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| {{#Wiki_filter:SSES-FSAR Text Rev. 56 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS Certain structures, components, and systems of the nuclear plant are considered important to safety because they perform safety actions required to avoid or mitigate the consequences of abnormal operational transients or accidents. The purpose of this section is to classify structures, components, and systems, according to the importance of the safety function they perform. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when required. | | {{#Wiki_filter:SSES-FSAR Text Rev. 56 |
| 3.2.1 Seismic Classification General Design Criterion 2 of Appendix A to 10CFR50 and Appendix A to 10CFR100 require that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes without loss of capability to perform their safety function. NRC Regulatory Guide 1.29 (Rev. 2, 2/76) provides additional guidance and defines Seismic Category I structures, components, and systems as those necessary to assure:
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| (1) The integrity of the reactor coolant pressure boundary (2) The capability to shut down the reactor and maintain it in a safe condition, or (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR 50.67.
| | 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS |
| Plant structures, systems, and components, including their foundations and supports, designed to remain functional in the event of a Safe Shutdown Earthquake are designated as Seismic Category I, as indicated in Table 3.2-1. Class 1E electric equipment is Seismic Category I equipment.
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| Seismic classification of systems instrumentation is discussed in Chapter 7.
| | Certain structures, components, and systems of the nuclear plant are considered important to safety because they perform safety actions required to avoid or mitigate the consequences of abnormal operational transients or accidents. The purpose of this section is to classify structures, components, and systems, according to the importance of the safety function they perform. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when required. |
| All Seismic Category I structures, systems, and components are analyzed under the loading conditions of the SSE and OBE. Since the two earthquakes vary in intensity, the design of Seismic Category I structures, components, equipment, and systems to resist each earthquake and other loads will be based on levels of material stress or load factors, whichever is applicable, and will yield margins of safety appropriate for each earthquake. The margin of safety provided for Safety Class structures, components, equipment, and systems for the SSE will be sufficiently large to assure that their design functions are not jeopardized.
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| Seismic Category I structures are sufficiently isolated or protected from other structures to ensure that their integrity is maintained at all times.
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| Components (and their supporting structures) which are not Seismic Category I and whose collapse could result in loss of required function through impact with or flooding of Seismic Category I structures, equipment, or systems required after a safe shutdown earthquake, are analytically checked to confirm their integrity against collapse when subjected to seismic loading resulting from the safe shutdown earthquake.
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| FSAR Rev. 68 3.2-1
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| SSES-FSAR Text Rev. 56 The Operating Basis Earthquake as defined in 10 CFR 100, Appendix A, is not incorporated as a part of the seismic classification scheme.
| | 3.2.1 Seismic Classification |
| The seismic classification indicated in Table 3.2-1 meets the requirements of NRC Regulatory Guide 1.29 except as otherwise noted in the table. Where only portions of systems are identified as Seismic Category I on this table, the boundaries of the Seismic Category I portions of the system are shown on the piping and instrument diagrams in appropriate sections of this report.
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| 3.2.2 System Quality Group Classifications System quality group classifications as defined in NRC Regulatory Guide 1.26 have been determined for each water, steam or radioactive waste containing component of those applicable fluid systems relied upon to:
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| (1) prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary, (2) permit shutdown of the reactor and maintain it in the safe shutdown conditions, and (3) contain radioactive material.
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| A tabulation of quality group classification for each component so defined is shown in Table 3.2-1 under the heading, "Quality Group Classification." Figure 3.2-1 is a diagram which depicts the relative locations of these components along with their quality group classification. Interfaces between components of different classifications are indicated on the system piping and instrumentation diagrams which are found in the pertinent section of the FSAR.
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| System Quality Group Classifications and design and fabrication requirements as indicated in Tables 3.2-1, 3.2-2, 3.2-3, and 3.2-4 meet the requirements of Regulatory Guide 1.26 (Rev. 3, 2/76) except as noted.
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| 3.2.2.1 Quality Group D (Augmented)
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| Certain portions of the radwaste system meet the additional requirements of Quality Group D (Augmented) as defined in the NRC Branch Technical Position ETSB 11-1 (Rev. 1), parts B.IV and B.VI. Portions of the radwaste system meeting the requirements of Quality Group D (Augmented) may be determined from notes on the appropriate figures in Chapter 11.
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| 3.2.3 System Safety Classifications Structures, systems, and components are classified as Safety Class l, Safety Class 2, Safety Class 3, or Other in accordance with the importance to nuclear safety. Equipment is assigned a specific safety class, recognizing that components within a system may be of differing safety importance. A single system may thus have components in more than one safety class.
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| FSAR Rev. 68 3.2-2
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| SSES-FSAR Text Rev. 56 The safety classes are defined in this section and examples of their broad application are given.
| | General Design Criterion 2 of Appendix A to 10CFR50 and Appendix A to 10CFR100 require that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes without loss of capability to perform their safety function. NRC Regulatory Guide 1.29 (Rev. 2, 2/76) provides additional guidance and defines Seismic Category I structures, components, and systems as those necessary to assure: |
| Because of specific design considerations, these general definitions are subject to interpretation and exceptions. Table 3.2-1 provides a summary of the safety classes for the principal structures, systems, and components of the plant.
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| Design requirements for components of safety classes are also delineated in this section. Where possible, reference is made to accepted industry codes and standards which define design requirements commensurate with the safety function(s) to be performed. In cases where industry codes and standards have no specific design requirements, the locations of the appropriate subsections that summarize the requirements to be implemented in the design are indicated.
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| 3.2.3.1 Safety Class 1 3.2.3.1.1 Definition of Safety Class 1 Safety Class 1, SC-1, applies to components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal makeup system.
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| 3.2.3.2 Safety Class 2 3.2.3.2.1 Definition of Safety Class 2 Safety Class 2, SC-2, applies to those structures, systems, and components, other than service water systems, that are not Safety Class 1 but are necessary to accomplish the safety functions of:
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| (1) inserting negative reactivity to shut down the reactor, (2) preventing rapid insertion of positive reactivity, (3) maintaining core geometry appropriate to all plant process conditions, (4) providing emergency core cooling, (5) providing and maintaining containment, (6) removing residual heat from the reactor and reactor core, and (7) storing spent fuel.
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| Safety Class 2 includes the following:
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| (1) Reactor protection system and Alternate Rod Injection system.
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| (2) Those components of the control rod system which are necessary to render the reactor subcritical.
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| (3) Systems or components which restrict the rate of insertion of positive reactivity.
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| FSAR Rev. 68 3.2-3
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| SSES-FSAR Text Rev. 56 (4) The assembly of components of the reactor core which maintain core geometry including the fuel assemblies, core support structure, and core grid plate, as examples.
| | (1) The integrity of the reactor coolant pressure boundary |
| (5) Other components within the reactor vessel such as jet pumps, core shroud, and core spray components which are necessary to accomplish the safety function of emergency core cooling.
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| (6) Emergency core cooling systems.
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| (7) Primary containment.
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| (8) Reactor building (secondary containment)
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| (9) Post-accident containment heat removal systems.
