ML16203A426
| ML16203A426 | |
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| Site: | Wolf Creek  |
| Issue date: | 05/31/2016 |
| From: | Wolf Creek |
| To: | Office of Nuclear Reactor Regulation |
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Text
WOLF CREEK TABLE OF CONTENTS CHAPTER 11.0 RADIOACTIVE WASTE MANAGEMENT
Section Page
11.1 SOURCE TERMS 11.1-1
11.1.1 RADIOACTIVE CONCENTRATIONS AND RELEASES 11.1-1 11.1.2 SHIELDING 11.1-1 11.1.3 ACCIDENT ANALYSIS SOURCE TERMS 11.1-1
App. 11.lA PARAMETERS FOR CALCULATION OF SOURCE 11.lA-1 TERMS FOR EXPECTED RADIOACTIVE CONCEN-
TRATIONS AND RELEASES
11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2-1
11.2.1 DESIGN BASES 11.2-1
11.2.1.1 Safety Design Basis 11.2-1 11.2.1.2 Power Generation Design Bases 11.2-1
11.2.2 SYSTEM DESCRIPTION 11.2-1
11.2.2.1 General Description 11.2-1 11.2.2.2 Component Description 11.2-6 11.2.2.3 System Operation 11.2-9
11.2.3 RADIOACTIVE RELEASES 11.2-13 11.2.3.1 Sources 11.2-13 11.2.3.2 Release Points 11.2-13 11.2.3.3 Dilution Factors 11.2-14 11.2.3.4 Estimated Doses 11.2-14 11.2.4 CALCULATED BASIS FOR LIQUID SOURCE TERMS 11.2-14
11.2.5 SAFETY EVALUATION 11.2-15 11.2.6 TESTS AND INSPECTION 11.2-15 11.2.7 INSTRUMENTATION DESIGN 11.2-15 11.
2.8 REFERENCES
11.2-15
11.3 GASEOUS WASTE MANAGEMENT SYSTEMS 11.3-1
11.3.1 DESIGN BASES 11.3-1
11.0-i Rev. 29 WOLF CREEK TABLE OF CONTENTS (Continued)
Section Page
11.3.1.1 Safety Design Basis 11.3-1 11.3.1.2 Power Generation Design Bases 11.3-1
11.3.2 SYSTEM DESCRIPTIONS 11.3-2 11.3.2.1 General Description 11.3-2 11.3.2.2 Component Description 11.3-4 11.3.2.3 System Operation 11.3-6
11.3.3 RADIOACTIVE RELEASES 11.3-7
11.3.3.1 Sources 11.3-7 11.3.3.2 Release Points 11.3-8 11.3.3.3 Dilution Factors 11.3-8 11.3.3.4 Estimated Doses 11.3-8
11.3.4 SAFETY EVALUATION 11.3-9 11.3.5 TESTS AND INSPECTIONS 11.3-9 11.3.6 INSTRUMENTATION APPLICATION 11.3-9 11.
3.7 REFERENCES
11.3-12
11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4-1
11.4.1 DESIGN BASES 11.4-1 11.4.1.1 Safety Design Bases 11.4-1 11.4.1.2 Power Design Bases 11.4-1
11.4.2 SYSTEM DESCRIPTION 11.4-3 11.4.2.1 General Description 11.4-3 11.4.2.2 Component Description 11.4-4 11.4.2.3 System Operation 11.4-5 11.4.2.4 Packaging, Storage, and Shipment 11.4-9 11.4.3 SAFETY EVALUATION 11.4-10 11.4.4 TESTS AND INSPECTIONS 11.4-11 11.4.5 INSTRUMENTATION APPLICATION 11.4-11
Appendix 11.4A Interim Onsite Storage 11.4A-1
11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5-1
11.5.1 DESIGN BASES 11.5-1
11.0-ii Rev. 29 WOLF CREEK TABLE OF CONTENTS (Continued)
Section Page
11.5.1.1 Safety Design Bases 11.5-1 11.5.1.2 Power Generation Design Bases 11.5-2 11.5.1.3 Codes and Standards 11.5-3
11.5.2 SYSTEM DESCRIPTION 11.5-3
11.5.2.1 General Description 11.5-3 11.5.2.2 Liquid Monitoring Systems 11.5-6 11.5.2.3 Airborne Monitoring Systems 11.5-12 11.5.2.4 Safety Evaluation 11.5-18
11.5.3 EFFLUENT MONITORING AND SAMPLING 11.5-19 11.5.4 PROCESS MONITORING AND SAMPLING 11.5-19
11.0-iii Rev. 29 WOLF CREEK TABLE OF CONTENTS (Continued)
LIST OF TABLES
Number Title
11.1-1 Reactor Coolant and Secondary Coolant Specific Activities 0.12-Percent Fuel Defects
11.1-2 Annual Effluent Releases - Liquid
11.1-3 Comparison of the Design to Regulatory Positions Of Regulatory Guide 1.112, Revision 0, Dated April, 1976, Titled "Calculation of
Releases of Radioactive Materials in Gaseous
and Liquid Effluents from Light-Water-Cooled
Power Reactors" 11.1-4 Reactor Coolant and Secondary Coolant
Shielding Source Terms - 0.25 Percent Fuel
Defects
11.1-6 Contained Sources of the Radioactive Waste Management Systems and Large Potentially
Radioactive Outside Storage Tanks
11.lA-1 Plant Data for Source Term Calculations 11.lA-2 Parameters Used in the Calculation of
Estimated Activity in Liquid Wastes
11.lA-3 Description of Major Sources of Gaseous Releases
11.lA-4 Characteristics of Release Points and Releases
11.2-1 Liquid Waste Processing System Equipment Principal Design Parameters
11.2-2 Tank Uncontrolled Release Protection
Provisions
11.0-iv Rev. 29 WOLF CREEK TABLE OF CONTENTS (Continued)
Number Title
11.2-3 Deleted 11.2-4 Deleted 11.2-5 Deleted 11.2-6 Deleted
11.2-7 Deleted
11.2-8 Deleted
11.2-9 Deleted 11.2-10 Deleted 11.2-11 Deleted
11.2-12 Liquid Waste Management System Instrumentation Principal Design Parameters
11.3-1 Gaseous Waste Processing System Major Component
Description
11.3-2 Deleted 11.3-3 Deleted
11.3-4 Deleted
11.0-v Rev. 14 WOLF CREEK TABLE OF CONTENTS (Continued)
Number Title
11.3-5 Gaseous Waste Processing System
Instrumentation Design Parameters
11.4-1 Design Comparison to Branch Technical Position ETSB 11-3 Revision 2, "Design Guidance for Solid Radioactive Waste Management System
Installed in Light-Water-Cooled Nuclear Power
Reactor Plants
11.4-2 Deleted
11.4-3 Deleted
11.4-4 Deleted 11.4-5 Solid Radwaste System - Component Description
11.4A Interim On-Site Storage Facility
11.5-1 Liquid Process Radioactivity Monitors
11.5-2 Liquid Effluent Radioactivity Monitors
11.5-3 Airborne Process Radioactivity Monitors 11.5-4 Airborne Effluent Radioactivity Monitors
11.5-5 Power Supplies for Process and Effluent
Monitors
11.0-vi Rev. 29 WOLF CREEK CHAPTER 11 - LIST OF FIGURES
- Refer to Section 1.6 and Table 1.6-3. Controlled drawings were removed from the USAR at Revision 17 and are considered incorporated by reference.
Figure # Sheet Title Drawing #* 11.1A-1 0 Liquid Waste Treatment Systems Block Diagram 11.1A-2 1 System Decontamination Factors 11.1A-2 2 System Decontamination Factors 11.1A-2 3 System Decontamination Factors 11.1A-2 3A System Decontamination Factors 11.1A-2 4 System Decontamination Factors 11.1A-2 4A Deleted 11.1A-2 5 System Decontamination Factors 11.1A-2 6 System Decontamination Factors 11.1A-2 7 System Decontamination Factors 11.1A-3 0 Potential Gaseous Release 11.2-1 1 Liquid Radwaste System M-12HB01 11.2-1 2 Liquid Radwaste System M-12HB02 11.2-1 3 Liquid Radwaste System M-12HB03 11.2-1 4 Liquid Radwaste System M-12HB04 11.2-1 5 Radioactive Liquid Release Flow Diagram 11.3-1 1 Gaseous Radwaste System M-12HA01 11.3-1 2 Gaseous Radwaste System M-12HA02 11.3-1 3 Gaseous Radwaste System M-12HA03 11.3-2 0 Potential Gaseous Release 11.3-3 0 Compressor Package Instruments 11.3-4 0 Hydrogen Recombiner Instruments 11.4-1 1 Solid Radwaste System M-12HC01 11.4-1 2 Solid Radwaste System M-12HC02 11.4-1 3 Solid Radwaste System M-12HC03 11.4-1 4 Solid Radwaste System M-12HC04 11.4-2 0 Deleted
11.0-vii Rev. 29 WOLF CREEK CHAPTER 11.0 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS This section presents the design bases for determining the source terms for radioactive releases from the plant, for shielding within the plant, and for accident analysis performed in Chapter 15.0. The source terms used for releases, shielding, and accident analyses are based on 0.12, 0.25, and 1.0
percent fuel defects, respectively.
Actual release data is contained in Annual Radioactive Effluent Release Reports filed with the NRC in accordance with Offsite Dose Calculation Manual (ODCM) requirements. Data supporting Chapter 15 accident analyses is not considered historical and is maintained current.
11.1.1 RADIOACTIVE CONCENTRATIONS AND RELEASES Reactor coolant and secondary coolant specific activities for an assumed 0.12-percent fuel defects and an assumed 100 pounds per day primary-to-secondary
leakage are listed in Table 11.1-1. The basis for calculating these sources is Regulatory Guide 1.112. Compliance with Regulatory Guide 1.112 is discussed in Table 11.1-3. Appendix 11.1A provides a description of the input used.
The decontamination factors applied are based on Regulatory Guide 1.112. A description of liquid leakage rates, process paths, and associated component activity levels is contained in Section 11.2 and Appendix 11.1A. A description of gaseous leakage rates, process paths, and associated activity levels is
contained in Appendix 11.1A and Sections 11.3 and 9.4. In-plant airborne
activity concentrations and other data regarding the ventilation systems are
provided in Sections 12.3 and 12.4.
11.1.2 SHIELDING Reactor coolant and secondary coolant source terms used for shielding are based on 0.25-percent fuel defects. The source terms and the parameters used to calculate the source terms are given in Table 11.1-4 and Appendix 11.1A, respectively. Table 11.1-6 provides the isotopic composition of the contained
sources for radioactive waste management systems and for large, potentially
radioactive outside storage tanks.
11.1.3 ACCIDENT ANALYSIS SOURCE TERMS Except for a LOCA and a fuel handling accident, the specific activity used for accident analysis releases is based on operating with 1-percent fuel defects which results in a RCS activity limit more limiting than the Technical Specification 3.4.16 limit of 500 uci/gm DOSE EQUIVALENT XE-133. Table 11.1-5 provides the isotopic 11.1-1 Rev. 21 WOLF CREEK composition of the reactor coolant based on 1 percent fuel defects. Table 11.1-5 also identifies those isotopes excluded from the Technical Specification definition of DOSE EQUIVALENT XE-133 based on low concentration, short half life, or small dose conversion factors. Table 11.1-6 provides the inventory of the contained sources for radioactive waste management systems and for large, potentially radioactive outside storage tanks.
Sources for the LOCA are based on TID 14844.
Sources for the fuel handling accident are based on Regulatory Guide 1.25.
Chapter 15.0 provides a complete discussion and a listing of the source terms for each accident analyzed. 11.1-2 Rev. 21 WOLF CREEK TABLE 11.1-1 Reactor Coolant and Secondary Coolant Specific Activities - 0.125% Fuel Defects (1)Class 1 Reactor Coolant Ci/gm Secondary Coolant Ci/gm Kr-83m 6.93E-02 2.40E-06 Kr-85m 2.83E-01 8.88E-06 Kr-85 1.18E+00 3.70E-05 Kr-87 1.84E-01 5.77E-06 Kr-88 5.33E-01 1.67E-05 Kr-89 1.51E-02 4.64E-07 Xe-131m 4.26E-01 1.34E-05 Xe-133 3.63E+01 1.14E-03 Xe-133m 6.71E-01 2.17E-05 Xe-135m 7.55E-02 1.08E-05 Xe-135 1.23E+00 4.00E-05 Xe-137 2.80E-02 8.62E-07 Xe-138 1.02E-01 3.19E-06 Total noble gas 4.11E+01 1.30E-03 Class 2 Br-83 1.36E-02 2.48E-05 Br-84 7.28E-03 5.48E-06 Br-85 8.57E-04 7.50E-08 I-130 4.47E-03 1.20E-05 I-131 3.50E-01 1.06E-03 I-132 3.93E-01 7.47E-04 I-133 6.16E-01 1.74E-03 I-134 9.40E-02 1.03E-04 I-135 3.60E-01 8.81E-04 Total halogens 1.84E+00 4.75E-03 Rev. 16 WOLF CREEK TABLE 11.1-1 (Sheet 2)
Reactor Coolant and Secondary Coolant Specific Activities - 0.125% Fuel Defects (1)Class 3 Reactor Coolant
µCi/gm Secondary Coolant
µCi/gm Rb-86 3.56E-03 1.96E-05 Rb-88 6.70E-01 3.40E-04 Rb-89 3.07E-02 1.35E-05 Cs-134 2.93E-01 1.62E-03 Cs-136 3.52E-01 1.93E-03 Cs-137 2.42E-01 1.34E-03 Cs-138 1.57E-01 1.34E-04 Total Cs, Rb 1.75E+00 5.40E-03 Class 4 N-16 1.31E+02 3.12E-10 Water activation product Class 5 H-3 3.50E+00 2.19E+00 Tritium Class 6 Cr-51 1.90E-03 5.83E-06 Mn-54 3.10E-04 9.53E-07 Fe-55 1.60E-03 4.92E-06 Fe-59 1.00E-03 3.07E-06 Co-58 1.60E-02 4.92E-05 Co-60 2.00E-03 6.15E-06 Sr-89 6.39E-04 3.55E-06 Sr-90 2.38E-05 1.31E-07 Sr-91 8.42E-04 3.55E-06 Y-90 1.85E-04 4.92E-07 Sr-92 6.48E-06 2.27E-08 Y-91m 4.94E-04 1.87E-06 Y-91 7.14E-05 2.23E-07 Rev. 13 WOLF CREEK TABLE 11.1-1 (Sheet 3)
Reactor Coolant and Secondary Coolant Specific Activities - 0.125% Fuel Defects (1)Class 6 Reactor Coolant
µCi/gm Secondary Coolant
µCi/gm Y-93 5.46E-05 1.45E-07 Zr-95 8.15E-05 2.50E-07 Nb-95 8.17E-05 2.51E-07 Mo-99 1.02E-01 3.07E-04 Tc-99m 9.43E-02 2.85E-04 Ru-103 6.69E-05 2.05E-07 Ru-106 2.06E-05 6.34E-08 Rh-103m 6.64E-05 2.05E-07 Rh-106 2.06E-05 3.21E-10 Ag-110m 1.64E-04 5.03E-07 Te-125m 7.40E-05 2.27E-07 Te-127m 3.69E-04 1.13E-06 Te-127 1.63E-03 4.42E-06 Te-129m 1.29E-03 3.95E-06 Te-129 1.70E-03 3.64E-06 Te-131m 3.19E-03 9.30E-06 Te-131 1.79E-03 2.45E-06 Te-132 3.74E-02 1.13E-04 Te-134 4.62E-03 4.27E-06 Ba-137m 2.29E-01 1.25E-03 Ba-140 5.17E-04 1.58E-06 La-140 1.69E-04 5.60E-07 Ce-141 7.92E-05 2.43E-07 Ce-143 6.91E-05 2.03E-07 Ce-144 5.87E-05 1.80E-07 Pr-143 7.67E-05 2.36E-07 Pr-144 5.87E-05 1.80E-07 Total other isotopes 5.05E-01 2.07E-03 Note (3)(1) Refer to Table 11.1A-1 for assumptions.
(2) For the secondary side, the noble gas activities are for the steam phase; all other activities are for the steam generator water activities.
(3) Lower blowdown rates result in higher secondary system activities.
A 60-gpm blowdown will result in a total of 5.85E-2
µCi/gm (excluding noble gases, N-16, and tritium) in the steam generator.
A maximum blowdown rate was used in this table.
Rev. 13 WOLFCREEKTABLE11.1-2TableDeletedRev.14 WOLF CREEK TABLE 11.1-3 COMPARISON OF THE DESIGN TO REGULATORY POSITIONS OF REGULATORY GUIDE 1.112, REVISION 0, DATED APRIL, 1976, TITLED "CALCULATION OF RELEASES OF RADIOACTIVE MATERIALS
IN GASEOUS AND LIQUID EFFLUENTS FROM LIGHT-WATER-COOLED
POWER REACTORS" Regulatory Guide 1.112 Position WCGS
- 1. Each application for a per- 1. Inplant control meas-
mit to construct a nuclear power ures to maintain radioactive
reactor should include in-plant releases as low as is rea-
control measures to maintain sonably achievable have been
releases of radioactive materials incorporated in the design.
in liquid and gaseous effluents
to the environment as low as is
reasonably achievable in accor-
dance with the requirements of
Paragraph 20.1(c) of 10 CFR Part
20 and of Paragraph 50.34a, Para-
graph 50.36a, and Appendix I of
10 CFR Part 50. For gaseous
effluents, such measures could
include storage for decay of
noble gases removed from the pri-
mary coolant and charcoal adsor-
bers or HEPA filters to remove
radioiodine and radioactive par-
ticulates released from building
ventilation exhaust systems. For
liquid effluents, such measures
could include storage for decay, demineralization, reverse osmosis, and evaporation.
- 2. The method of calculation 2. Parameters of NUREG-described in NUREG-0016 and NUREG- 0017 are used as discussed
0017 and the parameters presented in Appendix 11.lA. The
in Chapter 2 of each report should method of calculation des-
be used to calculate the quanti- cribed in NUREG-0017 has
ties of radioactive materials in been generally followed.
gaseous and liquid effluents from
light-water-cooled nuclear power
reactors.3. If methods and parameters 3. Justification for used in calculating source terms use of assumptions other
are different from those given than those used in NUREG-
in NUREG-0016 and NUREG-0017, 0017 are provided in
they should be described in detail Appendix 11.lA.
and in the Environmental Report
the basis for the methods and para-
meters used should be provided.
Rev. 0 WOLF CREEK TABLE 11.1-4 REACTOR COOLANT AND SECONDARY COOLANT SHIELDING SOURCE TERMS - 0.25 PERCENT FUEL DEFECTS (1)Class 1 Reactor Coolant
µCi/gm Secondary Coolant
µCi/gm Kr-83m 1.39E-01 4.80E-06 Kr-85m 5.66E-01 1.78E-05 Kr-85 2.35E+00 7.40E-05 Kr-87 3.68E-01 1.15E-05 Kr-88 1.07E+00 3.35E-05 Kr-89 3.03E-02 9.28E-07 Xe-131m 8.53E-01 2.68E-05 Xe-133 7.26E+01 2.28E-03 Xe-133m 1.34E+00 4.33E-05 Xe-135m 1.51E-01 2.16E-05 Xe-135 2.45E+00 7.99E-05 Xe-137 5.59E-02 1.72E-06 Xe-138 2.04E-01 6.37E-06 Total noble gas 8.21E+01 2.60E-03 Class 2 Br-83 2.73E-02 4.96E-05 Br-84 1.46E-02 1.10E-05 Br-85 1.71E-03 1.50E-07 I-130 8.93E-03 2.41E-05 I-131 6.99E-01 2.11E-03 I-132 7.85E-01 1.49E-03 I-133 1.23E+00 3.48E-03 I-134 1.88E-01 2.07E-04 I-135 7.19E-01 1.76E-03 Total halogens 3.68E+00 9.14E-03 Rev. 13 WOLF CREEK TABLE 11.1-4 (Sheet 2)
Reactor Coolant and Secondary Coolant Specific Activities - 0.25% Fuel Defects (1)Class 3 Reactor Coolant
µCi/gm Secondary Coolant
µCi/gm Rb-86 7.13E-03 3.91E-05 Rb-88 1.34E+00 6.80E-04 Rb-89 6.15E-02 2.71E-05 Cs-134 5.87E-01 3.25E-03 Cs-136 7.05E-01 3.86E-03 Cs-137 4.85E-01 2.68E-03 Cs-138 3.14E-01 2.68E-04 Total Cs, Rb 3.50E+00 1.08E-02 Class 4 N-16 1.31E+02 3.12E-10 Water activation product Class 5 H-3 3.50E+00 2.19E+00 Tritium Class 6 Cr-51 1.90E-03 5.83E-06 Mn-54 3.10E-04 9.53E-07 Fe-55 1.60E-03 4.92E-06 Fe-59 1.00E-03 3.07E-06 Co-58 1.60E-02 4.92E-05 Co-60 2.00E-03 6.15E-06 Sr-89 1.28E-03 7.10E-06 Sr-90 4.76E-05 2.63E-07 Sr-91 1.68E-03 7.10E-06 Y-90 3.70E-04 9.83E-07 Sr-92 1.30E-05 4.54E-08 Y-91m 9.88E-04 3.74E-06 Y-91 1.43E-04 4.47E-07 Rev. 13 WOLF CREEK TABLE 11.1-4 (Sheet 3)
Reactor Coolant and Secondary Coolant Specific Activities - 0.25% Fuel Defects (1)Class 6 Reactor Coolant
µCi/gm Secondary Coolant
µCi/gm Y-93 1.09E-04 2.89E-07 Zr-95 1.63E-04 5.01E-07 Nb-95 1.63E-04 5.02E-07 Mo-99 2.05E-01 6.15E-04 Tc-99m 1.89E-01 5.69E-04 Ru-103 1.34E-04 4.11E-07 Ru-106 4.13E-05 1.27E-07 Rh-103m 1.33E-04 4.10E-07 Rh-106 4.13E-05 6.43E-10 Ag-110m 3.28E-04 1.01E-06 Te-125m 1.48E-04 4.55E-07 Te-127m 7.38E-04 2.27E-06 Te-127 3.25E-03 8.85E-06 Te-129m 2.58E-03 7.90E-06 Te-129 3.40E-03 7.28E-06 Te-131m 6.37E-03 1.86E-05 Te-131 3.58E-03 4.91E-06 Te-132 7.48E-02 2.25E-04 Te-134 9.24E-03 8.55E-06 Ba-137m 4.58E-01 2.51E-03 Ba-140 1.03E-03 3.17E-06 La-140 3.38E-04 1.12E-06 Ce-141 1.58E-04 4.86E-07 Ce-143 1.38E-04 4.05E-07 Ce-144 1.17E-04 3.61E-07 Pr-143 1.53E-04 4.71E-07 Pr-144 1.17E-04 3.61E-07 Total other isotopes 9.86E-01 4.07E-03 Note (3)(1)Refer to Table 11.1A-1 for assumptions.(2)For the secondary side, the noble gas activities are for the steam phase; all other activities are for the steam generator water activities.(3)Lower blowdown rates result in higher secondary system activities. A 60-gpm blowdown will result in a total of 1.17E-1µCi/gm (excluding noble gases, N-16, and tritium) in the steam generator. A maximum blowdown rate was used in this table.
Rev. 13 WOLF CREEK TABLE 11.1-5 Reactor Coolant and Secondary Coolant Specific Activities - 1% Fuel Defects (1)Class 1 Reactor Coolant Ci/gm Secondary Coolant Ci/gm Kr-83m*5.54E-01 1.92E-05 Kr-85m 2.26E+00 7.10E-05 Kr-85*9.41E+00 2.96E-04 Kr-87 1.47E+00 4.62E-05 Kr-88 4.26E+00 1.34E-04 Kr-89*1.21E-01 3.71E-06 Xe-131m*3.41E+00 1.07E-04 Xe-133 2.90E+02 9.12E-03 Xe-133m 5.37E+00 1.73E-04 Xe-135m 6.04E-01 8.62E-05 Xe-135 9.82E+00 3.20E-04 Xe-137*2.24E-01 6.90E-06 Xe-138 8.15E-01 2.55E-05 Total noble gas 3.29E+02 1.04E-02 Class 2 Br-83 1.09E-01 1.98E-04 Br-84 5.82E-02 4.38E-05 Br-85 6.86E-03 6.00E-07 I-130 3.57E-02 9.62E-05 I-131 2.80E+00 8.46E-03 I-132 3.14E+00 5.97E-03 I-133 4.93E+00 1.39E-02 I-134 7.52E-01 8.27E-04 I-135 2.88E+00 7.05E-03 Total halogens 1.47E+01 3.66E-02
- Excluded from Technical Specification definition of DOSE EQUIVALENT XE-133.
Rev. 21 WOLF CREEK TABLE 11.1-5 (Sheet 2)
Reactor Coolant and Secondary Coolant Specific Activities - 1% Fuel Defects (1)Class 3 Reactor Coolant Ci/gm Secondary Coolant Ci/gm Rb-86 2.85E-02 1.56E-04 Rb-88 5.36E+00 2.72E-03 Rb-89 2.46E-01 1.08E-04 Cs-134 2.35E+00 1.30E-02 Cs-136 2.82E+00 1.54E-02 Cs-137 1.94E+00 1.07E-02 Cs-138 1.25E+00 1.07E-03 Total Cs, Rb 1.40E+01 4.32E-02 Class 4 N-16 1.31E+02 3.12E-10 Water activation product Class 5 H-3 3.50E+00 2.19E+00 Tritium Class 6 Cr-51 1.90E-03 5.83E-06 Mn-54 3.10E-04 9.53E-07 Fe-55 1.60E-03 4.92E-06 Fe-59 1.00E-03 3.07E-06 Co-58 1.60E-02 4.92E-05 Co-60 2.00E-03 6.15E-06 Sr-89 5.11E-03 2.84E-05 Sr-90 1.90E-04 1.05E-06 Sr-91 6.73E-03 2.84E-05 Sr-92 1.48E-03 3.93E-06 Y-90 5.19E-05 1.82E-07 Y-91m 3.95E-03 1.49E-05 Y-91 5.71E-04 1.79E-06 Rev. 13 WOLF CREEK TABLE 11.1-5 (Sheet 3)
Reactor Coolant and Secondary Coolant Specific Activities - 1% Fuel Defects (1)Class 6 Reactor Coolant Ci/gm Secondary Coolant Ci/gm Y-93 4.37E-04 1.16E-06 Zr-95 6.52E-04 2.00E-06 Nb-95 6.53E-04 2.01E-06 Mo-99 8.19E-01 2.46E-03 Tc-99m 7.54E-01 2.28E-03 Ru-103 5.35E-04 1.64E-06 Ru-106 1.65E-04 5.07E-07 Rh-103m 5.31E-04 1.64E-06 Rh-106 1.65E-04 2.57E-09 Ag-110m 1.31E-03 4.03E-06 Te-125m 5.92E-04 1.82E-06 Te-127m 2.95E-03 9.07E-06 Te-127 1.30E-02 3.54E-05 Te-129m 1.03E-02 3.16E-05 Te-129 1.36E-02 2.91E-05 Te-131m 2.55E-02 7.44E-05 Te-131 1.43E-02 1.96E-05 Te-132 2.99E-01 9.01E-04 Te-134 3.70E-02 3.42E-05 Ba-137m 1.83E+00 1.00E-02 Ba-140 4.14E-03 1.27E-05 La-140 1.35E-03 4.48E-06 Ce-141 6.34E-04 1.95E-06 Ce-143 5.53E-04 1.62E-06 Ce-144 4.69E-04 1.44E-06 Pr-143 6.13E-04 1.88E-06 Pr-144 4.69E-04 1.44E-06__________
__________
Total other isotopes 3.88E+00 1.61E-02 Note (3) (1) Refer to Table 11.1A-1 for assumptions. (2) For the secondary side, the noble gas activities are for the steam phase; all other activities are for the steam generator water activities. (3) Lower blowdown rates result in higher secondary system activities. A 60-gpm blowdown will result in a total of 4.65E-1 Ci/gm (excluding noble gases, N-16, and tritium) in the steam generator. A maximum blowdown rate was used in this table.
Rev. 13 WOLFCREEKTABLE11.1-6CONTAINEDSOURCESOFTHERADIOACTIVEWASTEMANAGEMENTSYSTEMSANDLARGEPOTENTIALLYRADIOACTIVEOUTSIDESTORAGETANKSComponent:RefuelingWaterDiameter,ft:40.0StorageTankLocation:OutsideHeight,ft:34.5Sourcevolume,gal(1):133,600Inventory(2)Concentration(3)Inventory(2)
Concentration(3)Class1 Ci Ci/gmClass5 CiµCi/gm Kr-83m NEG NEG H-3 3.79E+03 2.5E+0 Kr-85m NEG NEG Kr-85 NEG NEG Kr-87 NEG NEGClass6 Kr-88 NEG NEG Kr-89 NEG NEG Cr-51 3.47E-05 2.29E-08 Xe-131m NEG NEG Mn-54 6.99E-06 4.62E-09 Xe-133m NEG NEG Fe-55 3.66E-05 2.42E-08 Xe-133 NEG NEG Fe-59 1.99E-05 1.32E-08 Xe-135m NEG NEG Co-58 3.36E-04 2.22E-07 Xe-135 NEG NEG Co-60 4.58E-05 3.03E-08 Xe-137 NEG NEG Sr-89 5.92E-05 9.78E-09 Xe-138 NEG NEG Sr-90 1.92E-06 3.17E-10 Sr-91 NEG NEGTotalnoblegas NEG NEG Y-89m 5.33E-09 NEG Y-90 1.76E-05 2.90E-10Class2 Y-91m NEG NEG Y-91 1.17E-05 1.93E-09 Br-83 NGE NGE Y-93 NEG NEG Br-84 NGE NGE Zr-95 1.25E-06 8.27E-10 Br-85 NGE NGE Nb-95m 1.06E-06 7.01E-10 I-130 NGE NGE Nb-95 1.31E-06 8.65E-10 I-131 2.34E-02 3.87E-06 Mo-99 1.59E-03 2.62E-07 I-132 3.57E-04 5.89E-08 Tc-99m NEG NEG I-133 4.55E-05 7.52E-09 Ru-103 8.81E-07 5.82E-10 I-134 NEG NEG Ru-106 2.26E-07 1.49E-10 I-135 NEG NEG Rh-103m NEG NEG Rh-106 NEG NEG Te-125m 5.97E-07 3.95E-10Totalhalogens 2.38E-02 3.94E-06 Te-127m 6.07E-06 4.01E-09 Te-127 6.09E-06 4.03E-09Class3 Te-129m 2.67E-05 1.76E-08 Te-129 1.71E-05 1.13E-08 Rb-86 3.38E-05 5.59E-09 Te-131m 3.41E-08 2.25E-10 Rb-88 NEG NEG Te-131 6.22E-08 4.11E-11 Cs-134 1.39E-02 2.30E-06 Te-132 8.65E-05 5.72E-08 Cs-136 4.45E-03 7.35E-07 Ba-137m 9.55E-03 1.58E-06 Cs-137 1.01E-02 1.67E-06 Ba-140 2.56E-05 4.22E-09 La-140 2.90E-05 4.78E-09TotalCs,Rb 2.85E-02 4.71E-07 Ce-141 1.10E-05 1.82E-09 Ce-143 7.26E-08 1.20E-11Class4 Ce-144 6.19E-06 1.02E-09 Pr-143 6.52E-07 1.08E-09 N-16 NEG NEG Pr-144 6.20E-06 1.02E-09Totalother 1.19E-02 2.29E-06 isotopes Notes:(1)Forliquidvessels,thisisbased(3)Sourceisbasedon0.25percentonatleast80percentofvesselfueldefectsusablevolume(2)Sourceisbasedon1.0percentNEG-negligiblefueldefectsRev.14 WOLFCREEKTABLE11.1-6(Sheet2)Component:BoronRecycleHoldupTankAorBLocation:RadwasteBuildingDiameter,ft:21Height,ft:31SourceVolume,gal(1):44,800Inventory(2)Concentration(3)Inventory(2)
Concentration(3)Class1 CiµCi/gmClass5 CiµCi/gm Kr-83m 5.02E-01 7.40E-04 H-3 5.92E+02 3.50E+00 Kr-85m 4.93E+00 7.27E-03 Kr-85 1.59E+03 2.35E+00 Tritium Kr-87 9.06E-01 1.34E-03 Kr-88 5.80E+00 8.56E-03Class6 Kr-89 3.10E-03 4.57E-06 Xe-131m 3.35E+02 4.94E-01 Cr-51 5.48E-03 3.23E-05 Xe-133m 1.40E+02 2.06E-01 Mn-54 1.12E-03 6.62E-06 Xe-133 1.68E+04 2.47E+01 Fe-55 5.88E-03 3.47E-05 Xe-135m 1.06E-01 1.56E-04 Fe-59 3.16E-03 1.86E-05 Xe-135 4.40E+01 6.49E-02 Co-58 5.36E-02 3.16E-04 Xe-137 6.97E-03 1.03E-05 Co-60 7.38E-03 4.35E-05 Xe-138 9.38E-02 1.38E-04 Sr-89 1.65E-02 2.44E-05 Sr-90 7.04E-04 1.04E-06Totalnoblegas 1.89E+04 2.78E+01 Y-90 5.15E-03 7.59E-06 Sr-91 5.23E-06 7.71E-09 Y-91M 3.79E-05 5.59E-08Class2 Y-91 1.87E-03 2.76E-06 Sr-92 1.26E-05 1.86E-08 Br-83 2.88E-03 4.25E-06 Y-92 4.76E-05 7.02E-08 Br-84 3.40E-04 5.01E-07 Y-93 4.73E-05 6.97E-08 Br-85 3.61E-06 5.32E-09 Zr-95 2.17E-03 3.20E-06 I-129 2.18E-07 3.22E-10 Nb-95 2.39E-03 3.52E-06 I-130 4.89E-03 7.20E-06 Mo-99 5.72E-01 8.43E-04 I-131 4.96E+00 7.32E-03 Tc-99M 5.26E-01 7.75E-04 I-132 7.90E-02 1.16E-04 Ru-103 1.66E-03 2.45E-06 I-133 1.13E+00 1.66E-03 Rh-103M 5.28E-06 7.78E-09 I-134 7.25E-03 1.07E-05 Ru-106 6.00E-04 8.84E-07 I-135 2.09E-01 3.08E-04 Rh-106 1.46E-08 2.15E-11 Ag-110M 4.72E-03 6.96E-06Totalhalogens 6.39E+00 9.43E-03 Te-125M 1.94E-03 2.86E-06 Te-127M 1.02E-02 1.51E-05 Te-127 1.10E-02 1.63E-05Class3 Te-129M 3.10E-02 4.57E-05 Te-129 1.98E-02 2.91E-05 Rb-86 8.92E-01 1.32E-03 Te-131M 8.13E-03 1.20E-05 Rb-88 6.01E+00 8.86E-03 Te-131 6.35E-05 9.36E-08 Rb-89 1.12E-02 1.64E-05 Te-132 2.45E-01 3.61E-04 Cs-134 1.05E+02 1.54E-01 Te-134 2.75E-04 4.06E-07 Cs-136 7.65E+01 1.13E-01 Ba-137M 8.25E+01 1.22E-01 Cs-137 8.72E+01 1.29E-01 Ba-140 9.16E-03 1.35E-05 Cs-138 8.64E-02 1.27E-04 La-140 9.09E-03 1.34E-05 Ce-141 1.89E-03 2.79E-06TotalCs,Rb 2.75E+02 4.06E-01 Ce-143 1.94E-04 2.86E-07 Pr-143 1.52E-03 2.23E-06Class4 Ce-144 1.69E-03 2.50E-06 Pr-144 1.69E-03 2.50E-06 N-16 NEG NEGTotalotherisotopes 8.41E+01 1.24E-01 Notes:(1)Tankliquidusablevolumeis44800gal.(2)Basedon1.00%fueldefects.(3)Basedon0.25%fueldefects.Rev.14 WOLFCREEKTABLE11.1-6(Sheet3)Component:SpentResinStorageTank(Primary)Location:RadwasteBuildingDiameter,ft:7Height,ft:10.7Sourcevolume,ft3(1):280Inventory(2)Concentration(3)Inventory(2)
Concentration(3)Class1 CiCi/gmClass5 CiµCi/gm Kr-83m NEG NEG H-3 NEG NEG Kr-85m NEG NEG Kr-85 NEG NEG Kr-87 NEG NEGClass6 Kr-88 NEG NEG Kr-89 NEG NEG Cr-51 2.99E+01 3.90E+00 Xe-131m NEG NEG Mn-54 2.91E+01 3.80E+00 Xe-133m NEG NEG Fe-55 1.93E+02 2.52E+01 Xe-133 NEG NEG Fe-59 2.49E+01 3.26E+00 Xe-135m NEG NEG Co-58 6.10E+02 7.98E+01 Xe-135 NEG NEG Co-60 2.56E+02 3.34E+01 Xe-137 NEG NEG Sr-89 9.80E+00 2.67E+00 Xe-138 NEG NEG Sr-90 1.35E+00 3.67E-01 Sr-91 NEG NEGTotalnoblegas NEG NEG Y-90 1.33E+00 3.62E-01 Y-91m NEG NEGClass2 Y-91 2.18E+00 5.93E-01 Y-93 NEG NEG Br-83 NEG NEG Zr-95 2.12E+00 2.77E-01 Br-84 NEG NEG Nb-95m 2.11E+00 2.76E-01 Br-85 NEG NEG Nb-95 3.00E+00 3.92E-01 I-130 5.80E-01 1.57E-01 Mo-99 1.36E+02 3.71E+01 I-131 1.17E+03 3.16E+02 Tc-99m NEG NEG I-132 5.20E+01 7.51E+00 Ru-103 9.98E-01 1.31E-01 I-133 1.76E+02 4.80E+01 Ru-106 9.89E-01 1.29E-01 I-134 9.08E-01 2.47E-01 Rh-103m NEG NEG I-135 2.83E+01 7.73E+00 Rh-106 NEG NEG Te-125m 9.18E-01 1.20E-01Totalhalogens 1.43E+03 3.80E+02 Te-127m 1.50E+01 1.96E+00 Te-127 1.52E+01 1.99E+00Class3 Te-129m 2.69E+01 3.51E+00 Te-129 1.72E+01 2.25E+00 Rb-86 7.91E-01 2.15E-01 Te-131m 1.83E+00 2.39E-01 Rb-88 1.39E+00 3.80E-01 Te-131 NEG NEG Cs-134 1.78E+03 4.85E+02 Te-132 5.15E+01 6.74E+00 Cs-136 8.91E+01 2.43E+01 Ba-137m 1.40E+03 3.81E+02 Cs-137 1.48E+03 4.03E+02 Ba-140 1.63E+00 4.44E-01 La-140 1.77E+00 4.82E-01TotalCs,Rb 3.35E+03 9.13E+02 Ce-141 1.28E+00 3.48E-01 Ce-143 NEG NEGClass4 Ce-144 3.00E+00 8.15E-01 Pr-143 4.25E-01 1.16E-01 N-16 NEG NEG Pr-144 3.00E+00 8.15E-01Totalotherisotopes 2.89E+03 5.93E+02 Notes: (1)Forliquidvessels,thisisbased (3)Sourceisbasedon0.25percenton80percentofvesselusablefueldefects.
volume.(4)Liquidactivitiesareobtainedbymulti-(2)Sourceisbasedon0.12percentfuelplyinginventoryandconcentrationby.001.defectsand1yearaccumulatedactivity.Rev.14 WOLFCREEKTABLE11.1-6(Sheet4)Component:SecondaryLiquidWasteSystemDrainCollectorTankAorBLocation:TurbineBuildingDiameter,ft:12Height,ft:22.75Sourcevolume,gal(1):12,600Inventory(2)Concentration(3)Inventory(2)
Concentration(3)Class1 CiCi/gmClass5 CiµCi/gm Kr-83m NEG NEG H-3 1.66E-01 3.49E-03 Kr-85m NEG NEG Kr-85 NEG NEG Kr-87 NEG NEGClass6 Kr-88 NEG NEG Kr-89 NEG NEG Cr-51 1.89E-09 3.98E-11 Xe-131m NEG NEG Mn-54 4.28E-10 8.99E-12 Xe-133m NEG NEG Fe-55 1.72E-09 3.60E-11 Xe-133 NEG NEG Fe-59 1.27E-09 2.67E-11 Xe-135m NEG NEG Co-58 1.70E-08 3.57E-10 Xe-135 NEG NEG Co-60 1.93E-09 4.05E-11 Xe-137 NEG NEG Sr-89 3.54E-09 1.86E-11 Xe-138 NEG NEG Sr-90 7.13E-11 3.75E-13 Sr-91 1.36E-09 7.13E-12Totalnoblegas NEG NEG Y-90 2.58E-11 1.36E-13 Y-91m 9.21E-10 4.84E-12Class2 Y-91 5.51E-10 2.90E-12 Y-93 7.00E-11 3.68E-13 Br-83 1.68E-08 8.83E-11 Zr-95 8.53E-11 1.79E-12 Br-84 9.95E-10 5.23E-12 Nb-95m 1.24E-11 2.61E-13 Br-85 NEG NEG Nb-95 8.47E-11 1.78E-12 I-130 4.44E-08 2.34E-10 Mo-99 5.97E-07 3.14E-09 I-131 1.49E-05 7.85E-08 Tc-99m NEG NEG I-132 4.58E-07 2.68E-09 Ru-103 4.23E-11 8.89E-13 I-133 1.17E-05 6.17E-08 Ru-106 8.54E-12 1.79E-13 I-134 3.87E-08 2.03E-10 Rh-103m NEG NEG I-135 2.26E-06 1.19E-08 Rh-106 NEG NEG Te-125m 2.13E-11 4.47E-13Totalhalogens 2.94E-05 1.55E-07 Te-127m 2.13E-10 4.48E-12 Te-127 3.84E-10 8.06E-12Class3 Te-129m 1.27E-09 2.66E-11 Te-129 8.71E-10 1.83E-11 Rb-86 7.52E-10 3.95E-12 Te-131m 1.47E-09 3.08E-11 Rb-88 2.91E-09 1.53E-11 Te-131 2.75E-10 5.77E-12 Cs-134 2.28E-07 1.20E-09 Te-132 1.84E-08 3.86E-10 Cs-136 1.13E-07 5.94E-10 Ba-137m 1.56E-07 8.21E-10 Cs-137 1.65E-07 8.66E-10 Ba-140 1.72E-09 9.02E-12 La-140 1.44E-09 7.56E-12TotalCs,Rb 5.10E-07 2.68E-09 Ce-141 7.04E-10 3.70E-12 Ce-143 1.26E-10 6.63E-13Class4 Ce-144 3.57E-10 1.88E-12 Pr-143 3.50E-10 1.84E-12 N-16 NEG NEG Pr-144 3.61E-10 1.90E-12Totalotherisotopes 8.12E-07 5.01E-09 Notes: (1)Forliquidvessels,thisisbased (3)Sourceisbasedon0.25percenton84percentofvesselusablefueldefects.
