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| number = ML19150A486
| number = ML19150A486
| issue date = 05/10/2019
| issue date = 05/10/2019
| title = Revision 28 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents
| title = 8 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents
| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
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=Text=
=Text=
{{#Wiki_filter:GINNA/UFSAR 12           RADIATION PROTECTION                                             1 12.1         ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES                   2 ARE AS LOW AS IS REASONABLY ACHIEVABLE 12.1.1       ALARA PROGRAM                                                     2 12.1.2       ORGANIZATIONAL RESPONSIBILITIES                                   2 12.1.3       RADIATION PROTECTION PROGRAM                                     2 12.2         RADIATION SOURCES                                                 3 Table 12.2-1 SHIELDING SOURCE TERMS (T=0) (HISTORICAL)                         6 Table 12.2-2 SHIELDING SOURCE ACTIVITY at T=0 hrs - Power Level 1811         10 MWt 12.3         RADIATION PROTECTION DESIGN FEATURES                             16 12.3.1       DESIGN CRITERIA                                                 16 12.3.1.1     Conformance to 1967 Design Criteria                             16 12.3.1.2     Conformance to 1972 Design Criteria                             16 12.3.2       SHIELDING                                                       17 12.3.2.1     Design Basis                                                     17 12.3.2.2     Shielding Design                                                 19 12.3.2.2.1   Primary Shield                                                   19 12.3.2.2.2   Secondary Shield                                                 19 12.3.2.2.3   Containment Structure                                           20 12.3.2.2.4   Fuel Handling (Water and Pool) Shield                           20 12.3.2.2.5   Auxiliary Shielding                                             21 12.3.2.2.6   Shielding Design Modifications                                   21 12.3.2.2.7   Containment Accessibility Procedure                             22 12.3.3       VENTILATION                                                     22 12.3.3.1     Gas Collection and Decay Tank System                             23 12.3.3.2     Plant Ventilation System                                         23 12.3.3.3     Containment Ventilation System                                   24 12.3.3.4     Air Ejector and Gland Seal Exhaust System                       24 12.3.4       AREA RADIATION AND AIRBORNE RADIOACTIVITY MONI-                 24 TORING INSTRUMENTATION 12.3.4.1     Introduction                                                     24 Page 1 of 3            Revision 28 5/2019
{{#Wiki_filter:GINNA/UFSAR Page 1 of 3 Revision 28 5/2019 12 RADIATION PROTECTION 1
12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE 2
12.1.1 ALARA PROGRAM 2
12.1.2 ORGANIZATIONAL RESPONSIBILITIES 2
12.1.3 RADIATION PROTECTION PROGRAM 2
12.2 RADIATION SOURCES 3
Table 12.2-1 SHIELDING SOURCE TERMS (T=0) (HISTORICAL) 6 Table 12.2-2 SHIELDING SOURCE ACTIVITY at T=0 hrs - Power Level 1811 MWt 10 12.3 RADIATION PROTECTION DESIGN FEATURES 16 12.3.1 DESIGN CRITERIA 16 12.3.1.1 Conformance to 1967 Design Criteria 16 12.3.1.2 Conformance to 1972 Design Criteria 16 12.3.2 SHIELDING 17 12.3.2.1 Design Basis 17 12.3.2.2 Shielding Design 19 12.3.2.2.1 Primary Shield 19 12.3.2.2.2 Secondary Shield 19 12.3.2.2.3 Containment Structure 20 12.3.2.2.4 Fuel Handling (Water and Pool) Shield 20 12.3.2.2.5 Auxiliary Shielding 21 12.3.2.2.6 Shielding Design Modifications 21 12.3.2.2.7 Containment Accessibility Procedure 22 12.3.3 VENTILATION 22 12.3.3.1 Gas Collection and Decay Tank System 23 12.3.3.2 Plant Ventilation System 23 12.3.3.3 Containment Ventilation System 24 12.3.3.4 Air Ejector and Gland Seal Exhaust System 24 12.3.4 AREA RADIATION AND AIRBORNE RADIOACTIVITY MONI-TORING INSTRUMENTATION 24 12.3.4.1 Introduction 24  