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| (10) Initiating systems required to accomplish safety functions, including emergency core cooling initiating system and containment isolation initiating system.
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| (11) At least one of the systems which recirculates reactor coolant to remove decay heat when the reactor is pressurized and the system to remove decay heat when the reactor is not pressurized.
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| (12) Spent fuel storage racks and spent fuel pool.
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| (13) Electrical and instrument auxiliaries necessary to operation of the above.
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| Structures, systems, and components in Safety Class 2 are listed in Table 3.2-1.
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| 3.2.3.3 Safety Class 3 3.2.3.3.1 Definition of Safety Class 3 Safety Class 3, SC-3, applies to those structures, systems, and components that are not Safety Class 1 or Safety Class 2, but (1) Whose function is to process radioactive wastes and whose failure would result in release to the environment of gas, liquid, or solids resulting in a single-event whole body dose to a person at the site boundary greater than 500 mrem.
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| (2) Which provide or support any safety system function. Safety Class 3 includes the following:
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| : a. Service water systems required for the purpose of:
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| : 1. Removal of decay heat from the reactor
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| : 2. Emergency core cooling
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| : 3. Post-accident heat removal from the suppression pool FSAR Rev. 68 3.2-4
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| SSES-FSAR Text Rev. 56
| | (2) The capability to shut down the reactor and maintain it in a safe condition, or |
| : 4. Providing cooling water needed for the functioning of emergency systems.
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| : b. Fuel supply for the onsite emergency electrical system.
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| : c. Emergency equipment area cooling.
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| : d. Compressed gas or hydraulic systems required to support control or operation of safety systems.
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| : e. Electrical and instrumentation auxiliaries necessary for operation of the above.
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| 3.2.3.4 Other Structures, Systems, and Components 3.2.3.4.1 Definition of Other Structures, Systems, and Components A boiling water reactor has a number of structures, systems, and components in the power conversion or other portions of the facility which have no direct safety function but which may be connected to or influenced by the equipment within the Safety Classes defined above. Such structures, systems, and components are designated as "other."
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| 3.2.3.4.2 Design Requirements for Other Structures, Systems, and Components The design requirements for equipment classified as "other" are specified by the designer with appropriate consideration of the intended service of the equipment and expected plant and environmental conditions under which it will operate. Where possible, design requirements are based on applicable industry codes and standards. Where these are not available, the designer utilizes accepted industry or engineering practice.
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| 3.2.4 Quality Assurance Structures, systems, and components whose safety functions require conformance to the quality assurance requirement of 10CFR50, Appendix B, are summarized in Table 3.2-1 under the heading, "Quality Assurance Requirements." The Operational Quality Assurance Program is described in Chapter 17.
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| 3.2.5 Correlation of Safety Classes with Industry Codes The design of plant equipment will be commensurate with the safety importance of the equipment.
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| Hence, the various safety classes have a gradation of design requirements. The correlation of safety classes with other design requirements are summarized in Table 3.2-5.
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| FSAR Rev. 68 3.2-5
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR 50.67. |
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| ==SUMMARY==
| | Plant structures, systems, and components, including their foundations and supports, designed to remain functional in the event of a Safe Shutdown Earthquake are designated as Seismic Category I, as indicated in Table 3.2-1. Class 1E electric equipment is Seismic Category I equipment. |
| | Seismic classification of systems instrumentation is discussed in Chapter 7. |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | All Seismic Category I structures, systems, and components are analyzed under the loading conditions of the SSE and OBE. Since the two earthquakes vary in intensity, the design of Seismic Category I structures, components, equipment, and systems to resist each earthquake and other loads will be based on levels of material stress or load factors, whichever is applicable, and will yield margins of safety appropriate for each earthquake. The margin of safety provided for Safety Class structures, components, equipment, and systems for the SSE will be sufficiently large to assure that their design functions are not jeopardized. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * Reactor System 4.5 C Reactor vessel GE C A 1 III-A I Y Reactor vessel support skirt GE C NA 1 III-A I Y Reactor vessel appurtenances, pressure retaining portions GE C A 1 III-A I Y CRD housing supports GE C NA 2 X I Y Reactor internal structures, engineered safety features GE C NA 2 X I Y Reactor internal structures, other GE C N/A Other X N/A N Control rods GE C N/A 2 X I Y Control rod drives GE C N/A 2 III-2 I Y Core support structure GE C N/A 2 III-1 I Y Power range detector hardware - pressure retaining portions GE C A 1 III-1 I Y Fuel assemblies AREVA C N/A 2 X I Y Nuclear Boiler System 4.5 Vessels, level instrumentation condensing chambers GE C A 1 III-1 I Y 10 Vessels, air accumulators P C C 3 III-3 I Y Air supply check valves, piping downstream of air supply check valve P C C 3 III-3 I Y Piping, relief valve discharge P C C 3 III-3 I Y Piping, main steam, within outermost Isolation valve GE C A 1 III-1 I Y Pipe supports, main steam P C NA 1 III-1 I Y Pipe restraints, main steam P C NA 1 X I Y Piping, other within outermost isolation valves P C A 1 III-1 I Y 10 Piping, instrumentation beyond outermost isolation valves P R,T B 2 III-2 Note 20 N Safety/relief valves GE C A 1 III-1 I Y Valves, main steam isolation valves GE C,R A 1 III-1 I Y Quenchers and quencher supports P C C 3 III-3 I Y Valves, other, isolation valves within primary containment P C A 1 III-1 I Y 10 Feedwater piping inside isolation valves P C A 1 III-1 I Y Valves, instrumentation beyond outermost isolation valves P C,R,T B 2 111-2 I Y 5 Mechanical modules, instrumentation with safety function GE C NA 2 X I Y Electrical modules with safety function GE C NA 2 IEEE-279/323 I Y Cable, with safety function P C NA 2 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 1 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Seismic Category I structures are sufficiently isolated or protected from other structures to ensure that their integrity is maintained at all times. |