Volume.NEG-negligible (2)Sourceisbasedon1.0percentfueldefects.Rev.14 WOLFCREEKAPPENDIX11.1APARAMETERSFORCALCULATIONOFSOURCETERMSFOREXPECTEDRADIOACTIVECONCENTRATIONSANDRELEASES11.1A.1RegulatoryGuide1.112providesguidelinesfordevelopingradioactivesourceterms.Thefollowingparametersand modelsareusedtocalculateradioactivesourcetermsfor theevaluationofradioactivewastetreatmentsystemsin determiningtheimpactofradioactiveeffluentsonthe
environment.Figure11.1A-1showsablockdiagramofliquidreleases, andTable11.1A-2andFigure11.1A-2providethevolume, radioactivitylevel,anddecontaminationfactors(DF)for eachliquidpath.Figure11.1A-3showsablockdiagramofgaseousreleases, andTables11.1A-3and11.1A-4providethevolume, radioactivitylevel,andDFforeachgaseouspath.11.1A.2ThebasicplantdataforthesourcetermcalculationsareprovidedinTable11.1A-1.Table11.1A-5providessummaryGALECodeinputdata.
Thefollowingsectionsdiscussthedetaileddesignofwastesystems:a.Chemicalandvolumecontrol9.3.4b.Gaseousradwaste11.3c.Liquidradwaste11.2 d.Boronrecycle9.3.6e.Secondaryliquidwaste10.4.10f.Steamgeneratorblowdown10.4.8TheplantventilationsystemsarediscussedinSection 9.4.11.1A-1Rev.14 WOLF CREEK TABLE 11.1A-1 PLANT DATA FOR SOURCE TERM CALCULATIONS I.Reactor Power, MWt 3565 x 1.02 = 3636 II.Fuel Dataa.Number of fuel assemblies 193b.Uranium mass, MTU 87.8c.Enrichment, w/o 5.0d.Operation time, days 510e.Fuel with defects, %
1.0, 0.25, 0.125 III.Plant Parametersa.Reactor coolant average temperature, °F 593.2b.System pressure, psia 2250c.Letdown rate, gpm 75d.Mixed bed demineralizer volume, ft 3 30e.Cation demineralizer volume, ft 3 30f.Cation demineralizer effective flow, gpm 7.5g.Volume control tank Liquid volume, ft 3 Vapor volume, ft 3 Pressure, nominal, psig Temperature,°F 200 200 0-30 115-125h.Chemical and volume control system parameter See Figure 11.1A-2 (Sheet 1) and Table 11.1A-2i.Boron recycle system parameters See Figure 11.1A-2 (Sheet 2) and Table 11.1A-2 IV.Secondary System Parametersa.Steam flow rate, 10 7 lbs/hr 1.592b.Secondary side water, 10 5 lbs 3.82c.Steam fraction in the secondary 0.08d.Moisture carryover fraction from the steam generator 0.25e.Primary to secondary leak rte, gpm 1f.Steam generator blowdown rate, gpm 360 Rev. 13 WOLF CREEK TABLE 11.1A-1 (Sheet 2)
V.Liquid Waste Processing Systems1.Liquid radwaste system design parametersSee Figure 11.1A-2 (Sheets 3,4,5) and Table 11.1A-22.Secondary liquid waste system design parameters See Figure 11.1A-2 (Sheet 7) and Table 11.1A-2 VI.Gaseous Waste Processing SystemGaseous radwaste system design parametersSee Figure 11.3-2 and Tables 11.1A-3
& 4 VII.Ventilation and Exhaust SystemsHVAC system design parametersSee Figure 11.3-2 and Tables 11.1A-3
& 4 Rev. 13 WOLFCREEKTABLE11.1A-2PARAMETERSUSEDINTHECALCULATIONOFESTIMATEDACTIVITYINLIQUIDWASTESCollectionPeriodCollectorTankVolumeofSpecificAssumedBeforeWithSourcesLiquidWastes Activity Basis Processing CommentsA.Reactorcoolantdrain300gal/day1.0PCA(1)0.05gpm/R.C.pump#2Feedandbleed tanksealleakandotherB.Letdownshim-bleed1,840gal/day1.0PCA(1)CVCSinventorycontrolFeedandbleedC.Wasteholduptank400gal/day0.5PCA(1)10days1.EquipmentdrainsTankdrains,filterdrains,heatexchanger drains,demineralizer
drains2.ExcesssamplesMiscellaneouspre-purgessampleD.Floordraintank1,140gal/day0.06PCA(1)7days1.DecontaminationFuelcask,vesselheadNominaldischargeiswatersystemcomponentflushing,5,000gallonsat35floorwashdown,etc.gpm,approximatelytwiceaweek.2.LaboratoryWashingandrinsingofequipmentlaboratoryequipment.Reactorgradedrains whichareaerated.
Maintenancedrainsfor filters,H.Ex.,demin-eralizers,etc.E.Chemicaldraintanks7,000gal/yr0.15PCA(1)Samplesplussample90daysDrummedrinsewaterRev.14 WOLFCREEKTABLE11.1A-2(Sheet2)CollectionPeriodCollectorTankVolumeofSpecificAssumedBeforeWithSourcesLiquidWastes Activity Basis Processing CommentsF.Laundryandhot450gal/dayN/ADecon.tankwaste7daysThisitemishistorical.showertank300gal/daywithre-Laundryisprocessedoff-mainderforabnormalsite.andrefuelingoperationG.Steamgenerator86,400-1.0SCA(2)ContinuousblowdownNoneNormallyrecycledto518,400gal/dayof60-360gpmcondensate/feedwaterwatersystemH.Secondaryliquid7,200gal/day(3)FloordrainsNoneDischargedorrecycledwastedrainandequipmenttocondensatestorage collectortankdrainstank.I.Condensatedeminer-4,286gal/day(3)15,000gal/highNoneProcessingoptionsare:alizerregenerationTDSregeneration1.Neutralizeand wastewaste-perregenerationdischarge2.Processandrecycletocondenser3.Evaporateanddischarge12,857gal/day(3)45,000gal/lowRecycletosecondaryTDSregenerationcycleordischarge waste-perregeneration(1)PCA-Primarycoolantspecificactivity(2)SCA-Secondarycoolantspecificactivity (3)FractionofSCAinternallycalculatedbyGALECode.Rev.14 WOLF CREEK TABLE 11.1A-3 DESCRIPTION OF MAJOR SOURCES OF GASEOUS RELEASES Basis (per unit), Factors Which Mitigate Radioactive Releases O.12% Failed Fuel, Partition Factors (5)
Source 80% Plant Factor Noble Gas Iodines Holdup Filters (1)
Containment building 1%/day, 0.001%/day of noble 1 1 24 purges Internal: P-H-C-H (2
) gas and iodine inventory in year
the reactor coolant, res- Exhaust: P-H-C-H pectively Auxiliary/fuel/radwaste Noble gas and volatile iodine 1 0.15 No Exhaust: P-H-C-H buildings in 160 lbs/day or reactor coolant (4)
Turbine building 1700 lbs/hr of secondary 1 1 No No steam (3)
Condenser air Noble gas and volatile iodine 1 0.15 No Exhaust: P-H-C-H removal system in 100 lbs of primary coolant/
day (4)
Gaseous radwaste Stripping of gases - - 90 days Exhaust: P-H-C-H system during power operation and degassing of reactor coolant during 2 cold shutdowns/year is directed by Chemistry.
Notes: (1) P - prefilter or roughing filter; H - HEPA filter; C - charcoal adsorber efficiencies of 99 percent for particulates and 70 percent for radioiodines.
(2) No credit has been taken for the internal recirculation clean-up.
(3) Secondary steam activities are based on 100 lbs./day primary-secondary leakage and a partition factor of 0.01 betwee n liquid and vapor phases in the steam generator for iodines.
(4) 5 percent of the iodine in the primary coolant is assumed to be in the volatile form.
(5) Partition factors here mean either the partition on a mass basis between the liquid and vapor phases or the fraction of the leak that is airborne.
Rev. 13 WOLF CREEK TABLE 11.1A-4 CHARACTERISTICS OF RELEASE POINTS AND RELEASES
Physical Characteri stics of Effluent Building Str eams_________
Free Volume Point of Shape of Flow rate Temper ature Velocity Source (cu. ft.)
Release (1)
Filters(2)
Exhaust Vent Type (cfm)
(F)
(fpm)__
A. Reactor building 2,500,000 Unit vent Internal: - Intermittent 20,000 120 ma
- x. -
P-H-C-H 4 shutdown
Exhaust: purges/yr
P-H-C-H 20 purges/yr 4,000
at power B. Auxiliary build- 1,210,000/ Unit vent Exhaust: - Continuous 32,000 104 ma
- x. -
ing/fuel build- 824,000 P-H-C-H
ing C. Unit vent point - Top of - Rectangular Continuous 66,000/ 110 ma
- x. 1,800/2,200 of release for containment 7'6" x 5'0" 82,000
sources A, B, G, (Base El.
H, and I 2208'
Release El.
2218')
D. Vent collection - Radwaste Exhaust: - Continuous 250 Ambien t -
header bldg. vent P-H-C-H E. Radwaste building 477,400 Roof of Exhaust: Square Continuous 12,000 104 ma
- x. 1,600 point of release radwaste P-H-C-H 34" x 34" for sources D, E building
gaseous radwaste (Base El.
system releases 2055'-6" Release El.
2065'-6")
F. Turbine building 4,400,000 Roof of None Roof exhaust Continuous 800,000 100 ma
- x. -
turbine fans (summer)
building 80,000
(Base El. (winter)
2137'
Release El.
2147')
G. Condenser air - Unit vent Exhaust: - Continuous 1,000 120 ma
- x. -
removal filtra- P-H-C-H
tion system (1) Grade elevation is 2000'-0". Elevations shown are standard plant elevation - El. 2000'-0" is Wolf Creek El._MSL/
(2) P = prefilter or roughing filter, H = HEPA filter, C = charcoal adsorber Rev. 0 WOLF CREEK TABLE 11.1A-4 (Sheet 2)
Physical Characteri stics of Effluent Building Str eams_________
Free Volume Point of Shape of Flow rate Temper ature Velocity Source (cu. ft.)
Release (1)
Filters(2)
Exhaust Vent Type (cfm)
(F)
(fpm)__
H. Access control 208,000 Unit vent Exhaust: - Continuous 6,000 104 ma
- x. -
area P-H-C-H I. Main steam 166,000 Unit vent None - Continuous 23,000 120 ma
- x. -
enclosure
_______________________________
(1) Grade elevation is 2000'-0" (2) P = prefilter or roughing filter, H = HEPA filter, C = charcoal adsorber Rev. 0 WOLFCREEKTABLE11.1A-5DeletedTableRev.14 REV. 29 BORON RECYCLE SYSTEM (HE)
LIQUID RADWASTE SYSTEM "A" TRAIN (HB)(RCDT)DRAINS EQUIPMENT (350 GAL)DRAIN TANK (RCDT)
REACTOR COOLANT RCDT HEAT EXCHANGER (CRW)DRAINS AREA FLOOR RADIOACTIVE LIQUID RADWASTE SYSTEM "B" TRAIN (HB)
(2)DEMIN.FEED EVAP RECYCLE FEED FILTER RECYCLE EVAPORATOR GAL)(80,000 (2)TANK HOLD-UP RECYCLE FEED FILTER WASTE EVAPORATOR (DRW)DRAINS AREA FLOOR RADIOACTIVE TANK STRAINER FLOOR DRAIN TANK FILTER FLOOR DRAIN 13 S F 11 7 1 F F 12 12 LAUNDRY AND HOT SHOWER (HB)
HOT SHOWER (10,000 GAL)(L & HS) TANK HOT SHOWER LAUNDRY AND TANK STRAINER L & HS TANK FILTER L & HS S F SECONDARY LIQUID WASTE (HF)(LRW)FLOOR DRAINS TURBINE BUILDING RADIOACTIVE POTENTIALLY 6 INTERCEPTOR OIL GAL)(15,000 (2)TANK COLLECTOR DRAIN SLW TANKS COLLECTOR HIGH TDS LOW TDS WASTE REGENERATION POLISHER CONDENSATE S F S F STRAINER STRAINER FILTER FEED EVAPORATOR SLW FILTER (2)
LOW TDS STEAM GENERATOR BLOWDOWN (BM)
SYSTEM (BG)
REGERNATION BORON THERMAL 1 2 4 SYSTEM (BG)
VOLUME CONTROL CHEMICAL AND (BB)VESSEL REACTOR 7 HEAT EXCHANGER BLOWDOWN REGENERATIVE HEAT EXCHANGER BLOWDOWN NON-REGENERATIVE 10 9 MAIN STEAM (4)(BB)STEAM GENERATOR MAIN FEEDWATER 10 9 DEMIN. (AK)
CONDENSATE FACILITY TREATMENT WASTE WATER POND LAKE SLUDGE MAIN CONDENSER S F STRAINER FILTER (2)
BLOWDOWN ADSORBER CHARCOAL SLW DEMIN.SLW S (2)DEMIN.BED MIXED BLOWDOWN (2)DEMIN.BED MIXED BLOWDOWN M-31 DISCHARGE (2065 GAL)
TANK SURGE BLOWDOWN (450,000 GAL)(AP)STORAGE TANK CONDENSATE (50,000 GAL)
TANK (AN)WATER STORAGE DEMINERALIZED 11 GAL)(15,000 (2)TANK MONITOR SLW S (10,000 GAL)
TANK STORAGE WATER LAUNDRY (5,000 GAL)
TANK B WASTE MONITOR (5,000 GAL)
TANK A WASTE MONITOR 13 5 ADSORBER CHARCOAL L & HS DEMIN.TANK MONITOR WASTE TANK FILTER WASTE MONITOR F ADSORBER CHARCOAL WASTE LIQUID DEMIN.COND.EVAP WASTE FILTER CONDENSATE EVAPORATOR WASTE F (5,000 GAL)
CONDENSATE TANK WASTE EVAPORATOR (150,000 GAL)
TANK (BL)WATER STORAGE REACTOR MAKE-UP SPENT FUEL POOL (EC)
DECONTAMINATIONS MAKE-UP AND MISCELLANEOUS 2 PROCESSING SKID LIQUID RADWASTE (2350 GAL)
TANK FLASH BLOWDOWN (10,000 GAL)
TANK HOLD-UP WASTE 2. DASHED LINES REPRESENT ALTERNATE PROCESS PATHS
- 1. SOLID LINE REPRESENT PRIMARY PROCESS PATHS.
NOTES: (10,000 GAL)
TANK (2)FLOOR DRAIN 95 RE M-29 DISCHARGE (DW)DISCHARGE NON-RADIOACTIVE 6 52 RE 59 RE 45 RE 5 (2)W 18 RE (150 GPM)DEGASIFIER 29 (7.5gpmJ letdown (76 11Pn1 @ 1.0 PCA) 1. Mixed Bad Deminaralizars
- 2. Cation Bed Damineralizer*
- 3. Reactor Coolant Filter 4, Volume Control Tank (a) System OF (a) For noble gases, a value of 0.25 Is built into the GALE code for the y parameter for the case of continuous VCT pi.R'ging.
.) 2 CREEK Rev. 0 Divert to System (1.840 gpd 0 1.0 PCA) Ve ntto Ga Radwaste System Return to Reactor Coolant System FACTQB& Iodine 10 1 1 10 Cesium & Other Rubidium Nuclides 2 10 10 10 1 1 '20 102 WOLP CREEK OPDATED SAFETY ANALYSIS REPORT FISURE 11.1A-2 SYSTEM DECONTAMINATION FACTORS (SHEET 1) _)
DECONTAMINATION FACTORS Iodine Cesium &Rubidium Other Nuclides 1. Recycle Evaporator Mixed Bed Demineralizer 10 2 10 2. Recycle Evaporator Feed Filter 1 1 1 3. Recycle Holdup Tanks System DF 10 2 10 Decay TimeBoron Recycle Holdup Tank Collection Time T c08560002140209., ,.days R. C. Dr. Tank (300 gpd @ 1.0 PCA)
(Equipment Drains)
Letdown (1840 gpd @ 1.0 PCA)
(shim bleed) Liquid Radwaste Processing Skid(Sheet 3A)
WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 (Sheet 2)
SYSTEM DECONTAMINATION FACTORS 1 2 3Boron Recycle System Rev. 23 DECONTAMINATION FACTORS Iodine Cesium &Rubidium Other Nuclides 1. Waste Holdup Tank 2. Waste Evaporator Feed Filter 1 1 1 3. Waste Evaporator Note 1, 2 10 3 10 4 10 4 4. Liquid Waste Charcoal Adsorber Note 1, 2 1 1 1 5. Waste Evaporator Condensate Demineralizer Note 1, 210 10 10 6. Waste Evaporator Condensate Filter Note 1, 2 1 1 1 System DF Note 1 10 4 10 5 10 5Note 1: Liquid Radwaste is processed as shown on sheet 3A. This sheet retained for historical purposes only.
Note 2: Equipment permanently out of service. Decay TimeWaste Holdup Tank Waste Process Collection Time Time T c0410000 400 10., days T p0410000216000185., ,.day Liquid Radwaste Processing Skid Plant Discharge 1 2 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 (SHEET 3)
SYSTEM DECONTAMINATION FACTORS 3 4 5 6 Boron Recycle System (Sheet 2)
Dirty Wastes (Sheet 4)
Clean Wastes
(400 gpd @ 0.5 PCA) Liquid Radwaste Train A Clear Waste Rev. 23 DECONTAMINATION FACTORS Iodine Cesium &Rubidium Other Nuclides1.Liquid Radwaste Processing Skid
>10 6>10 6>10 5 Plant Discharge WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 (SHEET 3A)
SYSTEM DECONTAMINATION FACTORS 1 Waste Holdup Tank (Sheet 3)
Boron Recycle System (Sheet 2)
Dirty Wastes (Sheet 4)Liquid Radwaste Processing Skid Rev. 14 DECONTAMINATION FACTORS Iodine Cesium &Rubidium Other Nuclides 1. Floor Drain Tank 2. Floor Drain Tank Filter 1 1 1 3. Waste Monitor Tank Demineralizer 4. Waste Monitor Tank Filter 1 1 1 System DF 1 1 1 Decay Time Floor Drain Tank Collection Time T c08100001140 7., , days Plant Discharge 1 2 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 (SHEET 4)
SYSTEM DECONTAMINATION FACTORS 3 4 Dirty Wastes
(1,140 gpd @ 0.058 PCA)Liquid Radwaste Processing Skid(Sheet 3A)Liquid Radwaste Train B Dirty Wastes Rev. 23 WOLF CREEK Laundry & Hot Showers ____ .. (450gpd) (Built into the GALE code) 1 2 -.r 1. Laundry and Hot Shower Tank Decay Times* L + H.S. Tank Collection Time 2. Laundry and Hot Shower Filter System DF <NOTE 1) T c 0.4 8.9 days '0.4 x 10,000 ... 0.7 day Tp* 5,:760 . . *The GALE coda does not usa thasa decay credit factors. 1.> VOLUMES ARE EXTREMELY CONSERVATIVE.
LAUNDRY IS PROCESSED OFFSITE. NO CONTAMINATED INFLUENTS ARE NORMALLY RECEIVED BY THE L 8c HST. I ' (
- Plant Discharge DECONTAMINATION FACTORS Iodine --1 1 1 Cesium& Other Rubidium Nuclides 1 1 1 1 1 1 Liquid Radwaste
- Laundry Train WOLF CREEK REV.8 UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 SYSTEM DECONTAMINATION FACTORS CSHEET 5)
WOLF CREEK DECONTAMINATION FACTORS Iodine Cesium &Rubidium Other Nuclides 1. Steam Generator Blowdown Flashtank 2. Steam Generator Blowdown Regenerative Heat Exchanger 3. S.G. Blowdown Nonregenerative Heat Exchanger
- 4. S.G. Blowdown Filters 1 1 1 5. S.G. Blowdown Demineralizer (each) 10 2 2 10 2 System DF 10 4 4 10 4 Recycled to Secondary Cycle 1 2 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 (SHEET 6)
SYSTEM DECONTAMINATION FACTORS 3 5 Steam Generator Blowdown Max. 4.2 x 10 6 lb/day Min. 0.7 x 10 6 lb/day Vent to #5 Feedwater Heater 25% flash Rev. 18 4 LowTDS --WOLF CREEK 1 2 (12,857 gpd} .. 1
- 11 .. .... 13 ---9 -HighTDS -3 10 (4.286 gpd} 6 7 I
-...... -Pia !.@* -I Secondary I Secondary Cycle ntDischarge Side Floor 4
- 5 I -Drains -* Plant Discharge 7200 ( . gpd) DECONTAMINATION FACTORS Iodine 1. Low TDS Collector Tank 2. Low TDS Filter 3. High TDS Collector Tank 4. Oil Interceptor
- 5. SLW Drain Collector Tank 6. SLW Filter 7. SLW Evaporator (available only for high TDS) 8. SLW Charcoal Adsorber 9. SLW Demineralizer (C)
- 10. SLW Monitor Tank (Low TDS) System OF-High TDS LowTDS 11.. SL W Rodlotton t.tonltor RE *95 t2. Wostewoter Treatment F'ocllity
- 13. Lime Sludge Pond (a) Processing will be subject to chemistry requirements. (b) No credit is taken for collection and processing times. (c) Second number indicates Low TDS DF. 1 1 1o3 10(1o2) 1o4 1o2 Cesium & Rubidium 1 1 1o4 10(2) 1o5 2 Other Nuclides 1 1 1o4 10(1o2) UP 1o2 Secondary Liquid Waste System WOLF CREEK ) Rev. 5 UPDATED SAFETY ANALYSIS REPORT FIGURE 11.1A-2 SYSTEM DECONTAMINATION FACTORS SHEET 7 (
tlfACtOfl toeii.AifT IHOIJ :::::Aft 111M0V Ysmt ,...( ;,:_0-Y '"'"'" WASTI GAS lfAitAGf UNitVfHf fop Of COHf.utMIHf l<<lLF Cli!El( AUX. M.DG. SUMP
- PIMWlY SAMI'lJHG I UUM111Y *1101' SHUWIIt fA* I ' ,j II!Atftllt IUIUlltO l'!ft ft'l "iiUP" AUIICIUIIIW IIUUIIIfG
..-. ..... -..... [-----m;J -mmm" IWIICW:IM uo. lfOlJ f dfDf!!JfB
..... PHtilfC](f9" t IUl.DING TUIII .. IUI.OHI lUfiiM UCI. WHfiiATII!'f
............ .. ,., ... IUiDwAt1t
........ ,AM( crd'.Of 1CII STEAM TNIC M WAaft IVAf'CIIIIIATOftPICO.
flOOIIIIftMf
,..,. lEGIND m ... Fl. 'lUI: * ....... I!!J Hlf'AFI.ftll 1£)
AMoN lilt OASIICD UNlS fOil imftMiniNJ soucu. ----. -*--.. -----***-' --..... _ -...... Rev. 13
- WOLF CREEK UPDATED SAFETY ANALYSIS REPORT FIGURE .11. lA-3 :EtOTENTIAL GASEOUS RELEAsE ---------.... *-. ----_.,;... --:-.--* --. -----... ---------j .................
___ -----*----
Wolf Creek 11.2 LIQUID WASTE MANAGEMENT SYSTEMS Several systems within the plant serve to control, collect, process, handle, store, recycle, and dispose of liquid radioactive waste generated as a result of normal plant operation, including anticipated operational occurrences. This section discusses the design and operating features and performance of the
liquid radwaste system and the performance of other liquid waste management
systems which are discussed in other sections.
11.2.1 DESIGN BASES
11.2.1.1 Safety Design Basis Except for two containment penetrations and the component cooling water side of the reactor coolant drain tank heat exchanger, the liquid radwaste system (LRWS) is not a safety-related system.
SAFETY DESIGN BASIS ONE - The containment isolation valves in the LRWS are selected, tested, and located in accordance with the requirements of 10 CFR 50, Appendix A, GDC-56, and 10 CFR 50, Appendix J, Type C testing.
11.2.1.2 Power Generation Design Bases POWER GENERATION DESIGN BASIS ONE - The LRWS, in conjunction with other liquid waste management systems, is designed to meet the requirements of the discharge concentration limits of 10 CFR 20 and the ALARA dose objective of 10 CFR 50, Appendix I.
POWER GENERATION DESIGN BASIS TWO - The LRWS uses design and fabrication codes consistent with quality group D (augmented), as assigned by Regulatory Guide
1.143, for radioactive waste management systems.
POWER GENERATION DESIGN BASIS THREE - Liquid effluent discharge paths are monitored for radioactivity and isolated upon detection of unacceptable radioactivity.
11.2.2 SYSTEM DESCRIPTION
11.2.2.1 General Description This section describes the design and operating features of the LRWS. The
performance of the LRWS, in conjunction with other liquid waste management
systems, is discussed in Section 11.2.3. Detailed descriptions of other liquid waste management systems are provided in the following sections:
11.2-1 Rev. 13 Wolf Creek
- a. Boron recycle 9.3.6
- b. Steam generator blowdown 10.4.8
- d. Secondary liquid waste 10.4.10 The piping and instrumentation diagram for the LRWS is shown in Figure 11.2-1.
The LRWS collects and processes radioactive or potentially radioactive waste
water. The LRWS consists of two subsystems designated as drain channel A and drain channel B. Drain channel A is for processing water which could be recycled and drain channel B is for processing water which would normally be
discharged. Equipment drains and waste streams are segregated to prevent the intermixing of the liquid wastes. Tritiated waters (CRW), potentially
radioactive nontritiated waste (DRW), and detergent waste (SRW) are discussed in Section 9.3.3. A drain system is also provided inside the containment to collect drainage and leakage and transfer it to an appropriate tank.
Operating experience has shown that operating dose rates and overall release of
radioactivity to the environment are minimized by not recycling triatiated water to the Reactor Makeup Water Storage Tank (RMWST). This method of operation eliminates the potential for contamination of secondary systems while
degassing the Reactor Makeup Water System (BL) water in the Demineralized Water
Makeup Storage and Transfer System (AN).
The various waste streams are processed as follows:
BORON RECYCLE SYSTEM - The bulk of the radioactive liquid discharged from the
reactor coolant system is processed by the Boron Recycle System as described in
Section 9.3.6. This water is transferred from a Recycle Holdup Tank to the LRWS for processing by the Liquid Radwaste Processing Skid as indicated in Figure 11.1A-2.
TRITIATED WASTES - These consist of reactor coolant which has been exposed to
the atmosphere and has become aerated. This waste consists of equipment drains, leakoffs, and overflows from tritiated systems (e.g., CVCS and reactor coolant samples which have not been chemically contaminated). This waste is
typically collected in the floor and equipment drain system, transferred to the
waste holdup tank and processed in the Liquid Radwaste Processing skid prior to entering the waste evaporator condensate tank, waste monitor tanks or secondary liquid waste monitor tanks. The processed wastes are analyzed for chemical and radioactive content in the waste evaporator condensate tank, waste monitor tanks (WMTs) or secondary liquid waste monitor tanks prior to being discharged.
11.2-2 Rev. 22 Wolf Creek HIGH LEVEL CHEMICAL WASTE - High level chemical waste consists of plant samples which have been chemically contaminated and decontamination solutions used in
the decontamination tanks located in the hot machine shop. These wastes are collected in the chemical drain tank. The contents are received and sampled by chemistry to ensure that no highly contaminated chemical solutions are allowed to enter the floor drain system. This is done by analyzing for conductivity
and PH. (If an abnormal parameter exists the contents are drained in small
quantities to the floor drain system to allow for dilution).
The chemical drain tank contents are processed by draining its contents to the
Floor Drain Tanks for dilution then processed by the LRPS.
CONTROLLED ACCESS AREA FLOOR DRAINAGE - Controlled access area floor drain wastes are miscellaneous liquid wastes collected by the floor drain system within the radiologically controlled areas of the plant. The controlled access areas are radiation zones B through E and include the containment, auxiliary building, fuel building, radwaste building, hot machine shop, and the access
control areas of the control building.
Floor drainage consists of miscellaneous leakage from systems within the above
areas. Generally, the amount of highly radioactive reactor coolant leakage
into the drain system is very small. The bulk of the water originates as
leakage from nonradioactive or slightly radioactive systems, such as the service water and component cooling water systems. In addition to system leakage, the floor drain systems collect decontamination water used for area
washdowns, spent fuel cask decontamination, and laboratory equipment
decontamination and rinses. Highly contaminated chemical solutions are not allowed to enter the floor drain system in large volumes, and, therefore, are directed to the chemical drain tank for processing. During maintenance, equipment drains from nontritiated systems are directed to the floor drain
system. Large volumes of component cooling water are not drained to the floor
drain system to prevent contamination of the LRWS by corrosion inhibitors.
The floor drain tanks are processed through the liquid radwaste demineralizer skid. The FDT may contain chemical contaminants, mild decontamination
solutions, organics, etc. Filtration and ion exchange are capable of providing
the required purity for environmental discharge. Relatively small volumes of
exchange media are consumed in comparison to the volumes of solidified concentrates generated by evaporator bottoms processing. Since the processed water is not recycled, it is not necessary to deaerate for discharge to the
environment.
11.2-3 Rev. 22 Wolf Creek The liquid waste charcoal adsorber (LWCA) should be used only if the presence of organics is detected. If the waste in the FDT has a low level of dissolved
solids, an activity of less than 10-5 mCi/cc, and the operator intends to discharge, the floor drain tank filter, liquid waste charcoal adsorber, waste evaporator condensate filter, and waste monitor tank demineralizer in series
may be used to process the waste effectively. This method of processing can
also be employed when abnormally large volumes of floor drain wastes are to be
processed. When the effluent has not been processed, it should be directed to an aerated waste monitor tank.
A second floor drain tank is available to allow one tank to be isolated and
sampled prior to feeding the processing system while the other tank is
available to receive wastes. The second floor drain tank also provides greater system storage volumes which will minimize inventory problems by providing greater surge capacity during periods of abnormal waste generation or equipment
outages.
When processing floor drain waste it is highly desirable to operate with a known influent quality to ensure optimum system performance. This is normally accomplished by isolating the floor drain tank to be processed and withdrawing
a sample to determine its chemical properties. The operator selects the
appropriate process equipment.
If the sample indicates relatively clean waste (less than 25 ppm TDS without organic or boric acid contamination), it can be effectively processed through
the demineralizer train. Waste is processed with the Liquid Radwaste
Processing Skid. With known influent chemistry, the optimum process can be
selected.
LAUNDRY AND PERSONNEL DECONTAMINATION WASTE - Laundry waste is generated by the radioactive contamination of protective clothing and gear. The use of vendor provided laundry services is employed to process laundry waste. The hot shower in the access control area is used only for personnel decontamination; consequently, its use should be infrequent.
The washing machine water supplies have been disconnected and the washing machine hot water heater tank has been removed. Therefore, no laundry can be performed on site and no laundry water will be generated for processing through Radwaste Systems.
11.2-4 Rev. 27 Wolf Creek The waste from personnel decontamination is collected in the chemical and detergent waste system's detergent drain tank and then transferred to the laundry and hot shower tank. Also, they may be transferred to the monitor tanks for discharge. Suspended solids are removed by strainers and filters located at the beginning of the processing train. The Laundry and Hot Shower Tank (LHST) contents are normally not reprocessed due to the small amount of water that would be recycled. The system generates low volumes due to contaminated laundry being processed offsite through vender services.
All tanks which contain or may contain concentrations of radioactivity have provisions to prevent the uncontrolled release of the fluid. Table 11.2-2
indicates the provisions made for each tank.
The system is designed to handle the occurrence of equipment faults of moderate frequency such as:
- a. Malfunction in the LWPS
Malfunction in this system could include such things as pump or valve failures or evaporator failure. Because
of pump standardization throughout the system, a spare
pump can be used to replace most pumps in the system.
There is sufficient surge capacity in the system to accommodate waste until the failures can be fixed and normal plant operation resumed.
11.2-5 Rev. 27 Wolf Creek
- b. Excessive leakage in reactor coolant system equipment
The system is designed to handle a 1-gpm reactor coolant leak in addition to the expected leakage of 50 lb/day (Ref. 1) during normal operation, which is discussed in
Section 5.2.5. Operation of the system is almost the
same for normal operation, except that the load on the system is increased. A 1-gpm leak into the reactor coolant drain tank is handled automatically. If the 1-gpm leak enters the waste holdup tank, operation is the same as normal, except for the increased load on
the system. Abnormal liquid volumes of reactor coolant resulting from excessive reactor coolant or auxiliary building equipment leakage (in excess of 1 gpm) can also be accommodated by the floor drain tank and processed by
the LWPS.
- c. Excessive leakage in the auxiliary system equipment
Leakage of this type could include water from steam side
leaks and fan cooler leaks inside the containment which
are collected in the containment sump and sent to the floor drain tank. Other sources could be component cooling water leaks, service water leaks, and secondary
side leaks. This water enters the floor drain tank and is processed and discharged as during normal operation.
11.2.2.2 Component Description Codes and standards applicable to the LRWS are listed in Tables 3.2-1 and 11.2-
- 1. The LRWS is designed and constructed in accordance with quality group D (augmented). The LRWS is housed within a seismically designed building.
Regulatory Guide 1.143 is complied with to the extent specified in Table 3.2-5.
REACTOR COOLANT DRAIN TANK PUMPS - Due to the relative inaccessability of the
containment and the loop drain requirements, two pumps are provided. One pump
provides sufficient flow for normal tank operation with one pump for standby.
WASTE EVAPORATOR FEED PUMP - One standard pump is used. The waste evaporator
feed pump supplies feed to the evaporator and the liquid radwaste demineralizer
skid (LRDS). The pump is shut off when low level is reached in the waste
holdup tank.