GINNA/UFSAR 12.3.4.2     Description                                                               25 12.3.4.3     Radiation Monitoring System Detectors                                     26 12.3.5       EQUIPMENT AND SYSTEM DECONTAMINATION                                       27 12.3.5.1     Design Basis                                                               27 12.3.5.2     Methods of Decontamination                                                 27 12.3.5.3     Decontamination Facilities                                                 27 Table 12.3-1 PLANT ZONE CLASSIFICATIONS                                                 30 Table 12.3-2a PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-                           31 TERS - CALCULATED NEUTRON FLUXES (HISTORICAL)
GINNA/UFSAR Page 2 of 3 Revision 28 5/2019 12.3.4.2 Description 25 12.3.4.3 Radiation Monitoring System Detectors 26 12.3.5 EQUIPMENT AND SYSTEM DECONTAMINATION 27 12.3.5.1 Design Basis 27 12.3.5.2 Methods of Decontamination 27 12.3.5.3 Decontamination Facilities 27 Table 12.3-1 PLANT ZONE CLASSIFICATIONS 30 Table 12.3-2a PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-TERS - CALCULATED NEUTRON FLUXES (HISTORICAL) 31 Table 12.3-2b PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-TERS - DESIGN PARAMETERS (HISTORICAL) 32 Table 12.3-3 SECONDARY SHIELD DESIGN PARAMETERS (HISTORICAL) 33 Table 12.3-4 CONTAINMENT STRUCTURE DESIGN PARAMETERS (HISTOR-ICAL) 34 Table 12.3-5 REFUELING CANAL AND SPENT FUEL POOL DESIGN PARAM-ETERS (HISTORICAL) 35 Table 12.3-6 PRINCIPAL AUXILIARY SHIELDING (HISTORICAL) 36 12.4 DOSE ASSESSMENT 37 12.4.1 OPERATION IN MODES 1 AND 2 37 12.4.2 FUEL HANDLING OPERATIONS 37 12.4.3 POSTACCIDENT CONDITIONS 38 12.4.3.1 Summary 38 12.4.3.2 Methodology 39 12.4.3.2.1 Calculation of Dose Rates 39 12.4.3.2.2 Doses to Personnel During Postaccident Access to Vital Areas 39 12.4.3.3 Areas That May Require Access for Postaccident Operations 40 12.4.3.3.1 Hydrogen Recombiner Control Panel (Area A) 40 12.4.3.3.2 Postaccident Containment Air Sample Penetration No. 203 (Area B) 40 12.4.3.3.3 Nuclear Sample Room (Area C) 40 12.4.3.3.4 Primary Chemistry Laboratory (Area D) 41 12.4.3.3.5 Count Room (Area E) 41 12.4.3.3.6 Postaccident Containment Sample Penetration No. 305 (Area F) 41 12.4.3.3.7 Radwaste Control Panel (Area G) 41 12.4.3.3.8 Safeguards Bus 16 (Area H) 41  
Table 12.3-2b PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-                           32 TERS - DESIGN PARAMETERS (HISTORICAL)
Table 12.3-3 SECONDARY SHIELD DESIGN PARAMETERS (HISTORICAL)                           33 Table 12.3-4 CONTAINMENT STRUCTURE DESIGN PARAMETERS (HISTOR-                           34 ICAL)
Table 12.3-5 REFUELING CANAL AND SPENT FUEL POOL DESIGN PARAM-                         35 ETERS (HISTORICAL)
Table 12.3-6 PRINCIPAL AUXILIARY SHIELDING (HISTORICAL)                                 36 12.4         DOSE ASSESSMENT                                                           37 12.4.1       OPERATION IN MODES 1 AND 2                                                 37 12.4.2       FUEL HANDLING OPERATIONS                                                   37 12.4.3       POSTACCIDENT CONDITIONS                                                   38 12.4.3.1     Summary                                                                   38 12.4.3.2     Methodology                                                               39 12.4.3.2.1   Calculation of Dose Rates                                                 39 12.4.3.2.2   Doses to Personnel During Postaccident Access to Vital Areas               39 12.4.3.3     Areas That May Require Access for Postaccident Operations                 40 12.4.3.3.1   Hydrogen Recombiner Control Panel (Area A)                                 40 12.4.3.3.2   Postaccident Containment Air Sample Penetration No. 203 (Area B)           40 12.4.3.3.3   Nuclear Sample Room (Area C)                                               40 12.4.3.3.4   Primary Chemistry Laboratory (Area D)                                     41 12.4.3.3.5   Count Room (Area E)                                                       41 12.4.3.3.6   Postaccident Containment Sample Penetration No. 305 (Area F)               41 12.4.3.3.7   Radwaste Control Panel (Area G)                                           41 12.4.3.3.8   Safeguards Bus 16 (Area H)                                                 41 Page 2 of 3                        Revision 28 5/2019