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| ==SUMMARY==
| | Components (and their supporting structures) which are not Seismic Category I and whose collapse could result in loss of required function through impact with or flooding of Seismic Category I structures, equipment, or systems required after a safe shutdown earthquake, are analytically checked to confirm their integrity against collapse when subjected to seismic loading resulting from the safe shutdown earthquake. |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | FSAR Rev. 68 3.2-1 SSES-FSAR Text Rev. 56 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * Recirculation System 5 Piping GE C A 1 III-1 I Y 10 Piping suspension, recirculation line GE C NA 1 III-1 I Y 61 Pipe restraints, recirculation line GE C NA 2 X NA Y Pumps GE C A 1 III-1 I Y Valves GE C A 1 III-1 I Y 10 Pump Motors GE C NA 2 NEMA/NEC I N Electrical modules, with safety function GE/P C NA 2 IEEE-279/323 I Y Cable with safety function P C,R NA 2 IEEE-279/323/383 NA Y 15 Piping P T D Other B31.1.0 NA N CRD Hydraulic System 4 Valves, scram discharge volume lines P/GE R B 2 III-2 I Y 10 Valves, insert and withdraw lines P/GE R B 2 III-2 I Y 35 Valves, other P R D Other B31.1.0 NA N Piping, scram discharge volume lines P R,C B 2 III-2 I Y Piping, insert and withdraw lines P C,R B 2 III-2 I Y Piping, other P R D Other B31.1.0 NA N 50 Hydraulic control unit GE R NA 2 NA I Y 12 Electrical modules, with safety function GE R NA 2 IEEE-279/323 I Y Cable, with safety function P C,R NA 2 IEEE-279/323/383 NA Y 15 ENGINEERED SAFETY FEATURES Standby Liquid Control System 9.3.5 Standby liquid control tank GE R B 2 API 650 I Y 66 Pump GE R B 2 NP&V-II I Y Pump motor GE R NA 2 X I Y Valves, explosive GE R B 2 NP&V-II I Y Valves, isolation and within P C,R A 1 III-1 I Y 10 Valves, beyond isolation valves P R B 2 III-2 I Y 10 Piping, within isolation valves P C A 1 III-1 I Y 10 Piping, beyond isolation valves P R B 2 III-2 I Y 10 Electrical modules, with safety function GE R NA 2 IEEE-279/323 I Y Cable, with safety function P R NA 2 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 2 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | The Operating Basis Earthquake as defined in 10 CFR 100, Appendix A, is not incorporated as a part of the seismic classification scheme. |
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| ==SUMMARY==
| | The seismic classification indicated in Table 3.2-1 meets the requirements of NRC Regulatory Guide 1.29 except as otherwise noted in the table. Where only portions of systems are identified as Seismic Category I on this table, the boundaries of the Seismic Category I portions of the system are shown on the piping and instrument diagrams in appropriate sections of this report. |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | 3.2.2 System Quality Group Classifications |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * RHR System 5.4.7 Heat exchangers, primary side GE R B 2 III-2 I Y Heat exchangers, secondary side GE R C 3 III-3 I Y Piping, within outermost containment isolation valves P C A 1 III-1 I Y 10 Piping, beyond outermost containment isolation valves P R B 2 III-2 I Y 10 Containment spray line piping within isolation valve P C,R B 2 III-2 I Y Containment spray line piping beyond isolation valve P R B 2 III-2 I Y Pumps GE R B 2 NP&V-II I Y Pump motors GE R NA 2 NEMA/NEC I Y Reactor vessel head spray line piping inside second isolation valve P C A 1 III-1 I Y Reactor vessel head spray line piping beyond second isolation valve P R B 2 III-2 I Y Valves, isolation LPCI line P C,R A 1 III-1 I Y Valves, isolation, other P C,R B 2 III-2 I Y 10 Valves, beyond isolation valves P R B 2 III-2 I Y 10 Mechanical modules GE R NA 2 I Y Electrical modules, with safety function GE R NA 2 IEEE-279/323 I Y Cable, with safety function P C,R NA 2 IEEE-279/323/383 NA Y 15 Core Spray 6.3 Piping, within outermost isolation valves P C A 1 III-1 I Y 10 Piping, beyond outermost isolation valves P R,C B 2 III-2 I Y 10 Pumps GE R B 2 NP&V-II I Y Pump motors GE R NA 2 NEMA/NEC I Y Valves, containment isolation and within containment P C A 1 III-1 I Y 10 Valves, beyond outermost containment isolation valves P R B 2 III-2 I Y 10 Electrical modules with safety function GE R NA 2 IEEE-279/323 I Y Cable, with safety function P R NA 2 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 3 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | System quality group classifications as defined in NRC Regulatory Guide 1.26 have been determined for each water, steam or radioactive waste containing component of those applicable fluid systems relied upon to: |
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| ==SUMMARY==
| | (1) prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary, |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (2) permit shutdown of the reactor and maintain it in the safe shutdown conditions, and |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * High Pressure Coolant Injection 6.3 Piping, and valves within outermost containment isolation valve (turbine inlet steam line and instrument lines only) P C A 1 III-1 I Y 10,28 Piping and valves within outermost containment isolation valves (other than above) P C B 2 III-2 I Y 10,28 Piping, return test line to condensate storage tank beyond second isolation valve P R,O D Other B31.1.0 NA N Piping, beyond outermost containment isolation valve, other P R B 2 III-2 I Y 10 Pumps GE R B 2 NP&V-II I Y HPCI turbine GE R NA 2 X I Y 11,38 Valves, beyond isolation valves, motor operated P R B 2 III-2 I Y 10 Valves, other P R B 2 III-2 I Y 10 Electrical modules, with safety function GE R NA 2 IEEE-279/323 I Y Cable with safety function P R NA 2 IEEE-279/323/383 NA Y 15 RCIC System 5.4.6 Piping, and valves within outermost containment isolation - -