11.2-6 Rev. 14 Wolf Creek WASTE EVAPORATOR CONDENSATE TANK PUMP - The waste evaporator condensate tank pump is a transfer pump. One standard pump is used to transfer the contents of
the waste condensate tank to the waste monitor tanks.
CHEMICAL DRAIN TANK PUMP - One standard pump is used to recirculate the liquid
back to the chemical drain tank for mixing prior to sampling.
LAUNDRY AND HOT SHOWER TANK PUMP - One standard pump is used to transfer the water to the waste monitor tank.
FLOOR DRAIN TANK PUMPS - Two standard pumps are available to transfer the
contents of the floor drain tanks to the waste monitor tank. The pumps are
cross-connected to the pump from either floor drain tank. The pumps can also be used to supply the LRDS.
WASTE MONITOR TANK PUMPS - One standard pump is to be used for each tank to
discharge water from the plant site or for recycle if further processing is
required. The pump may also be used for circulating the water in the waste monitor tank in order to obtain uniform tank contents and hence a representative sample before discharge. The pump can be throttled to achieve
the desired discharge rate.
REACTOR COOLANT DRAIN TANK HEAT EXCHANGER - The reactor coolant drain tank heat exchanger is a U-tube type with one shell pass and four tube passes. Although the heat exchanger is normally used in conjunction with the reactor coolant
drain tank, it can also cool the pressurizer relief tank from 200 to 120°F in
less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
REACTOR COOLANT DRAIN TANK - One tank is provided to collect leakoff type drains inside the containment at a central collection point for further
disposition through a single penetration via the reactor coolant drain tank
pumps.
Only water which can be directed to the recycle holdup tanks enters the reactor coolant drain tank. The tank is provided with a hydrogen or nitrogen cover
gas. The water must be compatible with reactor coolant.
Sources of water entering the reactor coolant drain tank include the reactor vessel flange leakoff, reactor coolant pump number two seal leakoffs, and the excess letdown heat exchanger flow. No continuous leakage is expected from the
reactor vessel flange during operation.
11.2-7 Rev. 29 Wolf Creek The tank maintains a constant level to minimize the amount of gas sent to the gaseous waste processing system and also to minimize the amount of hydrogen or
nitrogen required. The level is maintained by using a proportional control valve in the discharge line. This valve operates, on a signal from a level controller, to maintain a constant level by discharging normally to the recycle
system. The remainder of the flow is recirculated to the tank.
WASTE HOLDUP TANK - One atmospheric pressure tank is provided outside the containment to collect equipment drainage, pump seal leakoffs, recycle holdup tank overflows, and other water from tritiated, aerated sources.
WASTE EVAPORATOR CONDENSATE TANK - One tank originally used to collect condensate from the waste evaporator which has been abandoned in place. This tank is now used for temporary water storage during outages or whenever a large surge of non-recyclable water occurs. The tanks damaged diaphragm has been removed.
CHEMICAL DRAIN TANK - One tank is provided to collect chemically contaminated tritiated water from the laboratories.
LAUNDRY AND HOT SHOWER TANK - One atmospheric pressure tank is used to collect
laundry and hot shower drainage.
FLOOR DRAIN TANKS - Two atmospheric pressure tanks are used to collect floor drainage from the reactor plant operations.
WASTE MONITOR TANKS - The two atmospheric waste monitor tanks are provided for
monitoring liquid discharges from the plant site. Each tank is sized to hold a volume large enough such that sampling requirements are minimized, thus minimizing laboratory effluent.
WASTE EVAPORATOR REAGENT TANK - One tank is used for adding chemicals to the
plant for such things as cleaning of the waste evaporator tubes.
WASTE EVAPORATOR CONDENSATE DEMINERALIZER - One mixed bed demineralizer with
nonregenerative hydrogen-hydroxide resin is provided to remove ionic
contaminants from the waste condensate.
WASTE MONITOR TANK DEMINERALIZER - One mixed bed demineralizer with nonregenerative hydrogen-hydroxide resin is provided to remove trace
contaminants from the water in the floor drain tank.
FILTERS - The filters provided are of a disposable-type cartridge.
11.2-8 Rev. 29 Wolf Creek The methods employed to change filters and screens are dependent on activity levels. Filters are valved out of service, drained to the appropriate tank, and vented locally. If the radiation level of the filter is low enough, it is changed manually. Filter handling is discussed in Section 11.4.
STRAINERS - Strainers are provided in the discharge of the laundry and hot
shower pump and the floor drain tank pumps to remove large particulate matter
and thus prevent clogging of the downstream lines and filters.
WASTE EVAPORATOR - The waste evaporator is abandoned in place.
LIQUID RADWASTE PROCESSING SKID (LRPS)- The LRPS consists of a vendor supplied skid containing a chemical injection system, filtration unit and a series of demineralizer vessels. Based on the chemical and/or isotopic analysis of the waste stream, the processing skid may use every component available, or bypass those components not needed. The processes include filtration, reverse osmosis, and/or demineralization. Filtration removes large complex radioactive isotopes not easily removed by ion exchange from plant radioactive wastewater.
Reverse osmosis only allows water and selected ions to pass through a membrane.
Demineralization provides filtration and selective ion exchange. Following filtration, the radioactive contaminants or other solids left in solution are removed by reverse osmosis or demineralization.
11.2.2.3 System Operation The LRWS operation is manually initiated, except for some functions of the
reactor coolant drain subsystem. The system includes adequate control
equipment to protect the system components and instrumentation and alarm functions to provide operator information to ensure proper system operation.
All pumps in the system have low level shutoffs, and all filters, strainers, and demineralizers have differential pressure indication to indicate fouling.
Operation of the LRWS is essentially the same during all phases of normal reactor plant operation; the only differences are in the load on the system.
The following sections discuss the operation of the system in performing its
various functions. In this discussion, the term "normal operation" should be
taken to mean all phases of operation, except operation under emergency or
accident conditions. The LRWS is not regarded as a safety-related system.
REACTOR COOLANT DRAIN TANK SUBSYSTEM OPERATION - Normal operation of the
reactor coolant drain subsystem is automatic and requires no operator action.
The system can be put in the manual mode, if desired. The leakage rate of
reactor coolant pump No. 2 seal leakoffs, reactor vessel flange leakoffs, and discharges from the excess letdown heat exchanger into the reactor coolant drain tank (RCDT) can be estimated by putting the system
11.2-9 Rev. 22 Wolf Creek in the manual mode, stopping operation of the reactor coolant drain tank pump, and watching the rate of level change. The reactor coolant drain tank pump
normally discharges to the boron recycle system. These drains can also be processed in the waste holdup tank. The level in the RCDT is maintained by running one RCDT pump continuously and using a proportional control valve (LCV-1003) in the discharge line. This valve operates on a signal from the RCDT
level controller to limit the flow out of the subsystem. The remainder of the
flow is recirculated to the RCDT. The RCDT heat exchanger is sized to maintain the RCDT contents at or below 170°F, assuming an in-leakage of 10 gpm at 600°F.
A venting system is provided to prevent wide pressure variations in the RCDT.
Hydrogen or nitrogen cover gas is supplied from the service gas system and is automatically maintained between 2 and 6 psig by pressure-regulating valves.
PCV-7155 maintains a minimum tank pressure by admitting hydrogen or nitrogen, while PCV-7152 maintains maximum tank pressure by venting the RCDT to the gaseous radwaste system. The hydrogen is supplied from no more than two 194 SCF
bottles, to limit the amount of hydrogen gas which might be accidentally
released to the containment atmosphere. The RCDT vents to the gaseous radwaste system to limit any releases of radioactive gases.
The reactor coolant drain subsystem may also be used in the pressurizer relief
tank (PRT) cooling mode of operation. In this mode, the level control valve in
the discharge line to the recycle evaporator feed demineralizers (LCV-1003), the isolation valve at the discharge of the reactor coolant drain tank (HV-7127) and the isolation valve in the reactor coolant drain tank recirculation
line (HV-7144) are all closed. The PRT contents are circulated through the
reactor coolant drain tank heat exchanger, via valve BB-HV-8031 and the reactor
coolant drain tank pumps, prior to returning to the PRT via valve BB-HV-7141.
In this mode of operation, the RCDT heat exchanger is capable of cooling the PRT contents from 200 F to 120 F in less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. As an alternative to returning the cooled fluid to the PRT, the fluid may be directly transferred to the recycle holdup tanks in the boron recycle system. In any and all cases of PRT cooling, the PRT is vented to less than 50 psig to prevent overpressurization of the RCDT subsystem.
The reactor coolant drain subsystem may be used to drain the reactor coolant
loops by first venting the reactor coolant system, then connecting the spool piece in the RCDT pump suction piping. The design objective of this mode of operation is to drain the RCS to the midpoint of the reactor vessel nozzles in
less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with both RCDT pumps running. In this mode, valve HV-7144 is
11.2-10 Rev. 15 Wolf Creek closed and, in order to maximize flow capability, the RCDT discharge level control valve (LCV-1003) may be bypassed during RCS draining operations. If
automatic RCDT level control is desired, then the flow path through LCV-1003 may be used.
The reactor coolant drain subsystem may be used to drain down portions of the
refueling pool which cannot be drained by the residual heat removal pumps. In
this mode of operation, the RCDT heat exchanger may be bypassed and the RCDT level control valve (LCV-1003) may be bypassed to maximize flow through the fuel pool cooling and cleanup system to the refueling water storage tank. An
alternate drain line is provided from the refueling pool to the containment
sump to route decontamination chemicals away from the RCDT subsystem and
minimize the possibility of contaminating any systems downstream of the RCDT pumps.
DRAIN CHANNEL "A" SUBSYSTEM OPERATION - Waste is accumulated in the waste holdup tank until a sufficient quantity exists to warrant processing. The
Waste Holdup Tank contents are normally processed for discharge by the Liquid Radwaste Processing Skid. Processed effluent is not returned to the RMWS.
Demineralized LRWS effluent is discharged.
WASTE EVAPORATOR OPERATION - The waste evaporator is abandoned in place.
11.2-11 Rev. 19
Wolf Creek DRAIN CHANNEL "B" SUBSYSTEM OPERATION - Normally, one floor drain tank is
aligned to receive the discharge from the floor and equipment drain system, while the other tank is being used to supply waste to the processing system.
This procedure allows the waste to be sampled and pH adjusted prior to processing to ensure optimum system performance.
If the waste in the floor drain tank has a low total dissolved solids content
(<25 ppm), an activity of less than 10
-5 mCi/cc, and does not contain significant organics, it may be processed using the liquid waste charcoal adsorber and waste monitor tank demineralizer in series, and
directed to waste monitor tanks.
Any planned releases from the system must be weighted with all other unit radioactive liquid releases to ensure that the local releases do not exceed the
ODCM limits at the boundary of the restricted area.
LAUNDRY SUBSYSTEM OPERATION - Laundry waste from the washing machines and waste from the personnel decontamination shower is directed by gravity drain to the detergent drain tank located in the basement of the control building. This waste is pumped to the LHST where it is sampled, prior to being processed. If discharge of the LHST contents is desired and the tank contents are found to be of acceptable quality for discharge, the fluid may be transferred to the Secondary Liquid Waste Monitor Tanks or Waste Monitor Tank "B" by way of the Laundry and Hot Shower Tank Basket Strainer and Filter.
The processed laundry water is stored in the laundry water storage tank. The laundry water is then pumped, on demand to the washing machines through the washing machine hot water heater to the laundry equipment in operation. Note that the hot water heater is provided with a bypass to allow a feed of relatively cold water to the laundry equipment. Laundry operation additives such as detergents and soaps are used sparingly to ensure laundry waste water is compatible with process paths. The use of vendor provided laundry services for contaminated laundry may also be employed. This helps prevent the spread of highly contaminated particles throughout the laundry water system.
The laundry water stored in the laundry water storage tank may also be directed to the LHST for reprocessing or to the waste monitor tank "B" or one of the secondary liquid waste monitor tanks. Any planned releases from this system must be weighed with all other radioactive liquid releases to ensure total releases do not exceed the ODCM limits at the boundary of the restricted area.
The LRWS is operated so that the waste discharges are segregated. Waste monitor tank "B" is normally aligned for laundry water while waste monitor tank "A" is normally aligned for demineralized floor drains. Laundry water is normally low radioactivity waste, and does not require treatment other than the removal of organics. Provision is made to demineralize the laundry water, via the waste monitor tank demineralizer, prior to discharge, if necessary.
11.2-12 Rev. 23 Wolf Creek Floor drain wastes are relatively dirty and may contain moderately high radioactivity. Treatment of floor drain wastes prior to discharge consists of
options for Ozone Injection, Ultra Filtration, Reverse Osmosis and demineralization. These options are provided using the (ZERO) liquid waste processing components.
The chemical drain tank (CDT) receives chemically contaminated tritiated water
from the plant sample stations, and chemically contaminated decontamination wastes. Contents of the tank are sampled as process initiation levels are reached then drained to the FDT subsystem to dilute any high conductivity prior
to being processed by the liquid waste process system. A high level alarm is
provided from the CDT for operator information.
11.2.3 RADIOACTIVE RELEASES
This section describes the estimated liquid release from the plant for normal operation and anticipated operational occurrences.
11.2.3.1 Sources Section 11.1 and Appendix 11.1A provide the bases for determining the contained
sources inventory and the normal releases.
A survey has been performed of liquid discharges from different Westinghouse pressurized water reactor plants. The results are presented in Table 11.2-17
of Reference 2. The data includes radionuclides released on an unidentified
basis, and are all within the permissible concentration for the release of
liquid containing all unidentified radionuclide mixtures.
11.2.3.2 Release points Radioactive plant wastes are treated inside the power block, where the majority
of radioactive material is concentrated for offsite disposal. Water containing small concentrations of radioactivity is discharged from the power block to the environment as plant effluent. The effluent normally discharges from the plant
into the circulating water discharge piping, which dilutes the power block
effluent and conveys it to the cooling lake. The point of discharge into the
cooling lake for these effluents is at the circulating water discharge structure (See Figure 11.2-1). Three other potential discharge points to the cooling lake are directly from the lime sludge pond, the oily waste separator, and the Technical Support Center. The Technical Support Center decontamination
shower would only be used by E-Plan personnel if access control and rad waste
showers were unavailable. These three pathways have no dilution. Further discussion of concentrations of radioactivity in the cooling lake from normal operational releases is provided in Section 11.2.3.3. A discussion of concentrations of radioactivity in the cooling lake from accidental release of
liquid effluents is discussed in Section 2.4.12.
11.2-13 Rev. 23 Wolf Creek This low level radioactive liquid effluent is stored in the power block in the primary and secondary waste monitor tanks (two each, four total) and the steam
generator blowdown surge tank. Each of these tanks feeds into the liquid radwaste discharge line, which is connected to the circulating water discharge piping (See Figure 11.2-2). Tank discharge is initiated manually in all cases.
The minimum flow of dilution water which conveys the power block radioactive
effluent to the cooling lake is 5,000 gpm. In the event that the dilution flow is less than 5,000 gpm, release of radioactive power block effluent is prohibited and is terminated through automatic controls at a point inside the
power block.
Circulating water pumps and service water pumps provide dilution to discharge from the power block. The release of radioactive effluent from the power block is automatically terminated when no Circulating Water Pumps are in service.
Minimum dilution flow necessary for the discharge of radioactive effluents is established through administrative controls to ensure compliance with Federal
discharge limits.
11.2.3.3 Dilution Factors Liquid radioactive releases are normally diluted by cooling water with a flow
rate of 1114 cfs and service water with a flow rate of 90 cfs for a total discharge of 1204 cfs. This is the normal dilution assumed for dose calculations to the maximum individual interacting with the cooling lake
environment.
11.2.3.4 Estimated Doses Preoperational estimates of doses from liquid effluents were shown to be in conformance with 10CFR50, Appendix I requirements. Actual dose from liquid
effluents during plant operation are calculated using the approved methodology presented in the Offsite Dose Calculation Manual (ODCM). The ODCM describes the methods used for calculating concentration of radioactive material in the environment and the estimated potential offsite doses associated with liquid
and gaseous effluents. The ODCM also specifies controls for release of liquid
and gaseous effluents to ensure compliance with NRC regulations.
11.2.4 CALCULATIONAL BASIS FOR LIQUID SOURCE TERMS
The Wolf Creek Generating Station, Unit No. 1 uses the mixed bed demineralizer
option shown in Item 5 of Figure 11.1A-2 (Sheet 2). The original GALE code
input and annual liquid effluent releases are shown in Tables 11.2-10 and 11.2-11 respectively.
11.2-14 Rev. 23 Wolf Creek 11.2.5 SAFETY EVALUATION
Except for two associated containment penetrations and the CCW pressure boundary integrity at the reactor coolant drain tank, the LRWS is not a safety-related system.
SAFETY EVALUATION ONE - Sections 6.2.4 and 6.2.6 provide the safety evaluation
for the system containment isolation arrangement and testability.
11.2.6 TESTS AND INSPECTION
Preoperational testing is discussed in Chapter 14.0.
The operability, performance, and structural and leaktight integrity of all system components are demonstrated by continuous operation.
11.2.7 INSTRUMENTATION DESIGN
The system instrumentation is described in Table 11.2-12 and shown on Figure 11.2-1.
The instrumentation readout is located mainly on the waste processing system
panel in the radwaste building. Some instruments are read locally.
All alarms are shown separately on the waste processing system panel and
further relayed to one common waste processing system annunciator on the main
control board.
The waste processing system pumps are protected against loss of suction pressure by a control setpoint on the level instrumentation for the respective vessels feeding the pumps. The reactor coolant drain tank pumps and the spent
resin sluice pump are, in addition, interlocked with flow rate instrumentation
and stop operating when the delivery flows reach minimum setpoints.
Differential pressure indicators with local readout are provided for filters, strainers, and demineralizers.
11.
2.8 REFERENCES
- 1. NUREG-0017, "Calculation of Releases of Radioactive Materials
in Gaseous and Liquid Effluents from Pressurized Water
Reactors" (PWR-GALE Code), NRC, April 1976, pg. 6-1.
- 2. "Appendix D to RESAR-3S, Liquid Waste Management System," WCAP 8665, March 1976.
11.2-15 Rev. 23 Wolf Creek
- 3. Attachment to Concluding Statement of Position of the Regulatory Staff. Public Rule-making Hearing on: Numerical
Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low as Practicable" for Radioactive Material in Light-Water-Cooled Nuclear Power Stations, USAEC, Docket No. RM-50-2, February 20, 1974.
- 4. Fletcher, J. F., and W. L. Dotson (compilers). HERMES-A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry, USAEC. Report HEDL-
TME-71-168, Hanford Engineering Development Laboratory, 1971.
- 5. Final Environmental Statement Concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low as
Practicable:" for Radioactive Material in Light-Water-Cooled, Nuclear Power Reactor Effluents, USAEC Report WASH-
1258, Washington, D.C., July 1973.
- 6. Lyon, R. J., Shearin, R. L., 1976, EPA-520 Radionuclide
Accumulation in a Reactor Cooling Lake: USEPA, Office of
Radiation Programs.
- 7. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of
Evaluating Compliance with 10 CFR 50, Appendix I, Office of
Standards Development.
- 8. Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Office of Standards
Development.
- 9. Simpson, D. B., McGill, B. L., 1980, NUREG/CR-1276 User's Manual for LADTAP II Computer Program: U.S.N.R.C. and Oak
Ridge National Laboratory.
11.2-16 Rev. 23 WOLF CREEK TABLE 11.2-1 LIQUID WASTE PROCESSING SYSTEM EQUIPMENT PRINCIPAL DESIGN PARAMETERS Reactor Coolant Drain Tank Pumps
Number 2
Type Horizontal centrifugal
Design pressure, psig 150 Design temperature, F 200
Design flow, gpm
Point l 100 Point 2 150
Design head, ft
Point 1 260
Point 2 250 Material Stainless steel
Design code MS Waste Evaporator Feed Pump Number l Type Canned centrifugal Design pressure, psig 150
Design temperature, F 200
Design flow, gpm Point 1 35
Point 2 100
Design head, ft Point l 250
Point 2 200
Rev. 16
WOLF CREEK TABLE 11.2-1 (Sheet 2)
Material Stainless steel Design code (1) MS Waste Evaporator Condensate Pump Number 1 Type Canned centrifugal Design pressure, psig 150
Design temperature, F 200 Design flow, gpm
Point 1 35
Point 2 100 Design head, ft
Point 1 250
Point 2 230 Material Stainless steel
Design code MS
Chemical Drain Tank Pump
Number 1
Type Canned centrifugal
Design pressure, psig 150 Design temperature, F 200
Design flow, gpm
Point 1 35 Point 2 100
Design head, ft
Point l 250 Point 2 230
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 3)
Material Stainless steel Design code MS Laundry and Hot Shower Tank Pump Number l Type Horizontal centrifugal Design pressure, psig 150
Design temperature, F 200 Design flow, gpm
Point 1 35
Point 2 100 Design head, ft
Point 1 250
Point 2 230 Material Stainless steel
Design code MS
Floor Drain Tank Pumps
Number 2
Type Horizontal centrifugal
Design pressure, psig 150 Design temperature, F 200
Design flow, gpm
Point 1 35 Point 2 100
Design head, ft
Point l 250 Point 2 230
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 4)
Material Stainless steel Design code MS Waste Monitor Tank Pumps Number 2 Type Canned centrifugal Design pressure, psig 150
Design temperature, F 200 Design flow, gpm
Point 1 35
Point 2 100 Design head, ft
Point 1 250
Point 2 230 Material Stainless steel
Design code MS
Laundry Water Storage Tank Pump
Number 1
Type Inline centrifugal
Design pressure, psig 150 Design temperature, F 200
Design flow, gpm 35
Design head, ft 81 Material Stainless steel
Design code MS
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 5)
Reactor Coolant Drain Tank Heat Exchanger
Number 1
Type U-tube
Estimated UA, Btu/hr-F 70,000 Design flow, lb/hr
Shell 112,000
Tube 44,600 (See *)
Temperature in, F
Shell 105 Tube 180 (See *)
Temperature out, F
Shell 125 Tube 130 Material Shell Carbon steel
Tube Stainless steel Design code
Shell side ASME Section III
Tube side ASME Section VIII
- At Operating temp. 170 F, Flow is 55,581 #/hr Reactor Coolant Drain Tank
Number 1
Type Horizontal
Usable volume, gal 350 Design pressure, psig* 100
Design temperature, F 250
- External design pressure is 60 psig.
Rev. 16
WOLF CREEK TABLE 11.2-1 (Sheet 6)
Material Stainless steel Design code (1) ASME Section VIII Waste Holdup Tank Number l Type Vertical Usable volume, gal 10,000
Design pressure Atmospheric
Design temperature, F 200 Material Stainless steel
Design code (1) ASME Section VIII (no code stamp)
Waste Evaporator Condensate Tank Number 1 Type Vertical Usable volume, gal 5,000
Design pressure, psig +0.433 Design temperature, F 200
Material Stainless steel
Design code ASME Section VIII (no code stamp)
Chemical Drain Tank
Number 1
Type Vertical
Usable volume, gal 600 Design pressure, psig +0.5
Design temperature, F 200
Material Stainless steel
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 7)
Design code ASME Section VIII (no code stamp)
Laundry and Hot Shower Tank Number 1
Type Vertical
Usable volume, gal 10,000 Design pressure, psig +0.5
Design temperature, F 200
Material Stainless steel Design code ASME Section VIII
(no code stamp)
Floor Drain Tanks Number 2 Type Vertical Usable volume, gal 10,000
Design pressure, psig +0.5
Design temperature, F 200 Material Stainless steel
Design code ASME Section VIII (no code stamp)
Laundry Water Storage Tank Number l Type Vertical Usable volume, gal 10,000
Design pressure Atmospheric Design temperature, F 200
Material Stainless steel
Design code ASME Section VIII (no code stamp)
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 8)
Waste Monitor Tanks
Number 2
Type Vertical
Usable volume, gal 5,000 Design pressure, psig +0.5
Design temperature, F 200
terial Stainless steel Design code ASME Section VIII
(no code stamp)
Waste Evaporator Reagent Tank Number 1 Type Vertical Usable volume, gal 5
Design pressure, psig 150
Design temperature, F 200 Material Stainless steel
Design code ASME Section VIII
Waste Evaporator Condensate Demineralizer
Number 1
Type Flushable
Design pressure, psig 300 Design temperature, F 250
Design flow, gpm 120
Resin volume, ft 3 max. 39
Material Stainless steel
Design code (1) ASME Section VIII
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 9)
Waste Monitor Tank Demineralizer
Number l
Type Flushable
Design pressure, psig 300 Design temperature, F 250
Design flow, gpm 120
Resin volume, ft 3 max. 39
Material Stainless steel
Design code (1) ASME Section VIII
Liquid Waste Charcoal Adsorber
Number 1
Type Flushable
Design pressure, psig 150 Design temperature, F 200
Design flow rate, gpm 35
Charcoal volume, ft 3 42
Material Stainless steel
Design code ASME Section VIII
Laundry and Hot Shower Charcoal Adsorber
Number 1
Type Flushable
Design pressure, psig 150 Design temperature, F 200
Design flow rate, (gpm) avg./max. 4/10
Charcoal volume, ft 3 10
Material Stainless steel
Design code ASME Section VIII
Rev. 0
WOLF CREEK TABLE 11.2-1 (Sheet 10)
Waste Evaporator Feed Filter
Number l
Design pressure, psig 300
Design temperature, F 250 Design flow, gpm 250
P at design flow, unfouled, psi 5
Particle Retention (see note 2 of Table 9.3-13)
Material Stainless steel
Design code (1) ASME Section VIII Waste Evaporator Condensate Filter (FHB10)*
Number l
Design pressure, psig 300
Design temperature, F 250 Design flow, gpm 250
P at design flow, unfouled, psi 5
Particle retention (See Note 2 of Table 9.3-13)
Material Stainless steel
Design code (1) ASME Section VIII
Laundry and Hot Shower Tank Filter (FHB07)*
Number l
Design pressure, psig 300
Design temperature, F 250 Design flow, gpm 250
P at design flow, unfouled, psi 5
Particle retention (See Note 2 of Table 9.3-13)
- See comments on Sheet 2 of Table 9.3-13.
Rev. 11
WOLF CREEK TABLE 11.2-1 (Sheet 11)
Material Stainless steel Design code (1) ASME Section VIII Waste Monitor Tank Filter (FHB08)* Number l Design pressure, psig 300 Design temperature, F 250
Design flow, gpm 250 P at design flow, unfouled, psi 5 Particle retention (See Note 2 of Table 9.3-13)
Material Stainless steel Design code (1) ASME Section VIII
Floor Drain Tank Filter (FHB06)* Number 1 Design pressure, psig 300 Design temperature, F 250
Design flow, gpm 250 P at design flow, unfouled, psi 5 Particle retention (See Note 2 of Table 9.3-13)
Material Stainless steel Design code (1) ASME Section VIII
Rev. 10
WOLF CREEK TABLE 11.2-1 (Sheet 12)
Liquid Radwaste Demineralizer Skid Number 1 Design flow rate, gpm 50 Nominal Design pressure, PSIG Maximum 150 Design temperature, F Maximum 150 Material MS Design code ASME Section VIII Laundry and Hot Shower Tank Strainer Number l Design pressure, psig 150 Design temperature, F 200
Design flow, gpm 35 P at design flow, unfouled, psi 0.2 Basket perforation size, inch 1/16
Material Stainless steel Design code ASME Section VIII
Floor Drain Tank Strainer Number 1 Design pressure, psig 150 Design temperature, F 200
Design flow, gpm 35 P at design flow, unfouled, psi 0.2 Basket perforation size, inch 1/16
Material Stainless steel Design code ASME Section VIII
Rev. 8
WOLF CREEK TABLE 11.2-1 (Sheet 13)
Waste Evaporator (2)
Number 1
Steam design pressure, psig 50 Design feed flow, gpm 15 Feed concentration, boron, ppm 10-2,500
Bottoms concentration, boron, ppm 7,200-21,000
Material (for concentrates) Incoloy 825 (or equivalent)
Design code ASME Section VIII/TEMA C
(1) Table indicates that the required code is based on its
safety-related importance as dictated by service and functional requirements and by the consequences of their failure. Note that the equipment may be supplied to a higher
principal construction code than required.
(2) Equipment is abandoned in place.
Rev. 19 WOLF CREEK TABLE 11.2-2 TANK UNCONTROLLED RELEASE PROTECTION PROVISIONS I. Tanks Outside Plant Buildings REF: Figure 1.2-1 Grade Elevation: 2000'-0" Overflow Tanks Elevation Control Level Indicator, High Alarms, Low Alarms, Etc. Remarks
- 1. Condensate storage tank 2000'-0" Overflows to Level indicator and high level alarm are pro-waste holdup vided in control room. Level is indicated in tank auxiliary shutdown panel. Refer to Figure 9.2-12.
- 2. Refueling water storage tank 2000'-0" Overflows to Low and high level alarms provided. Refer to waste holdup Figure 6.3-1. Level indicator also provided.
tank
- 3. Reactor makeup water storage tank 2000'-0" Overflows to Low and high level alarms provided in control
waste holdup room. Refer to Figure 9.2-13. Level indicator tank also provided.
II. Tanks Inside the Radwaste Building REF: Figures 1.2-2 through 1.2-8
- 1. Recycle holdup tanks (2) 1976'-0" Overflows to Low and high level alarms on radwaste panel Located in rad. bldg. located in radwaste building. Refer to watertight drain sump, Figure 9.3-11. Level indicator also provided. compartment from there below grade
pumped to the floor drain sump
- 2. Waste gas decay tanks (8) 1976'-0" None None.
- 3. Evaporator bottoms tanks (2) 1976'-0" Overflows to Low and high level alarms provided in con- Curb pro-2000'-0" chemical trol room. Refer to Figure 11.4-1. Level vided drain tank indicator also provided.
- 4. Spent resin storage tanks (2) 2000'-0" None Low and high level alarms provided on rad- Curb pro-waste panel in the radwaste building. Refer vided
to Figure 11.4-1. Level indicator also pro-vided.
- 5. Chemical drain tank 1976'-0" Overflows to Low and high level alarms provided on rad-rad. bldg. waste panel. Refer to Figure 11.2-1.
drain sump; Level indicator also provided.
from there to floor drain tank
- 6. Waste evaporator cond. tank 1976'-0" Overflows to Low and high level alarms provided on rad-rad. bldg. waste panel. Refer to Figure 11.2-1.
equipment Level indicator also provided.
drain tank
Rev. 0 WOLF CREEK TABLE 11.2-2 (Sheet 2)
Overflow Tanks Elevation Control Level Indicator, High Alarms, Low Alarms, Etc.
- 7. Waste holdup tank 1976'-0" Overflows to Low and high level alarms provided on rad waste panel rad. bldg drain sump.. Refer to Figure 11.2-1.
then pumped Level indicator also provided.
to floor drain tank
- 8. Floor drain tank (2) 1976'-0" Overflows to Low and high level alarms provided on rad-rad. bldg. waste panel. Refer to Figure 11.2-1.
drain sump; Level indicator also provided.
from there to the tank
itself
- 9. S.G. blowdown surge tank 1976'-0" Overflows to Low level pump shut-off and high level blow-
rad. bldg. down isolation provided. Refer to Figure 10.4-8.
drain sump; Level indicator also provided.
from there
to floor drain tank
- 10. Solid radwaste disposal station 2000'-0" Overflows to Level indication provided.
(HIC) drain trench
- 11. Waste monitor tanks (2) 2000'-0" Overflows to Low and high level alarms provided on radwaste rad. bldg. panel. Refer to Figure 11.2-1. Level indicator drain sump; also provided.
from there to floor drain tank
- 12. Recycle evaporator 2000'-0" None Evaporator package shown in Figure 9.3-11 has been permanently removed from service. (Abandoned in place)
- 13. Waste evaporator 2000'-0" None Evaporator package shown in Figure 11.2-1.
(Abandoned in place)
- 14. Laundry and hot shower tank 2031'-6" Overflows to Low and high level alarms provided. Level in-floor and dicator also provided. Refer to Figure 11.2-1.
equip. drain sump; then to floor drain tank
Rev. 19 WOLF CREEK TABLE 11.2-2 (Sheet 3)
Overflow Tanks Elevation Control Level Indicator, High Alarms, Low Alarms, Etc.
Remarks III. Tanks Inside the Auxiliary Building REF: Figures 1.2-9 through 1.2-18
- 1. Boric acid tanks (2) 1974'-0" Overflows to Low and high level alarms provided. Refer to aux. bldg. Figure 9.3-8. Level indicator also provided.
equip. drain tank
- 2. Boron injection tank 1974'-0" None No level alarms or level indicator provided.
Refer to Figure 6.3-1.
- 3. Deleted
- 4. Equipment drain sumps (2) 1974'-0" None Low and high level alarms provided in control
room. Refer to Figure 9.3-5. No level indicator provided.
- 5. Volume control tank 2000'-0" Relief valve Low and high level alarms provided. Refer to discharge to Figure 9.3-8. Level indicator also provided.
recycle hold-
up tank
- 6. Boric acid batching tank 2026'-0" Overflows to Low level alarm provided locally. Refer to
aux. bldg. Figure 9.3-8. Level indicator also provided.
equip. drain tank
- 7. Chemical addition tank (chemical 2026'-0" None No alarms or level indicator provided. Refer mixing tank) to Figure 9.3-8. Tank filled locally by opera-ting personnel.
IV. Tanks Inside Reactor Building REF: Figure 1.2-11
- 1. Reactor coolant drain tank 2000'-0" None Low and high level alarms provided. Refer to Figure 11.2-1. Level indicator also provided.
- 2. Pressurizer relief tank 2000'-0" None Low and high level alarms provided in control room. Refer to Figure 11.2-1. Level indicator
also provided.
Rev. 10 WOLF CREEK TABLE 11.2-3 (Historical Information)
CALCULATED LIQUID EFFLUENT DISCHARGE CONCENTRATIONS FROM ROUTINE OPERATION pCi/1 Isotope a Release Ci/yr Circulating Water b Cooling Lake c LeRoy d 1H 3 4.10+002 2.38+004 2.34+004 7.38E+002 24CR 51 9.00-005 1.62-004 7.83-005 2.47E-006 25MN 54 1.20-004 1.22-003 1.11-003 3.50E-005 26FE 55 9.00-005 2.39-003 2.30-003 7.26E-005 26FE 59 5.00-005 1.17-004 7.02-005 2.22E-006 27CO 58 1.30-003 4.09-003 2.88-003 9.09E-005 27CO 60 9.80-004 4.07-002 3.98-002 1.26E-003 35BR 83 3.00-005 2.79-005 9.40-008 2.97E-009 42MO 99 1.80-003 1.84-003 1.67-004 5.27E-006 43TC 99M 1.70-003 1.60-003 1.33-005 4.20E-007 52TE 129M 7.00-005 1.39-004 7.42-005 2.34E-006 53I 131 9.50-002 1.12-001 2.40-002 7.57E-004 52TE 132 6.10-004 6.30-004 6.19-005 1.95E-006 53I 132 1.70-003 1.58-003 5.11-006 1.61E-007 53I 133 3.00-002 2.87-002 8.23-004 2.60E-005 55CS 134 8.10-003 1.79-001 1.71-001 5.40E-003 53I 135 5.20-003 4.89-003 4.55-005 1.44E-006 55CS 136 2.10-003 2.81-003 8.54-004 2.70E-005 55CS 137 7.30-003 5.03-001 4.96-001 1.57E-002 40ZR 95 1.40-004 4.14-004 2.84-004 8.96E-006 41NB 95 2.00-004 4.06-004 2.20-004 6.94E-006 37RB 86 2.00-005 3.03-005 1.17-005 3.69E-007 44RU 103 2.00-005 4.35-005 2.49-005 7.86E-007 44RU 106 2.40-004 2.90-003 2.68-003 8.46E-005 47AG 110M 4.00-005 3.46-004 3.09-004 9.75E-006 58CE 144 5.20-004 4.98-003 4.50-003 1.42E-004 38SR 89 2.00-005 5.12-005 3.26-005 1.03E-006 52TE 127M 1.00-005 4.32-005 3.39-005 1.07E-006 52TE 127 2.00-005 1.88-005 2.46-007 7.76E-009 52TE 129 5.00-005 4.65-005 7.49-008 2.36E-009 53I 130 1.00-004 9.49-005 1.63-006 5.14E-008 52TE 131M 3.00-005 2.90-005 1.18-006 3.72E-008 93NP 239 2.00-005 2.01-005 1.47-006 4.64E-008 a M = Metastable b Based solely on dilution by the circulating water discharge and buildup of radionuclides over 40 year plant life.
c Based on dilution by the circulating water discharge and buildup of radionuclides in the cooling lake over 40 year plant life.
d Concentration of radionuclides at the LeRoy water works intake.
Based on dilution by circulating water discharge and build-up of radionuclides in the cooling lake over 40 year plant life and additional dilution in the Neosho River.