GINNA/UFSAR 12.4.3.3.9   Safeguards Bus 14 (Area I)                                                   42 12.4.3.3.10   Postaccident Containment Air Sample Penetration (Area J)                     42 12.4.3.3.11   Auxiliary Building Heating, Ventilation, and Air Conditioning (Area         43 K) 12.4.3.3.12   Spent Fuel Pool (SFP) and Auxiliary Building Heating, Ventilation,           43 and Air Conditioning Filters (Area L and Area M) 12.4.3.3.13   Control Access High Efficiency Particulate Air and Charcoal Filters         43 (Area N) 12.4.3.3.14   Control Room                                                                 43 12.4.3.3.15   Control Room                                                                 43 Table 12.4-1 RADIATION MONITORING SYSTEM READINGS (1983)                                 45 Table 12.4-2 RADIATION SURVEY READINGS IN PLANT AREAS (1983)                             46 Table 12.4-3 Table DELETED                                                               48 Table 12.4-4 EXPOSURE RATES FOR VITAL AREAS AS A FUNCTION OF                             49 TIME (R/hr)
GINNA/UFSAR Page 3 of 3 Revision 28 5/2019 12.4.3.3.9 Safeguards Bus 14 (Area I) 42 12.4.3.3.10 Postaccident Containment Air Sample Penetration (Area J) 42 12.4.3.3.11 Auxiliary Building Heating, Ventilation, and Air Conditioning (Area K) 43 12.4.3.3.12 Spent Fuel Pool (SFP) and Auxiliary Building Heating, Ventilation, and Air Conditioning Filters (Area L and Area M) 43 12.4.3.3.13 Control Access High Efficiency Particulate Air and Charcoal Filters (Area N) 43 12.4.3.3.14 Control Room 43 12.4.3.3.15 Control Room 43 Table 12.4-1 RADIATION MONITORING SYSTEM READINGS (1983) 45 Table 12.4-2 RADIATION SURVEY READINGS IN PLANT AREAS (1983) 46 Table 12.4-3 Table DELETED 48 Table 12.4-4 EXPOSURE RATES FOR VITAL AREAS AS A FUNCTION OF TIME (R/hr) 49 Table 12.4-5 VITAL AREA RADIATION DOSE  
Table 12.4-5 VITAL AREA RADIATION DOSE  


