-03 2.84E-03 9.41E-04 3.27E-02 ;
TEEN 2.68E-02 4.04E-02 4.37E-02 2.64E-09 1.35 E-02 5.25E-03 9.76E-04 3.27E-02 CHILD 6.29E-02 6.75E-02 3.94E-02 4.94E-09 2.16E-02 7.81E-03 6.72E-04 3.27E-02 INFANT 5.01E-02 6.51E-02 3.32E-02 1.88E-09 1.73E-02 7.04E-03 2.27E-04 3.27E-02 As evident from Tables 3.10-1 through 3.10-4, H-3 contributes a significant portion of the thyroid dose for all age groups for the 1985 - 1991 mixture of radionuclides released to the atmosphere. Comparison of Tables 3.10-5 and 3.10-6 to Table 3.10-4 reveals that the major portion of the organ doses from radionuclides other than H-3 and radiciodines results from cobalt and cesium. Cs-134 and Cs-137 are the major dose contributors to the bone, liver, skin and kidneys whereas cobalt is the major contributor to the GI-LLI dose. Therefore, the dose results obtained from the 1985 - 1991 radionuclides mixture is consistent with the dose results from current effluents.
Table 3.10-5 MREM from Cs-134 and Cs-137 (1.84E-03 Ci)
MREM from Cs-134 and Cs-137 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin I ADULT 1.62E-02 2.53E-02 4.21E-02 0.00E+00 8.48E-03 2.82E-03 4.76E-04 2.84E-02 TEEN 2.64E-02 4.04E-02 3.98E-02 0.00E+00 1.35E-02 5.22E-03 5.52E-04 2.84E-02 CHILD 6.22E-02 6.74E-02 3.54E-02 0.00E+00 2.16E-02 7.78E-03 4.05E-04 2.84E-02 INFANT 5.01E-02 6.50E-02 2.95E-02 0.00E+00 1.73E-02 7.02E-03 1.96E-04 2.84E-02 Table 3.10-6 MREM from Co-57, Co-58, and Co-60 (1.93E-04 Ci) l MREM from cobalts Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 0.00E+00 2.24E-05 3.72E-03 0.00E+00 0.00E+00 2.32E-05 4.26E-04 4.32E-03 TEEN 0.00E+00 2.97E-05 3.73E-03 0.00E+00 0.00E+00 3.40E-05 3.88E-04 4.32E-03 CHILD 0.00E+00 4.35E-05 3.80E-03 0.00E+00 0.00E+00 2.76E-05 2.43E-04 4.32E-03 INFANT 0.00E+00 7.75E-06 3.69E-03 0.00E+00 0.00E+00 1.78E-05 1.86E-05 4.32E-03 1
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NUCLEAR POWER BUSINESS UNIT ODCM
'.* OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT December 2,1997 OFFSITE DOSE CALCULATION MANUAL Based on these results, the release rates for various radionuclides mixture can be determined using the methodology in Section 3.10.1.
i For the total radionuclides mixture, the maximum release rate is Ci/sec =1.16E+02 Ci *1500 mrem /yr/ (1.04E-01 mrem
- 3.15E+07 sec/yr) or 5.33E-02 Ci/sec, For radioiodines (I-131 and I-133), the maximum release rate is Ci/sec =2.42E-03 Ci
- 1500 mrem /yr/ (1.01E-01 mrem
- 3.15E+07 sec/yr) or 1.14E-06 Ci/sec, l For H-3, the maximum release rate is Ci/sec =1.16E+02 Ci *1500 mrem /yr/ (1.53E-02 mrem
- 3.15E+07 sec/yr) or 3.62E-01 Ci/sec, For all radionuclides (other than H-3 and radioiodines) with a half-life > 8 days, the maximum release rate is Ci/sec =2.15E-03 Ci *1500 mrem /yr/ (6.75E-02 mrem
- 3.15E+07 sec/yr) or 1.52E-06 Ci/sec, ,
For cesium (Cs-134, -137), the maximum release rate is Ci/sec =1.84E-03 Ci *1500 mrem /yr/ (6.74E-02 mrem
- 3.15E+07 sec/yr) or 1.30E-06 Ci/sec, For cobalt (Co-57, -58, -60), the maximum release rate is Ci/sec =1.93E-04 Ci *1500 mrem /yr/ (4.26E-02 mrem
- 3.15E+07 sec/yr) or 2.16E-05 Ci/sec, Page 22 of120
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'." OFFSITE DOSE CALCULATION MANUAL Revision 11 DRAFT OFFSITE DOSE CALCULATION MANUAL Finally, for the total of all radionuclides in the mixture except H-3, the maximum release rate is .
Ci/sec =4.57E-03 Ci *1500 mrem /yr/ (1.01E-01 mrem
- 3.15E+07 sec/yr) or' 2.15E-06 Ci/sec.
l Because the limiting release rate is that of the radioiodines, a mixture of radionuclides whose half-lives is >8 days should be restricted to 1.14E-06 Ci/sec. However, if there is no I-131 and I-133, the cesium doses become limiting and the release rate limit may be raised to 1.30E-06 Ci/sec.
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