Rev. 19 WOLF CREEK TABLE 11.2-4 (Historical Information)
BIOACCUMULATION FACTORS (pCi/kg per pCi/liter)
FRESHWATER SALTWATER ELEMENT FISH INVERTEBRATE FISH INVERTEBRTATE H 9.0E-01 9.0E-01 9.0E-01 9.3E-01 C 4.6E 03 9.1E 03 1.8E 03 1.4E 03 NA 1.0E 02 2.0E 02 6.7E-02 1.9E-01 P 1.0E 05 2.0E 04 2.9E 04 3.0E 04 CR 2.0E 02 2.0E 03 4.0E 02 2.0E 03 MN 4.0E 02 9.0E 04 5.5E 02 4.0E 02 FE 1.0E 02 3.2E 03 3.0E 03 2.0E 04 CO 5.0E 01 2.0E 02 1.0E 02 1.0E 03 NI 1.0E 02 1.0E 02 1.0E 02 2.5E 02 CU 5.0E 01 4.0E 02 6.7E 02 1.7E 03 ZN 2.0E 03 1.0E 04 2.0E 03 5.0E 04 BR 4.2E 02 3.3E 02 1.5E-02 3.1E 00 RB 2.0E 03 1.0E 03 8.3E 00 1.7E 01 SR 3.0E 01 1.0E 02 2.0E 00 2.0E 01 Y 2.5E 01 1.0E 03 2.5E 01 1.0E 03 ZR 3.3E 00 6.7E 00 2.0E 02 8.0E 01 NB 3.0E 04 1.0E 02 3.0E 04 1.0E 02 MO 1.0E 01 1.0E 01 1.0E 01 1.0E 01 TC 1.5E 01 5.0E 00 1.0E 01 5.0E 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 RH 1.0E 01 3.0E 02 1.0E 01 2.0E 03 TE 4.0E 02 6.1E 03 1.0E 01 1.0E 02 I 1.5E 01 5.0E 00 1.0E 01 5.0E 01 CS 2.0E 03 1.0E 03 4.0E 01 2.5E 01 BA 4.0E 00 2.0E 02 1.0E 01 1.0E 02 LA 2.5E 01 1.0E 03 2.5E 01 1.0E 03 CE 1.0E 00 1.0E 03 1.0E 01 6.0E 02 PR 2.5E 01 1.0E 03 2.5E 01 1.0E 03 ND 2.5E 01 1.0E 03 2.5E 01 1.0E 03 W 1.2E 03 1.0E 01 3.0E 01 3.0E 01 NP 1.0E 01 4.0E 02 1.0E 01 1.0E 01 *Regulatory Guide 1.109 Rev. 19 WOLF CREEK TABLE 11.2-5 (Sheet 1 of 4) (Historical Information)
ASSUMPTIONS USED FOR ESTIMATING DOSES FROM LIQUID EFFLUENTS AT THE WOLF CREEK GENERATING STATION SITE The following assumptions and parameters were used in LADTAP II for estimating doses at the Wolf Creek Generating Station site from liquid effluents:
PARAMETER INDIVIDUAL POPULATION REFERENCE Cooling Lake volume, Normal 4.847E+009 ft 3 4.847E+009 ft 3 Sections 2.4.8.2 and Pre-drought 4.649E+009 ft 3 4.649E+009 ft 3 2.4.11.3 Low-drought 4.451E+009 ft 3 4.451E+009 ft 3 Seepage 3.5 ft 3/sec 3.5 ft 3/sec Page 2.4-43 Blowdown Discharge Sargent & Lundy Normal-post drought 40.0 ft 3/sec 40.0 ft 3/sec Report SL-3204 Revised Pre-drought 3.5 ft 3/sec 3.5 ft 3/sec March 26, 1976, on Drought 0.0 ft 3/sec 0.0 ft 3/sec Cooling Lake Operation pgs. 10, 11, 13, 14 & 15 Avg. Neosho River 1335 ft 3/sec 1335 ft 3/sec WCGS-ER(OLS) flow rate 5.1.2.2 page 5.1-3 Dilution at Le Roy 31.69 31.69 Population at Le Roy -- 624 1980 Census from Coffey County Clerk Telephone Call Record 4/17/81 Population - 50 mile -- 1980 168,130 Table 2.1-3 2000 184,470 Rev. 19 WOLF CREEK TABLE 11.2-5 (Sheet 2 of 4) (Historical Information)
PARAMETER INDIVIDUAL POPULATION REFERENCE Circulating water 1204 cfs 1204 cfs WCGS-ER(OLS) discharge flow rate Section 3.3 page 3.3-1 Circulating Water and Service Water Shore width factor, .3 .3 Reg. Guide 1.109 Cooling Lake p. 15 Table A-2 Shore width factor, .2 .2 Reg. Guide 1.109 Neosho River p. 15 Table A-2 Drinking Water Reg. Guide 1.109 Adult 730 1/yr 370 1/yr pgs. 39 & 40, Teen 510 1/yr 370 1/yr Tables E-4, E-5 Child 510 1/yr 370 1/yr Infant 330 1/yr 370 1/yr Fish Consumption Reg. Guide 1.109 Adult 21 Kg/yr 6.9 Kg/yr Pgs. 39 & 40, Teen 16 Kg/yr 5.2 Kg/yr Tables E-4 & E-5 Child 6.9 Kg/yr 2.2 Kg/yr Infant 0.0 Kg/yr 0.0 Kg/yr Invertebrate Consumption Reg. Guide 1.109 Adult 5 Kg/yr 1.0 Kg/yr Pgs. 39 & 40, Teen 3.8 Kg/yr .75 Kg/yr Tables E-4 & E-5 Child 1.7 Kg/yr .33 Kg/yr Infant 0.0 Kg/yr 0.0 Kg/yr Shoreline Exposure Reg. Guide 1.109 Adult 12 hr/yr 8.3 hr/yr Pgs. 39 & 40, Teen 67 hr/yr 47 hr/yr Tables E-4 & E-5 Child 14 hr/yr 9.5 hr/yr Rev. 19 WOLF CREEK TABLE 11.2-5 (Sheet 3 of 4) (Historical Information)
PARAMETER INDIVIDUAL POPULATION REFERENCE Swimming hrs per person HERMES Pgs. 144 & 145, Adult 7.8 hr/yr 3.42 hr/yr Tables III-31 & 32 Teen 45.0 hr/yr 19.2 hr/yr Child 28.2 hr/y 12.0 hr/yr Boating hrs per person HERMES Pgs. 144 & 145, Adult 52.2 hr/yr 29 hr/yr Tables III-31 & 32 Teen 52.2 hr/yr 29 hr/yr Child 29.0 hr/yr 16.53 hr/yr Hold up time hrs hrs Inherent to program Water 12 24 Reg. Guide 1.109 P. 69 Fish 24 168 Pgs. 12 & 69 Invertebrate 24 168 Pgs. 12 & 69 Shoreline exposure 0 0 P. 69 Swimming 0 0 P. 69 Boating 0 0 P. 69 POPULATION Fraction of Population Inherent to program Adult 71% Teen 11% Child 18%
Le Roy Population - 1980 50 Mile Population - 1980 Reference calculated Adult 443 Adult 119,372 from Le Roy - 1980 Teen 69 Teen 18,494 Census from Coffey Child 112 Child 30,263 County Clerk. 50 Mile - Total 624 Total 68,130 Table 2.1-3 Sport Fish Harvest - Hazleton Lake Use Feasibility Study WCGS-ER(OLS) Appendix 2A Page 2A-8 Lake Capability 54,000 fishing trips annually 2 lbs per trip from lake.
Page 2A-4 18.4% of Kansas population are fishermen.
Rev. 19 WOLF CREEK TABLE 11.2-5 (Sheet 4 of 4) (Historical Information)
Sport Fish Harvest Fish Harvest Site Specific 675 Kg/yr 48,990 Kg/yr Sport Invertebrate Harvest Invertebrate Harvest Site Specific 97.9 Kg/yr 26,350 Kg/yr POPULATION REFERENCE Le Roy Population - 1980 50 Mile Population - 1980 Shoreline Recreation Shoreline Recreation 7,984 hrs/yr 2,147,000 hrs/yr Site Specific Swimming Swimming 4,184 hrs/yr 1,126,500 hrs/yr Site Specific Boating Boating 16,700 hrs/yr 4,498,000 hrs/yr Site Specific Nearest Downstream Water Intake Location - Le Roy Individual Intake Population Intake Reg. Guide 1.109 .2678 gal/day 167 gal/day Site Specific Annual Liquid Release Source Terms Table 11.1-2 Rev. 19 WOLF CREEK TABLE 11.2-6 (Historical Information)
ESTIMATED DOSE RATES TO MAXIMUM INDIVIDUALS RESIDING IN THE TOWN OF LE ROY, FROM LIQUID EFFLUENTS ADULT MREM PER YEAR PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 6.64-002 1.07-001 7.57-002 1.89-003 3.66-002 1.31-002 3.59-003 Invertebrate 8.13-004 1.68-003 1.26-003 3.89-004 8.71-004 4.89-004 9.27-004 Drinking 1.16-003 5.83-002 5.78-002 5.75-002 5.71-002 5.67-002 5.66-002 Shoreline 8.11-005 6.95-005 6.95-005 6.95-005 6.95-005 6.95-005 6.95-005 6.95-005 Swimming .00 2.97-007 2.97-007 2.97-007 2.97-007 2.97-007 2.97-007 2.97-007 Boating .00 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 Total 8.11-005 6.84-002 1.67-001 1.35-001 5.99-002 9.47-002 7.04-002 6.12-002 TEENAGER PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 7.04-002 1.10-001 4.29-002 1.53-003 3.73-002 1.51-002 2.72-003 Invertebrate 8.61-004 1.64-003 7.88-004 3.06-004 8.07-004 4.35-004 6.86-004 Drinking 1,13-003 4.16-002 4.05-002 4.07-002 4.04-002 4.01-002 3.99-002 Shoreline 4.53-004 3.88-004 3.88-004 3.88-004 3.88-004 3.88-004 3.88-004 3.88-004 Swimming .00 1.71-006 1.71-006 1.71-006 1.71-006 1.71-006 1.71-006 1.71-006 Boating .00 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 9.90-007 Total 4.53-004 7.28-002 1.53-001 8.46-002 4.30-002 7.89-002 5.60-002 4.37-002 CHILD PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 8.79-002 9.70-002 1.69-002 1.34-003 3.18-002 1.20-002 1.55-003 Invertebrate 1.12-003 1.48-003 4.54-004 2.72-004 7.08-004 3.67-004 3.87-004 Drinking 3.26-003 7.99-002 7.69-002 7.84-002 7.75-002 7.67-002 7.64-002 Shoreline 9.46-005 8.10-005 8.10-005 8.10-005 8.10-005 8.10-005 8.10-005 8.10-005 Swimming .00 1.07-006 1.07-006 1.07-006 1.07-006 1.07-006 1.07-006 1.07-006 Boating .00 5.52-007 5.52-007 5.52-007 5.52-007 5.52-007 5.52-007 5.52-007 Total 9.46-005 9.24-002 1.78-001 9.44-002 8.01-002 1.10-001 8.92-002 7.84-002 INFANT 1 PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish .00 .00 .00 .00 .00 .00 .00 Drinking 3.37-003 7.93-002 7.53-002 7.83-002 7.61-002 7.54-002 7.50-002 Shoreline .00 .00 .00 .00 .00 .00 .00 .00 Tota .00 3.37-003 7.93-002 7.53-002 7.83-002 7.61-002 7.54-002 7.50-002 (1) Assumes drinking water is the only liquid pathway an infant would receive exposure from.
Rev. 19 WOLF CREEK TABLE 11.2-7 (Historical Information)
ESTIMATED DOSE RATES TO MAXIMUM INDIVIDUALS FROM LIQUID EFFLUENT CONCENTRATIONS AT THE CIRCULATING WATER DISCHARGE POINT 2 ADULT MREM PER YEAR PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 2.15+000 3.46+000 2.46+000 1.12-001 1.19+000 4.26-001 1.19-001 Invertebrate 2.73-002 5.53-002 4.12-002 1.71-002 3.35-002 1.58-002 5.11-002 Drinking 1 .00 .00 .00 .00 .00 .00 .00 Shorelin 3.93-003 3.37-003 3.37-003 3.37-003 3.37-003 3.37-003 3.37-003 3.37-003 Swimming .00 1.05-005 1.05-005 1.05-005 1.05-005 1.05-005 1.05-005 1.05-005 Boating .00 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 Total 3.93-003 2.18+000 3.52+000 2.51+000 1.32-001 1.22+000 4.45-001 1.74-001 TEENAGER PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 2.28+000 3.56+000 1.39+000 9.67-002 1.21+000 4.89-001 9.00-002 Invertebrate 2.89-002 5.39-002 2.60-002 1.42-002 3.17-002 1.40-002 3.71-002 Drinking .00 .00 .00 .00 .00 .00 .00 Shoreline 2.20-002 1.88-002 1.88-002 1.88-002 1.88-002 1.88-002 1.88-002 1.88-002 Swimming .00 6.06-005 6.06-005 6.06-005 6.06-005 6.06-005 6.06-005 6.06-005 Boating .00 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 3.50-005 Total 2.20-002 2.33+000 3.63+000 1.44+000 1.30-001 1.26+000 5.22-001 1.46-001 CHILD PATHWAY SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Fish 2.84+000 3.15+000 5.51-001 9.27-002 1.03+000 3.89-001 5.06-002 Invertebrate 3.75-002 4.87-002 1.53-002 1.35-002 2.79-002 1.19-002 1.72-002 Drinking .00 .00 .00 .00 .00 .00 .00 Shoreline 4.59-003 3.93-003 3.93-003 3.93-003 3.93-003 3.93-003 3.93-003 3.93-003 Swimming .00 3.77-005 3.77-005 3.77-005 3.77-005 3.77-005 3.77-005 3.77-005 Boating .00 1.95-005 1.95-005 1.95-005 1.95-005 1.95-005 1.95-005 1.95-005 Total 4.59-003 2.88+000 3.20+000 5.70-001 1.10-001 1.06+000 4.05-001 7.18-002 1 Assumes the lake is not a source of drinking water.
2 Assumes an infant would not be exposed to the existing pathways.
Rev. 19 WOLF CREEK TABLE 11.2-8 (Historical Information)
ESTIMATED DOSE FROM LIQUID EFFLUENTS TO POPULATION OF LEROY POPULATION DOSE (person-rem/yr)________________________________
SKIN BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI INGESTION Fish 2.60E-003 3.88E-003 2.28E-003 5.84E-005 1.32E-003 4.85E-004 1.15E-004 Invertebrate 1.95E-005 3.68E-005 2.38E-005 7.71E-006 1.84E-005 1.03E-005 1.70E-005 Drinking Water 4.85E-004 1.91E-002 1.88E-002 1.88E-002 1.87E-002 1.85E-002 1.85E-002 EXTERNAL EXPOSURE Shoreline 5.40E-005 4.62E-005 4.62E-005 4.62E-005 4.62E-005 4.62E-005 4.62E-005 4.62E-005 Swimming 1.59E-007 1.59E-007 1.59E-007 1.59E-007 1.59E-007 1.59E-007 1.59E-007 Boating 3.18E-007 3.18E-007 3.18E-007 3.18E-007 3.18E-007 3.18E-007 3.18E-007 Totals 5.40E-005 3.15E-003 2.31E-002 2.12E-002 1.89E-002 2.01E-002 1.90E-002 1.87E-002 Rev. 19 WOLF CREEK TABLE 11.2-9 (Historical Information)
APPENDIX I CONFORMANCE
SUMMARY
TABLE FOR LIQUID EFFLUENTS
__________________________________________________________________
Type of Dose Design Calculated Point of Dose Liquid Effluents Objective a Dose b Evaluation Dose to total body 3 mrem/yr 2.51 mrem/yr b Point of from all pathways per site Discharge, Cooling Lake Dose to any organ 10 mrem/yr 3.63 mrem/yr c Same as above from all pathways per site a Appendix I design objectives from Sections II.A, II.B, II.C, and II. D (by Annex, RM50-2) of Appendix I, 10CFR Part 50; considers doses to maximum individual.
b Maximum dose to an individual from all liquid pathways.
c Maximum dose to a teen liver from all liquid pathways.
Rev. 19 WOLF CREEK TABLE 11.2-10 (Original Historical Information)
GALE CODE INPUT DATA PWR Parameters Value Thermal power level (megawatts) 3565.000 Plant capacity factor 0.800 Mass of primary coolant (thousands lbs) 530.000 Percent fuel with cladding defects 0.120 Primary system letdown rate (gpm) 75.000 Letdown cation demineralizer flow (gpm) 7.500 Number of steam generators 4.000 Total steam flow (millions lbs/hr) 15.850 Mass of steam in each steam generator (thousands lbs) 8.000 Mass of liquid in each steam generator (thousands lbs) 104.000 Mass of water in steam generators (thousands lbs) 416.000 Total mass of secondary coolant (thousands lbs) 3570.000 Steam generator blowdown rate (thousands lbs/hr) 176.000 Primary to secondary leak rate (lbs/day) 100.000 Condensate demineralizer regeneration time (days) 17.500 Fission product carry-over fraction 0.001 Halogen carry-over fraction 0.010 Condensate demineralizer flow fraction 0.684 Radwaste dilution flow (thousands gpm) 5.000 Liquid Waste Inputs Collection Decay Flow Rate Fraction Fraction Time Time Decontamination Factors Steam (gal/day) of PCA Discharged (days) (days) I CS Others Shim bleed rate 1.84E+03 1.000 .1 20.9 2.0 1.00E+04 2.00E+04 1.00E+05 Equipment drains 3.00E+02 1.000 .1 20.9 2.0 1.00E+04 2.00E+04 1.00E+05 Clean waste input 4.00E+02 .500 .1 10.0 .185 1.00E+04 1.00E+05 1.00E+05 Dirty waste input 1.14E+03 .058 1.0 7.0 .370 1.00E+04 1.00E+05 1.00E+05 S.G. blowdown 3.80E+05 (1) .0 .0 .000 1.00E+03 1.00E+02 1.00E+03 Untreated blowdown 1.27E+05 (1) 1.0 .0 .000 1.00E+00 1.00E+00 1.00E+00 Regenerant solutions 1.71E+04 (1) .0 .0 .350 1.33E+02 2.67E+02 1.33E+02 (1) Fraction of SCA internally calculated by GALE Code Gaseous Waste Inputs There is continuous low vol. purge of vol. control tk Holdup time for xenon (days) 9.0E+1 Holdup time for krypton (days) 9.0E+1 Fill time of decay tanks for the gas stripper (days) 0.0E+0 Rev. 19 WOLF CREEK TABLE 11.2-10 (Sheet 2) (Original Historical Information)
Gas waste system: particulate release fraction 1.0E-2 Primary leakage to buildings outside containment (lb/day) 1.6E+2 Noncontainment: iodine release fraction 1.0E-1 Particulate release fraction 1.0E-2 Containment volume (million cu ft) 2.5E+0 Containment atmosphere cleanup rate (thousand cfm) 0.0E+0 Frequency of containment bldg. high vol. purge (times/yr.) 2.4E+1 Containment-shutdown purge iodine release fraction 1.0E-1 particulate release fraction 1.0E-2 Containment-normal purge rate (cfm) 4.0E+3 Containment-normal purge iodine release fraction 1.0E-1 particulate release fraction 1.0E-2 Steam leak to turbine bldg. (lbs/hr) 1.7E+3 Fraction iodine released from blowdown tank vent 0.0E+0 air ejector 3.0E-1 There is no cryogenic offgas system 3.0E-1 Rev. 19 WOLF CREEK TABLE 11.2-11 (Historical Information)
ANNUAL EFFLUENT RELEASES LIQUID Coolant Concentrations Adjusted Detergent Half-life Primary Secondary Boron Rs Misc Wastes Secondary Turb Bldg Total LWS Total Wastes Total Nuclide (Days) (Micro Ci/ml) (Micro Ci/ml) (Curies) (Curies) (Curies) (Curies) (Curies) (Ci/yr) (Ci/yr) (Ci/yr) Corrosion and Activation Products Cr-51 2.78+001 1.90-003 4.07-008 .00000 .00000 .00000 .00000 .00000 .00009 .00000 .00009 Mn-54 3.03+002 3.10-004 9.02-009 .00000 .00000 .00000 .00000 .00000 .00002 .00010 .00012 Fe-55 9.50+002 1.60-003 3.61-008 .00000 .00000 .00000 .00000 .00000 .00009 .00000 .00009 Fe-59 4.50+001 1.00-003 2.71-008 .00000 .00000 .00000 .00000 .00000 .00005 .00000 .00005 Co-58 7.13+001 1.60-002 3.61-007 .00001 .00002 .00000 .00000 .00003 .00088 .00040 .00130 Co-60 1.92+003 2.00-003 4.06-008 .00000 .00000 .00000 .00000 .00000 .00011 .00087 .00098 Zr-95 6.50+001 .00 .00 .00000 .00000 .00000 .00000 .00000 .00000 .00014 .00014 Nb-95 3.50+001 .00 .00 .00000 .00000 .00000 .00000 .00000 .00000 .00020 .00020 Np-239 2.35+000 1.20-003 2.81-008 .00000 .00000 .00000 .00000 .00000 .00002 .00000 .00002 Fission Products Br-83 1.00-001 4.80-003 5.13-008 .00000 .00000 .00000 .00000 .00000 .00003 .00000 .00003 Rb-86 1.87+001 8.50-005 1.96-009 .00000 .00000 .00000 .00000 .00000 .00002 .00000 .00002 Sr-89 5.20+001 3.50-004 9.04-009 .00000 .00000 .00000 .00000 .00000 .00002 .00000 .00002 Mo-99 2.79+000 8.40-002 1.86-006 .00001 .00004 .00000 .00002 .00007 .00182 .00000 .00180 Tc-99m 2.50-001 4.80-002 1.74-006 .00001 .00004 .00000 .00002 .00006 .00173 .00000 .00170 Ru-103 3.96+001 4.50-005 9.04-010 .00000 .00000 .00000 .00000 .00000 .00000 .00001 .00002 Ru-106 3.67+002 1.00-005 1.80-010 .00000 .00000 .00000 .00000 .00000 .00000 .00024 .00024 Ag-110m 2.53+002 .00 .00 .00000 .00000 .00000 .00000 .00000 .00000 .00004 .00004 Te-127m 1.09+002 2.80-004 4.51-009 .00000 .00000 .00000 .00000 .00000 .00002 .00000 .00001 Te-127 3.92-001 8.50-004 1.62-008 .00000 .00000 .00000 .00000 .00000 .00002 .00000 .00002 Te-129m 3.40+001 1.40-003 2.71-008 .00000 .00000 .00000 .00000 .00000 .00007 .00000 .00007 Te-129 4.79-002 1.60-003 4.88-008 .00000 .00000 .00000 .00000 .00000 .00005 .00000 .00005 I-130 5.17-001 2.10-003 2.91-008 .00000 .00000 .00000 .00000 .00000 .00010 .00000 .00010 Te-131m 1.25+000 2.50-003 4.82-008 .00000 .00000 .00000 .00000 .00000 .00003 .00000 .00003 I-131 8.05+000 2.70-001 4.06-006 .00071 .00229 .00000 .00040 .00339 .09468 .00006 .09500 Te-132 3.25+000 2.70-002 4.63-007 .00000 .00001 .00000 .00000 .00002 .00061 .00000 .00061 I-132 9.58-002 1.00-001 1.42-006 .00000 .00003 .00000 .00003 .00006 .00174 .00000 .00170 I-133 8.75-001 3.80-001 5.50-006 .00003 .00058 .00000 .00045 .00106 .02961 .00000 .03000 Cs-134 7.49+002 2.50-002 5.75-007 .00021 .00003 .00000 .00001 .00024 .00680 .00130 .00810 I-135 2.79-001 1.90-001 2.51-006 .00000 .00005 .00000 .00013 .00019 .00524 .00000 .00520 Cs-136 1.30+001 1.30-002 2.99-007 .00006 .00001 .00000 .00000 .00007 .00209 .00000 .00210 Cs-137 1.10+004 1.80-002 4.16-007 .00015 .00002 .00000 .00000 .00018 .00495 .00240 .00730 Ba-137m 1.77-003 1.60-002 9.58-007 .00014 .00002 .00000 .00000 .00017 .00462 .00000 .00460 Ce-144 2.84+002 3.30-005 9.03-010 .00000 .00000 .00000 .00000 .00000 .00000 .00052 .00052 All Others 2.53-001 1.13-006 .00000 .00000 .00000 .00000 .00000 .00006 .00000 .00006 Total (Except Tritium) 1.46+000 2.17-005 .00133 .00317 .00000 .00107 .00557 .15557 .00629 .16000 Tritium Release 410 Curies Per Year Rev. 19 WOLFCREEKTABLE11.2-12LIQUIDWASTEMANAGEMENTSYSTEMINSTRUMENTATIONPRINCIPALDESIGNPARAMETERSDesignDesignChannelLocationofPressureTemperatureLocationof NumberPrimarySensor (psig)(°F)Range ReadoutLICA-1001Wasteholduptank1502000to100pctLocalandWPSpanelLICA-1002Chemicaldraintank1502000to100pctLocalandWPSpanel LICA-1003Reactorcoolantdraintank1502500to100pctWPSpanel LICA-1004Reactorcoolantdraintank1502500to100pctWPSpanel LICA-1005Primaryspentresinstoragetank1502000to100pctWPSpanelPIA-1006Primaryspentresinstoragetank1502000to100psigWPSpanelFI-1007Wasteevaporatorfeedpumpdischarge1502000to30gpmLocalFIC-1008Reactorcoolantdraintankpumpdischarge1502500to250gpmWPSpanelFIA-1009Reactorcoolantdraintankrecirculation1502500to250gpmWPSpanelLICA-1010Laundryandhotshowertank1502000to100pctWPSpanelandlocalFICA-1011Primaryspentresinsluicepump1502000to150gpmWPSpanelLICA-1012Wasteevaporatorcondensatetank1502000to100pctWPSpanelandlocalFQI-1014Reactorcoolantdraintankdischargetorecycleholdup tank1502500to10gpmLocalPI-1017WasteevaporatorfeedfilterP1502000to25psidLocalPI-1018AReactorcoolantdraintankpumpNo.1discharge1502500to150psigLocalPI-1018BReactorcoolantdraintankpumpNo.2discharge1502500to150psigLocalRev.0 WOLFCREEKTABLE11.2-12(Sheet2)DesignDesignChannelLocationofPressureTemperatureLocationof NumberPrimarySensor (psig)(°F)Range ReadoutPI-1018CLaundryandhotshowertankpumpdischarge1502000to150psigLocalPI-1018DChemicaldraintankpumpdischarge1502000to150psigLocalPI-1018GWasteevaporatorcondensatepump1502000to150psigLocalTIA-1058Reactorcoolantdraintank15025050to250FWPSpanel PI-1074Wasteevaporatorcondensate demineralizerP1502000to25psidLocalPI-1075Wasteevaporatorcondensate filterP1502000to25psidLocalLICA-1077AFloordraintank1502000to100pctWPSpanelandlocalLICA-1077BFloordraintank1502000to100pctWPSpanelandlocalPI-1078FloordraintankfilterP1502000to25psidLocalPI-1079FloordraintankstrainerP1502000to25psidLocalPI-1080Laundryandhotshowertank filterP1502000to25psidLocalPI-1081Laundryandhotshowertanks strainerP1502000to25psidLocalLICA-1082WastemonitortankNo.11502000to100pctWPSpanelandlocalLICA-1083WastemonitortankNo.21502000to100pctWPSpanelandlocal PI-1084AWastemonitortankpumpNo.1discharge1502000to150psigLocalPI-1084BWastemonitortankpumpNo.21502000to150psigLocalFI-1085AWastemonitortankpumpNo.1discharge1502000to100gpmWPSpanelandlocalFI-1085BWastemonitortankpumpNo.2discharge1502000to100gpmWPSpanelandlocalPI-1086ResinsluicefilterP1502000to25psidLocalRev.0 WOLFCREEKTABLE11.2-12(Sheet3)DesignDesignChannelLocationofPressureTemperatureLocationof NumberPrimarySensor (psig)(°F)Range ReadoutPI-1088WastemonitortankfilterP1502000to25psidLocalPI-1089Wastemonitortankdeminerali-1502000to25psidLocal zerPPI-1090AFloordraintankpumpdis-1502000to150psigLocal chargePI-1090BFloordraintankpumpdis-1502000to150psigLocal charge NOTES:
F-Flow Q-Flowintegrator P-Pressure L-Level T-Temperature R-Radiation I-Indication C-Control A-Alarm S-SwitchRev.0 r .. --.. *--c . -*---------'---
.. .. ----...
- -.--.-,...,.. --_,..-*. :------*---.---.---
r*--. -: I WOLF I o I I I I I cnrr* . SITE UNDERGROUND PIPING &: I I. :::>
- z* ' en I .. . r RADIOACTIVE LIQUID RELEASE 42" WARMING 144" CIRCULATING WATER <AND SERVICE WATER DISCHARGE>
CIRCULATING WATER DISCHARGE STRUCTURE
- WARMING LINE TO CIRCULATING WATER SCREENHOUSE REV. 12 WOLF Cl\BBK UPDATED SAFETY ANALYSIS REPORT FIGURE 11.2-1 RADIOACTIVE LIQUID RELEASE FLOW DIAGRAM .. I --. -.. -, ---. -'---.. -----" --------. --------. -. --. --.. -. ---. -" ---. ---.. --.. -....... -. J WOLF CREEK 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS The gaseous radwaste system (GRWS) and the plant ventilation exhaust systems control, collect, process, store, and dispose of gaseous radioactive wastes generated as a result of normal operation, including anticipated operational occurrences. This section discusses the design, operating features, and
performance of the GRWS and the performance of the ventilation systems. The
plant ventilation exhaust systems accommodate other potential release paths for gaseous radioactivity due to miscellaneous leakages, aerated vents from systems containing radioactive fluids, and the removal of noncondensables from the
secondary system. Systems which handle these gases are not normally considered
gaseous waste systems and are discussed in detail in other sections. These
systems are included here to the extent that they represent potential release paths for gaseous radioactivity.
11.3.1 DESIGN BASES
11.3.1.1 Safety Design Basis The GRWS and other gaseous waste management systems serve no safety-related function.
11.3.1.2 Power Generation Design Bases POWER GENERATION DESIGN BASIS ONE - The GRWS and the ventilation exhaust
systems are designed to meet the requirements of the discharge concentration limits of 10 CFR 20 and the as low as reasonably achievable dose objective of 10 CFR 50, Appendix I.
POWER GENERATION DESIGN BASIS TWO - The GRWS includes design features to
preclude the possibility of an explosion where a potential for an explosive
mixture exists.
POWER GENERATION DESIGN BASIS THREE - The GRWS uses design and fabrication codes consistent with quality group D (augmented), as assigned by Regulatory
Guide 1.143 for radioactive waste management systems.
POWER GENERATION DESIGN BASIS FOUR - The ventilation exhaust system complies with Regulatory Guide 1.140 to the extent specified in Table 9.4-3.
POWER GENERATION DESIGN BASIS FIVE - Gaseous effluent discharge paths are
monitored for radioactivity.
11.3-1 Rev. 13 WOLF CREEK POWER GENERATION DESIGN BASIS SIX - The Radwaste Building (including the Waste Bale Drumming Area) is equipped with a monitored ventilation system which
ensures that the potential release pathways are controlled and monitored as per 10 CFR 50, Appendix A, in case of a breach of container.
11.3.2 SYSTEM DESCRIPTIONS
11.3.2.1 General Description This section describes the design and operating features of the GRWS. The
performance of the GRWS and other plant gaseous waste management systems with respect to the release of radioactive gases is discussed in Section 11.3.3.
Detailed descriptions of the plant ventilation systems and main condenser evacuation system are presented in Sections 9.4 and 10.4.2, respectively.
The piping and instrumentation diagram for the GRWS is shown in Figure 11.3-1.
The main flow path in the GRWS is a closed loop comprised of two waste gas compressors, two catalytic hydrogen recombiners, six gas decay tanks for normal power service, and two gas decay tanks for service at shutdown and startup.
The system also includes a gas decay tank drain collection tank, drain pump, four gas traps to handle normal operating drains from the system, and a waste
gas drain filter to permit maintenance and handle normal operating drains from the system. All of the equipment is located in the radwaste building.
The closed loop has nitrogen for a carrier gas. The primary influents to the
GRWS are combined with hydrogen as the stripping or carrier gas. The hydrogen
that is introduced to the system is recombined with oxygen, and the resulting water is removed from the system. As a result, the bulk of all influent gases is removed, leaving trace amounts of inert gases, such as helium and
radioactive noble gases to build up.
The primary source of the radioactive gas is via the purge of the volume control tank with hydrogen, as described in Section 9.3.4. The operation of the GRWS serves to reduce the fission gas concentration in the reactor coolant system which, in turn, reduces the escape of fission gases from the reactor
coolant system during maintenance operations or through equipment leakage.
Smaller quantities are received, via the vent
11.3-2 Rev. 11 WOLF CREEK connections, from the reactor coolant drain tank, the pressurizer relief tank, and the recycle holdup tanks.
Since hydrogen is continuously removed in the recombiner, this gas does not build up within the system. The largest contributor to the nonradioactive gas
accumulation is helium generated by a B10 (n,a)Li7 reaction in the reactor core. The second largest contributors are impurities in the bulk hydrogen and oxygen supplies. Stable and long-lived isotopes of fission gases also contribute small quantities to the system gas volume accumulation.
Operation of the system is such that fission gases are distributed throughout
the six normal operation gas decay tanks. Separation of the GRWS gaseous
inventory in several tanks assures that the allowable site boundary dose will not be exceeded in the event of a gas decay tank rupture. Radiological consequences of such a postulated rupture are discussed in Section 15.7.1.
The GRWS also provides the capacity for indefinite holdup of gases generated
during reactor shutdown. Nitrogen gas from previous shutdowns is contained in the shutdown gas decay tank for use in stripping hydrogen from the reactor coolant system. The shutdown tank is normally at low pressure and is used to
accept relief valve discharges from the normal operation gas decay tanks.
For all buildings where there is potential airborne radioactivity, the ventilation systems are designed to control the release. Where applicable, each building has a vent collection system for tanks and other equipment which
contain air or aerated liquids. The condenser evacuation system discharge is
filtered and discharged to the unit vent in addition to the discharges from the
reactor building, auxiliary building, and fuel building. The radwaste building, which houses the GRWS, has its own release vent. The turbine building has an open ventilation system, and the steam packing exhaust
discharges outside the turbine building.
The vent collection systems receive the discharge of vents from tanks and other equipment in the radwaste and auxiliary buildings which contain air or aerated liquids. These components contain only a very small amount of fission product
gases. Prior to release via the radwaste or auxiliary building ventilation
system, the gases are monitored, as described in Section 11.5, and passed
through a prefilter, HEPA filter, charcoal filter, and another
11.3-3 Rev. 14 WOLF CREEK HEPA filter in series which reduce any airborne particulate radioactivity to negligible levels and provide a decontamination factor of at least 10 for
radioactive iodines and 100 for particulates. Expected efficiencies for iodine removal are better than 99 percent for elemental iodine and 95 percent for organic iodine at 70-percent relative humidity. However, for gaseous effluent release calculations, 70-percent efficiency is conservatively used for
radioiodine isotopes.
Although plant operating procedures, equipment inspection, and preventive maintenance are performed during plant operations to minimize equipment
malfunction, overall radioactive release limits have been established as a
basis for controlling plant discharges during operation with the occurrence of
a combination of equipment faults of moderate frequency. These faults include operation with fuel defects in combination with steam generator tube leaks and malfunction of liquid or gaseous waste processing systems or excessive leakage
in reactor coolant system equipment or auxiliary system equipment. Operational occurrences such as these can result in the discharge of radioactive gases from
various plant systems. These unscheduled discharges may be from plant systems which are not normally considered gas processing systems or from a gas decay tank after a 90-day holdup period. These potential sources are tabulated in
Table 11.1-2. The bases for assumed releases, the factors which tend to
mitigate the release of radioactivity, and the release paths are given in
Appendix 11.1A.
A further discussion of the gaseous releases from the plant is provided in
Section 11.3.3.
11.3.2.2 Component Description Codes and standards applicable to the GRWS are listed in Tables 3.2-1 and 11.3-
- 1. The GRWS is designed and constructed in accordance with quality group D (augmented). The GRWS is seismically designed to the requirements of Reg. Guide 1.143, as discussed in Table 3.2-5. The GRWS is housed within a building also seismically designed to the requirements of Reg. Guide 1.143. The GRWS design complies with Regulatory Guide 1.143, as specified in Table 3.2-5.
WASTE GAS COMPRESSOR - The waste gas compressor is a water-sealed centrifugal
displacement unit which maintains continuous circulation of nitrogen around the waste gas loop. The compressor is provided with a mechanical shaft seal to minimize water leakage. The compressor moisture separator normal water level
is maintained to keep the shaft immersed at all times.
11.3-4 Rev. 0 WOLF CREEK Two waste gas compressor packages are provided. One compressor is normally used, and the other compressor is on standby. The packages are self-contained
and skid-mounted. Construction is primarily of carbon steel.
CATALYTIC HYDROGEN RECOMBINER - The catalytic recombiner disposes of hydrogen brought into the GRWS. This is accomplished by adding a controlled amount of
oxygen to the recombiner which reacts with the hydrogen as the gas flows
through a catalyst bed. The control system for the recombiner is designed to preclude the possibility of a hydrogen explosion. This is further discussed in Section 11.3.6.
Two hydrogen recombiner packages are provided. One recombiner is normally
used, and the other is on standby. The packages are self-contained and skid-mounted. The recombiner is located in the system where the hydrogen concentration and pressure are optimum with respect to hydrogen removal.
DECAY TANK - Eight gas decay tanks are provided, six for normal power operation
and two for service at shutdown and startup. The tanks are of the vertical-cylindrical type and are constructed of carbon steel.
MISCELLANEOUS COMPONENTS - The gas decay drain collection tank provides a
collection point for condensation drained from the gas decay tanks, recombiners, and gas compressors.
All control valves, with the exception of those on the recombiner, are provided
with bellow seals to minimize the leakage of radioactive gases through the
valve bonnet and stem. Valves on the recombiner package are provided with
leakoffs. The leakoff port was removed and capped on the Feed Gas Pressure Control Valve for SHA01A "A" Hydrogen recombiner skid. This leak off line remains intact for the "B" Hydrogen Gas Recombiner skid.
Relief valves have soft seats and are exposed to pressures which are normally
less than two-thirds of the relief valve set pressure. The relief valves of the major components discharge to the shutdown tanks. This permits decay and controlled disposal of all discharges less than about 3,000 scf. The relief valves are designed to relieve full flow from both waste gas compressors.
To maintain leakage from the system at the lowest practicable level, diaphragm-type manual valves are used throughout the waste gas system. For low temperature, low pressure service valves with a synthetic rubber-type diaphragm
are used. This application includes all parts of the system, except the
recombiners. Because of the high temperature that may exist in the recombiner, globe type valves with a metal diaphragm seal in the stem are used. There should be no measurable stem leakage from either type of valve.
11.3-5 Rev. 26 WOLF CREEK The gas decay tank drain pump directs water from the gas decay drain collection tank (due to condensation or maintenance) to the waste holdup tank or recycle
holdup tanks. It is used when there is insufficient pressure in the gas system to drive the fluid. All parts of the pump in contact with the drain water are of austenitic stainless steel. The pump is a canned-motor type.
The waste gas drain filter is a disposable cartridge filter provided to prevent
particulate matter, including rust, from entering the LRWS and BRS. Parts of the filter in contact with the drain water are of austenitic stainless steel.