==SUMMARY==
==SUMMARY==
50 12.5         RADIATION PROTECTION PROGRAM ADMINISTRATION                                 51 12.5.1       ORGANIZATION                                                                 51 12.5.2       EXPOSURE CONTROL PROGRAM                                                     51 12.5.2.1     External Exposure                                                           51 12.5.2.2     Internal Exposure                                                           51 12.5.2.3     Respiratory Protection                                                       52 12.5.2.4     Radioactive Sources Control                                                 52 12.5.2.5     Medical Examinations                                                         52 12.5.3       SURVEILLANCE PROGRAM                                                         53 12.5.3.1     Surveys                                                                     53 12.5.3.2     Radiation Work Permits                                                       53 12.5.3.3     Access Control, Posting, and Labeling                                       53 12.5.3.3.1   Restricted Areas                                                             53 12.5.3.3.2   Access Control                                                               53 12.5.3.3.3   Protective Apparel                                                           54 12.5.4       RADIATION PROTECTION FACILITIES AND EQUIPMENT                               54 Table 12.5-1 Table DELETED                                                               56 FIGURES Figure 12.5-1 Figure DELETED Page 3 of 3                        Revision 28 5/2019}}
50 12.5 RADIATION PROTECTION PROGRAM ADMINISTRATION 51 12.5.1 ORGANIZATION 51 12.5.2 EXPOSURE CONTROL PROGRAM 51 12.5.2.1 External Exposure 51 12.5.2.2 Internal Exposure 51 12.5.2.3 Respiratory Protection 52 12.5.2.4 Radioactive Sources Control 52 12.5.2.5 Medical Examinations 52 12.5.3 SURVEILLANCE PROGRAM 53 12.5.3.1 Surveys 53 12.5.3.2 Radiation Work Permits 53 12.5.3.3 Access Control, Posting, and Labeling 53 12.5.3.3.1 Restricted Areas 53 12.5.3.3.2 Access Control 53 12.5.3.3.3 Protective Apparel 54 12.5.4 RADIATION PROTECTION FACILITIES AND EQUIPMENT 54 Table 12.5-1 Table DELETED 56 FIGURES Figure 12.5-1 Figure DELETED}}

Latest revision as of 02:16, 5 January 2025

8 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents
ML19150A486
Person / Time
Site: Ginna 
Issue date: 05/10/2019
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19150A453 List: ... further results
References
Download: ML19150A486 (3)


Text

GINNA/UFSAR Page 1 of 3 Revision 28 5/2019 12 RADIATION PROTECTION 1

12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE 2

12.1.1 ALARA PROGRAM 2

12.1.2 ORGANIZATIONAL RESPONSIBILITIES 2

12.1.3 RADIATION PROTECTION PROGRAM 2

12.2 RADIATION SOURCES 3

Table 12.2-1 SHIELDING SOURCE TERMS (T=0) (HISTORICAL) 6 Table 12.2-2 SHIELDING SOURCE ACTIVITY at T=0 hrs - Power Level 1811 MWt 10 12.3 RADIATION PROTECTION DESIGN FEATURES 16 12.3.1 DESIGN CRITERIA 16 12.3.1.1 Conformance to 1967 Design Criteria 16 12.3.1.2 Conformance to 1972 Design Criteria 16 12.3.2 SHIELDING 17 12.3.2.1 Design Basis 17 12.3.2.2 Shielding Design 19 12.3.2.2.1 Primary Shield 19 12.3.2.2.2 Secondary Shield 19 12.3.2.2.3 Containment Structure 20 12.3.2.2.4 Fuel Handling (Water and Pool) Shield 20 12.3.2.2.5 Auxiliary Shielding 21 12.3.2.2.6 Shielding Design Modifications 21 12.3.2.2.7 Containment Accessibility Procedure 22 12.3.3 VENTILATION 22 12.3.3.1 Gas Collection and Decay Tank System 23 12.3.3.2 Plant Ventilation System 23 12.3.3.3 Containment Ventilation System 24 12.3.3.4 Air Ejector and Gland Seal Exhaust System 24 12.3.4 AREA RADIATION AND AIRBORNE RADIOACTIVITY MONI-TORING INSTRUMENTATION 24 12.3.4.1 Introduction 24