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| valves (turbine inlet steam line and instrument lines only) P C,R A III-1 Piping and valves within outermost containment isolation 1 I Y 10,28 valves (other than above) P C,R B III-2 Piping, and valves beyond outermost containment isolation 2 I Y 10,28 valves (except for other shown below) P R B 2 III-2 I Y 10 Piping, and valves: Other; return test line to condensate storage tank beyond second isolation valve; vacuum pump discharge from vacuum pump to check valve F028; condensate pump discharge to valve for F049; all leakoff piping from RCIC governor valve; gland exhaust piping from RCIC turbine P O,R D Other B31.1.0 NA N RCIC barometric condenser GE R D Other B31.1.0 NA N RCIC condensate pump and condenser vacuum pump GE R D Other X NA N Pumps GE R B 2 NP&V-II I Y RCIC turbine GE R NA 2 X I Y 11,38 Electrical modules, with safety function GE R NA 2 IEEE-279/323 I Y Cable, with safety function P R,C NA 2 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 4 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (3) contain radioactive material. |
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| ==SUMMARY==
| | A tabulation of quality group classification for each component so defined is shown in Table 3.2-1 under the heading, "Quality Group Classification." Figure 3.2-1 is a diagram which depicts the relative locations of these components along with their quality group classification. Interfaces between components of different classifications are indicated on the system piping and instrumentation diagrams which are found in the pertinent section of the FSAR. |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | System Quality Group Classifications and design and fabrication requirements as indicated in Tables 3.2-1, 3.2-2, 3.2-3, and 3.2-4 meet the requirements of Regulatory Guide 1.26 (Rev. 3, 2/76) except as noted. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * FUEL STORAGE AND HANDLING 9.1 Storage Equipment 9.1.1, 9.1.2, 9.1.4 New fuel storage racks GE R NA 2 AWS D1.1 I Y Spent fuel storage racks (includes storage of control rods, P R NA 2 AISI/AA I Y control rod guide tubes, defective fuel storage containers, out-of core sipping containers and channels)
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| Control Rod Storage Hangers (includes control rod blades) P R NA 2 AISC I Y Channel storage racks GE R NA Other AWS DI.I NA N In vessel racks GE R NA Other AWS DI.I I Y Defective fuel storage containers GE R NA 3 AWS DI.I NA Y Independent Spent Fuel Storage Facility (ISFSI)
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| Horizontal Storage Modules TNW ISFSI NA Other ACI 349 I Y 62 ACI 318 Dry Shielded Canisters TNW ISFSI NA Other ASME I Y 62,63 HI-STORM FW Overpacks HI ISFSI NA Other NA I Y 62 Multi-Purpose Canisters HI ISFSI NA Other NA I Y 62 Fuel Servicing Equipment 9.1.4 Fuel preparation machine GE R NA 3 X I Y New fuel inspection stand GE R NA Other X NA N General purpose grapple GE R NA 2 X I Y Irradiated fuel shipping cask NA R NA Other 49CFR 173.393, I Y 45 49CFR 173.396 Jib cranes P R NA Other CMAA 70/B30.10 NA N Railway bay unloading crane P R NA Other CMAA 70/B30.10 NA N FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 5 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 3.2.2.1 Quality Group D (Augmented) |
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| ==SUMMARY==
| | Certain portions of the radwaste system meet the additional requirements of Quality Group D (Augmented) as defined in the NRC Branch Technical Position ETSB 11-1 (Rev. 1), parts B.IV and B.VI. Portions of the radwaste system meeting the requirements of Quality Group D (Augmented) may be determined from notes on the appropriate figures in Chapter 11. |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | 3.2.3 System Safety Classifications |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
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| * Reactor Vessel Servicing Equipment 9.1.4 Main Steam Line Plugs (REM*Light Model) GEH R NA Other AA I Y 48, 58 Dryer & separator sling [Supplied with Nuclear System] GE R NA Other X NA Y RPV head strongback/carousel GE R NA Other X NA Y 53 Service platform GE R NA Other X NA N 73 Control rod grapple GE R NA Other X NA Y Reactor building crane P R NA Other CMAA 70/B30.20 I Y 23 Main Steam Line Plugs (Spring Disk Model) [Wetlift] NA R NA Other X I Y 57,58 MSL Plugs Restraint Ring [Wetlift] NA R NA Other X I Y 57 Watertight Hook Box [Wetlift] NA R NA Other X NA Y 59 Rigid Pole Handling System [Wetlift] NA R NA Other X NA Y 60 Refuel Floor Auxiliary Platform (RFAP) GE R NA Other CMAA-74 NA Y 23 Jet Pump Plugs NA R NA Other X L Y 69 360 Degree Refuel Work Platform GE R NA Other AISC NA Y 23 Refueling Equipment 9.1.4 Refueling platforms GE R NA 2 X I Y 23 Fuel grapples GE R NA Other X NA N Under Reactor Vessel Service Equipment 9.1.4 Equipment handling platform GE C NA Other X NA N CRD handling equipment NES C NA Other X NA N FSAR Rev. 71
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| * Refer to the general notes at the end of this table. Page 6 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Structures, systems, and components are classified as Safety Class l, Safety Class 2, Safety Class 3, or Other in accordance with the importance to nuclear safety. Equipment is assigned a specific safety class, recognizing that components within a system may be of differing safety importance. A single system may thus have components in more than one safety class. |
|
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| ==SUMMARY==
| | FSAR Rev. 68 3.2-2 SSES-FSAR Text Rev. 56 |
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| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | The safety classes are defined in this section and examples of their broad application are given. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| | Because of specific design considerations, these general definitions are subject to interpretation and exceptions. Table 3.2-1 provides a summary of the safety classes for the principal structures, systems, and components of the plant. |
| * Fuel Pool Cooling & Cleanup System 9.1.3 Heat Exchangers P R C Other III-3, TEMA C NA N Pumps P R C Other III-3 NA N Skimmer surge tanks P R C 3 III-3 I Y Filter demineralizer vessels P R D Other VIII-1 NA N 19,31 Resin and precoat tanks P R D Other API-650 NA N Cooling loop piping and valves downstream of Valve 1-53-001, 2-53-001 P R C Other III-3 NA N 46,55 RHR intertie piping and valves P R C 3 III-3 I Y Emergency service water makeup piping and valves P R C 3 III-3 I Y Other piping and valves P R D Other B31.1.0 NA N 19,31,56 Cooling loop piping upstream of Valve 1-53-001, 2-53-001 from skimmer surge tank P R C 3 III-3 I Y RADIOACTIVE WASTE MANAGEMENT 11 Liquid Waste Management Systems 11.2 Centrifugal pumps P R/RW/T D Other III-3** NA N 31,22 Atmospheric tanks P RW/T D Other VIII-1/III-3 NA N 31,22 Filter vessel P RW D Other VIII-1 NA N 31,22 Demineralizer vessel P RW D Other III-3** NA N 31,22 Evaporator, complete system P RW D Other III-3**/MA B NA N 31,22 Laundry drain filter P RW D Other VIII-1 NA N Liquid and chemical waste piping and valves P R/RW/T D Other B31.1 NA N 31,22 Laundry drain waste and auxiliary piping and valves P RW D Other B31.1 NA N
| |
| **These items were constructed to the ASME Code but are not required to be maintained to this code per NRC Branch Technical Position ETSB 11-1.