The waste gas traps are designed to prevent gases from leaving the GRWS. There
are four gas traps - two in the gas decay tank drain line and one each in the
recombiner drain lines and compressor drain lines.
The component description for the ventilation systems is provided in Section
9.4.
11.3.2.3 System Operation Operation of the ventilation systems is described in Section 9.4. The following
is a description of the GRWS.
NORMAL OPERATION - During normal power operation, nitrogen gas, with contained fission gases, is circulated around the GRWS loop by one of the two compressors. Fresh hydrogen gas is introduced into the volume control tank
where it is mixed with fission gases stripped from the reactor coolant by the
action of the volume control tank letdown line spray nozzle. The gas is vented
from the volume control tank into the circulating nitrogen in the waste gas system, at the compressor suction. Normal operational mode of the system is dependent on the reactor coolant system (RCS) gas concentration and the RCS status. A purge of the Volume Control Tank is performed as directed by Chemistry. During a VCT purge using the same Gas Decay Tank is advantageous.
However, switching GDTs may be required, depending on the high operating pressure parameters of the system.
The resulting mixture of nitrogen, hydrogen, and fission gases is pumped by one
of the compressors to one of the two catalytic hydrogen recombiners where
enough oxygen is added to react with and reduce the hydrogen to a low residual level. Water vapor formed in the recombiner by the hydrogen and oxygen reaction is condensed and removed, and the cooled gas stream (now composed
primarily of nitrogen, helium, and fission gases) is discharged from the
recombiner, routed through a gas decay tank, and sent back to the compressor
suction to complete the loop circuit.
Only one gas decay tank is valved into the waste gas loop at any time. By
switching tanks when tank pressure nears the upper operating parameters, this will allow for more decay time for the gases stored in the tanks. This practice will result in fewer radioactive curies released.
11.3-6 Rev. 11 WOLF CREEK If it has been determined that excessive nitrogen buildup is occurring within the system or when other occurrences require it, one tank can be valved out of
service and allowed to decay for a period of 90 days, and then discharged.
STARTUP - At plant startup, the system is first flushed free of air and filled with nitrogen at atmospheric pressure. One compressor, one recombiner, and one
shutdown decay tank are in service. The reactor is at the cold shutdown
condition. Fresh hydrogen is charged into the volume control tank, and the volume control tank vent gas mixes with the circulating nitrogen in the GRWS.
This circulating mixture enters the compressor suction, passes through the
recombiner and shutdown gas decay tank, and returns to the compressor suction.
When the reactor coolant system hydrogen concentration is within operating
specifications, the shutdown gas decay tank is isolated and the gas flow directed to one of the gas decay tanks provided for normal power operation.
Gases accumulated in the shutdown tank will be retained for reuse during
hydrogen stripping from the reactor coolant system during subsequent shutdown operations.
SHUTDOWN AND DEGASSING OF THE REACTOR COOLANT SYSTEM - Plant shutdown operations are essentially startup operations in reverse sequence. The volume
control tank hydrogen purge is maintained until after the reactor is shut down
and coolant fission gas concentrations have been reduced to specified level.
During this operation, hydrogen purge flow may be increased to speed up coolant degassing. The gas decay tank in service for normal power operation is valved out, and a nitrogen purge from the shutdown tank to the volume control tank is
begun. The shutdown tank is placed in the process loop at the compressor
discharge so that the gas mixture from the volume control tank vents to the
compressor suction and passes through the shutdown tank and to the recombiner where hydrogen is removed and returned to the compressor suction. The nitrogen purge continues until the reactor coolant hydrogen concentration reaches the required level. Degassing is then complete, and the reactor coolant system may
be opened for maintenance or refueling.
11.3.3 RADIOACTIVE RELEASES
This section describes the estimated gaseous release from the plant for normal
operation and anticipated operational occurrences.
11.3.3.1 Sources Section 11.1 and Appendix 11.1A provide the bases for determining the contained
source inventory and the normal releases.
11.3-7 Rev. 0 WOLF CREEK 11.3.3.2 Release Points Potential release paths for gaseous radioactivity are illustrated schematically in Appendix 11.1A. The general location of potential gaseous radioactivity release points is depicted in Figure 1.2-1. A description of potential release points for radioactive gaseous effluents is given in Appendix 11.1A, along with
the physical characteristics of the gaseous effluent streams. Release points
from the gaseous waste processing systems are shown on Figure 11.3-2.
11.3.3.3 Dilution Factors The annual average dilution factors used in evaluating the release of gaseous
radioactive effluents are derived and justified in Section 2.3.
11.3.3.4 Estimated Doses The GASPAR computer code, which calculates doses due to normal gaseous
effluents in accordance with Regulatory Guide 1.109, was used to determine the doses listed herein. This code was validated and verification is maintained on file.
The doses due to normal gaseous effluents from WCGS are listed in Tables 11.3-
2, 3 and 4. Doses attributable to radioactive iodines and particulates at the controlling sector Exclusion-Restricted Area boundary are contained within Table 11.3-3 (Hypothetical Worst Case). Doses from iodines and particulates at
the controlling residence are contained within Table 11.3-4 (Controlling
Existing Resident). Table 11.3-2 contains doses from noble gases at the
Exclusion-Restricted Area boundary.
The doses in these tables were calculated assuming intermittent purge operation. Intermittent purge mode release rates were taken from Section 11.1.
The values of the dispersion and deposition coefficients, X/Q (non-decayed),
X/Q (depleted and non-decayed) and D/Q used in the calculations were taken from Section 2.3 and Table 2.3-75. A comparison of the half lives of the radionuclides released to the time needed for released nuclides to disperse to
any point within the 5-mile radius of interest shows that the effect of decay
during this dispersion period is negligible. Thus, the values for X/Q (decayed)
and X/Q (decayed and depleted) were taken to be equivalent to the corresponding X/Q (non-decayed) and X/Q (depleted and non-decayed) values.
11.3-8 Rev. 0 WOLF CREEK A survey of the area within a five-mile radius of the site was conducted during June 1980 and was used to determine the pathways present at the controlling
locations. A 1986 survey of the same area indicates the pathways present at the controlling locations are still the same. X/Qs for the controlling locations were used in calculating doses from iodines and particulates as well as noble gases.
The total doses for Table 11.3-3 and 11.3-4 were calculated by summing the doses from each pathway present. It was conservatively assumed that all age groups were present at each controlling location.
Doses due to noble gases and radioactive iodines and particulates in no case
exceed 10 CFR 50 Appendix I limits.
Actual doses from gaseous effluent during plant operation will be calculated using the approved methodology presented in the Offsite Dose Calculation Manual. 11.3.4 SAFETY EVALUATION The GRWS serves no safety-related function.
11.3.5 TESTS AND INSPECTIONS Preoperational testing is described in Chapter 14.0.
The operability, performance, and structural and leaktight integrity of all
system components are demonstrated by continuous operation.
11.3.6 INSTRUMENTATION APPLICATION
The GRWS instrumentation, as described in Table 11.3-5, is designed to
facilitate automatic operation and remote control of the system and to provide continuous indication of system parameters.
The instrumentation readout is located mainly on the waste processing system
panel in the radwaste building. Some instruments are read where the equipment
is located. Alarms are shown separately on the waste processing system panel and further relayed to one common waste processing system annunciator on the main control board of the plant. Where suitable, instrument lines are provided
with diaphragm seals to prevent fission gas outleakage through the instrument.
Figure 11.3-3 shows the location of the instruments on the compressor package.
11.3-9 Rev. 5 WOLF CREEK The compressors are interlocked with the seal water inventory in the moisture separators and trip off on either high or low moisture separator level. During
normal operation, the proper seal water inventory is maintained automatically.
Figure 11.3-4 indicates the location of the instruments on the recombiner installation.
The catalytic recombiner system is designed for automatic operation with a minimum of operation attention. Each package includes two online gas analyzers, one to measure hydrogen and oxygen in and one to measure hydrogen and oxygen out. The analyzers are the primary means of recombiner control.
Each of these online gas analyzers is independently controlled. In the event
that these analyzers are declared inoperable, operation of the system may continue provided grab samples are taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both oxygen channels or both the inlet oxygen and inlet hydrogen channels inoperable, oxygen supply is suspended to the recombiner. Addition of waste gas to the system may continue provided grab samples are taken and analyzed 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 degassing operations and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations.
The GRWS is designed to operate with hydrogen concentrations above 4 percent by volume. Flammable mixtures of gases in the system are prevented by monitoring
and controlling the oxygen concentration to appropriate levels. The setpoints for oxygen concentration in the catalyst bed inlet stream are 3 percent for the hi-alarm and 3.5 percent for the hi-hi alarm and isolation of the oxygen
supply. The setpoint for oxygen concentration downstream of the catalyst bed
is 60 ppm oxygen for the hi-hi alarm and isolation of inlet oxygen supply.
Thus the oxygen supply to the recombiner would be terminated before the concentration in the GRWS would reach levels favorable for hydrogen flammability.
Since the GRWS is designed to operate with hydrogen concentrations up to 6 percent by volume, up to 3 percent oxygen is necessary for operation of the catalytic recombiner. Termination of oxygen feed at 2 percent as suggested by regulatory guidance is inappropriate. Further, since the minimum oxygen
concentration necessary to support combustion at 4 percent by volume hydrogen
concentrations is 5 percent, the hi-alarm setpoint of 3 percent provides
sufficient margin (i.e., 60 percent of the limit) to flammability.
A multipoint temperature recorder monitors temperatures at several locations in
the recombiner packages.
The process gas flow rate is measured by an orifice located upstream of the recombiner preheater. Local pressure gauges indicate pressure at the recombiner inlet and oxygen supply pressure.
The following controls and alarms are incorporated to maintain the gas
composition outside the range of flammable and explosive mixtures:
11.3-10 Rev. 21 WOLF CREEK
- a. If the recombiner feed concentration exceeds 6 percent by volume, a high-hydrogen alarm sounds to warn that all
hydrogen entering the recombiner is not reacted. This
alarm is followed by a second alarm indicating high
hydrogen in the recombiner discharge. These alarms warn
of a possible hydrogen accumulation in the system.
- b. If the hydrogen concentration in the recombiner feed reaches 9 percent by volume, a high-high hydrogen alarm sounds, the oxygen feed is terminated, and the volume
control tank hydrogen purge flow is terminated. These controls limit the possible accumulation of hydrogen in the GRWS to 3 percent by volume.
- c. If the oxygen concentration in the recombiner feed reaches 3 percent by volume, an alarm sounds and oxygen feed flow is limited so that no further increase in flow is possible. This control maintains the system oxygen concentration at 3 percent or less, which is below the
flammable limit for hydrogen-oxygen mixtures.
- d. If the oxygen concentration in the recombiner feed reaches 3.5 percent by volume, an alarm sounds and the oxygen feed flow is terminated.
- e. If hydrogen in the recombiner discharge exceeds 0.25 percent by volume, an alarm sounds. This alarm warns of
high hydrogen feed, possible catalyst failure, or loss
of oxygen feed.
- f. If oxygen in the recombiner discharge exceeds 60 ppm, an alarm sounds and oxygen feed is terminated. This
control prevents any accumulation of oxygen in the
system in case of hydrogen recombiner malfunction.
- g. On low flow through the recombiner, oxygen feed is terminated. This control prevents an accumulation of
oxygen following system malfunction.
- h. High discharge temperature from the cooler-condenser (downstream from the reactor) terminates oxygen feed.
This protects against loss of cooling water flow in the cooler-condenser.
11.3-11 Rev. 10 WOLF CREEK
- i. High temperature indication by any one of six thermocouples in the catalyst bed limits oxygen feed so that no further increase is possible.
- j. High temperature indication at the recombiner reactor discharge terminates oxygen feed to the recombiner.
11.
3.7 REFERENCES
Published References
- 1. Eckerman, K.F. and Lash, D G, 1978, GASPAR version marked
"revised 8/19/77": U S Nuclear Regulatory Commission, Radiological Assessment Branch.
- 2. Eckerman, K.F., Congel, F.J., Roecklein, A.K. and Pasciak, W.J., 1980, NUREG-0597 Users Guide to GASPAR Code: U.S.
Nuclear Regulatory Commission, Radiological Assessment Branch.
Personal References 1 Warminski, N C, 1979, Horticulture agent for the Sedgwick County Extension Office of the Kansas State University Cooperative Extension Service, Wichita, Kansas, telephone conversation (25, 26 January), written communication (29
January).
11.3-12 Rev. 10 WOLFCREEKTABLE11.3-1GASEOUSWASTEPROCESSINGSYSTEMMAJORCOMPONENTDESCRIPTIONWaterGasCompressorsTypeCentrifugalQuantity2 Designpressure,psig150 Designtemperature,F180 Operatingtemperature,F70to130 Designsuctionpressure,N 2 at130F,psig0.5Designdischargepressure,psig110 Designflow,N 2at130F,scfm40MaterialCarbonsteelDesigncode(1)ASMEVIII/D(augmented)
SeismicdesignInaccordancewithTable3.2-1GasDecayTanksTypeVerticalQuantity8 Designpressure,psig150 Designtemperature,F180Volume,each,ft 3 600MaterialofconstructionCarbonsteel Designcode(1)ASMEVIII/D(augmented)
SeismicdesignInaccordancewithTable3.2-1 RecombinersTypeCatalyticQuantity2 Designpressure,psig150 Designtemperature,F(2)
Designflowrate,scfm50 Operatingdischargepressure,psig20 Operatingdischargetemperature,F70to140 MaterialofconstructionStainlesssteel Designcode(1)ASMEVIII/D(augmented)
SeismicdesignInaccordancewithTable3.2-1(1)Tableindicatestherequiredcodebasedonitssafety-relatedimportanceasdictatedbyserviceandfunctional requirementsandbytheconsequencesoftheirfailure.
Notethattheequipmentmaybesuppliedtoahigher principalconstructioncodethanrequired.(2)Variesbycomponentintherecombinerpackage,butexceedsoperatingtemperaturesby100F.Rev.0 WOLFCREEKTABLE11.3-2DeletedTableRev.14 WOLFCREEKTABLE11.3-3DeletedTableRev.14 WOLFCREEKTABLE11.3-4DeletedTableRev.14 WOLF CREEK TABLE 11.3-5 GASEOUS WASTE PROCESSING SYSTEM INSTRUMENTATION DESIGN PARAMETERS Design Design Location Channel Pressure Tempera- Alarm Control of Number Location of Primary Sensor (psig) ture (°F) Range Setpoint Setpoint Readout Flow Instrumentation QIA-1091 Gas decay tank water flush 150 180 0 to 6,000 3,000 to 6,000 - Local galgal(adjustable)
HIC-1094 Volume control tank purge control 150 250 0 to 100 pct None Manual con- WPS pane l trol (normal flow 0.7 scfm)Pressure Instrumentation PI-1031 Moisture separator 150 180 0 to 100 psig - - Local PI-1033 Moisture separator 150 180 0 to 100 psig - - Local PIA-1036 Gas decay tank number 1 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psigPIA-1037 Gas decay tank number 2 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psigPIA-1038 Gas decay tank number 3 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psigPIA-1039 Gas decay tank number 4 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psigPIA-1052 Gas decay tank number 5 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psig Rev.
10 WOLF CREEK TABLE 11.3-5 (Sheet 2) Design Design Location Channel Pressure Tempera- Alarm Control of Number Location of Primary Sensor (psig) ture
(°F) Range Setpoint Setpoint ReadoutPressure Instrumentation (Cont'd)PIA-1053 Gas decay tank number 6 150 180 0 to 150 psig 100 psig - WPS pane l 0 to 30 psig 20 psigPIA-1054 Gas decay tank number 7 150 180 0 to 150 psig 90 psig - WPS pane l 0 to 30 psig 18 psigPIA-1055 Gas decay tank number 8 150 180 0 to 150 psig 90 psig - WPS pane l 0 to 30 psig 18 psigPIA-1065 Hydrogen supply header 150 180 0 to 150 psig 90 psig - WPS pane lPIA-1066 Nitrogen supply header 150 180 0 to 150 psig 90 psig - WPS pane lPICA-1092 Compressor suction header 150 180 2 psi vac 0.5 psi 0.5 psi vac WPS pane l 2 psig vacPI-1093 Gas decay tank makeup water 150 180 0 to 150 psig N.A. N.A. Local PI-1094 Volume control tank discharge 150 250 0 to 20 psig N.A. N.A. Local pressure Level Instrumentation
LICA-1030 Compressor 10 inches H 2 0 WPS panel Moisture 8 inches H 2 0 and Local Separator 150 180 0 to 30 inches 15 inches 5 inches H 2 0 H 2 0 H 2 0 1 inch H 2 0 LICA-1032 Compressor 10 inches H 2 0 WPS panel Moisture 0 to 30 inches 15 inches 8 inches H 2 0 and Local Separator 150 180 H 2 0 H 2 0 5 inches H 2 0 1 inch H 2 0 Rev.
8
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OlfMtAl atAII tAMt ...,....., SAMPINJ $YS. IPIINf Milt S'IOIUIGI TMIIS lu:MOOWN-tANit WAPOM*IIDI"DMS TMIIS Rev. 13 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT F:i:GURE 11.3-2 POTENTIAL GASEOUS RELEASE ------------.. -----------------------------------------. --------------. -.. --* .. -.. -J c* COMPRESSOR tROM VOLUME CONTROL TANK COOlER c* CREEK TO RECOMBIHER MOISTURE SEPARATOR SEAL WATER RETURN T -TEMPERATURE MEASUREMENT P
- PRESSURE MEASUREMEHT L -LEVEl MEASUREMENT WOLF CREEK ( OPDA'l"BD ANAL'fSlS REPORT Rev. 0 FIGURE U. 3-3 COMPRESSOR INSTRUMENTS FROM GAS COMPRESSOR TO GAS DECAY TAHK TO GAS ANALYZER HEATER WOlF CREEK PHASE SEPARATOR OXYGEN CATALYTIC REACTOR TO GAS ANALYZER COOLER/CONDENSOR T -TEMPERATURE MEASUREMENT P -PRESSURE MEASUREMENT F -FLOW MEASUREMENT WOLF CRBBB:
ANALYSIS REPORT FIGURE 11. 3-L.f HYDROGEN RECOHBINER INSTRUMENTS Rev.21 WOLF CREEK 11.4 SOLID WASTE MANAGEMENT SYSTEM The solid radwaste system (SRS) is designed to meet the functional requirements of the solid waste management system. The SRS is designed to collect, process, and package low-level radioactive wastes (LLW) generated as a result of normal plant operation, including anticipated operational occurrences, and to store
this packaged waste until it is shipped offsite to a waste processor for treatment and/or disposal or to a licensed burial site. The process and effluent radiological and sampling systems are described in Section 11.5.
11.4.1 DESIGN BASES
11.4.1.1 Safety Design Bases The SRS performs no function related to the safe shutdown of the plant, and its failure does not adversely affect any safety-related system or component;
therefore, the SRS has no safety design bases.
11.4.1.2 Power Design Bases POWER GENERATION DESIGN BASIS ONE - The SRS is designed to meet the following objectives:
- a. Provide remote transfer and hold-up capability for spent radioactive resins from the chemical and volume control
system, fuel pool cooling and cleanup system, boron
recycle system, liquid radwaste system, steam generator
blowdown system, and secondary liquid waste system and for spent radioactive activated charcoal from the liquid radwaste system and the secondary liquid waste system.
- b. Provide a means to semiremotely remove and transfer the spent filter cartridges from the filter vessels to the solid radwaste processing system in a manner which minimizes radiation exposure to operating personnel and the spread of contamination.
- c. Provide a means for compacting and packaging miscellaneous dry radioactive materials, such as paper, rags, and contaminated clothing.
- d. Provide a means for dewatering primary and secondary resin storage and shipment offsite.
11.4-1 Rev. 18 WOLF CREEK POWER GENERATION DESIGN BASIS TWO - The SRS is designed and constructed in accordance with Regulatory Guide 1.143, as described in Table 3.2-5, and Branch Technical Position ETSB 11-3, as described in Table 11.4-1. The seismic design classification of the radwaste building, which houses the solid waste management system, and the seismic design and quality group classification for the system components and piping are provided in Section 3.2.
POWER GENERATION DESIGN BASIS THREE - The SRS design parameters are based on the radionuclide concentrations and volumes consistent with reactor operating experience for similar designs and with the source terms of Section 11.1.
POWER GENERATION DESIGN BASIS FOUR - Collection, packaging, and storage of radioactive wastes are to be performed so as to maintain any potential radiation exposure to plant personnel during system operation or during maintenance to "as low as is reasonably achievable" (ALARA) levels, in
accordance with the intent of Regulatory Guide 8.8 in order to maintain personnel exposures well below 10 CFR 20 requirements. Design features
incorporated to maintain ALARA criteria include remote system operation, remotely actuated flushing, and equipment layout permitting the shielding of components containing radioactive materials. Additionally, access to the solid
waste processing and storage areas is controlled to minimize personnel
exposure.POWER GENERATION DESIGN BASIS FIVE - The onsite storage facilities for solid wastes have a capacity for temporary storage of solid wastes resulting from
approximately 5 years of plant operation. Temporary onsite storage and shipping
offsite of solid radwaste do not present a radiation hazard to persons onsite
or offsite, for either normal conditions or extreme environmental conditions, such as tornados, floods, or seismic events. Greater detail on interim on-site storage is provided in section 11.4.A.
POWER GENERATION DESIGN BASIS SIX - The SRS is designed to meet the requirements of General Design Criterion 60 of 10 CFR 50, Appendix A.
Packaging and shipment of radioactive wastes is performed in accordance with the requirements of 10 CFR 61, 10 CFR 71, 49 CFR 173, and applicable state
regulations.
POWER GENERATION DESIGN BASIS SEVEN - Temporary storage, on a concrete slab or within a building addition located West of the IOS facility and South of the Radwaste Building provides temporary indoor/outdoor storage of large waste material which becomes activated during reactor operation. Each stored item will be unique, therefore procedures for storing items outdoors will be
determined on a case by case basis.
11.4-2 Rev. 13 WOLF CREEK 11.4.2 SYSTEM DESCRIPTION 11.4.2.1 General Description The SRS consists of the following subsystems which are illustrated in the piping and instrumentation diagrams provided in Figure 11.4-1:
- a. Dry waste system
- b. Resin handling system
- c. Filter handling system
- d. Waste disposal system The activity of the influents to the SRS is dependent on the activities of the various fluid systems, such as the boron recycle system, secondary liquid waste
system, liquid waste management system, chemical and volume control system, fuel pool cooling and cleanup system, floor and equipment drain system, and the steam generator blowdown system. Reactor coolant system activities and the
decontamination factors for the systems given above also determine theinfluent
activities to the solid radwaste system.
Table 11.4-2 lists the estimated expected and maximum activities of waste to be processed on an annual basis and their physical form and source. The isotopic
makeup and curie content of the expected influents to the SRS are given in Table 11.4-2. The estimated maximum annual quantities of solid radwaste generation are presented in Table 11.4-3. The estimated annual expected and maximum curie and isotopic content is presented in Table 11.4-4, for each waste category. Packaged waste volumes are based on the following:
- a. Waste content volume in Table 11.4-3, when based on packaging in 55-gallon and solidified with concrete, are:
(1) 3.5 ft3 primary spent resin, primary charcoal, and primary evaporator bottoms per drum (2) 4.8 ft3 secondary spent resin and charcoal per drum (3) 5.3 ft3 secondary evaporator bottoms (4) 4.0 ft3 chemical waste per drum (5) 1 filter cartridge per drum (6) 7.5 ft3 shipped volume per drum (including cement
- b. Disposal volumes are based on packaging in the following typical containers:
11.4-3 Rev. 8 WOLF CREEK Waste Stream Container Type Container VolumePrimary Resin PL8-120 120.3 cuft Secondary Resin PL14-215 205.8 cuft Filters PL6-80 83.4 cuft DAW 85 Gallon Drum 11.6 cuft 79 Gallon Drum 10.8 cuft 55 Gallon Drum 7.5 cuft B-25 Box 96 cuft Section 11.1 and Appendix 11.1A provided the bases for determination of liquid source terms which are used to calculate the solid waste source terms The
sources presented in Tables 11.4-2 and 11.4-4 are conservatively based on Section 11.1, Appendix 11.1A and the following additional information:
- a. As a basis for the activities given in Table 11.4-4, 30 days decay is assumed.
- b. The miscellaneous dry and compacted waste volume will reflect the historical increases since the issuance of Case 6 in Table 2-49 of WASH-1258, July 1973.
11.4.2.2 Component Description Codes and standards applicable to the SRS are listed in Tables 3.2-1 and 11.4-
- 5. The SRS is housed within a seismically designed building. Regulatory Guide 1.143 is complied with to the extent specified in Table 3.2-5.
SRS component parameters are presented in Table 11.4-5. The following is a functional description of the major system components:
SPENT RESIN STORAGE TANK (PRIMARY) - Provides for storage and decay of the spent resins from the demineralizers in the chemical and volume control system, fuel pool cooling and cleanup system, boron recycle system, and liquid radwaste system.SPENT RESIN STORAGE TANK (SECONDARY) - Provides for storage and decay of the spent resins and spent activated charcoal from the demineralizers and charcoal adsorbers in the steam generator blowdown system, secondary liquid waste system, and charcoal adsorbers in the liquid radwaste system.
EVAPORATOR BOTTOMS TANK (PRIMARY) - Provides for storage, decay, sampling, and chemistry control of the concentrated wastes from the liquid radwaste system.
EVAPORATOR BOTTOMS TANK (SECONDARY) - Provides for storage, decay, sampling, and chemistry control of the concentrated wastes from the secondary liquid
waste system.
11.4-4 Rev. 14 WOLF CREEK SPENT RESIN SLUICE PUMPS (PRIMARY AND SECONDARY) - Provides the motive flow to transfer spent resin or spent activated charcoal from the various demineralizers or adsorbers to the appropriate spent resin storage tank.
EVAPORATOR BOTTOMS TANK PUMPS (PRIMARY AND SECONDARY) - Are available to transfer the concentrated liquid wastes from the evaporator bottoms tanks to
the solid radwaste disposal station.
ACID ADDITION TANK AND METERING PUMP - Provides chemistry control to the chemical drain tank, and floor drain tank.
CAUSTIC ADDITION TANK AND METERING PUMP - Provides chemistry control to the
chemical drain tank, floor drain tank, waste holdup tank, evaporator bottoms tank (primary), and evaporator bottoms tank (secondary).
RESIN CHARGING TANKS - Provides remote means of gravity sluicing clean resin and activated charcoal into the demineralizer and adsorber units.
WASTE DISPOSAL STATION - The waste disposal station provides the capability to transfer primary/secondary spent resins and evaporator bottoms, and liquid
radwaste demineralizer skid spent resins, to a HIC for storage/shipping. A
return header provides a path for decanted water to be returned to the liquid
radwaste system or the Secondary Spent Resin Storage Tank or the Primary Spent Resin Storage Tank. The waste disposal station also provides necessary interface support requirements for mobile vendor processing systems.
RADWASTE BRIDGE CRANE - A crane, remotely operated from the solid radwaste control console, which provides the means of moving containers to the processing area, from the processing area to the solid waste storage area, and from the solid waste storage area to the shipping area. The crane is equipped with a television camera system to facilitate the remote handling operation.
DRY WASTE COMPACTORS - Hydraulic power mechanical ram devices that are used to reduce the volume of compressible dry wastes by a factor of approximately five.
They are designed with exhaust fan and filter to control the airborne dust
during dry waste compaction operations.
11.4.2.3 System Operation 11.4.2.3.1 Waste Disposal System The waste disposal station provides the capability to transfer primary/secondary spent resins and evaporator bottoms, and liquid radwaste demineralizer skid spent resins, to a HIC for storage/shipping. A return header provides a path for decanted water to be returned to the liquid radwaste
system or the Secondary Spent Resin Storage Tank or the Primary Spent Resin
Storage Tank. The waste disposal station also provides necessary interface
support requirements for mobile vendor processing systems.
11.4-5 Rev. 14 WOLF CREEK Evaporator concentrates are stored in either the evaporator bottoms tank (primary) or the evaporator bottoms tank (secondary). Each tank is provided with a mixer, and the piping system contains a relatively high flow pump for recirculation of the tank's contents to maintain the concentrates in the homogeneous state. Each tank is supplied with external strip heaters, and all piping that
can contain the concentrated waste is heat traced to preclude crystallization
and eventual plugging within the piping system.
Spent resins are stored in either the primary or secondary resin storage tank.
Each tank is supplied with nitrogen gas for sluicing the spent resin to the
waste disposal station. Spent resin from the liquid radwaste demineralizer
skid is also sluiced to the waste disposal station using Reactor make-up water or the associated system pump. Spent resins are normally sluiced into a High Integrity Container (HIC) for disposal. Resins are dewatered in accordance
with the Process Control Program using approved procedures.
The waste disposal station area consists of a segmented concrete shield with nine inch walls, capable of containing the largest anticipated HIC, 60 inch diameter and 73 inch height, with 630 curies of activitie without disturbing
normal operations.
The waste disposal station utilizes the necessary system controls to prevent improper system operation to preclude the spillage of waste. Because of these system design features, waste spillage is not anticipated although provisions
are made for processing waste spillage. A drain system is provided in the waste disposal station for handling waste spillage. Provisions are also contained in the drain system to feed waste to a mobile vendor solidification system/mobile vendor resin dewatering system.
11.4.2.3.2 Dry Waste System Low-level dry wastes are collected in drums at appropriate locations throughout the plant, as dictated by the volume of these wastes generated during operation or maintenance. Dry wastes, which can be compressed by a factor of five to
minimize the volume, may be compacted in 55-gallon drums with a dry waste
compactor. Compactors are located in the radwaste building and the auxiliary
building. The dry waste compactors have an integral shroud which directs any airborne dusts created by the compaction operation through an exhaust fan and filter, and then to the respective building's ventilation system.
The filled drums are sealed and moved to the storage area in the radwaste building, or other designated areas, where they are stored until shipment offsite. 11.4-6 Rev. 11 WOLF CREEK Dry wastes can also be processed/compacted offsite by contractor as part of the shipment and waste disposal contract. The low level dry waste collected can be placed in a NRC/DOT approved waste container (e.g., sea van) which is shipped offsite when filled. The container is placed outside the radwaste building within the radiological controlled area.
Large components and equipment which have been activated during reactor operation and which are not amenable to solidification or compaction are handled either by qualified plant personnel or by outside contractors specializing in radioactive materials handling, and are packaged in shipping
casks or appropriate shipping packages of an appropriate size.
Dry noncompressible radwaste (such as hoses, buckets, etc.) will be packaged in approved containers and shipped as Low Specific Activity (LSA) or Type A waste.
11.4.2.3.3 Resin Handling System The resin handling system provides the capability for remote removal of spent radioactive resin and activated charcoal from the demineralizer and charcoal adsorber vessels in the chemical and volume control system, fuel pool cooling
and cleanup system, boron recycle system, liquid radwaste system, steam
generator blowdown system, and secondary liquid waste system and to transfer
them to the associated spent resin storage tank.
In the resin transfer mode, the spent resin sluice pumps take suction from the storage tank via a screened connection on the tank and pump water through the
respective vessel to first backflush the resin and then sluice the resin to the
spent resin storage tank. Positive indication that the resin has been sluiced to the spent resin storage tank is provided by an ultrasonic density element located in the spent resin sluice header. Alternate Sluice water may be
provided by the Reactor Makeup Water system, if the sluice pumps are
The spent resin storage tank (primary), which accepts resins from the reactor purification systems, is capable of accommodating at least 60 days' waste
generation at normal generation rates. The spent resin storage tank (secondary), which accepts spent resin and spent activated charcoal from the
remaining vessels, is capable of accommodating at least 30-days' waste generation at normal generation rates.
Spent resin and spent activated charcoal are transferred from the spent resin storage tanks to the waste disposal station by pressurizing the storage tank
with nitrogen and supplying sluice water at the outlet nozzle on the tank.
Positive indication that resin has been transferred is provided by a local camera, monitoring at the container entry at the solid radwaste disposal
station. Upon completion of the resin transfer, the tank is vented to the radwaste building ventilation system.
The empty demineralizer or charcoal adsorber vessels are filled with clean resin or activated charcoal by gravity sluicing from the resin charging tank into the associated vessels. The filling operations are performed remotely from the vessels being filled. 11.4-7 Rev. 10 WOLF CREEK 11.4.2.3.4 Filter Handling System
The filter handling system is a semiremote system which provides the capability to remove spent radioactive cartridge filters from their filter housings and to transport them to the solid radwaste processing area in the radwaste building.
The system, requires the operator to be in the proximity of the filters;
however, they are protected by distance which minimizes operator exposure.
The filter handling system consists of long handled tools for removal of the
filter housing top and assemblies. As necessary, shielded transport casks are
used for transport and storage of the filter assembly.
The steps required by the operator for the removal of the filters are as follows:
- a. Using a monorail hoist, the shield plug above the filter housing is removed and set aside. Any time the
plug hole is uncovered, the operators must take care to stay well away from the proximity of the hole, to avoid exposure. This necessitates that the monorail hoist be
operated with a remote pendant controller.
- b. Using long-handled tools the operator loosens the housing head bolts and flips them back out of the way.
- c. With another tool, he engages the housing head and flips
it back out of the way.
- d. The filter is lifted part way out of the housing and allowed to drip until it has decayed to an acceptable level. It is placed into a shielded cask or shielded storage location.
- e. A new cartridge is installed in the filter housing, either by reversing the previous sequence or, if filter
housing radiation levels permit, by manually loading and
securing the head.
11.4.2.3.5 Mixed Waste Handling System Mixed waste (MW) is defined as radioactive waste that has hazardous
characteristics or components as defined by 40 CFR 260/261. MW (liquid and
solid) is collected in the plant and placed in the appropriate containers. The containers are then stored in the Mixed Waste Storage Facility (MWSF) in the Owens Corning Building (Figure 1.2-44). The MWSF meets the EPA requirements
for storage of hazardous wastes, and the NRC requirements for storage of
radioactive wastes.
The MW will be processed (if required) and shipped for disposal. Radioactive content of the MWSF will be limited to prevent exceeding the limits in 10 CFR 20 and 10 CFR 50 Appendix I during normal operation, including anticipated
operational occurrences.
11.4-8 Rev. 29 WOLF CREEK 11.4.2.4 Packaging, Storage, and Shipment Solidified radwaste, or waste meeting the no free standing water criteria of Branch Technical Position ETSB 11-3 (i.e., dewatered), shall be stored in the Waste Bale Drumming Area. These wastes satisfy all applicable transportation and disposal requirements.
Wet radioactive waste, defined as any waste which does not meet receiving burial site free liquid requirements may be temporarily stored in the Waste Bale Drumming Area. Wet waste storage containers are designed to withstand the corrosive nature of the wet waste for the expected duration of the storage.
Temporarily stored wet waste will be processed (i.e., dewatered) or shipped to a waste processor for treatment prior to disposal.
DRY ACTIVE WASTE (DAW) - includes contaminated trash (paper, cloth, plastic, etc.)SOLIDIFIED/DEWATERED WASTES - includes resin, filter cartridges and filter sludges transferred into HICs, and dewatered to less than 1% free standing
water.UNCOMPACTIBLE CONTAMINATED WASTE - other wastes not suitable for packaging in drums or HICs may be packaged in LSA boxes (B-25 or equivalent) or packaged into modular storage containers and stored on the temporary outdoor storage
slab.Spent resins, evaporator bottoms, spent charcoal, spent filter cartridges, and solid compactable waste such as contaminated paper, rags, and clothing are packaged in approved containers in accordance with 10CFR61 and shipped in
accordance with applicable NRC (10CFR71) and DOT (49CFR173) regulations.
The 55-gallon drums used in the solid radwaste system meet the requirements of DOT approved containers.
Packaged solid radwaste is stored in the Waste Bale Drumming Area of the existing radwaste building prior to shipment offsite. The NRC/DOT approved
waste container (e.g., sea van) is placed outside the radwaste building within the radiological controlled area prior to shipment offsite for processing.
The radwaste building storage areas have the ability to store 1,450 fifty-five gallon drums. However, other container sizes and storage configuration may be used.Containers with radwaste are inventoried and their location recorded prior to being placed in storage.
Primary radwaste normally consists of:
- Spent resins, primary
- Filter cartridges, primary Secondary waste normally consists of:
- Spent resins, secondary
- Filter cartridges, secondary
- Dry and compacted wastes
- Chemical wastes 11.4-9 Rev. 18 WOLF CREEK Of the secondary waste, it is possible that Most or all of it will be surveyed and released, rather than stored as radioactive waste.
Refer to Table 11.4-3 for Estimated Maximum Annual Quantities of Solid Radwaste.11.4.3 SAFETY EVALUATION Packaged solid radwastes containing, or potentially containing, significant quantities of radioactivity (i.e., spent resins, evaporator bottoms, are in a
form that is highly resistant to release and spread of radioactivity during an
extreme environmental event, such as a tornado or earthquake. This configuration provides, in effect, a double barrier against the release of radioactivity.
The containers that require radiation shielding are stored in the waste bale drum area which is resistant to tornados as described in Section 11.4-A. The containers with significant quantities of radioactivity remain in place during any extreme environmental event. The drums or other approved containers for
the storage of dry active waste (DAW) have a low specific activity. See Section 11.4A for further details.
The packaged radwaste storage areas protect the containers from rainfall and corrosion. As described in Chapter 2.0, flooding is not a potential concern in
grade-level buildings at the Wolf Creek site.
Although compacted and solidified wastes are expected to be stored onsite for some period of time prior to shipment, normally no credit other than 30-day decay is taken for radioactive decay realized by such storage when filling
containers for shipping in accordance with 49 CFR 173 dose limitations. That is, once filled, containers can normally be shipped immediately, with the proper shielding, without exceeding Department of Transportation radiation limits. If 49 CFR 173 dose limitations cannot be met with the available shielding, however, the applicable containers are stored in the shielded storage area until the doses are acceptable for shipping in accordance with
Department of Transportation requirements.
The normal onsite residence time for low level solid radwaste prior to shipping, such as dry compacted waste, steam generator blowdown spent resins, evaporator bottoms, spent charcoal, and ranges from several days to a few months. The normal onsite residence time for primary solid radwaste prior to shipping, such as primary spent resins and spent filter cartridges from the primary system, ranges from a few months to a few years. Onsite residence time is based on the initial activity of the container, the time required to have sufficient containers to completely load a transporting vehicle, the thickness of the shields available, the number of containers which can be stored in the available shipping casks, the availability of a transporting vehicle, and the
availability of ultimate disposal facilities. 11.4-10 Rev. 8 WOLF CREEK Solid radwaste is shipped from the site in Department of Transportation-approved containers by Department of Transportation-approved carriers.