GINNA/UFSAR Page 2 of 3 Revision 28 5/2019 12.3.4.2 Description 25 12.3.4.3 Radiation Monitoring System Detectors 26 12.3.5 EQUIPMENT AND SYSTEM DECONTAMINATION 27 12.3.5.1 Design Basis 27 12.3.5.2 Methods of Decontamination 27 12.3.5.3 Decontamination Facilities 27 Table 12.3-1 PLANT ZONE CLASSIFICATIONS 30 Table 12.3-2a PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-TERS - CALCULATED NEUTRON FLUXES (HISTORICAL) 31 Table 12.3-2b PRIMARY SHIELD NEUTRON FLUXES AND DESIGN PARAME-TERS - DESIGN PARAMETERS (HISTORICAL) 32 Table 12.3-3 SECONDARY SHIELD DESIGN PARAMETERS (HISTORICAL) 33 Table 12.3-4 CONTAINMENT STRUCTURE DESIGN PARAMETERS (HISTOR-ICAL) 34 Table 12.3-5 REFUELING CANAL AND SPENT FUEL POOL DESIGN PARAM-ETERS (HISTORICAL) 35 Table 12.3-6 PRINCIPAL AUXILIARY SHIELDING (HISTORICAL) 36 12.4 DOSE ASSESSMENT 37 12.4.1 OPERATION IN MODES 1 AND 2 37 12.4.2 FUEL HANDLING OPERATIONS 37 12.4.3 POSTACCIDENT CONDITIONS 38 12.4.3.1 Summary 38 12.4.3.2 Methodology 39 12.4.3.2.1 Calculation of Dose Rates 39 12.4.3.2.2 Doses to Personnel During Postaccident Access to Vital Areas 39 12.4.3.3 Areas That May Require Access for Postaccident Operations 40 12.4.3.3.1 Hydrogen Recombiner Control Panel (Area A) 40 12.4.3.3.2 Postaccident Containment Air Sample Penetration No. 203 (Area B) 40 12.4.3.3.3 Nuclear Sample Room (Area C) 40 12.4.3.3.4 Primary Chemistry Laboratory (Area D) 41 12.4.3.3.5 Count Room (Area E) 41 12.4.3.3.6 Postaccident Containment Sample Penetration No. 305 (Area F) 41 12.4.3.3.7 Radwaste Control Panel (Area G) 41 12.4.3.3.8 Safeguards Bus 16 (Area H) 41

GINNA/UFSAR Page 3 of 3 Revision 28 5/2019 12.4.3.3.9 Safeguards Bus 14 (Area I) 42 12.4.3.3.10 Postaccident Containment Air Sample Penetration (Area J) 42 12.4.3.3.11 Auxiliary Building Heating, Ventilation, and Air Conditioning (Area K) 43 12.4.3.3.12 Spent Fuel Pool (SFP) and Auxiliary Building Heating, Ventilation, and Air Conditioning Filters (Area L and Area M) 43 12.4.3.3.13 Control Access High Efficiency Particulate Air and Charcoal Filters (Area N) 43 12.4.3.3.14 Control Room 43 12.4.3.3.15 Control Room 43 Table 12.4-1 RADIATION MONITORING SYSTEM READINGS (1983) 45 Table 12.4-2 RADIATION SURVEY READINGS IN PLANT AREAS (1983) 46 Table 12.4-3 Table DELETED 48 Table 12.4-4 EXPOSURE RATES FOR VITAL AREAS AS A FUNCTION OF TIME (R/hr) 49 Table 12.4-5 VITAL AREA RADIATION DOSE

SUMMARY

50 12.5 RADIATION PROTECTION PROGRAM ADMINISTRATION 51 12.5.1 ORGANIZATION 51 12.5.2 EXPOSURE CONTROL PROGRAM 51 12.5.2.1 External Exposure 51 12.5.2.2 Internal Exposure 51 12.5.2.3 Respiratory Protection 52 12.5.2.4 Radioactive Sources Control 52 12.5.2.5 Medical Examinations 52 12.5.3 SURVEILLANCE PROGRAM 53 12.5.3.1 Surveys 53 12.5.3.2 Radiation Work Permits 53 12.5.3.3 Access Control, Posting, and Labeling 53 12.5.3.3.1 Restricted Areas 53 12.5.3.3.2 Access Control 53 12.5.3.3.3 Protective Apparel 54 12.5.4 RADIATION PROTECTION FACILITIES AND EQUIPMENT 54 Table 12.5-1 Table DELETED 56 FIGURES Figure 12.5-1 Figure DELETED