| |
| FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 7 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Design requirements for components of safety classes are also delineated in this section. Where possible, reference is made to accepted industry codes and standards which define design requirements commensurate with the safety function(s) to be performed. In cases where industry codes and standards have no specific design requirements, the locations of the appropriate subsections that summarize the requirements to be implemented in the design are indicated. |
|
| |
|
| ==SUMMARY==
| | 3.2.3.1 Safety Class 1 |
| | |
| | 3.2.3.1.1 Definition of Safety Class 1 |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Safety Class 1, SC-1, applies to components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal makeup system. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Offgas System 11.3 Heat exchangers P D Other NA N 22,31 Recombiner Condenser-Unit 2 & Common T VIII-1 50 Recombiner Condenser-Unit 1 T III/VIII-1 Recombiner Preheater T III-3 Motive Steam Jet Condenser T III-3 Condensate Cooler T VIII-1 Charcoal Treatment Inlet RW VIII-1 Precooler Chiller T VIII-1 Piping P T,RW D Other B31.1.0 NA N 10,22,31 Valves, flow control P T,RW D Other B31.1.0 NA N 22,31 Valves, other P T,RW D Other B31.1.0 NA N 10,22,31 Motors P RW NA Other NEMA-MG1 NA N 22 HEPA filters P RW D Other VIII-1 NA N 22,31 Pressure vessels P D Other NA N 22,31 Recombiner Vessel-Unit 1, 2 & D Common T VIII-3 Motive Steam Jet Ejector T VIII-1 Charcoal Guard Bed RW VIII-1 Charcoal Adsorber Vessels RW VIII-1 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 8 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 3.2.3.2 Safety Class 2 |
|
| |
|
| ==SUMMARY==
| | 3.2.3.2.1 Definition of Safety Class 2 |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Safety Class 2, SC-2, applies to those structures, systems, and components, other than service water systems, that are not Safety Class 1 but are necessary to accomplish the safety functions of: |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Solid Waste Management System 11.4 Centrifugal pumps P RW D Other III-3 NA N 19,31,22 Regeneration waste transfer pumps P T D Other Manuf. Standard NA N 22 Solidification system pumps P RW D Other Manuf. Standard NA N 22 Filter demineralizer backwash tanks P R D Other III-3 NA N 22 Phase separators P RW D Other VIII-1 NA N 31,22 Regen. Waste surge tanks P T D Other VIII-1 NA N 22 Waste mixing tanks P RW D Other VIII-1 NA N 22 Waste containers, HSA PL RW NA Other D1.1,D1.1 NA N Waste containers, LSA PL RW NA Other D1.1 NA N Solid radwaste collecting piping and valves P R/T/RW D Other B31.1 NA N 31,22 Solidification system piping and valves P RW D Other B31.1 NA N 22 Aux. piping and valves P R/T/RW D Other B31.1 NA N Backwash tank drain lines P R/T/RW D Other B31.1 NA N 22 Reactor Water Cleanup System 5.4.8 Filter demineralizer vessels GE R C Other III-3 NA N Regenerative and nonregenerative heat exchangers GE R C Other III-3 NA N Piping and valves within reactor coolant pressure boundary 26 (RCPB) P R,C A 1 III-1 I Y 10 RWCU Recirc Pumps GE R C Other III-3 NA N Piping and valves beyond outermost containment isolation valve up to valves F104, F042, F034, F035 P R C Other III-3 NA N Piping and valves beyond valves F104 and F042 to feedwater system P R B 2 III-2 I Y Piping and valves beyond F034 and F035 P R D Other B31.1.0 NA N Mechanical modules GE R NA Other X NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 9 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (1) inserting negative reactivity to shut down the reactor, |
|
| |
|
| ==SUMMARY==
| | (2) preventing rapid insertion of positive reactivity, |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (3) maintaining core geometry appropriate to all plant process conditions, |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * WATER SYSTEMS RHR Service Water and Spray Pond System 9.2.6 Cross connect piping to RHR system, within second automatic isolation valve P R B 2 III-2 I Y Piping and valves, chemical treatment makeup water, blowdown P O D Other B31.1.0 NA N Piping, other P O,R,SW C 3 III-3 I Y RHR SW Pumps P SW C 3 III-3 I Y Pump motors P SW NA 3 IEEE-323/344 I Y Valves, isolation P C,R B 2 III-2 I Y Valves, other P O,R,SW C 3 III-3 I Y Electrical modules, with safety function P O,R,SW NA 3 IEEE-279/323 I Y 15 Cable, with safety function P O,R,SW NA 3 IEEE-279/323/383 NA Y Heat exchangers P R C 3 III-3/TEMA C I Y Piping drain pumps P O NA Other NA NA N Emergency Service Water System 9.2.5 Piping up to RHR SW system P,GH O,G,R, C 3 III-3 1 Y T,CS, EG,SW Piping supports in Diesel Generator E building GH EG C 3 III-3 I Y Pumps P SW C 3 III-3 I Y Pump Motors P SW NA 3 IEEE-323/344 I Y Valves P,GH O,G,R, C 3 III-3 I Y T,CS, SW,EG Electrical modules with safety function P O,G,R,T, NA 3 IEE-279/323 I Y CS,SW Cable, with safety function P O,G,R, NA 3 IEEE-279/323/383 NA Y 15 SW,T,CS Heat exchangers P,GH R,T,G, C 3 III-3 I Y 52 CS,EG FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 10 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (4) providing emergency core cooling, |
|
| |
|
| ==SUMMARY==
| | (5) providing and maintaining containment, |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (6) removing residual heat from the reactor and reactor core, and |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Reactor Building Closed Cooling Water System 9.2.2 Piping and valves forming part of containment boundary P R,C B 2 III-2 I Y Piping and valves, other P R,C,T D Other B31.1.0 NA N Tanks P R D Other VIII-1 NA N Heat exchangers P R D Other VIII-1/TEMA C NA N Pumps P R D Other Hyd.I NA N 24 Plant Service Water System 9.2.1 Piping and valves forming part of the SW/ESW Interface P R,C C 3 III-3 I Y Piping and valves, other P R,C,T D Other B31.1.0 NA N Heat Exchangers P CT D Other VIII-1/TEMA C NA N Pumps P CW D Other Hyd.I NA N 24 Turbine Building Closed Cooling Water System 9.2.3 Piping and valves P T D Other B31.1.0 NA N Heat exchangers P T D Other VIII-1/TEMA C NA N Tanks P T D Other VIII-1 NA N Pumps P T D Other Hyd.I NA N 24 Circulating Water System 9.2 Piping P O,T,CW D Other AWWA-C201 NA N Condenser P T D Other HEI NA N Pumps P CW NA Other VIII-1/Hyd.I NA N 24 Valves P T,CW D Other AWWA-C201 & C504 NA N Cooling tower P O NA Other NONE NA N Piping, Non-pipe Class P O,T,CW NA Other AWWA NA N Valves, Non-pipe Class P T,CW NA Other AWWA NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 11 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (7) storing spent fuel. |
|
| |
|
| ==SUMMARY==