Containers with any significant surface dose rate are moved remotely from the shielded storage areas to the transporting vehicle.
Radiation measurements made at the time of shipment of any radioactive waste material ensure that all shipments leave the site well within prescribed
limits. Similarly, external contamination measurements are made to detect any potential release of radioactive material from the container prior to shipment.
Mixed waste will be stored in liquid and solid form in the MWSF. The total Curie content of the MWSF will be restricted accordingly to maintain doses to the maximally exposed individual during an extreme environmental event (e.g.
fire, tornado, etc.) below the applicable limits in 10 CFR 20 and 10 CFR 100.
11.4.4 TESTS AND INSPECTIONS
The SRS is in intermittent use throughout normal reactor operation. Periodic visual inspection and preventive maintenance are conducted using normal industry practice. Refer to Chapter 14.0 for information on preoperational and
startup testing.
11.4.5 INSTRUMENTATION APPLICATION Two control panels are provided for the equipment in the SRS which contains or processes potentially radioactive fluids or slurries. One control panel is located in the radwaste building control room and contains the instrumentation for the equipment which interfaces the influent systems (i.e., evaporator bottoms tank - primary, evaporator bottoms tank - secondary, spent resin storage tank - primary, and spent resin storage tank - secondary) and for the
equipment used for process control (i.e., acid addition tank, acid addition metering pump, caustic addition tank, and caustic addition metering pump).
The second control panel (radwaste crane control panel) is located in a separate room in close proximity to the solid radwaste processing area. The control panel contains all instrumentation, including television monitors, required for remote operations. Pertinent instruments and controls for the transferring of the wastes from the tanks containing the wastes are duplicated on this panel so that the solid radwaste system operator can transfer the waste from these tanks to the waste disposal station. 11.4-11 Rev. 8 WOLF CREEK TABLE 11.4-1 DESIGN COMPARISON TO BRANCH TECHNICAL POSITION ETSB 11-3 REVISION 2, "DESIGN GUIDANCE FOR SOLID RADIOACTIVE WASTE MANAGEMENT SYSTEM INSTALLED IN LIGHT-WATER-COOLED NUCLEAR POWER REACTOR PLANTS" ETSB 11-3 POSITION WCGS POSITION I. PROCESSING REQUIREMENTS
- 1. Dry Wastes
- a. Compaction devices for compressible I.1.a Complies. Dry waste compactors dry wastes (rags, paper, and clothing) are designed with ventilation should include a ventilated shroud shroud exhaust fan and filter around the waste container to control to control the airborne dust
the release of airborne dusts generat- during the compaction process.
ed during the compaction process.
- b. Activated charcoal, HEPA filters, and I.1.b Complies.
other dry wastes which do not normally require solidification processing
should be treated as radioactively contaminated solids and packaged for disposal in accordance with applicable
Federal regulations.
- 2. Wet Wastes
- a. Liquid wastes such as evaporator I.2.a Complies. Radioactive and reverse osmosis. spent demineralizer resins, evaporator concentrates, Rev. 4 WOLF CREEK TABLE 11.4-1 (Sheet 2)
ETSB 11-3 POSITION WCGS POSITION concentrates should be rendered and other liquid wastes immobile by combining with a demineralized/dwatered suitable binding agency (cement, to form a homogeneous solid urea formaldehyde, asphalt, etc.) to matrix prior to offsite form a homogeneous solid matrix shipment. No adsorbent (absent of free water) prior to off- such as vermiculite is site shipment. Adsorbents such as used for liquid wastes.
vermiculite are not acceptable
substitutes for binding agents.
- b. Spent resins and filter sludges I.2.b Complies. Vendor portable may, if acceptable to the receiving dewatering systems are utilized
burial site, be shipped dewatered. which meet or exceed the These dewatered wastes are subject maximum free liquid acceptance to (1) items B.II.1.b, and B.II.2 criteria of the receiving
below, (2) to the receiving burial burial site.
site maximum free liquid criteria (upon receipt at the burial site),
and (3) applicable DOT regulations.
Furthermore, the activity level of the dewatered wastes may, subject
to receiving burial site require-ments, dictate the type of container used. Solidification of spent resins
and filter sludges in a suitable binder is also an acceptable alternative
- c. Spent cartridge filter elements may I.2.c Complies. Spent cartridge be packaged in a shielded container filter elements are dewatered and packaged with a suitable adsorber such as in HICs vermiculite, although it would be desirable to solidify the elements in a suitable binder. Rev. 8 WOLF CREEK TABLE 11.4-1 (Sheet 3)
ETSB 11-3 POSITION WCGS POSITION II. ASSURANCE OF COMPLETE SOLIDIFICATION Complete solidification or dewatering of wet wastes should be assured by the implementation of a process control program or by methods to detect free liquids within container contents prior to shipment.
- a. Solidification (binding) agents and II.1.a Complies. Solidification potential waste constituents should formula demonstrating complete
be tested and a set of process para- solidification for the expected meters (pH, ratio of waste to agent, wastes is determined by etc.) established which provide shop tests. These tests
boundary conditions within which provide the boundary condition reasonable assurance can be given within which reasonable that solidification will be complete. assurance is given that
complete solidification, i.e., lack of free water, has occurred.
- b. Dewatering procedures, equipment II.1.b Complies. Vendor portable and potential waste constituents dewatering procedures have been should be tested and a set of tested for compliance to the processing parameters (settling receiving burial site free time, drain time, drying time, etc.) liquid acceptance criteria.
be established which provide boundary Results of these tests have conditions within which reasonable confirmed that dewatering is assurance can be given that de- complete with essentially watering will be complete, with zero free liquid.
essentially zero free liquid. Rev. 4 WOLF CREEK TABLE 11.4-1 (Sheet 4)
ETSB 11-3 POSITION WCGS POSITION
- c. The solid waste processing system II.1.c Complies. Sample (or liquid waste processing system, provisions exist for the
as appropriate) should include determination of chemical appropriate instrumentation and wet constituents to be solidified.
waste sampling capability necessary In addition, pH adjustments
to successfully implement and/or can be made to optimize verify the process control program solidification operations.
described in II.1.a and/or II.1.b .
above.
- d. The plant operator should provide II.1.d Complies. Administrative
assurance that the process is run controls are used and within the parameters established records are maintained under I.1.a and II.1.b above. to ensure that the process Appropriate records sould be main- is operated within the tained for individual batches established boundaries.
showing conformance with the
established parameters.
- 2. Free Liquid Detection II.2 The shop-tested solidification formula and dewatering Each container filled with solidified procedures coupled with the
or dewatered wet wastes should be checked administrative controls assure
by suitable methods to verify the absence the absence of free liquids.
of free liquids if a process control program is not followed or an off-normal condition exists during processing.
Visual inspection of the upper surface of the waste in the container is not alone sufficient to ensure that Rev. 4 WOLF CREEK TABLE 11.4-1 (Sheet 5)
ETSB 11-3 POSITION WCGS POSITION free water is not present in the container. Provisions to be used to verify the absence of free liquids should consider actual solidification procedures which may create a thin layer of solidification agent on top without
affecting the lower portion of the container.
III. WASTE STORAGE
- 1. Tanks accumulating spent resins from III.1 Complies.
reactor water purification systems
should be capable of accomodating at least 60 days waste generation at normal generation rates. Tanks accumulating
spent resins from other sources and tanks accumulating filter sludges should be capable of accommodating at least 30
days waste generation at normal generation rates.
- 2. Storage areas for solidifed wastes III.2 Complies.
should be capable of accommodating at least 30 days waste generation at normal
gerenation rates. These storage areas should be located indoors.
- 3. Storage areas for dry wastes and III.3 Complies.
packaged contaminated equipment should be capable of accommodating at least one
full offsite waste shipment. Rev. 4 WOLF CREEK TABLE 11.4-1 (Sheet 6)
ETSB 11-3 POSITION WCGS POSITION IV. PORTABLE SOLID WASTE SYSTEMS
The following supplementary guidance should be incorporated into the design and use of portable (mobile) solid-ification and/or dewatering sytems:
- 1. Tanks containing wet wastes are IV.1 Complies.
limited to inplant installation, they should not be part of the portable system.
- 2. The use of flexible piping should IV.2 Complies.
be limited to necessary interfaces with plant systems. Such piping is
also subject to the hydrostatic test requirements delineated in Regulatory Guide 1.143.
- 3. Portable water systems should be IV.3 Complies. Dewatering procedures located, as a minimum, on concrete coupled with administrative controls pads with curbs and drainage which require continuous monitoring of provisions for containing radio- spent resin transfer to the shipping active spills. Provisions should be container and a spill containment barrier available for interfacing with drains of absorbent material when processing in with the plant's liquid radwaste system. the truck bay provide for containing Portable systems should have integral radioactive spills.
ventilation systems with either self-contained filters, or interface with the plant's ventilation exhaust system.
- 4. Regulatory Guide 1.143 seismic criteria IV.4 Complies.
for structures housing solid waste systems are not applicable. Rev. 6 WOLF CREEK TABLE 11.4-1 (Sheet 7)
ETSB 11-3 POSITION WCGS POSITION V. ADDITIONAL DESIGN FEATURES
The following additional design features should be incorporated into the design of the solid waste system.
- 1. Evaporator concentrate piping and tanks IV.1 Complies.
should have heat tracing if the concentrates are likely to solidify at
ambient temperatures.
- 2. Components and piping which contain IV.2 Complies.
radioactive slurries should have flushing connections.
- 3. Solidification agents should be stored IV.3 Complies.
in low radiation areas, generally less than 2.5 mr/hr, with provisions for
sampling.
- 4. Tanks or equipment which use compressed IV.4 Complies.
gases for transport or drying of resins or filter sludges should be vented directly to the plant ventilation
exhaust system which includes HEPA filters as a minimum. The vent design should prevent liquids and solids from
entering the plant ventilation system.
Rev. 4 WOLFCREEKTABLE11.4-2DeletedTableRev.14 WOLFCREEKTABLE11.4-3DeletedTableRev.14 WOLFCREEKTABLE11.4-4DeletedTableRev.14 WOLF CREEK TABLE 11.4-5 SOLID RADWASTE SYSTEM - COMPONENT DESCRIPTION Evaporator Bottoms Tank (Primary)
Quantity l Capacity (usable), gal 1,000 Design pressure, psig 15 Design temperature,°F 250 Material SB-424, Incoloy 825
Design Code ASME Sec. VIII Evaporator Bottoms Tank (Secondary)
Quantity 1 Capacity (usable), gal 2,500 Design pressure, psig 15 Design temperature,°F 250 Material SB-424, Incoloy 825
Design code ASME Sec. VIII Spent Resin Storage Tank (Primary)
Quantity l Capacity (usable), ft3 350 Design pressure, psig 150 Design temperature,°F 200 Material Austenitic stainless
steel
Design code(1) ASME Sec. VIII Spent Resin Storage Tank (Secondary)
Quantity l Capacity (usable), gal 4,200 Design pressure, psig 150 Design temperature,°F 200 Material Austenitic stainless
steel
Design code ASME Sec. VIII Spent Resin Sluice Pump (Primary)
Quantity 1 Type Canned centrifugal Design pressure psig 150 Design temperature,°F 200 Design flow, gpm
Rated 140 Runout 250 Rev. 0 WOLF CREEK TABLE 11.4-5 (Sheet 2)
Design head, ft Rated 250 Runout 210 Material Austenitic stainless
steel Design code(1) Manufacturer's standard (MS)
Spent Resin Sluice Pump (Secondary)
Quantity 1 Type Vertical inline centrifugal Design pressure, psig 300 Design temperature,°F 140 Design flow, gpm 225
Design head, ft 250 Material Austenitic stainless
steel
Design code MS Evaporator Bottoms Tank Pump (Primary)
Quantity 1 Type Vertical inline centrifugal Design pressure, psig 300 Design temperature,°F 220 Design flow, gpm 225 Design head, ft 50 Material Alloy 20 Design code MS Evaporator Bottoms Tank Pump (Secondary)
Quantity 1 Type Vertical inline centrifugal Design pressure, psig 300 Design temperature,°F 220 Design flow, gpm 225 Design head, ft 50 Material Alloy 20 Design code MS Acid Addition Tank Quantity 1 Capacity (usable), gal 250 Design pressure, psig 10 Design temperature,°F 150 Material Carbon steel Design code ASME Sec. VIII Rev. 0 WOLF CREEK TABLE 11.4-5 (Sheet 3)
Caustic Addition Tank Quantity 1 Capacity (usable), gal 550 Design pressure, psig 10 Design temperature,°F 150 Material Austenitic stainless
steel
Design code ASME Sec. VIII Acid Addition Metering Pump Quantity l Type Positive displacement
diaphragm Design pressure, psig 220 Design temperature,°F 104 Design flow, gph 25
Design head, psi 45 Material Alloy 20 S.S.
Design code MS
Contained solution 3% H2SO4 Caustic Addition Metering Pump
Quantity 1 Type Positive displacement diaphragm Design pressure, psig 110 Design temperature,°F 104 Design flow, gph 60
Design head, psi 45 Material Alloy 20 S.S Design code MS Contained solution 50% NaOH Resin Charging Tank (CVCS)
Quantity 1 Type Vertical, conical bottom, on wheels
Capacity (usable), gal 325 Design pressure, psig ATM Design temperature,°F 120 Material Austenitic stainless
steel
Design code ASME Sec. VIII Rev. 0 WOLF CREEK TABLE 11.4-5 (Sheet 4)Resin Charging Tank (Radwaste)
Quantity l Type Vertical, conical bottom, on wheels Capacity (usable), gal 325 Design pressure, psig Atmospheric Design temperature,°F 120 Material Austenitic stainless steel Design code ASME Sec. VIII Spent Resin Sluice Filter (Primary) (FHC01)
- Quantity 1 Design pressure, psig 300 Design temperature,°F 250 Design flow, gpm 250
P @ design flow, psi 5 Particle Retention (See Note 2 of Table 9.3-13) Material Austenitic stainless
steel
Design code(1) ASME Sec. VIII Spent Resin Sluice Filter (Secondary) (FHC02)
- Quantity 1 Design pressure, psig 150 Design temperature,°F 250 Design flow, gpm 225
P @ design flow, psi 5
Particle Retention (See Note 2 of Table 9.3-13) Material Austenitic stainless
steel
Design code ASME Section VIII
- See comments on Sheet 2 of Table 9.3-13.
Dry Waste Compactors
Quantity 2 Type Hydraulic press
Design code MS Rev. 10 WOLF CREEK TABLE 11.4-5 (Sheet 5)Solid Radwaste Bridge Crane Quantity 1 Capacity, tons 9.3 TV cameras, quantity 4 (1) Table indicates the required code based on its safety-related importance as dictated by service and functional
requirements and by the consequences of their failure.
Note that the actual equipment may be supplied to a higher
principal construction code than required. Rev. 8 ThisfigurehasbeendeletedRev. 8WOLF CREEKUPDATED SAFETY ANALYSES REPORT FIGURE 11.4-2 DRUMMING PROCESS OPERATION SCHEMATIC WOLF CREEK APPENDIX 11.4A INTERIM ON-SITE STORAGE FACILITY 11.4A.1 Introduction
In order to permit plant operation in the event that a permanent disposal site
is unavailable, it is necessary to store waste temporarily on-site. This
temporary storage is provided by the Interim On-Site Storage (IOS) Facility.
The existing waste bale drum structure, which is South of the Radwaste
Building, will be used as the IOS facility.
Temporary storage, on a concrete slab or within a building addition located
West of the IOS facility and South of the Radwaste Building, provides temporary
indoor/outdoor storage of large waste material which becomes activated during
reactor operation. Each stored item will be unique, therefore procedures for
storing items outdoors will be determined on a case by case basis.
11.4A.2 Design Objectives The design of the IOS facility provides storage for solid waste produced at
WCGS based on five years of processed waste (i.e. resins and sludges, including
filter cartridges) and, due to storage capacity limitations, three and one half years of Dry Active Waste (DAW) generated as a result of normal operation of
WCGS. The values contained in Table 11.4A-4, "Estimated Capacity and Radwaste
Container Distribution for the IOS Facility", serve as the basis for the design
storage capacity.
11.4A.3 Description of Containers Containers used for packaging of radioactive material, and stored in the IOS, shall meet the applicable DOT requirements for quantity and form or the current
burial site regulations for disposal (HIC) when placed in storage. Typical containers expected to be stored in the IOS facility are detailed in Table
11.4A-4. All containers are designed to reduce the occurrence of uncontrolled
releases of radioactive materials due to handling, transportation, and storage.
All containers are designed with materials compatible with the stored waste to
prevent significant container corrosion.
11.4A.4 Description of Stored Wastes Solidified radwaste, or waste meeting the no free standing water criteria of
Branch Technical Position ETSB 11-3 (i.e. dewatered), shall be stored in the
IOS facility. These wastes satisfy all applicable transportation and disposal requirements.
Wet radioactive waste, defined as any waste which does not meet receiving burial site free liquid requirements may be temporarily stored in the IOS facility.
11.4A.4.1 Dry Active Waste (DAW)
This includes contaminated trash (paper, cloth, plastic, etc.) super compacted
into drums, typically by an off-site vendor. The exposure rate from these containers is low (2 mrem/hr to about 100 mrem/hr with a majority less than 10
mrem/hr).
11.4A.4.2 Solidified/Dewatered Wastes
Resin, filter cartridges and filter sludges will be transferred into HICs, and
dewatered to less than 1% free standing water. Tables 11.1-6 (Sheet 1) to
11.1-6 (Sheet 24) and 11.4-4 provide normal activity concentrations in the
input streams.
11.4A-1 Rev.18 WOLF CREEK 11.4A.4.3 Uncompactible Contaminated Waste
Other wastes not suitable for packaging in drums or HICs may be packaged in LSA
boxes (B-25 or equivalent) and stored in the IOS facility, or packaged in modular storage containers and stored on the temporary outdoor storage slab.
11.4A.5 Design Concepts 11.4A.5.1 Storage areas
The wastes will be stored in four separate storage areas as identified in Table 11.4A-4 and Figures 11.4A-1 and 2.
- a. High and Low Level Storage Areas Two separate areas containing all three forms of waste (i.e. super compacted DAW in drums, solidifed/dewatered waste in HICs, and uncompactible waste in LSA boxes).
- b. DAW Storage Areas Two separate areas, adjacent to the high and low level storage areas, containing super compacted DAW in drums.
The storage areas act as a protective barrier to:
- a. Protect the waste containers from weather effects.
- b. Prevent an uncontrolled release of radioactive material to the environment.
- c. Provide shielding for radiation emitted by the waste.
11.4A.5.2 Handling and Storage Operations
Inventory data including batch number, container number, date of storage, and
other necessary data shall be maintained. The design includes an index system
that allows specific identification of container locations so that
administrative controls may be used to effectively inventory stored wastes.
Containers to be stored in the IOS facility are first visually inspected and
checked for surface contamination. No damaged containers will be sent to the IOS facility. Details of the IOS facility layout are shown in Figures 11.4A-1
and 2. The actual waste container configuration may deviate from the above
description based on changing waste processing/storage needs. Upon retrieval
of containers from storage for transport and permanent disposal, each container
is swipe tested.
11.4A.5.3 Personnel Exposure
As required by 10CFR20, occupational exposures shall be kept as low as
reasonably achievable (ALARA). During waste handling operations, only employees required to handle the shipment, perform maintenance activities, or perform inspections are allowed in the areas of the IOS facility for the time
needed to perform their task.
All operations in the IOS facility are controlled by plant radiation protection personnel to assure that all employees are monitored, confirm that dose limits
are not exceeded, and ensure that good working practices are being followed.
All operations are conducted in accordance with written procedures.
11.4A-2 Rev. 18 WOLF CREEK To reduce the possible exposure of personnel during inspection and maintenance, the following concepts have been incorporated in the design of the IOS
facility:
- a. The IOS facility and equipment are designed to require minimum maintenance activities in high radiation storage
areas.
- b. Containers are handled by a remote-controlled crane carrying CCTV cameras and lights.
- c. Inspection of the storage areas in the IOS facility is to be accomplished using CCTV from the solidification control panel
room.
- d. Access to the bridge crane and its cables is provided over the truck bay area to reduce exposure to maintenance personnel. Additional portable shielding may be used as
necessary.
- e. Additional portable shields may be used as necessary.
11.4A.5.4 Provision for Liquid Drainage
The IOS facility is provided with an internal drainage system consisting of
trenches and stainless steel piping which route potentially contaminated water to a radwaste sump. The drainage is then pumped to the liquid radwaste system, and processed prior to discharging. Walls and curbs are utilized to confine
any potentially contaminated water inside the building. The IOS facility is
also provided with exterior storm drains to prevent water from entering the
storage areas. (see Section 9.3)
11.4A.5.5 Structural and Architectural
The IOS facility is a non-nuclear safety non-seismic Category I structure. The
finished floors in the storage areas are constructed with minimal slope in
order to accommodate drum stacking, and covered with an easily decontaminable material. The roof of the storage building consists of built up roofing and
rigid insulation on a metal deck.
11.4A.5.6 Shielding
Shielding evaluations were performed utilizing the waste stream distribution, historical generation, isotopic activities, and storage configurations as
described in Tables 11.4A-1, 2, 3A - 3D, and 4, and Figures 11.4A-1 and 2. The
storage configuration provides adequate shielding for five years of radioactive
waste. The concrete walls provide shielding primarily for the outer layers of
containers. Consideration was given for a self-shielding effect due to the
large number of containers in the storage areas (i.e. containers with high
exposure rates will, to the extent possible, be placed in the center of the
storage areas using containers with lower exposure rates for shielding). The
roof, made of built up roofing and rigid insulation on a metal deck, provides
shielding equivalent to approximately 0.25 inches of steel. Additional portable container shields may be used as necessary.
Maximum anticipated dose rates outside of the IOS are shown in Tables 11.4A-5A
and 5B. Maximum anticipated dose rates along the south RCA boundary are shown
in Table 11.4A-6. The dose rates are also shown in Figures 11.4A-3, 11.4A-3A
and 11.4A-3B.
11.4A-3 Rev. 18 WOLF CREEK 11.4A.5.7 Design Basis Events
11.4A.5.7.1 Fire Protection
Fire protection is accomplished through the use of non-combustible construction
materials, local fire extinguishers, and local hose stations. Fire/smoke
detection devices, which alarm locally, and in the main control room, are
provided throughout the IOS facility. The only combustible material in the IOS
facility is DAW and HIC liner material (high density, cross linked polyethylene).
11.4A.5.7.2 Flood Protection
The topography of the site is such that flooding from natural causes is not a design basis event for above grade buildings. (see Section 2.0)
11.4A.5.7.3 Wind Protection
The IOS is a reinforced structure designed for a wind velocity of 100 miles/hr.
This velocity corresponds to a recurrence time of 100 years.
11.4A.5.7.4 Tornado Protection
The storage areas and stored waste have been evaluated with respect to a
tornado, and it has been determined that the design is such that there will be no adverse affects from a tornado for the following reasons.
a) All waste is stored in a form that is resistant to the release and spread of radioactivity.
b) Waste with high activity levels will be stored in tornado resistant rooms (i.e. rooms that have three foot thick reinforced walls which
are 16'-9" high) in containers that, due to their weight, will
remain in place during a tornado.
c) Waste with low activity levels will be stored in non-tornado resistant rooms (i.e. rooms that have only one foot thick reinforced masonry block walls which are 14' high). However, the waste that
will be stored in the non-tornado resistant rooms will have low
activity levels (i.e., 2 mrem/hr to 100 mrem/hr, with the majority
less than 10 mrem/hr).
d) The non-tornado resistant rooms, although they themselves do not provide resistance to a tornado, are protected from a tornado by
surrounding structures. The rooms are located in the Waste Bale Drumming Area which is designed to withstand 100 mph winds. Also, most tornadoes come from the southwest, and the rooms will be
shielded by three foot thick 16'-9" high walls on the west, a
concrete segmented shield on the south, and the Radwaste Building on
the north.
e) If, in the unlikely event that most of the waste stored in the non-tornado resistant rooms were dispersed during a tornado, the
released activity levels would remain below the 2.5 rem whole body
or 30 rem thyroid dose limit allowed by GL 81-38.
f) In the unlikely event a tornado missile were to enter one of these rooms, and penetrate a container, the missile would tend to plug its
own hole, minimizing any potential for release of radioactivity.
Liquid waste will be contained by the curbs and floor drain system.
11.4A-4 Rev. 18 WOLF CREEK Based on these reasons, the storage of radwaste as allowed per this
modification does not present a radiation hazard with respect to a tornado. In
the unlikely event of waste container failure or dispersal due to a tornado, plant procedures will provide instructions on handling and repackaging/reprocessing of the waste on a case by case basis. In case of a
unique failure not anticipated in plant procedures, WCGS Engineering and
Technical personnel would evaluate the situation and determine the best course
of action based on the specific conditions.
11.4A.5.7.5 Seismic Event
In the unlikely event of waste container failure due to a seismic event, plant
procedures will provide instructions on handling and repackaging/reprocessing
of the waste on a case by case basis. A failure due to a seismic event would
in all likelihood result in the failed container remaining within the IOS facility. In case of a unique failure not anticipated in plant procedures, WCGS Engineering and Technical personnel would evaluate the situation and
determine the best course of action based on the specific conditions. In no
case would the method of resolution fail to meet shipping and burial criteria, or result in any radioactive release to the environment.
11.4A.5.7.6 Waste Container Failure
In the unlikely event of waste container failure after final packaging, during
storage, or prior to shipment, plant procedures will provide instructions on
handling and repackaging/ reprocessing of the waste on a case by case basis. A
failure within the IOS facility would in all likelihood result in the failed
container remaining within the IOS facility. In case of a unique failure not
anticipated in plant procedures, WCGS Engineering and Technical personnel would
evaluate the situation and determine the best course of action based on the
specific conditions. In no case would the method of resolution fail to meet shipping and burial criteria, or result in any radioactive release to the
environment.
11.4A.5.8 HVAC Systems
The IOS facility is maintained at a negative pressure by the Radwaste Building
ventilation system. This is accomplished by an interlock that requires an
exhaust fan in operation, prior to starting a supply fan. Also, two exhaust
fans are provided with interlocks to ensure that upon the loss of one fan, the
other will automatically start. All exhaust air is monitored and filtered
prior to release. (see Section 9.4.5)
11.4A.5.9 Bridge Crane
11.4A.5.9.1 Crane Description
The bridge crane has a rated capacity of 9-1/3 tons. The crane has the
capability to handle all containers (i.e. HICs, LSA boxes, and drums). The
drum grab has the capability to recover fallen drums. The crane carries TV
cameras and lighting for storage, handling and inspection of containers, and
may perform other tasks in the storage and truck bay areas as required.
There are two motors on the crane, one high speed and one low speed for bridge, trolley and hoist movement. The redundant motors can be used to move the crane
in the event one motor fails. In the event of other problems, a cable can be
manually attached for crane retrieval.
11.4A-5 Rev.13 WOLF CREEK 11.4A.5.9.2 Crane Control
The solid radwaste control console is equipped so that radwaste movements may
be accomplished by remotely controlling the bridge crane. The crane system is designed for precise placement of drums, HICs or LSA boxes, and for lifting and
placement of the cask transportation lid. The bridge and trolley are
accurately positioned by the use of a CCTV monitoring system and an overhead
index system. It will have sufficient range to move HICs from the solid
radwaste disposal station to the storage areas, and unload drums and boxes from
the trucks and move them to their storage areas.
11.4A.5.9.3 CCTV System
The CCTV includes cameras mounted on the bridge crane. Monitors are installed
in the solidification control panel room. They are equipped with manual control capabilities to adjust the pan and tilt for the cameras. The cameras
on the crane are fixed focus and adjusted locally to get a close view of any container for inspection purposes, the two surveillance cameras have pan and tilt capabilities.
11.4A.5.10 Lighting
Fixed lights are provided throughout the IOS facility. These lights provide
illumination for all IOS activities, including inspections.
11.4A.5.11 Security
The IOS facility is surrounded by a chain link fence bounding the RCA. Access
to the IOS facility is controlled to minimize personnel exposure.
11.4A.6 Monitoring Operations 11.4A.6.1 Containers
Before the radioactive waste containers are placed in storage, the activity level of each container is determined. Radiological monitoring of the storage
containers is performed using portable equipment. Swipe testing and analysis
capability is provided in the truck bay area.
11.4A.6.2 Storage Areas
The IOS facility includes provision for remote monitoring of the storage areas
through closed circuit television (CCTV) so that the condition of any stored
container can be observed. In order to maximize visual inspection in the
storage areas for the longest period of time, drums will initially be stacked
in every other row, to the extent practicable.
Area radiation monitors are installed, one in the corridor across from the
radwaste control room and another in a truck bay area near the personnel
entrance. If predetermined radiation setpoints are exceeded, alarms sound both
locally and in the main control room. Additional radiation monitoring is
performed by the plant radiation protection group using portable equipment as
necessary.
11.4A-6 Rev.19 WOLF CREEK 11.4A.6.3 Offsite
The IOS facility is designed to ensure that the annual dose to the public is a
small fraction of the 25 mrem/yr allowed from all sources of the Uranium cycle, as per 40CFR190. Exposure levels are monitored at the RCA boundary fence using
RDD dosimeters. Table 11.4A-7 details anticipated dose rates at the restricted area boundary.
All potential pathways for the release of radioactivity to the environment are
controlled and monitored. In particular, water from potentially contaminated
drains is processed in the liquid radwaste system, and air from the IOS facility is processed in the Radwaste Building exhaust system. Both systems
sample and analyze for radioactivity prior to release to the environment. (see
Section 11.5)
Since the normal operation of the IOS facility is not expected to produce any
radioactive discharge or otherwise hazardous effluents, no significant effects
on environmental air or water quality are expected. Offsite environmental
surveillance is implemented through the environmental monitoring program.
11.4A-7 Rev. 25
TABLE 11.4A-1 ISOTOPIC DISTRIBUTION OF RADWASTE (PERCENT ABUNDANCE) NUCLIDE HALF-LIFE *** RESINS, FILTERS & EVAP *** DAW (DAYS) CLASS A CLASS B CLASS C ------- Mn-54 312.7 1.43 3.94 1.80 1.45 Fe-55 2.7* 57.35 21.70 41.00 59.70 Co-57 270.9 0.00 0.43 0.00 0.11 Co-58 70.8 2.28 22.70 25.60 1.69
Co-60 5.27
- 12.67 11.70 6.60 24.90 Ni-59 75000
- 0.00 0.17 0.00 0.00 Ni-63 100.1
- 15.07 16.20 12.60 7.37 Ag-110m 249.85 0.00 0.00 1.90 0.24
H-3 12.28*0.88 0.00 3.40 0.02 C-14 5730* 0.17 0.54 0.50 0.00 Nb-95 35.06 0.00 0.10 1.60 1.73
Cs-134 2.062
- 4.02 9.07 0.30 1.02 Cs-137 30.17
- 6.07 12.50 0.50 1.46 Ce-144 284.3 0.00 0.00 0.10 0.34
Sb-125 2.77
- 0.00 0.76 0.00 0.00 Cm243/44 28.5
- 0.002 0.00 0.00 0.00 Sr-95 24.4
- 0.00 0.00 0.00 0.00 Zr-95 64.02 0.00 0.15 2.40 0.00
SR-90 28.6
- 0.00 0.01 0.00 0.00 Cr-51 27.7 0.00 0.00 1.70 0.00 BASED ON CHARACTERIZATION OF WASTE SAMPLES FROM PLANT OPERATIONS DURING 1988 TO 1991 AND RADMAN COMPUTER CODE.
DAW ISOTOPIC DISTRIBUTION IS BASED ON RADMAN COMPUTER CODE.
- HALF-LIFE IN YEARS
- HALF-LIFE IN SECONDS Rev. 8 TABLE 11.4A-2 AVERAGE ANNUAL ACTIVITY OF RADWASTE (RESINS/FILTERS)
(1988 TO 1991)
- WASTE CLASS **********
TYPE/ ***** CLASS A ***** ***** CLASS B ***** ***** CLASS C *****
PERIOD VOLUME ACTIVITY VOLUME ACTIVITY VOLUME ACTIVITY (ft
- 3) (mCi) (ft
- 3) (mCi) (ft
- 3) (mCi)
====== ======== ====== ======== ====== ==
120.3 5.31E+05 120.3 5.05E+05 84.3 1.72E+04 120.3 6.29E+05 120.3 2.56E+05 120.3 1.11E+05 205.8 2.31E+05 1988 TO 411.6 3.46E+01 120.3 1.94E+05 1991 411.6 1.06E+02 120.3 2.07E+05 205.8 2.64E+05 205.8 8.00E+03 388.2 1.30E+00 83.4 8.91E+02 83.4 8.53E+02 83.4 7.80E+03 83.4 2.12E+03 205.8 4.65E-02 TOTAL 2523.3 1.55E+06 687 1.39E+06 84.3 1.72E+04 ANNUAL AVE 630.8 3.89E+05 171.8 3.48E+05 21.1 4.30E+03 mCi/Cuft 6.16E+02 2.03E+03 2.04E+02 PROJECTED VOL. CUFT. 710 200 80 EST'D Ci/Yr 4.37E+02 4.06E+02 1.63E+01 Rev. 8
TABLE 11.4A-3A ONE YEAR ISOTOPIC ACTIVITY OF RADWASTE STORED AT WCGS (CURIE)
- RESIN/EVA/FIL****** ****** DAW ****** ***** YEAR TOTAL *****
NUCLIDE 710 CUFT 200 CUFT 80 CUFT 2610 CUFT 1610 CUFT 3600 CUFT 2600 CUFT
CLASS A CLASS B CLASS C OUTAGE NON OUTAGE OUTAGE YR NON OUTAGE YR Mn-54 6.25E+00 1.60E+01 2.94E-01 3.61E-02 2.22E-02 2.26E+01 2.26E+01 Fe-55 2.51E+02 8.81E+01 6.69E+00 1.48E+00 9.16E-01 3.47E+02 3.46E+02
Co-57 0.00E+00 1.75E+00 0.00E+00 2.74E-03 1.69E-03 1.75E+00 1.75E+00
Co-58 9.96E+00 9.22E+01 4.18E+00 4.20E-02 2.59E-02 1.06E+02 1.06E+02
Co-60 5.54E+01 4.75E+01 1.08E+00 6.19E-01 3.82E-01 1.05E+02 1.04E+02
Ni-59 0.00E+00 6.90E-01 0.00E+00 0.00E+00 0.00E+00 6.90E-01 6.90E-01
Ni-63 6.59E+01 6.58E+01 2.06E+00 1.83E-01 1.13E-01 1.34E+02 1.34E+02 Ag-110m 0.00E+00 0.00E+00 3.10E-01 5.97E-03 3.68E-03 3.16E-01 3.14E-01 H-3 3.85E+00 0.00E+00 5.55E-01 4.97E-04 3.07E-04 4.40E+00 4.40E+00
C-14 7.47E-01 2.19E+00 8.16E-02 0.00E+00 0.00E+00 3.02E+00 3.02E+00
Nb-95 0.00E+00 4.06E-01 2.61E-01 4.30E-02 2.65E-02 7.10E-01 6.94E-01
Cs-134 1.76E+01 3.68E+01 4.90E-02 2.54E-02 1.56E-02 5.45E+01 5.45E+01
Cs-137 2.65E+01 5.08E+01 8.16E-02 3.63E-02 2.24E-02 7.74E+01 7.74E+01
Ce-144 0.00E+00 0.00E+00 1.63E-02 8.46E-03 5.22E-03 2.48E-02 2.15E-02
Sb-125 4.37E-03 3.09E+00 0.00E+00 0.00E+00 0.00E+00 3.09E+00 3.09E+00
Cm243/44 8.74E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.74E-03 8.74E-03
Sr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Zr-95 0.00E+00 6.09E-01 3.92E-01 0.00E+00 0.00E+00 1.00E+00 1.00E+00
Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Sr-90 0.00E+00 4.06E-02 0.00E+00 0.00E+00 0.00E+00 4.06E-02 4.06E-02
Cr-51 0.00E+00 0.00E+00 2.77E-01 0.00E+00 0.00E+00 2.77E-01 2.77E-01
Fe-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Sn-113 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
== ======== ======== ======== ======== ======== ==
TOTALS 4.37E+02 4.05E+02 1.57E+01 2.49E+00 1.53E+00 8.60E+02 8.59E+02 NOTES: ISOTOPIC DISTRIBUTION IS BASED ON CHARACTERIZATION OF WASTE SAMPLE (CLASS B) AND RADMAN COMPUTER PROGRAM (CLASS A/B):
CLASS A - FEBRUARY 1991 SHIPMENT PL6-80
CLASS B - CVCS WASTE IN PL8-120 POLY HIC, MAY 1991 SHIPMENT
CLASS C - FILTER SHIPMENT IN PL6-80. SEPTEMBER 1990. THE ONE YEAR TOTAL ACTIVITY IS BASED ON: 1993 OUTAGE YEAR. RADWASTE ACTIVITY WITH NO DECAY. Rev. 12 TABLE 11.4A-3B TWO YEAR PROJECTED ISOTOPIC ACTIVITY OF RADWASTE STORED WITHIN THE IOS (CURIE)
HIGH LEVEL *********** LOW LEVEL STORAGE AREA ***********
STORAGE SEC 5 SEC 6 SEC 7 SEC 8 8 PL-120 8 PL-120 3 PL-215 16 B25 70 DRUMS NUCLIDE 76%A & B C & 12%A C & 12%A DAW DAW
= ======== ======== ======== ======== ==
Mn-54 3.00E+01 1.51E+00 1.08E+00 4.35E-02 2.90E-02 Fe-55 4.94E+02 6.61E+01 5.34E+01 1.79E+00 1.19E+00 Co-57 2.43E+00 0.00E+00 0.00E+00 3.30E-03 2.20E-03 Co-58 1.03E+02 5.52E+00 1.23E+00 5.07E-02 3.38E-02 Co-60 1.68E+02 1.45E+01 1.25E+01 7.47E-01 4.98E-01 Ni-59 1.33E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 2.31E+02 1.98E+01 1.58E+01 2.21E-01 1.47E-01 Ag-110m 0.00E+00 4.23E-01 0.00E+00 7.20E-03 4.80E-03 H-3 5.68E+00 1.98E+00 8.98E-01 6.00E-04 4.00E-04 C-14 5.52E+00 3.43E-01 1.79E-01 0.00E+00 0.00E+00 Nb-95 4.06E-01 2.61E-01 0.00E+00 5.19E-02 3.46E-02 Cs-134 8.60E+01 3.70E+00 3.61E+00 3.06E-02 2.04E-02 Cs-137 1.40E+02 6.46E+00 6.29E+00 4.38E-02 2.92E-02 Ce-144 0.00E+00 2.30E-02 0.00E+00 1.02E-02 6.80E-03 Sb-125 5.49E+00 9.33E-04 9.33E-04 0.00E+00 0.00E+00 Cm243/44 1.31E-02 2.07E-03 2.07E-03 0.00E+00 0.00E+00 Zr-95 6.21E-01 3.00E-01 0.00E+00 0.00E+00 0.00E+00 SR-90 8.02E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 2.77E-01 0.00E+00 0.00E+00 0.00E+00
== ======== ======== ======== ==
TOTAL 1.27E+03 1.21E+02 9.50E+01 3.00E+00 2.00E+00 NOTE: The activities of the DAW stored at the Drum Areas A and B are estimated at 2 and 1 curies, respectively. They will have negligible contributions to the dose rates.