| | Safety Class 2 includes the following: |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (1) Reactor protection system and Alternate Rod Injection system. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Diesel Generator A-D Systems 9.5.4,9.5.5, 9.5.6, 9.5.7, 9.5.8 Diesel Generator P G NA 2 IEEE-387 I Y Heat Exchangers, Jacket Water, Intercoolers and Lube Oil P G C 3 III-3/TEMA C I Y 54 Engine Mounted Piping and Valves for Fuel Oil, Lube Oil, Jacket Water, Intake/Exhaust, Starting Air Systems P G NA Other X I Y Filter Housings P G C 3 VIII/B31.1.0 I Y Starting Air System Piping and Valves From Air Receiver Inlet Check Valves to Engine Skid P G C 3 III-3 I Y Other Starting Air Piping and Valves Upstream of the Air Receiver Inlet Check Valves P G D Other B31.1.0 NA N Air Dryer Piping and Components P G NA Other NA NA N Air receivers P G C 3 III-3 I Y Air Compressors P G D Other NA NA N Fuel Oil Storage Tanks P O C 3 III-3 I Y Fuel Oil Day Tanks P G C 3 III-3 I Y Fuel Oil System Piping and Valves, Auxiliary Skid and Transfer System (except vent lines and portion of fill lines) P G, O C 3 III-3 I Y Fuel Oil Transfer Pump P O C 3 III-3 I Y Fuel Oil Transfer Pump Motor P O NA 3 IEEE-323/344 I Y Jacket Water System Piping and Valves P G D Other X I Y Jacket Water Heater P G NA Other NA I Y Jacket Water Circulating Pump P G D Other Hyd. I I Y 24 Air Intake and Exhaust Piping System (except Mufflers, Filers, Manifolds and Expansion Joints) P G C 3 III-3 I Y Lube Oil System Piping and Valves P G D Other X I Y Lube Oil Circulating Pump P G D Other Hyd. I NA N 24 Dirty Lube Oil Drain Tank P G NA Other None NA N Lube Oil Heater P G NA Other None NA N Electrical Modules with Safety Functions P G NA 3 IEEE-279 I Y Cable with Safety Functions P G NA 3 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 12 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (2) Those components of the control rod system which are necessary to render the reactor subcritical. |
|
| |
|
| ==SUMMARY==
| | (3) Systems or components which restrict the rate of insertion of positive reactivity. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | FSAR Rev. 68 3.2-3 SSES-FSAR Text Rev. 56 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Diesel Generator E Systems 9.5.4,-5,-
| |
| .6,-.7,-.8 Diesel Generator GH EG N/A 2 DEMA I Y Diesel Engine intercoolers GH EG C 3 III-3 I Y Engine mounted piping and valves for lube oil, jacket water, fuel oil, intake/exhaust, starting air systems required to perform a safety function GH EG N/A Other X I Y Intake/Exhaust piping and expansion joints GH EG C 3 III-3 I Y Auxiliary skid mounted piping, valves, filters and strainers GH EG C 3 III-3 I Y Jacket water, lube oil, fuel oil motor driven pumps GH EG C 3 III-3 I Y Jacket water and lube oil pump motor GH EG N/A Other IEEE-323,-344 I Y Fuel oil pump motor GH EG N/A 3 IEEE-323,-344 I Y Jacket water Stand Pipe GH EG C 3 III-3 I Y Jacket water, lube oil, fuel oil, heat exchangers GH EG C 3 III-3 I Y Jacket water and lube oil heaters GH EG N/A Other IEEE-323,-344 I Y Fuel oil transfer system piping and valves (except vent line and portion of fill line) GH EG,O C 3 III-3 I Y Fuel oil transfer pump GH EG C 3 III-3 I Y Fuel oil transfer pump motor GH EG N/A 3 IEEE-323,-344 I Y Fuel oil day tank GH EG C 3 III-3 I Y Fuel oil storage tank GH O C 3 III-3 I Y Fuel oil transfer system strainer GH EG C 3 III-3 I Y Electrical modules with safety function GH EG N/A 3 IEEE-323,-344 I Y Cable, with safety functions GH EG,O N/A 3 IEEE-383 I Y Air receiver skid piping and valves GH EG C 3 III-3 I Y Air receivers GH EG C 3 III-3 I Y Air Compressors GH EG D Other NA NA N Engine mounted equipment required to perform a safety function GH EG N/A 3 DEMA I Y Engine mounted equipment and valves not required to perform safety function GH EG N/A Other DEMA N/A N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 13 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (4) The assembly of components of the reactor core which maintain core geometry including the fuel assemblies, core support structure, and core grid plate, as examples. |
|
| |
|
| ==SUMMARY==
| | (5) Other components within the reactor vessel such as jet pumps, core shroud, and core spray components which are necessary to accomplish the safety function of emergency core cooling. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (6) Emergency core cooling systems. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * HEATING, VENTILATING & AIR CONDITIONING SYSTEMS Control Structure 9.4.1 Control Structure Emergency Outside Air Supply System CSEOASS or CREOASS Motors P CS NA 3 IEEE323/344 I Y 16 Fans P CS NA 3 AMCA I Y 16 Prefilters P CS NA 3 UL CLASS I I Y 16 Electric Heaters P CS NA 3 UL-1096 I Y 16 HEPA Filters P CS NA 3 MIL-F-51068C I Y 16 (or ASME AG-1-1997)71 MIL-F-51079A (or ASME AG-1-1997)71 UL-586 Adsorber Units P CS NA 3 AACC CS-8 I Y 16 Ductwork P CS NA 3 AISI, AAWS I Y 16 Dampers P CS NA 3 AMCA I Y 16 Control Room & Computer Room HVAC Motors P CS NA 3 NEMA MG1 I Y IEEE-344/323 Instrumentation P CS NA IEEE-279/323 I Y Fans P CS NA 3 AMCA I Y Prefilters P CS NA 3 UL Class I I Y HEPA filters P CS NA 3 MIL-F-51068C I Y (or ASME AG-1-1997)71 Adsorber units P CS NA 3 MIL-F-51079 I Y (or ASME AG-1-1997)71 Dampers, isolation P CS NA 3 AACC CS-8 I Y Dampers, flow distribution ANSI N509-80 Table 5-1 I P CS NA 3 Y Ductwork P CS NA 3 AMCA I Y Coils, cooling P CS 3 AMCA I Y Electric heating coils P CS C 3 AISI, AWS I Y ARI NEC,NEMA FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 14 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (7) Primary containment. |
|
| |
|
| ==SUMMARY==
| | (8) Reactor building (secondary containment) |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (9) Post-accident containment heat removal systems. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Relay Room, Cable Spreading, Battery Room HVAC, and HVAC Equipment 9.4.1 Room Motors P CS NA 3 NEMA MG1 I Y IEEE-344/323 Fans P CS NA 3 AMCA I Y Prefilters P CS NA 3 UL Class 1 I Y Coils, heating, electric P CS NA 3 NEC, NEMA I Y Coils, cooling P CS NA 3 ARI I Y Dampers P CS NA 3 AMCA I Y Ductwork P CS NA 3 AISI I Y Piping & valves P CS C 3 B31.1 I Y Instrumentation P CS NA Other IEEE-279/323 I Y SGTS Equipment Room H&V 9.4.1.1.5 Motors P CS NA 3 NEMA MG1 I Y IEEE-344/323 Fans P CS NA 3 AMCA I Y Heaters, electric P CS NA 3 NEC 424 I Y NFPA 90A & 90B Dampers P CS NA 3 AMCA I Y Ductwork P CS NA 3 AISI,AWS I Y Instrumentation P CS NA 3 IEEE-279/323 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 15 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (10) Initiating systems required to accomplish safety functions, including emergency core cooling initiating system and containment isolation initiating system. |
|
| |
|
| ==SUMMARY==