The two year activity is based on the sum of the first year activity decayed for one year and the second year activity with no decay.
Rev. 8 TABLE 11.4A-3C THREE YEAR PROJECTED ISOTOPIC ACTIVITY OF RADWASTE STORED WITHIN THE IOS (CURIE)
HIGH LEVEL *** ***
STORAGE ******** LOW LEVEL STORAGE AREA ******** *** DRUM STORAGE ***
SEC 1+2 SEC 5 SEC 6 SEC 7 SEC 8 AREA A AREA B 12 PL120 3 (PL80) 4 PL215 26 B25 100 DRUM NUCLIDE CL76%A&B CL C+12%A CL 12%A DAW DAW DAW DAW
== ======== ======== ======== ======== ========= ===
Mn-54 3.41E+01 1.71E+00 1.23E+00 5.80E-02 4.36E-02 2.30E-02 1.15E-02 Fe-55 6.61E+02 8.72E+01 7.13E+01 2.39E+00 1.79E+00 1.50E+00 7.48E-01 Co-57 2.70E+00 0.00E+00 0.00E+00 4.40E-03 3.31E-03 1.61E-03 8.04E-04 Co-58 1.03E+02 5.53E+00 1.23E+00 6.76E-02 5.08E-02 1.36E-02 6.79E-03 Co-60 2.37E+02 2.04E+01 1.76E+01 9.96E-01 7.49E-01 7.11E-01 3.55E-01 Ni-59 2.07E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 3.45E+02 2.97E+01 2.35E+01 2.95E-01 2.22E-01 2.42E-01 1.21E-01 Ag-110m 0.00E+00 4.64E-01 0.00E+00 9.60E-03 7.22E-03 3.35E-03 1.67E-03 H-3 8.30E+00 2.88E+00 1.31E+00 8.00E-04 6.01E-04 6.20E-04 3.10E-04 C-14 8.28E+00 5.14E-01 2.69E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 4.06E-01 2.61E-01 0.00E+00 6.92E-02 5.20E-02 1.33E-02 6.64E-03 Cs-134 1.12E+02 4.80E+00 4.69E+00 4.08E-02 3.07E-02 2.37E-02 1.18E-02 Cs-137 2.08E+02 9.57E+00 9.33E+00 5.84E-02 4.39E-02 4.70E-02 2.35E-02 Ce-144 0.00E+00 2.58E-02 0.00E+00 1.36E-02 1.02E-02 5.10E-03 2.55E-03 Sb-125 7.37E+00 1.25E-03 1.25E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce243/44 1.95E-02 3.07E-03 3.07E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 6.21E-01 3.99E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 1.19E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 0.00E+00 2.77E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
== ======== ======== ======== ======== ======== ==
TOTALS 1.73E+03 1.64E+02 1.31E+02 4.00E+00 3.00E+00 2.58E+00 1.29E+00 THE THREE YEAR TOTAL ACTIVITY IS BASED ON THE SUM OF:
1993 OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 2 YEARS.
1994 OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 1 YEAR. 1995 NON-OUTAGE YEAR. RADWASTE ACTIVITY WITH NO DECAY. Rev. 8 TABLE 11.4A-3D FIVE YEAR PROJECTED ISOTOPIC ACTIVITY OF RADWASTE STORED WITHIN THE IOS (CURIE)
HIGH LEVEL STORAGE ** LOW LEVEL STORAGE AREA ** ** DRUM STORAGE AREAS **
20 PL120 5 (PL80) 6 PL215 36 B25 162 DRUM 147 DRUMS 72 DRUMS NUCLIDE CL76%A&B CLC+12%A CL 12%A 6 Ci DAW 5 Ci DAW 4 Ci DAW 2 Ci DAW
= ======== ======== ======= ======= ======== ======== ==
SEC 5 SEC 6 SEC 7 SEC 8 AREA A AREA B Mn-54 3.67E+01 1.81E+00 1.29E+00 8.70E-02 7.25E-02 5.80E-02 2.90E-02 Fe-55 8.90E+02 1.15E+02 9.33E+01 3.58E+00 2.99E+00 2.40E+00 1.20E-00 Co-57 2.85E+00 0.00E+00 0.00E+00 6.60E-03 5.50E-03 4.40E-03 2.20E-03
Co-58 1.03E+02 5.49E+00 1.20E+00 1.01E-01 8.45E-02 6.76E-02 3.38E-02
Co-60 3.50E+02 2.95E+01 2.52E+01 1.49E+00 1.25E+00 9.96E-01 4.98E-01
Ni-59 3.45E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Ni-63 5.71E+02 4.80E+01 3.79E+01 4.42E-01 3.69E-01 2.95E-01 1.47E-01
Ag-110m 0.00E+00 4.84E-01 0.00E+00 1.44E-02 1.20E-02 9.60E-03 4.80E-03
H-3 1.31E+01 4.50E+00 2.01E+00 1.20E-03 1.04E-03 8.00E-04 4.00E-04
C-14 1.38E+01 8.43E-01 4.36E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Nb-95 4.06E-01 2.61E-01 0.00E+00 1.04E-01 8.65E-02 6.92E-02 3.46E-02
Cs-134 1.43E+02 5.98E+00 5.84E+00 6.12E-02 5.10E-02 4.08E-02 2.04E-02 Cs-137 3.39E+02 1.52E+01 1.48E+01 8.76E-02 7.90E-02 5.84E-02 2.92E-02
Ce-144 0.00E+00 2.74E-02 0.00E+00 2.04E-02 1.70E-02 1.36E-02 6.80E-03 Sb-125 9.96E+00 1.64E-03 1.64E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Cm243/44 3.17E-02 4.86E-02 4.86E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Zr-95 6.21E-01 3.99E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
SR-90 1.94E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Cr-51 0.00E+00 2.77E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
== ======== ======== ======== ======== ======== ==
TOTAL 2.48E+03 2.28E+02 1.82E+02 6.00E+00 5.00E+00 4.00E+00 2.00E+00
GRAND TOTAL - 2.91E+03 THE FIVE YEAR TOTAL ACTIVITY IS BASED ON THE SUM OF:
1993 OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 4 YEARS.
1994 OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 3 YEARS.
1995 NON-OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 2 YEARS
1996 OUTAGE YEAR. RADWASTE ACTIVITY DECAYED FOR 1 YEAR. 1997 OUTAGE YEAR. RADWASTE ACTIVITY WITH NO DECAY. Rev. 8 TABLE 11.4A-4 Estimated Capacity and Radwaste Container Distribution for the IOS Facility
AREA DIMENSIONS WASTE 5 Yr CAPACITY*
ACTIVITY (Inside) TYPE CONTAINERS (cuft) (CURIE) HLSA 30' x 20'9" Primary 20 PL8-120 2,406 2,480 Resin LLSA 30' x 46' SECTION 5 Resin/ 5 PL6-80 417 228 Filter SECTION 6 Sec Resin 6 PL14-215 1,235 182 SECTION 7 DAW 36 B25-boxes 3,456 6 SECTION 8 DAW 162 Drums 1,782 5 DRUM AREA 'A' 5'5" x 32'11" DAW 147 Drums 1,617 4 DRUM AREA 'B' 15'5" x 17'10" DAW 72 Drums 792 2 TOTAL 60' x 100' 31 HICS 11,705 2,907 including Truck Bay: 36 boxes and 381 drums
- Volume is based on the Following anticipated usage and waste configuration as shown in Figure 11.4A-1.
WASTE CONTAINER CONTAINER STREAM TYPE VOLUME PRIMARY RESIN PL8-120 120.3 cuft SECONDARY RESIN PL14-215 205.8 cuft FILTERS PL6-80 83.4 cuft DAW 85 Gal.Drum 11 cuft 79 Gal.Drum 11 cuft 55 Gal.Drum 7.5 cuft B-25 Box 96 cuft Rev. 8 TABLE 11.4A-5A Total Offsite Dose Rates (mrem/hr) from 3-Year Storage (2,036 Ci)
Distance From Outside Wall Surface 1 M 15 M 29 M 43 M 57 M WEST SIDE Skyshine Dose Rate 3.2298 2.8393 1.2070 0.7552 0.5252 0.3842
Direct Exposure Dose Rate 0.0734 0.0636 0.0056 0.0016 0.0007 0.0004 TOTAL 3.3032 2.9029 1.2126 0.7568 0.5259 0.3846 SOUTH SIDE Skyshine Dose Rate 1.0911 1.0462 0.6956 0.4989 Direct Exposure Dose Rate 0.0029 0.0025 0.0006 0.0001 TOTAL 1.0940 1.0487 0.6962 0.4990 EAST SIDE Skyshine Dose Rate 1.6607 1.6027 0.9932 0.6874 0.5042 0.3814 Direct Exposure Dose Rate 0.1427 0.1119 0.0108 0.0033 0.0015 0.0008 TOTAL 1.8034 1.7146 1.004 0.6907 0.5057 0.3822 Rev. 13 TABLE 11.4A-5B Total Offsite Dose Rates (mrem/hr) from 5-Year Storage (2907 Ci)
Distance From Outside Wall Surface 1 M 15 M 29 M 43 M 57 M WEST SIDE Skyshine Dose Rate 4.3900 3.9586 1.8515 1.1887 0.8382 0.6192 Direct Exposure Dose Rate 0.0812 0.0698 0.0060 0.0017 0.0007 0.0004 TOTAL 4.4712 4.0284 1.8575 1.1904 0.8389 0.6196 SOUTH SIDE Skyshine Dose Rate 1.5180 1.4572 0.9716 0.6975 Direct Exposure Dose Rate 0.0038 0.0032 0.0008 0.0003 TOTAL 1.5218 1.4604 0.9724 0.6978 EAST SIDE Skyshine Dose Rate 2.6574 2.5690 1.5443 1.0742 0.7904 0.5993 Direct Exposure Dose Rate 0.2281 0.1791 0.0173 0.0053 0.0024 0.0013 TOTAL 2.8855 2.7481 1.5616 1.0795 0.7928 0.6006Rev. 13 TABLE 11.4A-6 TOTAL DOSE RATES (mrem/hr)
ALONG THE SOUTH RCA BOUNDARY West Side of the IOS Distance From the West Wall (METERS)
Source Surface 1 M 15 M 29 M 43 M 57 M 5 year Storage
- 1. HLSA 2.0385 1.9962 1.3601 0.9027 0.6527 0.4913
- 2. LLSA Section 5
- 0.1856 0.1811 0.1182 0.0755 0.0543 0.0409 LLSA Section 6
- 0.1593 0.1500 0.0743 0.0484 0.0343 0.0254 Total 5 yr Dose Rate 2.3834 2.3273 1.5526 1.0266 0.7413 0.5576
- - Low Level Storage Sections are described by Figure 11.4A-1.
Rev. 13 TABLE 11.4A-7 TOTAL OFFSITE DOSE AT THE UNRESTRICTED AREA (Exclusion Area Boundary, EAB, is 1200 meters from Center of Containment)
Dose at the EAB Source/EAB direction Hourly Dose Annual Dose (mrem/hr) (mrem/yr) 5 Year Storage West Side High Level Storage 1.5160E-06 Low Level Storage 5 1.1515E-07
Low Level Storage 6 5.4731E-08 5 yr Storage Dose At West EAB 1.6859E-06 0.0148 South Side High Level Storage 7.7607E-07
Low Level Storage 5 8.0440E-07
Low Level Storage 6 1.7227E-07 5 yr Storage Dose At South EAB 1.7527E-06 0.0154 East Side High Level Storage 1.7690E-06
Low Level Storage 5 1.1512E-07
Low Level Storage 6 6.1442E-08 5 yr Storage Dose At East EAB 1.9456E-06 0.0171 3 Year Storage West Side High Level Storage 4.9940E-07 Low Level Storage 5 4.2856E-08
Low Level Storage 6 3.8725E-08 3 yr Storage Dose At West EAB 5.8097E-07 0.0051 South Side High Level Storage 5.4989E-07
Low Level Storage 5 5.3937E-07
Low Level Storage 6 5.9423E-08 3 yr Storage Dose At South EAB 1.1486E-06 0.0101 Rev. 13 TABLE 11.4A-7 (Sheet 2)
TOTAL OFFSITE DOSE AT THE UNRESTRICTED AREA (Exclusion Area Boundary, EAB, is 1200 meters from Center of Containment - Continued)
Dose at the EAB Source/EAB direction Hourly Dose Annual Dose (mrem/hr) (mrem/yr)
East Side High Level Storage 8.9247E-07
Low Level Storage 5 9.6958E-08
Low Level Storage 6 4.3531E-08 3 yr Storage Dose At East EAB 1.0330E-06 0.0091 2 Year Storage High Level Storage 8.3118E-07
Low Level Storage 5 2.3780E-08
Low Level Storage 6 2.7916E-08 2 yr Storage Dose At West EAB 8.8288E-07 .0077 South Side High Level Storage 4.0898E-07
Low Level Storage 5 4.1932E-07
Low Level Storage 6 2.7141E-08 3 yr Storage Dose At South EAB 8.5544E-07 .0075 East Side High Level Storage 4.5226E-07
Low Level Storage 5 8.8748E-08
Low Level Storage 6 3.1376E-08 2 yr Storage Dose At East EAB 5.7238E-07 0.0050 NOTE: Low Level Storage Sections are described by Figure 11.4A-1.
Rev. 13 c c , 0 r 0 z )> f'1 --iO 0 "TJ (I) (II-i G) --io c mo -tr o"TJ ::u -<., ::;u 1"'1 --i ::: O:J: f'Tl(TI f:f;l .,_ )> -(A z I (/) o--i Vi -ITI ;:o !: ::u --i -f'1 -< , 0 ;:o -t ;:o ,.., -:::.* 00 c LOW LEVEL STORAGE AREA t l{J ! I I ...........
l_ __ , EAST WALL HIGH LEVEL STORAGE AREA WEST WALL SECTION 7 (.36 825 BOXES) SECTION 6 <6 PL14-215, SECTION 8 C162 DRUMS> J' DRUM AREA II A" DRUM AREA "8" 8
I t I I +----+-I I I I I B I I t----r-WOLF CREEK w I " <( I 0:: ..L 0 I 1-I I (/) I ...J w I > I w 1 _J I i 3: ..L I 0 I ..J TRUCK BAY REV. a WOLf CREEK UPDATED SAFETY ANJIL YSIS REPORT fiGURE 11.4A-2 STORAGE CONfiGURATION OF THE INTERIM ONSITE STORAGE FACILITY WOLF' CR££1< I I I I I I w I I 5 I I ... "' I I "' 2 i ... ... .l e .. "'
- I '-J.* I I I I 1111: 1 w I § I I ' I .. !
- VI I a::: I I I
- t w -! i I I I I _, * ._ ______ _, I I I Rev.13 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT Figure 11.4A-3 TOTAL DOSE RATES OUTSIDE THE lOS UP TO THE RCA BOUNDARY 1 I I I ' I 1
- j II! I
- 0 I r-: I I I \j_ t f
- I I ... Cit I (!)
.... LaJO I ::)-l u.s .... CD .... J! D i J .,. c I * ., I w VI i ----' I I I I 1 Rev.13 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT Figure 11.4A-3A TOTAL DOSE RATES OUTSIDE THE UP TO THE RCA BOUNDARY .__.---.. ----.... -.. -----... --.. ---------------------------
.. ----.. ---... -..... --..
- ---------1 WOLF CR£!1< I
- t 1 i I 1 I I I I ' I I I ! e "' ___ _,I t I I I 1 Rev.13 WOLF CREEK UPDATED SAFETY ANALYSIS REPORT Figure 11.4A-38 TOTAL DOSE RATES OUTSIDE THE lOS UP TO THE RCA BOUNDARY ----------------
.. -----------------*---------*----------*----------
WOLFCREEK11.5PROCESSANDEFFLUENTRADIOLOGICALMONITORINGANDSAMPLING SYSTEMSThefunctionoftheprocessandeffluentradiologicalmonitoringsystemsistomonitor,record,andcontrolthereleaseofradioactivematerialsthatmaybe generatedduringnormaloperation,anticipatedoperationaloccurrences,and postulatedaccidents.Theprocessandeffluentradioactivitymonitoringsystemsfurnishinformationtooperationspersonnelconcerningradioactivitylevelsinprincipalplant processstreamsandatmospheres.Themonitoringsystemsindicateandalarmexcessiveradioactivitylevels(GDC-63).Theyinitiateoperationofstandbysystems,provideinputstotheventilationandliquiddischargeisolation systems,andrecordtherateofreleaseofradioactivematerialstothe environs,asoutlinedinRegulatoryGuide1.21andGDCs60and64.Thesystems consistofpermanentlyinstalled,continuous-monitoringdevicestogetherwitha programandprovisionsforspecificsamplecollectionsandlaboratoryanalyses.11.5.1DESIGNBASES Theprincipalobjectivesandcriteriaoftheprocessandeffluentradiologicalmonitoringsystemsareprovidedbelow.11.5.1.1SafetyDesignBasesSAFETYDESIGNBASES-Thecontrolroomventilationmonitors,thecontainmentatmospheremonitors,thecontainmentpurgemonitors,andthefuelbuildingexhaustmonitorsaredesignedtoactivateengineeredsafetyfeaturessystemsin theeventthatairborneradioactivityinexcessofallowablelimitsexists.
Additionaldesignbasesarestatedinthefollowingsections:a.Containmentpurgeisolationsystem,Sections6.2.4,7.3.2,9.4.6,and12.3.4.b.Fuelbuildingventilationisolation,Sections7.3.3,9.4.2,and12.3.4.c.Controlroomintakeisolation,Sections6.4.1,7.3.4,9.4.1,and12.3.4.TheseradioactivitymonitorsareprotectionsystemelementsandaredesignedinaccordancewithIEEEStandard279.ThesafetyevaluationofthesesystemsisdiscussedinSection7.3.11.5-1Rev.0 WOLFCREEKThesemonitorsalsoserveforin-plantworkerprotection,andthisfunctionisdiscussedinSection12.3.4.CompliancewithRegulatoryGuide1.97isdiscussedinAppendix7A.11.5.1.2PowerGenerationDesignBasesPOWERGENERATIONDESIGNBASISONE-Theprocessandeffluentradioactivitymonitorsoperatecontinuouslyduringbothintermittentandcontinuousdischargesofpotentiallyradioactiveplanteffluents,incompliancewithRegulatoryGuide1.21.Themonitorsverifythatthemostrestrictiveanticipatednuclidesareatconcentrationswithinthelimitsspecifiedin10CFR20andthattheconcentrationsarelowenoughthat10CFR50,AppendixI,doseguidelinesaremetforunrestrictedareas.POWERGENERATIONDESIGNBASISTWO-Theprocessandeffluentradioactivitymonitorsalarmandautomaticallyterminatethereleaseofeffluentswhenradionuclideconcentrationsexceedthelimitsspecified(GDC-60).Whereterminationofreleasesisnotfeasible,themonitorsprovidecontinuousindicationofthemagnitudeoftheactivityreleased.POWERGENERATIONDESIGNBASISTHREE-Theradwasteprocesssystemmonitorsmeasureradioactivityinprocessstreamstoaidpersonnelinthetreatmentofradioactivefluidspriortorecycleordischarge(GDC-63).POWERGENERATIONDESIGNBASISFOUR-Theprocessandeffluentradioactivitymonitorsmonitorthecontainmentatmosphere,spacescontainingcomponentsfor recirculationofLOCAfluids,andeffluentdischargepathsforradioactivity thatmaybereleasedfrompostulatedaccidents,asrequiredbyGDC-64.POWERGENERATIONDESIGNBASISFIVE-Theprocessandeffluentmonitorsindicatetheexistenceand,totheextentpossible,themagnitudeofreactorcoolantand reactorauxiliarysystemleakagetothecontainmentatmosphere,coolingwater systems,orthesecondarysideofthesteamgenerators.POWERGENERATIONDESIGNBASISSIX-Theprocessandeffluentradioactivitymonitorsprovidealarmandautomaticterminationofthetransferof radioactivityfluidstostoragefacilitiesinzoneAareas,definedinSection
12.4.1.1.POWERGENERATIONDESIGNBASISSEVEN-Processradioactivitymonitorsprovidealarmandgrossindicationoftheextentofanyfailedfuelwithintheprimary system.11.5-2Rev.7 WOLFCREEKPOWERGENERATIONDESIGNBASISEIGHT-TheeffluentradioactivitymonitorsprovidesufficientradioactivityreleasedatatopreparethereportsrequiredbyRegulatoryGuide1.21.11.5.1.3CodesandStandardsCodesandstandardsapplicabletotheprocessandeffluentradioactivitymonitorsareindicatedinTable3.2-1.ThemonitorslistedinSection11.5.1.1 aredesignedasprotectionsystemelements.11.5.2SYSTEMDESCRIPTION11.5.2.1GeneralDescription11.5.2.1.1DataCollectionTheprocessandeffluentradiologicalmonitoringsystemsconsistofliquidandairborneradioactivitymonitorswiththeattendantcontrols,alarms,pumps, valves,andindicatorsrequiredtomeetthedesignbases.Eachmonitor consistsofthedetectorassemblyandalocalmicroprocessor.Thelocal microprocessorprocessesthedetectorassemblysignalindigitalform,computes averageradioactivitylevels,storesdata,performsalarmorcontrolfunctions, andtransmitsthedigitalsignaltothecontrolroommicroprocessor.Signaltransmissionisaccomplishedviaredundantdatahighways.Asinglefaultin eitherdatahighwaywouldnotpreventthecontrolroommicroprocessorfrom receivingthedata.Thelocalmicroprocessorsformonitorswhichperformsafetyfunctions(controlroomventilation,fuelbuildingventilation,containmentatmosphere,andcontainmentpurgemonitors,refertoSection12.3.4)arewireddirectlyto individualindicatorslocatedontheseismicCategoryIradioactivity monitoringsystemcabinetsinthecontrolroom.Theinputfromthesafety-relatedchannelstothedaisy-chainloopisanisolatedsignaltoensurethatthesafety-relatedsignalsarenotaffectedbysignalsorconditionsexistinginthenonsafetyportionofthesystem.Thecontrolroommicroprocessorprovidescontrolsandindicationfortheradioactivitymonitoringsystem.IndicationisviaaCRTlocatedinthe controlroom.Thesignalsfromeachmonitormayalsoberecordedonasystem printer.11.5.2.1.2AlarmsEachmonitorchannelisprovidedwithathree-levelalarmsystem.Onealarmsetpointisbelowthebackgroundcountingrateandservesasacircuitfailure alarm.Theothertwo-alarmsetpointsprovidesequentialalarmsonincreasing radioactivitylevels.Loss11.5-3Rev.0 WOLFCREEKofpowercausesanalarmonallthree-alarmcircuits.Thealarmsmustbemanuallyresetandcanberesetonlyafterthealarmconditioniscorrected.11.5.2.1.3CheckSourcesEachmonitorisprovidedwithachecksource,operatedfromthecontrolroom,whichsimulatesaradioactivesampleinthedetectorassemblyforoperational andgrosscalibrationchecks.11.5.2.1.4PowerSuppliesAllClassIEradioactivitymonitoringsystemsarepoweredfromClassIEmotorcontrolcenters.ThepowersuppliesforallofthemonitorsaregiveninTable
11.5-5.11.5.2.1.5CalibrationandMaintenanceTheradioactivitymonitorsarecalibratedbythemanufacturerforatleasttheprincipalradionuclideslistedinTables11.5-1through11.5-4.The manufacturer'scalibrationstandardsaretraceabletoNationalInstituteofStandardsandTechnologyprimarycalibrationstandardsourcesandareaccuratetoatleast5percent.Thesourcedetectorgeometryduringthisprimary calibrationisidenticaltothesampledetectorgeometry.Secondarystandards countedinreproduciblegeometryduringtheprimarycalibrationaresupplied witheachcontinuousmonitor.Eachcontinuousmonitoriscalibratedata frequencyestablishedbystationprocedures.Thecountrateresponseofeachcontinuousmonitortoremotelypositionablechecksourcesisrecordedbythemanufactureraftertheprimarycalibration.
Thiscountrateresponseandbackgroundcountrateischeckedatintervals specifiedbyplantproceduresduringreactoroperation.SurveillanceisperformedinaccordancewithTechnicalSpecificationsorthe ODCM.Anyfluidreleasedtotheenvironmentisanalyzedforradioactivitypriortorelease.If,atanytime,amonitorrequiresmaintenanceordecontamination, theprocessflowisterminatedorperiodicgrabsamplingwithlaboratory analysisisimplemented.11.5-4Rev.13 WOLFCREEKThisdoesnotimpairsystemintegritysincethedetectorisoff-lineandnotinstalledinthestream.11.5.2.1.6SensitivitiesEacheffluentmonitoringsystemisabletodetectaminimumconcentrationwithinthereleaselimitsestablishedintheTechnicalSpecifications.Duetosensitivityconsiderations,monitorsarelocatedattheeffluentreleasepoints.Dilutionfactorsbetweenthereleasepointandthesiteboundaryareconsideredincomplyingwiththelimitationsof10CFR50,AppendixI.Tables11.5-1through11.5-4providethedetailedsensitivityselectioncriteriafortheprocessandeffluentmonitors.11.5.2.1.7MonitorLocationsThelocationofeachprocessandeffluentradioactivitymonitorisshownontheradiationzonedrawings,Figure12.3-2.Themonitorsarelocatedinlow backgroundareas,nearthesystemsbeingmonitored,tominimizebackgroundand samplinginterferences.11.5.2.1.8RangesandSetpointsTherangesofthevariousprocessmonitorsarebasedontheexpectedactivitylevelsinthesystembeingmonitored.Thebasesfortheirsetpointsaredeterminedbytheneedforprocesscontrolandtoalerttheoperatorsofleakageofradioactivityintonormallynonradioactivesystems.Therangesofthevariouseffluentmonitorsarebasedontheabilitytodetectradioactivityconcentrationsattheeffluentreleasepointwhichmightresult insiteboundarydosesinexcessof10CFR50AppendixIlevelstothosefrom postulatedaccidents.TheHialarmisadministrativelyestablishedatapointsufficientlybelowtheHi-HialarmsoastoprovideadditionalassurancethatTechnicalSpecificationlimitsarenotexceeded.TheHi-HialarmisestablishedtoensurethatTechnicalSpecificationlimitsarenotexceeded.
(SeeOffsiteDoseCalculationManual.)TherangesandsetpointsfortheprocessandeffluentmonitorsareprovidedinTables11.5-1through11.5-4.11.5-5Rev.14 WOLFCREEK11.5.2.1.9ExpectedSystemParametersTheexpectedrangesofsystemparameters,suchasflow,composition,andconcentrations,aresummarizedinTables11.5-1through11.5-4.DetailedinformationontheindividualsystemscanbefoundinothersectionsoftheUSAR,principallyChapters9.0and11.0.11.5.2.2LiquidMonitoringSystems11.5.2.2.1SelectionCriteriaforLiquidMonitorsTheliquidmonitorsconsistoffixed-volume,off-line,leadshieldedsamplechambersthroughwhichtheliquidsamplesflow.ANaI(Tl)gammascintillation detectorislocatedwithineachsamplechambertodetecttheactivitylevel.
Thedetectorassembliesmonitorgrossgammaactivityintherangeof10
-7 to10-2mCi/ml.TheserangeapplytoallliquidmonitorsexceptO-SJ-RE-01ThecontrollingisotopefortheliquidmonitorsisCs-137.Minimumdetectable concentrationsarelistedinTables11.5-1and11.5-2.Amanuallyoperatedisolationvalveatthesamplechamberinletisprovidedtopermitpurgingofthesamplechambertofacilitatebackgroundactivitychecks.Asourceofnoncontaminatedwaterisprovidedfordecontaminationpurposes.Samplechambersinwhichpermanentcontaminationinterfereswithmeasurementcanreadilybereplaced.Liquidmonitoralarmsareannunciatedinthecontrol roomontheplantannunciator,theNPIScomputer,andtheradiationmonitoringsystemCRT(RM-11).TheNPIScomputerlocatedintheTSCprovidesavisualdisplayofalarmstatus.TheRM-11inthecontrolroomprovidesaudibleandvisualalarmindication.Theliquidradioactivitymonitorsarelocatedtocomplywiththedesignbases.
Thespecificsamplepointsareselectedtoproviderepresentativesamplesof thesystemsmonitored,toreducesampletransporttimes,andtolimitthe amountofradioactivityreleasedintheeventofahighradioactivitysignal.Thecontinuousliquidradioactivitymonitoringsystemsarediscussedinthefollowingsections.Asummaryofthefunctionsandcharacteristicsofeach monitorispresentedinTables11.5-1and11.5-2.11.5-6Rev.14 WOLFCREEK11.5.2.2.2LiquidProcessRadioactivityMonitorsAdetailedlistingofliquidprocessmonitorparametersisgiveninTable11.5-1.11.5.2.2.2.1ComponentCoolingWaterMonitorsThecomponentcoolingwatersystem(CCWS)isdiscussedinSection9.2.2.
TheCCWSradioactivitymonitors,0-EG-RE-9and0-EG-RE-10,detect,indicate,andalarmelevatedradiationlevelsintheCCWS.TheelevatedradiationlevelswouldbeindicativeofradioactiveleakageintotheCCWSfromsystemsandcomponentsservedbytheCCWS.EachdetectorassemblyreceivesacontinuoussampleflowwhenanassociatedCCWSpumpisoperating.TheCCWSpumpsprovidethemotiveforceforthesampleflow.EachdetectorsampleistakenfromtheCCWSupstreamoftheCCWheatexchangerandthesampleisreturnedtotheCCWSdownstreamoftheheatexchanger.Thealertalarmprovidesindicationofradioactiveinleakagetothesystem.Ahighalarmisprovidedtoindicateincreasingradioactivitylevelsandtoclosethecomponentcoolingwatersurge tankairventandmakeupwatervalves.11.5.2.2.2.2SteamGeneratorLiquidRadioactivityMonitorThesteamgeneratorliquidsamplesystemisdiscussedinSection9.3.2.
Thesteamgeneratorliquidradioactivitymonitor,0-SJ-RE-2,continuouslymonitorstheblowdownfromthesteamgenerators,eitherindividuallyor collectively,todetect,indicate,andalarmprimary-to-secondarysystemleaks inthesteamgenerators.Thismonitorclosesthesteamgeneratorblowdown isolationvalvesonhighradiationtopreventthedischargeofradioactive fluidandtolimitradioactivecontaminationoftheblowdowndemineralizers.
Themonitoralsoprovidesbackupinformationandverificationofthecondenser airremovalsystemgaseousradioactivitymonitor(Section11.5.2.3.2.1).The fixed-volumedetectorassemblyreceivesacontinuousflowfromthesteam generatorliquidsampleheaderwhichsamplesthetubesheetareanearthe minimumwaterlevelofthesteamgenerators.Thesamplepointislocated downstreamofthesamplesystemheatexchangertoprovideconditioningand pressurereductionoftheradioactivitymonitorsample.Theradioactivity alarmsprovideindicationofprimary-to-secondaryleakageinthesteam
generator.11.5-7Rev.11 WOLFCREEK11.5.2.2.2.3SteamGeneratorBlowdownProcessingSystemRadio-activityMonitorThesteamgeneratorblowdownprocessingsystemisdiscussedinSection10.4.8.
Thesteamgeneratorblowdownprocessradioactivitymonitor,0-BM-RE-25,continuouslymonitorsthefluidenteringthesteamgeneratorblowdownfilterstodetect,alarm,andindicateexcessiveradioactivitylevelsintheblowdown system.Thesteamgeneratorblowdownprocessradioactivitymonitoractsto terminateblowdownfromthesteamgeneratorstopreventdischargeof radioactivefluidandtolimitradioactivecontaminationoftheblowdowndemineralizers.Themonitorprovidesbackupinformationforthesteamgeneratorliquidradioactivitymonitor(Section11.5.2.2.2.2)andthecondenserairremovalgaseousradioactivitymonitor(Section11.5.2.3.2.1)forthedetectionofaprimary-to-secondaryleakageinthesteamgenerator.Thefixed-volumedetectorassemblyreceivesacontinuousflowfromthedischargeoftheblowdownsystemheatexchangersandreturnsthesampletothesystem.Thesamplelocationprovidesanunfilteredsampleattemperatureswithinthelimits ofthedetector.Thehighradioactivityalarmclosesthesteamgenerator blowdownisolationvalvesandtheblowdownsystemdischargevalvetoterminate blowdownandpreventdischargeofradioactivityfromthesteamgenerators.11.5.2.2.2.4BoronRecycleSystemDistillateRadioactivity MonitorTheboronrecyclesystemisdiscussedinSection9.3.6.
Theboronrecycleradioactivitymonitor,0-HE-RE-16,ispermanentlyoutofserviceandnolongerused11.5-8Rev.14 WOLFCREEK11.5.2.2.2.5ChemicalandVolumeControlSystemLetdownMonitorThechemicalandvolumecontrolsystem(CVCS)isdiscussedinSection9.3.4.TheCVCSletdownradioactivitymonitor,0-SJ-RE-01,actsasagrossfailedfueldetector.Thefixed-volumedetectorassemblycontinuouslymonitorstheCVCS letdownsamplelinewhichextractsasampleupstreamoftheCVCSletdown demineralizers.Theradiationalarmsalerttheoperatortoanabnormal increaseingrossgammaactivityintheCVCSletdownsystem.Determinationofthecausecanbemadebylaboratoryanalysis.Thesamplelocationprovidesanunfilteredsamplepriortodemineralization.Thearrangementandlocationofthesamplelineprovidesufficientdelayintransporttoallowdecayofnitrogen-16,whichcouldcauseerroneouslyhighreadings.11.5.2.2.2.6AuxiliarySteamSystemCondensateRecoveryMonitorTheauxiliarysteamsystemisdiscussedinSection9.5.9.Theauxiliarysteamcondensaterecoveryradioactivitymonitor,0-FB-RE-50,detectsradioactivecontaminationfromthepotentiallyradioactivesystems whichdischargetotheauxiliarysteamcondensaterecoverytank.Thefixed-volumedetectorassemblycontinuouslymonitorsthedischargeoftheauxiliary steamcondensatetransferpumps.Theradioactivityalarmsalerttheoperator topossiblecontamination,isolatesauxiliarysteamsupplytotheradwastebuildingandtripstheauxiliarysteamcondensatetransferpumps.Thesourceofthecontaminationcanbedeterminedbyselectiveisolationofthe potentiallyradioactivesystems.Thesamplelocationensuresthatallpotentiallyradioactivesourcesaremonitored.11.5-9Rev.14 WOLFCREEK11.5.2.2.3LiquidEffluentRadioactivityMonitorsAdetailedlistingoftheliquideffluentmonitorparametersisgiveninTable 11.5-2.11.5.2.2.3.1SteamGeneratorBlowdownDischargeRadioactivity MonitorThesteamgeneratorblowdownsystemisdiscussedinSection10.4.8.