| | (11) At least one of the systems which recirculates reactor coolant to remove decay heat when the reactor is pressurized and the system to remove decay heat when the reactor is not pressurized. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (12) Spent fuel storage racks and spent fuel pool. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * REACTOR BUILDING Reactor Building HVAC (Zone I and Zone II) 9.4 Includes Steam Tunnel Cooling, U2 Elec. Eq. Room H&V and U1 Remote Shutdown Room Ventilation Motors P R NA Other NEMA MG 1 NA N Fans P R NA Other AMCA NA N Prefilters P R NA Other UL Class I NA N HEPA Filters MIL-F-51068C, (or ASME AG-1-1997)71 MIL-F-51079 (or ASME AG-1-1997)71 Adsorber Units P R NA Other AACC CS-8 NA N RDT M-16-1T Coils, Coiling - Chilled & Service Water P R NA Other ARI NA N Coils, Heating P R NA Other NEC, NEMA NA Y Dampers, Isolation, & Ductwork Connected to RB P R NA 3 AMCA, SMACNA, I Y Recirculation System AISI, AWS Dampers, Other P R NA Other AMCA NA N Ductwork - Other P R NA Other SMACNA, AISI, NA N AWS Piping Connected to SGTS P R C 3 NFPC I Y Remainder P R D Other B31.1 NA N Also see Plant Chilled Water System ECCS and RCIC Pump Rooms 9.4.2 Motors P R NA 3 IEEE-323/344 I Y Fans P R NA 3 AMCA I Y Filters P R NA 3 NA I Y Coils, cooling P R NA 3 ARI I Y Piping and valves P R C 3 III-3 I Y FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 16 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (13) Electrical and instrument auxiliaries necessary to operation of the above. |
|
| |
|
| ==SUMMARY==
| | Structures, systems, and components in Safety Class 2 are listed in Table 3.2-1. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | 3.2.3.3 Safety Class 3 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Emergency SWGR and Load Center Rooms 9.4 Motors P R NA 3 NEMA MG1 I Y IEEE-344/323 Fans P R NA 3 AMCA I Y Prefilters P R NA 3 UL Class 1 I Y Coils, cooling U1-CSCW, U2-DX & condenser P R C 3 III-3 I Y Coils Cooling - RBCW, Both Units Dampers P R NA 3 ARI I Y Ductwork P R NA 3 AMCA I Y Piping & Valves, P R NA 3 AISI,AWS I Y Unit 1-CSCW, Unit 2-Refrigeration P R C 3 III-3 I Y Instrumentation P R NA Other IEEE-279/323 I Y Also See Plant Chilled Water System Refueling Floor HVAC (Zone III)-Both Units 9.4.6 Motors P R NA Other NEMA MG1 NA N Fans P R NA Other AMCA NA N Prefilters P R NA Other UL Class 1 NA N HEPA filters P R NA Other MIL-F-51079 NA N (or ASME AG-1-1997)71 Adsorber units P R NA Other MIL-F-51068C NA N (or ASME AG-1-1997)71 Coils, Cooling (RBCW) & Heating P R NA Other RDT M-16-1T NA N Damper-Isolation and Ductwork Connected to RB AACC CS-8 Recirculation System R R NA 3 ARI I Y Ductwork - Other P R NA Other AMCR,SMACNA NA N Dampers - Other P R NA Other AISI,AWS NA N Piping & Valves P R NA Other SMACNA/AISI NA N Also See Plant Chilled Water System AMCA B31.1 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 17 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 3.2.3.3.1 Definition of Safety Class 3 |
|
| |
|
| ==SUMMARY==
| | Safety Class 3, SC-3, applies to those structures, systems, and components that are not Safety Class 1 or Safety Class 2, but |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (1) Whose function is to process radioactive wastes and whose failure would result in release to the environment of gas, liquid, or solids resulting in a single-event whole body dose to a person at the site boundary greater than 500 mrem. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Drywell Atmosphere Recirculation and Cooling System 9.4.5 Motors P C NA Other IEEE-334/ I Y 65 NEMA MG1 Fans P C NA Other AMCA 210 I Y 65 Coils, cooling P C NA Other ARI I Y 65 Ductwork P C NA Other AISI,AWS I Y 65 Dampers P C NA 3 AMCA I Y 65 Piping and valves P C NA Other B31.1 NA N Combustible Gas Control System Primary Containment Atmosphere monitoring system IEEE-344 (PCAMS) P C,R B,D 2 III-2 I Y 10, 41 Piping valves forming Containment Penetration Boundary P C,R B 2 IEEE-344 I Y 69 III-2 Standby Gas Treatment & RB Recirculation System Motors P CS NA 3 IEEE-323/344 I Y 16 Fans P CS NA 3 AMCA I Y 16 Prefilters P CS NA 3 UL Class 1 I Y 16 Demisters P CS NA 3 MSAR 71-45 I Y 16 HEPA filters P CS NA 3 MIL-F-51079 (or ASME I Y 16 AG-1-1997)71 MIL-F-51068C (or ASME AG-1-1997)71 Adsorber units P CS NA 3 AACC CS-8 I Y 16 ANSI N509-80 Table 5-1 Ductwork P CS NA 3 AISI,AWS I Y 16 Dampers P CS NA 3 AMCA I Y 16 Piping P CS C 3 NFPC I Y 16 Valves P CS C 3 B31.1 I Y 16 Electric heaters P CS NA 3 NEMA & NEC I Y Control panels P CS NA 3 NEMA, IEEE 323 I Y FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 18 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (2) Which provide or support any safety system function. Safety Class 3 includes the following: |
| | : a. Service water systems required for the purpose of: |
| | : 1. Removal of decay heat from the reactor |
| | : 2. Emergency core cooling |
| | : 3. Post-accident heat removal from the suppression pool |
|
| |
|
| ==SUMMARY==
| | FSAR Rev. 68 3.2-4 SSES-FSAR Text Rev. 56 |
| | : 4. Providing cooling water needed for the functioning of emergency systems. |
| | : b. Fuel supply for the onsite emergency electrical system. |
| | : c. Emergency equipment area cooling. |
| | : d. Compressed gas or hydraulic systems required to support control or operation of safety systems. |
| | : e. Electrical and instrumentation auxiliaries necessary for operation of the above. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | 3.2.3.4 Other Structures, Systems, and Components |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Radwaste Building HVAC 9.4.3 Motors P RW NA Other NEMA MG1 NA N Fans P RW NA Other AMCA NA N Prefilters P RW NA Other UL Class 1 NA N HEPA filters P RW NA Other MIL-F-51079A NA N (or ASME AG-1-1997)71 Coils, cooling & heating P RW NA Other MIL-F-51068C NA N Adsorber units P RW NA Other (or ASME AG-1-1997)71 NA N ARI & UL Ductwork P RW NA Other MIL-C-17605 NA N Dampers P RW NA Other RDT M-16-1T NA N Electric heating coil P RW NA Other SMACNA NA N AMCA NEC Diesel Generator Buildings HVAC 9.4.7 Motors P,GH G,EG NA 3 NEMA MG-1 I Y IEEE344 Fans P,GH G,EG NA 3 AMCA I Y Ductwork P,GH G, EG NA 3 AISI,AWS I Y Dampers P,GH G,EG NA 3 AMCA I Y Turbine Building HVAC 9.4.4 Motors P T NA Other NEMA MG1 NA N Fans P T NA Other AMCA NA N Filters P T NA Other NA NA N Coils, cooling P T NA Other ARI NA N Ductwork P T NA Other SMACNA NA N Dampers P T NA Other AMCA NA N Electric heating coil P T NA Other NEC,NEMA NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 19 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 3.2.3.4.1 Definition of Other Structures, Systems, and Components |
|
| |
|
| ==SUMMARY==