Thesteamgeneratorblowdowndischargeradioactivitymonitor,0-BM-RE-52,continuouslymonitorstheblowdowndischargepumpoutlettodetect radioactivityduetosystemdemineralizerbreak-throughandtoprovidebackuptothesteamgeneratorblowdownprocessradioactivitymonitor(Section11.5.2.1.2.3)topreventdischargeofradioactivefluid.Thesamplepointis locatedonthedischargeofthepumpinordertomonitordischargeorrecycled blowdownfluidandupstreamofthedischargeisolationvalvetolimittheradioactivityreleased.Thehighradioactivityalarmactstoclosetheblowdownisolationvalvesandtheblowdowndischargevalve.Aweeklylaboratoryisotopicanalysisismadeforanyliquiddischarged,inconformancewithRegulatoryGuide1.21.11.5.2.2.3.2LiquidRadwasteDischargeMonitorTheliquidradwastesystemisdiscussedinSection11.2.Theliquidradwasteradiationmonitor,0-HB-RE-18,continuouslymonitorsthedischargeoftheliquidradwasteprocessingsystemtopreventthedischargeofradioactivefluidtotheenvirons.Thefixed-volumedetectorassemblycontinuouslymonitorsthesystemdischargelineupstreamofthedischargevalve.Thehighradioactivityalarmclosestheliquidradwastesystemdischargevalvetoterminatedischarge.Thesamplepointislocatedtoensurethatallpotentiallyradioactivefluidsfromtheliquidradwasteprocessingsystemaremonitoredpriortodischarge.Laboratoryisotopicanalysesaremadeofeachbatchpriortodischarge,asrequiredbyRegulatoryGuide1.21andtheplantTechnicalSpecifications.11.5-10Rev.8 WOLFCREEK11.5.2.2.3.3SecondaryLiquidWasteSystemMonitorThesecondaryliquidwastesystemisdiscussedinSection10.4.10.Thesecondaryliquidwastesystemdischargeradioactivitymonitor,0-HF-RE-45,monitorssecondaryliquidwastesystemeffluentspriortodischargetotheenvirons.Thefixed-volumedetectorassemblycontinuouslymonitorsthe dischargelineupstreamofthedischargeisolationvalve.Thehigh radioactivityalarmclosesthesecondaryliquidwastesystemdischargevalveto preventthedischargeofradioactivefluid.Thesamplelocationensuresthatallpotentiallyradioactivesourcesfromthesystemaremonitoredpriortodischarge.Laboratoryisotopicanalysesaremadeofeachbatchpriortodischarge,inaccordancewithRegulatoryGuide1.21.11.5.2.2.3.4TurbineBuildingDrainMonitorTheturbinebuildingdraineffluentradioactivitymonitor,0-LE-RE-59,isprovidedtomonitorturbinebuildingliquideffluentspriortoreleasetotheenvirons.Thefixed-volumedetectorassemblycontinuouslymonitorsthedraineffluentlineupstreamofthedrainlineisolationvalve.Thehigh radioactivityalarmclosesthedrainlineisolationvalvetopreventthe releaseofradioactivefluids.Thesamplelocationensuresthatall potentiallyradioactiveturbinebuildingliquideffluentsaremonitoredpriortodischarge.Aweeklyisotopicanalysisismadeinthelaboratory,inconformancewithRegulatoryGuide1.21.11.5.2.2.3.5WastewaterTreatmentSystemMonitorRadioactivitymonitorHF-RE-95monitorsthedischargefromthehighandlowTDScollectiondraintankstotheWastewaterTreatmentSystem.Thefixedvolume detectorassemblycontinuouslymonitorsthedischargelineupstreamofthe dischargeisolationvalve.Thehighradioactivitysetpointwillclosethedischargeisolationvalveautomaticallytoterminatethereleaseofradioactivefluid.Thisdischargeisnormallynotradioactiveandwouldremainsounlessa primarytosecondarysteamgeneratortubeleakwouldoccur.Suchatubeleakandresultantradioactivityreleasefromtheprimarysystemwouldfirstbe detectedinthesteamgeneratorliquidradiationmonitor(SJ-RE-02)steam generatorblowdownprocessradiationmonitor(BM-RE-25)steamgeneratordischargeradiationmonitor(BM-RE-52)and/orcondenserairdischargemonitor (GE-RE-92).11.5-11Rev.8 WOLFCREEK11.5.2.3AirborneMonitoringSystems11.5.2.3.1SelectionCriteriaforAirborneMonitors11.5.2.3.1.1Introduction Thetypeoffixedinstrumentationusedformonitoringairborneradioactivityisoffline.Theofflinesystemextractsasamplefromtheprocessstreamandtransportsthatsampletotheradioactivitymonitoringsystem,whichcontainsthespecifiedequipmenttodetectparticulates,halogens,and/ornoblegases.11.5.2.3.1.2SamplingCriteriaThesamplingsystemfortheparticulate/halogen/noblegasmonitorsisdesignedandinstalledtomeettheintentofANSIN13.1-1969.Systemswhosesensitivityisdependentuponsampleflowemployisokineticnozzlesandsuitablecontrolofflowrate.11.5.2.3.1.3DetectionCriteriaSincebothradioactiveparticulatesandradioactivenoblegasesarebetaemitters,betasensitivescintillationdetectorsareusedtosense radioactivityinordertominimizetheeffectsduetobackgroundradiationand, consequently,obtainalowerminimumdetectableconcentration.Wherespectrometricanalysisisrequired(suchasiniodinemonitoring)anNaI(Tl),gammascintillationdetectorassemblyisemployed.11.5.2.3.1.4InstrumentationCriteriaInstrumentationnecessarytoindicate,alarm,andperformcontrolfunctionsisprovidedtocompletethemonitoringsystem.Sinceradioactiveconcentrationsmayvarysubstantially,widerangeinstrumentsareutilized.Allairborneradiationmonitorsincludeprovisionsforobtaining agrabsampleforlaboratoryisotopicanalysis.Theparticulateandcharcoal filterscanreadilyberemovedforperiodicisotopiclaboratoryanalyses,as requiredbytheTechnicalSpecifications.Theairborneparticulatemonitorseachconsistofafixedfilteruponwhichradioactiveparticulatematterisdeposited.Thefixedfilterislocatedin frontofabetascintillationdetectorcoupledtoaphotomultipliertube.Eachairborneiodinemonitorconsistsofacharcoalcartridgeuponwhichiodineisadsorbed.Theairsampleisprefilteredtoremoveparticulates.The charcoalcartridgeislocatedinfrontofagammascintillationdetector coupledtoaphotomultipliertube.11.5-12Rev.4 WOLFCREEKEachairbornenoblegasmonitorconsistsofafixed-volumesamplechamberthroughwhichprefilteredsampleairispassed.Abetascintillationdetectorislocatedwithinthesamplechambertodetecttheactivityleveloftheair sample.Allofthedetectorsandsamplechambersareenclosedinheavilyshieldedleadpigs.Twomotor-operatedvalvesoperatedlocallyareprovidedtopermitair-purgingofthesamplechambertofacilitatebackgroundactivitychecks.ThesensitivitiesandalarmsetpointsaregiveninTables11.5-3and11.5-4.Thealert-alarmpointsarebasedonthemethodologiespresentedintheODCM.11.5.2.3.2AirborneProcessRadioactivityMonitorsAdetailedlistingofairborneprocessmonitorparametersisgiveninTable 11.5-3.11.5.2.3.2.1CondenserAirDischargeMonitorThecondenserairdischargemonitor,0-GE-RE-92,isprovidedtodetect,indicate,andalarmgaseousactivityinthecondenserairremovalsystem exhaust.Thecondenserairdischargemonitorclosesthesteamgenerator blowdownisolationvalvesonhighradiationtopreventdischargeofradioactive fluidandtolimitradioactivecontaminationoftheblowdowndemineralizers.
Themonitorisalsoequippedwithparticulateandiodinefilterswhichare removedandanalyzedinthelaboratory.Thismonitorprovidesbackuptothe steamgeneratorliquidandthesteamgeneratorblowdownprocessingradiation monitorsfordetectionofprimary-to-secondaryleaksinthesteamgenerator.Thecondenserairremovalsystemremovesnoncondensablegaseswhichwouldbe presentifaprimary-to-secondaryleakoccurred.Particulateandiodineswould alsoberemovedbyentrainmentintheairdischarged.Themonitorisprovidedwithanozzletoextractarepresentativesamplefromtheexhaustduct.Asamplecoolerisprovidedtodrythesamplepriortoenteringthesamplefiltersorthefixed-volumegaseousdetectorassemblyto precludedamagetothefiltersortothedetector.Thesamplepointislocated upstreamofthecondenserairremovalsystemfilters.Theradiationalarmsalerttheoperatortothepresenceofgaseousactivityandthepossibilityofsteamgeneratortubeleakage.11.5-13Rev.7 WOLFCREEK11.5.2.3.2.2ContainmentAtmosphereRadioactivityMonitorsThecontainmentatmosphereradioactivitymonitors,0-GT-RE-31and0-GT-RE-32,continuouslymonitorthecontainmentatmosphereforparticulate,iodine,andgaseousradioactivity.TheyisolatethecontainmentpurgesystemonhighgaseousactivityviatheESFAS.SeeSections7.3.2and9.4.6forfurther discussionofthisfunction.Thesemonitorsalsoserveforreactorcoolantpressureboundaryleakagedetection(SeeSection5.2.5foradetaileddescriptionofthisfunction)andforpersonnelprotection(seeSection12.3.4 foradetaileddescriptionofthisfunction).Thecontainmentatmosphere radioactivitymonitorsprovidebackupindicationforthecontainmentpurgemonitors.TheseseismicCategoryImonitorsarecompletelyredundant.Samplesareextractedfromtheoperatingdecklevel(El.2047'-6")throughsamplelineswhichpenetratethecontainment.Themonitorsarelocatedascloseaspossibletothecontainmentpenetrationstominimizethelengthofthesampletubingandtheeffectsofsampleplateout.Thesamplepointsarelocatedinareaswhichensurethatrepresentativesamplesareobtained.Eachsamplepassesthroughthepenetration,thenthroughthefixedfilter(particulate),charcoalfilter(iodine),andfixed-volumegaseousdetectorassemblies.Afterpassingthroughthepumpingsystem,thesampleisdischarged backtothecontainmentthroughaseparatepenetration.Indicationisprovidedforeachmonitoronindividualindicatorsontheradioactivitymonitoringsystemcontrolpaneland,throughisolatedsignals,on theradioactivitymonitoringsystemCRTinthecontrolroom.11.5.2.3.2.3ContainmentPurgeSystemRadioactivityMonitorsThecontainmentpurgesystemradioactivitymonitors,0-GT-RE-22and0-GT-RE-33,continuouslymonitorthecontainmentpurgeexhaustductduringpurgeoperationsforparticulate,iodine,andgaseousradioactivity.Thepurposeofthesemonitorsistoisolatethecontainmentpurgesystemonhighgaseousactivity viatheESFAS.SeeSections7.3.2and9.4.6foradditionalinformation concerningthisfunction.Thesemonitorsalsoserveasbackupindicationforpersonnelprotection(seeSection12.3.4)andreactorcoolantpressureboundaryleakagedetection(seeSection5.2.5)forthecontainmentatmosphere radioactivitymonitors.TheseseismicCategoryImonitorsarecompletelyredundant.Thesamplepointsarelocatedoutsidethecontainmentbetweenthecontainmentisolationdampersandthecontainmentpurgefilteradsorberunit.11.5-14Rev.0 WOLFCREEKEachmonitorisprovidedwithtwoisokineticnozzlestoensurethatrepresentativesamplesareobtainedforbothnormalpurgeandminipurgeflowrates.Isokineticnozzleselectionisaccomplishedbysampleselectorvalveswhichautomaticallyalignthecorrectnozzletothemonitorbasedonoperation oftheminipurgeandnormalpurgeexhaustsystems.Thesampleisextracted throughtheselectednozzleandthenpassedthroughtheselectorvalve,thefixedfilter(particulate),charcoalfilter(iodine),andfixed-volumegaseousdetectors.Thesamplethenpassesthroughthepumpingsystemandisdischarged backtotheduct.Indicationisprovidedforeachmonitoronindividualindicatorsontheradioactivitymonitoringsystemcontrolpaneland,throughisolatedsignals,ontheradioactivitymonitoringsystemCRTinthecontrolroom.11.5.2.3.2.4ContainmentHighRangeRadiationMonitorsThecontainmentdigitalhighrangeradiationmonitor(DHRRM)systemincludestworedundantmonitors,0-GT-RT-59and0-GT-RT-60,todetectandindicategammaradiationlevelsinthecontainmentoverarangefrom1rad/hrto10 8 rads/hr.TheDHRRMalsoprovidesanalarmfunction.EachDHRRMsubsystemconsistsofagammaradiationdetector,amicroprocessor,junctionbox,andcontrol/displaymodule.Thesubsystemsaresafetyrelated anddesignedandqualifiedtoIEEE323-1974forthenormalandaccident environmentsfortheirinstalledlocations.Thesubsystemsarealsodesigned andqualifiedtobeseismicCategoryI.Thedetectorlocationsareindicated onFigure12.3-2,Sheet4.Detectorsaremountedontheinsidesurfaceofthe containmentwallatEl.2052'-0"forGT-RE-60andatEl.2073'-0"forGT-RE-59.
TheDHRRMsubsystemsarealsoconnectedtotheprocessandeffluentradiation monitoringsystem(opticallyisolated)forreadoutontheCRT(SPO-56A)inthe controlroom.11.5.2.3.2.5Auxiliary/FuelBuildingVentilationExhaustRadioactivity MonitorTheAuxiliary/Fuelbuildingventilationexhaustradiationmonitors0-GG-RE-27and0-GG-RE-28,continuouslymonitorforparticulate,iodine,andgaseousradioactivityintheAuxiliary/Fuelbuildingventilationexhaustsystem.Intheeventofafuelhandlingaccident,thesemonitorsfunctiontoisolatethenormalventilationandstartuptheemergencyventilationsystemonhighgaseousactivityviatheESFAS.Sections7.3.3and9.4.2haveadditionalinformationaboutthisfunction.Thesemonitorshaveanadditionalfunctionto alertworkerstohighairborneradioactivityinthefuelbuilding.Thislatter functionisdiscussedinSection12.3.4.11.5-15Rev.14 WOLFCREEKTheseseismicCategoryImonitorsarecompletelyredundant.Duringnormaloperation,eachmonitorextractsasamplefromthenormalexhaustductthroughindividualisokineticnozzlesandsampleselectorvalves.Thisnormalsamplepointisupstreamofthefuelbuildingnormalexhaustfilteradsorberunit.Whentheemergencyventilationsystemisinuse,thecapabilityisprovidedfromthecontrolroomtotransferthesamplepointsviasampleselectorvalves toisokineticnozzleslocatedinthefuelbuildingemergencyexhaustsystemupstreamoftheemergencyexhaustfilteradsorberunits,withonemonitor alignedtoeachemergencyexhaustduct.Indicationisprovidedbyindividualindicatorsontheradioactivitymonitoringsystemcontrolpaneland,throughisolatedsignals,bytheradioactivity monitoringsystemCRTinthecontrolroom.11.5.2.3.2.6ControlRoomVentilationRadioactivityMonitorThecontrolroomventilationradioactivitymonitors,0-GK-RE-04and0-GK-RE-05,continuouslymonitorthesupplyairofthenormalheating,ventilation,and air-conditioningsystemforparticulate,iodine,andgaseousradioactivityto provideprotectionforthecontrolroomoperators.ThesemonitorsfunctionautomaticallytoswitchthecontrolroomfromthenormaltotheemergencyventilationsystemonhighgaseousactivityviatheESFAS.SeeSections6.4, 7.3.4,and9.4.1formoredetails.Thesemonitorsalsofunctiontoalertthe operatorstohighairborneradioactivityinthecontrolroomventilation supply.ThisfunctionisdescribedinSection12.3.4.TheseseismicCategoryImonitorsarecompletelyredundant.Samplesareextractedthroughindividualisokineticnozzles,andflowthroughthefixedfilter(particulate),charcoalfilter(iodine),andfixed-volume gaseousdetectorassembliespriortopassingthroughthepumpingsystemfor
discharge.Indicationforthesemonitorsisprovidedonindividualindicatorsonthe radioactivitymonitoringsystemcontrolpaneland,throughisolatedsignals,on theradioactivitymonitoringsystemCRTinthecontrolroom.11.5.2.3.3AirborneEffluentRadioactivityMonitorsAdetailedlistingofairborneeffluentmonitorparametersisgiveninTable 11.5-4.11.5-16Rev.8 WOLFCREEK11.5.2.3.3.1UnitVentRadioactivityMonitorTheunitventradioactivitymonitor,0-GT-RE-21,continuouslymonitorstheeffluentfromtheunitventforparticulate,iodine(halogen),andgaseousradioactivity.Theunitvent,viaventilationexhaustsystems,continuouslypurgesvarioustanksandsumpsnormallycontaininglow-levelradioactive aeratedliquidsthatcanpotentiallygenerateairborneactivity.Theexhaustsystemswhichsupplyairtotheunitventarefromthefuelbuilding,auxiliarybuilding,theaccesscontrolarea,thecontainmentpurge, andthecondenserairdischarge.Allofthesesystemsarefilteredbeforetheyexhausttotheunitvent.Theunitventmonitormeasuresactualplanteffluentsandnotinplant concentrations.Thus,thesystemcontinuouslymonitorsdownstreamofthelast pointofpotentialradioactivityentry.Themonitoringsystemconsistsofan off-line,three-wayairborneradioactivitymonitor.Anisokineticsampling probeislocateddownstreamofthelastpointofpotentialradioactivityentry forsamplecollection.TheAlertalarmsaresetbelowtheHighalarmstoactasprecautionarywarnings.TheHighalarmissettoensurethatTechnicalSpecificationlimits arenotexceeded.(SeeOffsiteDoseCalculationManual.)RefertoTable11.5-4forthealertandhighalarmsetpoints,therange,andthesensitivity.Portionsofthesampletubinglocatedoutsidethebuildingareadequatelyprotectedandroutedtopreventtheaccumulationandfreezingofcondensate.
Thesampleextractedbytheisokineticnozzleispassedthroughthefixed filter(particulate),charcoalfilter(iodine),andfixed-volume(gaseous) detectorassembliesandthenthroughthepumpingsystemfordischargebacktotheunitvent.IndicationisprovidedontheradioactivitymonitoringsystemCRTinthecontrolroom.Thismonitorprovidesasignaltotheradioactivereleasereport generationsystemdescribedinSection11.5.2.1.1.11.5.2.3.3.2RadwasteBuildingVentilationEffluentRadioactivity MonitorTheradwastebuildingventilationeffluentradiationmonitor,0-GH-RE-10,continuouslymonitorsforparticulate,halogen,andgaseousradioactivityin theeffluentductdownstreamoftheexhaustfilterandfans.Thesamplepoint islocateddownstreamofthelastpossiblepointofradioactiveinfluent, includingthe11.5-17Rev.0 WOLFCREEKwastegasdecaytankdischargeline.Theflowpathprovidesventilationexhaustforallpartsofthebuildingstructureandcomponentswithinthebuildingandprovidesadischargepathforthewastegasdecaytankreleaseline.Thesecomponentsrepresentpotentialsourcesforthereleaseofgaseous andairparticulateandiodineactivitiesinadditiontothedrainagesumps, tanks,andequipmentpurgedbythewasteprocessingsystem.Themonitoringsystemconsistsofafixedfilterparticulatemonitor,aniodinemonitor,andgaseousactivitymonitor.Thesampleisextractedthroughanisokineticnozzletoensurethatarepresentativesampleoftheairisobtainedpriortoreleasetotheenvironment.Afterpassingthroughthefixedfilter(particulate),charcoalfilter(halogen),andfixed-volume(noblegas)detectorassembliesandthepumpingsystem,thesampleisdischargedbacktotheexhaustduct.ThesensitivitiesandalarmsetpointsaregiveninTable11.5-4.TheAlertalarmissetbelowtheHighalarmtoactasaprecautionarywarning.TheHigh alarmissettoensurethatTechnicalSpecificationlimitsarenotexceeded.
(SeeOffsiteDoseCalculationManual.)IndicationofthismonitorisprovidedontheradiationmonitoringsystemCRTinthecontrolroom.ThismonitorprovidesasignaltotheNPIScomputerintheTSCcomputerroom,(seeSection11.5.2.1.1).Thismonitorisolatesthewastegasdecaytankdischargelineifthe radioactivityreleaserateisabovethepresetlimitwhenthewastegas dischargevalvehasbeendeliberatelyorinadvertentlyopened.11.5.2.4SafetyEvaluationThecontrolroomventilationmonitors,thecontainmentatmospheremonitors,thecontainmentpurgemonitors,thecontainmentLOCAatmospheremonitors,andthe fuelbuildingexhaustmonitorsareredundant,independent,seismicCategoryI, withClassIEpowersupplies.Thecontrolroomandfuelbuildingmonitorswill automaticallyswitchfromthenormaltotheemergencyventilationsystemson highgaseousactivityviatheESFAS.Thecontainmentatmosphereand containmentpurgemonitorswillautomaticallyisolatethecontainmentpurgeand stopthefansonhighgaseousactivityviatheESFAS.11.5-18Rev.14 WOLFCREEK11.5.3EFFLUENTMONITORINGANDSAMPLINGAllpotentiallyradioactiveeffluentdischargepathsarecontinuouslymonitoredforgrossradiationlevel.Liquidreleasesaremonitoredforgrossgamma.Airbornereleasesaremonitoredforgrossbetaactivity(particulatesandnoblegases)andgrossgamma(iodines).Anisotopicanalysisisperformedonsamplesobtainedfromeachcontinuouseffluentreleasepathandperbatchforeachbatchtypeeffluentreleasepath inordertoverifytheadequacyofeffluentprocessingtomeetthedischargelimitstounrestrictedareas.Thiseffluentsamplingprogramisofsucha comprehensivenatureastoprovidetheinformationfortheeffluentmeasuring andreportingprogramsrequiredby10CFR50Part36AandAppendixIandRegulatoryGuide1.21inannualreportstotheNRC.Theeffluentreleasedataiscompiledandtheannualeffluentreportisgenerated.ByacombinationoftheinstalledequipmentdescribedpreviouslyinSection 11.5andtheinstalledequipmentdescribedinSection12.3.4,alongwithportableequipmentdescribedinSection12.5,andtheEmergencyPlan,the requirementsofGeneralDesignCriterion64tomonitornormaloperations, anticipatedoperationaloccurrences,andpostulatedaccidentsaremet.11.5.4PROCESSMONITORINGANDSAMPLINGAllpotentiallysignificantradioactivesystemswhichleadtoeffluentdischargepathsareequippedwithacontrolsystemtoautomaticallyisolatethe dischargeonindicationofahighradioactivitylevel.Theseincludethe containmentpurgesystem,thefuelbuildingventilationsystem,andthegaseous andliquidradwastesystems.Batchreleasesaresampledandanalyzedpriorto discharge,inadditiontothecontinuouseffluentmonitoring.Bymeansofthecontinuousradioactivitymonitorsmentionedaboveandtheirassociatedcontrolvalves,andduetotheextensivesamplingprogramdescribedintheEnvironmentalReport,GeneralDesignCriterion60andtheRadiological EffluentTechnicalSpecificationsaremetwithregardtothecontrolofreleasesofradioactivitytotheenvironment.ProcessmonitoringisaccomplishedbycontinuousradioactivitymonitorsdiscussedinSections11.5.2.2.2and11.5.2.3.2.Bymeansofthecontinuousradioactivitymonitors,GDC-63ismetwithregardtomonitoringradioactivity levelsintheradioactivewasteprocesssystems.11.5-19Rev.7 WOLF CREEK
TABLE 11.5-1 LIQUID PROCESS RADIOACTIVITY MONITORS Sample Control- Hi Hi-Hi Flow Monitor Monitor Type Range MDC (1) ling Alarm Alarm Rate Control Number Description (continuous) Detection ( Ci/cc) (Ci/cc) Isotope ( Ci/cc) (Ci/c) (gpm) Function O-EG-RE-9 Component Liquid NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 1 X 10
-5 (3) 1 X 10
-4(4) 1-5 (9) Isolates O-EG-RE-10 cooling gamma air vents water scintilla- and makeup monitor tion water valves on component cooling water surge tanks on Hi-Hi alarms O-SJ-RE-2 Steam gener- Liquid (2) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 1 X 10
-5 (3) 1 X 10
-4(4) 1-5 Closes ator liquid gamma blowdown radioactiv- scintilla- isolation ity monitor tion valves on Hi-Hi alarm O-BM-RE-25 Steam gener- Liquid (2) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 1 X 10
-5 (3) 1 X 10
-4(4) 1-5 Closes ator blowdown gamma blowdown processing scintilla- isolation system monitor tion Hi-Hi alarms
O-SJ-RE-01 Chemical and Liquid NaI (T1) 1.7E-3 to NA --- (7) (8) .2-1 Alarms volume cont- gamma 1.7E+3 trol system scintilla-letdown tion
monitor
O-FB-RE-50 Auxiliary Liquid NaI(T1) 10
-7 to 10-2 1 X 10-6 Cs-137 1 X 10
-5 (3) 1 X 10
-4(4) 1-5 Hi-Hi alarm steam system gamma isolates condensate scintilla- auxiliary recovery tion steam monitor supply to radwaste building a trips auxiliary steam con-densate transfer pumps
Rev. 28 WOLF CREEK
TABLE 11.5-1 (Sheet 2)
LIQUID PROCESS RADIOACTIVITY MONITORS
Sample Control- Hi Hi-Hi Flow Monitor Monitor Type Range MDC (1) ling Alarm Alarm Rate Control Number Description (continuous) Detection (Ci/cc) (Ci/cc) Isotope (Ci/cc) (Ci/cc) (gpm) Function O-FB-RE-50 Auxiliary Liquid (2) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 1 X 10
-5 (3) 1 X 10
-4(4) 1-5 Hi-Hi alarm steam system gamma isolates condensate scintilla- auxiliary recovery tion steam monitor supply to radwaste building and trips auxiliary steam con-densate transfer pumps
(1) MDC - minimum detectable concentration.
(2) When in operation.
(3) One order of magnitude above MDC to avoid spurious alarms and to indicate the leakage of radioactivity into an otherwise nonradioactive system. Setpoint may be changed based on plant conditions to provide prompt indication of increased leakage.
(4) Two orders of magnitude above MDC to indicate significant inleakage of radioactivity. Setpoint may be changed based on plant conditions to provide prompt indication of increased leakage.
(5) Only water cleaner than this is sent to the reactor makeup water storage tank.
(6) High activity may indicate evaporator operating problem.
(7) High activity may indicate a crud burst or iodine spiking. Alarm is varied based on normal to ensure the operators are alerted to changes in activity levels from normal.
(8) High activity may indicate a crudburst, iodine spiking, or failed fuel. Laboratory analyses are performed to determine cause. Alarm is varied based on normal to ensure the operators know that significant changes in activity have occurred.
(9) 1 - 5 gpm is a nominal or expected range when the CCW system is flowing at approximately 10,000 gpm or greater regardless of the temperature control valve (TCV 29 or 30) position. Sample flow rates are proportionately reduced for system flow rates less than 10,000 gpm and with the TCV open. The sample flow rate will range from about 0.3 gpm with the system flow rate at 3,000 gpm and the TCV open, to about 1 gpm with the system flow rate at 10,000 gpm and the TCV open. The sample flow rate will be 0 gpm when the CCW system flow rate is 0 gpm.
Rev. 28 WOLF CREEK
TABLE 11.5-2 LIQUID EFFLUENT RADIOACTIVITY MONITORS
Sample Control- Hi Hi-Hi Flow Monitor Monitor Type Range MDC (1) ling Alarm Alarm Rate Control Number Description (continuous) Detection ( Ci/cc) ( Ci/cc) Isotope ( Ci/cc) ( Ci/cc) (gpm) Function
O-HF-RE-45 Secondary Liquid (4) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 (7) (2) 1-5 Closes liquid waste gamma discharge system scintilla- valves on monitor tion Hi-Hi alarm 1-HF-RE-95 Wastewater Liquid (6) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 (3) (2) 1-5 Closes treatment gamma discharge system scintilla- valve on influent tion Hi-Hi alarm monitor O-HB-RE-18 Liquid rad- Liquid (4) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 (7) (2) 1-5 Closes waste dis- gamma discharge charge scintilla- valve on monitor tion Hi-Hi alarm O-LE-RE-59 Turbine Liquid (5) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 (3) (2) 1-5 Closes building gamma discharge drain scintilla- valve on monitor tion Hi-Hi alarm O-BM-RE-52 Steam gener- Liquid (4) NaI (T1) 10
-7 to 10-2 1 X 10-6 Cs-137 (3) (2) 1-5 Closes dis- ator blow- gamma charge and down discharge scintilla- blowdown monitor tion isolation valves on Hi-Hi alarm (1) MDC = minimum detectable concentration.
(2) Hi-Hi alarm is set to ensure that the ODCM limit is not exceeded and to initiate isolation before
the limit can be exceeded.
(3) The Hi alarm is set one order of magnitude below the Hi-Hi Alarm/Trip Setpoint for release points that have dilution and up to the Hi-Hi Alarm value for those without dilution.
(4) The monitor is to prevent inadvertent discharge valve opening and to ensure that any releases that
might become necessary are within limits. In accordance with the ODCM, batch analyses are performed before any releases are made.
(5) Normally, not radioactive since potentially radioactive drains are segregated from this waste stream.
(6) The monitor is to terminate inadvertent radioactive discharges to the wastewater treatment facility.
(7) The alert alarm is set to 80% of the Hi-Hi Alarm/Trip Setpoint.
Rev. 28 WOLF CREEK TABLE 11.5-3 AIRBORNE PROCESS RADIOACTIVITY MONITORS Total Minimum Control- Hi Hi-Hi Venti- Required Monitor
Type Range MDC (1) ling Alarm Alarm lation Sensitivity Control Monitor (continuous) (Ci/cc) (Ci/cc) Isotope (Ci/cc) (Ci/cc) Flow (cfm) (Ci/cc) Function O-GT-RE-31 Particulate (3) 10
-12 to 10-7 1 X 10-11 Cs-137 1 X 10
-8 (8) 1 X 10
-7 (7) 420,000 1 X 10
-7 (7) Isolates con-O-GT-RE-32 tainment purge, Containment Iodine (4) 10
-11 to 10-6 1 X 10-10 I-131 2 X 10
-8 (8) 2 X 10
-7 (7) 420,000 2 X 10
-7 (7) de-energizes atmosphere purge fans on monitors Gaseous (3) 10
-7 to 10-2 2 X 10
-7 Xe-133 2.06 X 10
-4 (13) 2.06 X 10
-3 (14) 420,000 1 X 10
-4 (7) Hi-Hi gaseous
activity via
the ESFAS (see
Section 7.3)
O-GT-RE-22 Particulate (3) 10
-12 to 10-7 1 X 10-11 Cs-137 1 X 10
-8 (8) 1 X 10
-7 (7) 20,000/4000 1 X 10
-7 (7) Isolates con-O-GT-RE-33 tainment purge, Containment Iodine (4) 10
-11 to 10-6 1 X 10-10 I-131 2 X 10
-8 (8) 2 X 10
-7 (7) 20,000/4000 2 X 10
-7 (7) de-energizes purge system purge fans on monitors Gaseous (3) 10
-7 to 10-2 2 X 10
-7 Xe-133 (12) (11) 20,000/4000 1 X 10
-4 (7) Hi-Hi gaseous
activity via
the ESFAS (see
Section 7.3)
O-GT-RE-59 Gamma (5) 1 to 10 8 rads 1 rad NA NA NA NA NA NA O-GT-RE-60 hr hr
Containment
high activity
monitors O-GE-RE-92 Gaseous 10
-7 to 10-2 2 X 10
-7 Xe-133 2 X 10
-6 (9) 2 X 10
-5 (10) 1000 NA Closes blow-Condenser (continuous) down isolation
air dis- (3), (6), (19) valve on charge Hi-Hi alarms
monitor Particulate
(lab analysis) (6)
Iodine (lab
analysis) (6)
O-GG-RE-27 Particulate (3) 10
-12 to 10-7 1 X 10-11 Cs-137 1 X 10
-8 (8) 1 X 10
-7 (7) 20,000 1 X 10
-7 (7) Initiates O-GG-RE-28 switch to fuel
Fuel build- Iodine (4) 10
-11 to 10-6 1 X 10-10 I-131 2 X 10
-8 (8) 2 X 10
-7 (7) 20,000 2 X 10
-7 (7) building ing exhaust emergency ven-
monitors(2) Gaseous (3) 10
-7 to 10-2 2 X 10
-7 Xe-133 1.62 X 10
-4 (15) 1.62 X 10
-3 (16) 20,000 1 x 10
-3 (7) tilation on
Hi-Hi gaseous
activity via
the ESFAS (see
Section 7.3)
O-GK-RE-04 Particulate (3) 10
-12 to 10-7 1 X 10-11 Cs-137 1 X 10
-8 (8) 1 X 10
-7 (7) 1950 1 X 10
-7 (7) Initiates O-GK-RE-05 switch to con-
Control Iodine (4) 10
-11 to 10-6 1 X 10-10 I-131 2 X 10
-8 (8) 2 X 10
-7 (7) 1950 2 X 10
-7 (7) trol room room air emergency ven-
supply Gaseous (3) 10
-7 to 10-2 2 X 10
-7 Xe-133 1.35 X 10
-4 (17) 1.35 X 10
-3 (18) 1950 1 x 10
-3 (7) tilation on monitors Hi-Hi gaseous
activity via
the ESFAS (see
Section 7.3)
Sample flow for each channel is 3 cfm (1) MDC = minimum detectable concentration.
(2) When fuel is in the building.
(3) Beta scintillation detector.
(4) Gamma scintillation detector.
(5) Gamma sensitive ion chamber.
(6) When in operation.
(7) 10 (DAC) on monitor maximum, which ever is less.
(8) DAC or one tenth of Hi Alarm, which ever is less.
(9) One order of magnitude above MDC to avoid spurious alarms and to indicate primary to secondary leakage. Setpoint may be changed based on plant conditions to provide prompt indication of increased leakage.
(10) Two orders of magnitude above MDC to indicate significant inleakage of radioactivity. Setpoint may be changed based on plant conditions to provide prompt indication of increased leakage.
(11) Hi-Hi alarm is set to ensure that Technical Specification limits (10 CFR 20 general population Dose Rate for the controlling isotopes at the boundary of the restricted area) are not exceeded. See ODCM. (12) See ODCM (13) Equivalent to 0.9 mR/hr submersion dose rate (may increase per Tech Spec Table 3.3-6)
(14) Equivalent to 9 mR/hr submersion dose rate (may increase per Tech Spec Table 3.3-6)
(15) Equivalent to 0.4 mR/hr submersion dose rate (16) Equivalent to 4 mR/hr submersion dose rate.
(17) Equivalent to 0.2 mR/hr submersion dose rate (18) Equivalent to 2 mR/hr submersion dose rate (19) GERE0092 is approved for a vacuum flow rate of 2.6 to 3.0 SCFM Rev. 29 WOLF CREEK
TABLE 11.5-4 AIRBORNE EFFLUENT RADIOACTIVITY MONITORS
Total Minimum Control- Hi Hi-Hi Venti- Dilu- Required Monitor Type Range MDC (1) ling Alarm Alarm lation tion Sensitivity Control Monitor (continuous) (Ci/cc) (Ci/cc) Isotope (Ci/cc) (Ci/cc) Flow (cfm) Factor (Ci/cc) Function O-GT-RE-21A Particulate (2) (11) 10
-12 to 10-7 1 X 10-11 Cs-137 1 x 10
-8 (9) 1 x 10
-7(10) 66,000 (4) (5) Alarms Plant unit vent Iodine (3) (11) 10
-11 to 10-6 1 X 10-10 I-131 6 x 10
-9 (9) 6 x 10
-8 (10) 66,000 (4) (5) (6) monitor
O-GT-RE-21B Gaseous (2) 10
-7 to 10 5 2 X 10
-7 Xe-133 (8) (7) 66,000 (4) (5)
Plant unit vent
monitor
O-GH-RE-10A Particulate (2) (12) 10
-12 to 10-7 1 X 10-11 Cs-137 1 x 10
-8 (9) 1 x 10
-7(10) 12,000 (4) (5) Hi-Hi alarm Radwaste isolates the building Iodine (3) (12) 10
-11 to 10-6 1 X 10-10 I-131 6 x 10
-9 (9) 6 x 10
-8(10) 12,000 (4) (5) waste gas decay exhaust tank discharge monitor line O-GH-RE-10B Gaseous (2) 10
-7 to 10 5 2 X 10
-7 Xe-133 (8) (7) 12,000 (4) (5) Hi-Hi alarm Radwaste isolates the Building waste gas decay Exhaust tank discharge Monitor line Sample flow for each channel is 3 cfm
(1) MDC = minimum detectable concentration.
(2) Beta scintillation detector.
(3) Gamma scintillation detector. (4) Dilution factor = vent flow rate in m3/sec Q (annual average). (5) Minimum required sensitivity of monitor in Ci/cc at maximum allowable annual average concentration of controlling isotope at monitor which will result in annual average Appendix I dose at the site boundary = population MPC for controlling isotope X 1 X 1 X 1 where the bioaccumulation factor is 1 for 100 bioaccumulation factor dilution factor noble gases and 1,000 for iodines and particulates. See Offsite Dose Calculation Manual.
(6) Grab samples are analyzed in the laboratory, and low iodine concentrations are calculated, using previously established ratios.
(7) Hi-Hi alarm is set to ensure that ODCM limits (the 10 CFR 20 general population MPCs for the controlling isotopes at the boundary of the restricted area) are not exceeded.
(8) Hi alarm is set to alert operators to that average concentration which, if maintained for a full year, would reult in the 10 CFR 50 Appendix I annual dose guidelines being reached.
See Offsite Dose Calculation Manual.
(9) 10% of Hi-Hi Alarm (10) ODCM calculated setpoint or monitor maximum ( Ci/cc) whichever is less. (11) O-GT-RE-21B may be used as an alternate sampler. (12) O-GH-RE-10B may be used as an alternate sampler.
Rev. 25 WOLF CREEK TABLE 11.5-5 POWER SUPPLIES FOR PROCESS AND EFFLUENT MONITORS Liquid Process Radioactivity Monitors (non-IE)
Normal Restored After Monitor Name Power Loss of Offsite
and Number Supply Power Component cooling water Non-IE MCCs No
0-EG-RE-9 0-EG-RE-10 Steam generator Non-IE MCCS No liquid radioactivity
0-SJ-RE-2 Steam generator Non-IE MCCs No blowdown processing
system 0-BM-RE-25 Boron recycle Non-IE MCCs No
system distillate
0-HE-RE-16 CVCS letdown Non-IE MCCs No 0-SJ-RE-01 Auxiliary steam Non-IE MCCs No system liquid condensate recovery
0-FB-RE-50 Rev. 8 WOLF CREEK TABLE 11.5-5 (Sheet 2)
Liquid Effluent Radioactivity Monitors (Non-IE)
Normal Restored After Monitor Name Power Loss of Offsite
and Number Supply Power Secondary liquid Non-IE MCCS No waste system
0-HF-RE-45
Wastewater treatment Non-IE MCCS No system influent 1-HF-RE-95 Liquid radwaste Non-IE MCCs No discharge 0-HB-RE-18
Turbine building Non-IE MCCs No
drain 0-LE-RE-59
Steam generator Non-IE MCCs No
blowdown discharge
0-BM-RE-52 Airborne Process Radioactivity Monitors (Class IE)
Containment Class IE MCCs Yes atmosphere
0-GT-RE-31
0-GT-RE-32
purge system
0-GT-RE-22
0-GT-RE-33
Containment high Class IE MCCs Yes
activity monitors
0-GT-RE-59
0-GT-RE-60
Fuel building Class IE MCCs Yes
exhaust 0-GG-RE-27
0-GG-RE-28
Control room Class IE MCCs Yes
air supply
0-GK-RE-04
0-GK-RE-05 Rev. 4 WOLF CREEK TABLE 11.5-5 (Sheet 3)
Airborne Process Radioactivity Monitor (Non-IE)
Normal Restored After Monitor Name Power Loss of Offsite
and Number Supply Power Condenser air Non-IE MCC No
discharge 0-GE-RE-92 Airborne Effluent Radioactivity Monitors (Non-IE)
Plant unit Non-IE MCCs No vent 0-GT-RE-21 Radwaste building Non-IE MCCs No exhaust 0-GH-RE-10 Rev. 0