| | A boiling water reactor has a number of structures, systems, and components in the power conversion or other portions of the facility which have no direct safety function but which may be connected to or influenced by the equipment within the Safety Classes defined above. Such structures, systems, and components are designated as "other." |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | 3.2.3.4.2 Design Requirements for Other Structures, Systems, and Components |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Emergency Service Water Pumphouse Ventilation 9.4.8 Motors P SW NA 3 NEMA MG1 I Y IEEE344 Fans P SW NA 3 AMCA I Y Ductwork P SW NA 3 AISI,AWS I Y Dampers P SW NA 3 AMCA I Y Administration Building HVAC Motors P O NA Other NEMA MG1 NA N Fans P O NA Other AMCA NA N Prefilters P O NA Other UL Class 1 NA N Dampers P O NA Other AMCA NA N Coils, cooling P O NA Other ARI NA N Coils, heating P O NA Other NEC, NEMA NA N Ductwork P O NA Other SMACNA NA N Main Steam and Power Conversion System 10.3 Main Steam System Main steam piping to turbine stop valves and branch line piping up to and including first valve. P R,T B 2 III-2 NA N 20 Main Steam piping from and including the turbine stop valve to turbine HP casing and branch line piping up to and including first valve. P T D Other B31.1.0 NA N 9,18,33 Steam piping and valves, other P T D Other B31.1.0 NA N Main Condenser Evacuation System 10.4.2 Piping and components P T,RW D Other B31.1.0 NA N Heat exchangers P T D Other VIII-1 NA N Air ejectors P T D Other B31.1.0 NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 20 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | The design requirements for equipment classified as "other" are specified by the designer with appropriate consideration of the intended service of the equipment and expected plant and environmental conditions under which it will operate. Where possible, design requirements are based on applicable industry codes and standards. Where these are not available, the designer utilizes accepted industry or engineering practice. |
|
| |
|
| ==SUMMARY==
| | 3.2.4 Quality Assurance |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Structures, systems, and components whose safety functions require conformance to the quality assurance requirement of 10CFR50, Appendix B, are summarized in Table 3.2-1 under the heading, "Quality Assurance Requirements." The Operational Quality Assurance Program is described in Chapter 17. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Condensate and Feedwater System 10.4.7 Reactor feedwater piping and valves, RPV to outermost isolation valve P C,R A 1 III-1/III-2 I Y 32 Reactor feedwater, piping and valves, other P R,T D Other B31.1.0 NA N Steam piping to feedwater pump turbine P T D Other B31.1.0 NA N Crossover (low pressure) piping P T D Other B31.1.0 NA N Bypass (high pressure) piping, downstream of first isolation valve Condensate piping and valves P T D Other B31.1.0 NA N Heat exchangers P T D Other VIII-1/TEMA C NA N Pressure Vessels P T D Other VIII-I NA N Pumps, feedwater and condensate P T NA Other Hyd.I NA N 24 Condensate Cleanup System 10.4.6 Piping and valves P T D Other B31.1.0 NA N Pressure vessels P T D Other VIII-1 NA N Condensate Storage and Transfer System 9.2.10 Tanks P O D Other D100 NA N Piping and valves P RW,O,T,R D Other B31.1.0 NA N Pumps P T D Other Hyd.I NA N 24 Turbine Gland Sealing System 10.4.3 Steam seal evaporator (SSE) P T D Other VIII-1 NA N Steam Packing Exhauster P T D Other X NA N Piping and valves P T D Other B31.1.0/X NA N SSE Drain Tank P T D Other VIII-1 NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 21 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 3.2.5 Correlation of Safety Classes with Industry Codes |
|
| |
|
| ==SUMMARY==
| | The design of plant equipment will be commensurate with the safety importance of the equipment. |
| | Hence, the various safety classes have a gradation of design requirements. The correlation of safety classes with other design requirements are summarized in Table 3.2-5. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | FSAR Rev. 68 3.2-5 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Auxiliary Steam System 10.4.11 Auxiliary boilers P T D Other I NA N Piping and valves P T D Other B31.1.0 NA N Main Chlorination System 9.2.8 Pumps P CA D Other Hyd.I NA N 24 Motors P CA NA Other NEMA MG1 NA N Piping and valves P CA D Other B31.1.0 NA N Lube Oil System 10.2 Batch oil tank P O D Other VIII-1 NA N Reservoirs P T D Other API-620 NA N Pumps P T D Other VIII/Hyd.I NA N 24 Motors P T NA Other NEMA MG1 NA N Conditioners P T NA Other NA NA N Heat Exchangers P T D Other VIII/TEMA C NA N Piping and valves P T D Other B31.1.0 NA N Instrumentation and Control Systems Reactor Instrumentation 7.2 Reactor Protection System GE C,R,T NA 2 IEEE-279 I Y All portions that must operate to control and safety shut down the reactor to a hot shutdown condition (Electronic modules)
| |
| Cable with safety function P C,R,T NA 2 IEEE-279/383 NA Y 15 Alternate Rod Injection P R NA 2 10CFR50.62 NA Y 47 All portions that must operate to control and safely shut down the reactor to a hot shutdown condition (Electronic modules) Cable with safety function FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 22 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA | | SSES-FSAR TABLE l.2-2 |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| | Of CODES AND STANDARDS FOR COMPONENTS Of WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE (ORDERED PRIOR TO JULY 1, 1971 WITH THE EXCEPTfONS OF THOSE COMPONENTS LOCATED INSIDE THE RCPB, ANO THE REACTOR PRESSURE VESSEL) |
| | |
| | CODE ClASSIFICA TIONS |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | COMPONENT CROUP A CROUP B CROUPC GROUP 0 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Neutron Monitoring System Guide Tubes, TIP (from Ball/Shear valve assembly through penetration to first connection) GE C,R B 2 III-2 I Y Guide Tubes, TIP (remainder of tube after first connection) GE C,R B 2 III-2 NA Y Valves, isolation, TIP subsystem GE C,R B 2 III-2 I Y Electrical modules, IRM and APRM GE C,R NA 2 IEEE-279 I Y Cable, IRM and APRM, with safety function P C,R NA 2 IEEE-279/383 NA Y 15 Non-Nuclear Instrumentation All portions that input to the reactor protection system GE C,R NA 2 IEEE-279 I Y All portions that input to the engineered safety feature actuation system P/GE C,R NA 2 IIII-279 I Y Engineered Safety Features Actuation System 7.3 All portions GE C,R NA 2 IEEE-279 I Y Engineered Safety Features Systems 7.3 (controls and instrumentation required for safety associated with each actuated system)
| |
| Emergency core cooling system GE C,R NA 2 IEEE-279 I Y Containment isolation system P C,R NA 2 IEEE-279 I Y Containment purge systems P C,R NA 2 IEEE-279 I Y (pressure boundary only)
| |
| Emergency diesel generator systems P,GH G,EG NA 2 IEEE-279 I Y Main steam line break detection system C,R,T NA 2 IEEE-279 I Y Controls and Instrumentation Associated with Safe 7.4 Shutdown Systems PCAMS P C,R B,D 2 IEEE-279 I Y FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 23 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Pressure Vessels ASME Soifer and Pressure Vessel ASME Boiler and Pressure Ve5sel ASME Boiler and Pressure Vessel ASME Boiler and Pressure Vessel Code, Section 111, Class A.. Code, s<<tion 111, Class C. Code, Section VIII, Division 1 Code, Section VIII, Division 1 or See Footnote (2) See Footnote (2) Equivalent |
|
| |
|
| ==SUMMARY==
| | 0-15 Psig - APl-620 with NOT Examination A.Pl-620 with NOT Examination APl-620 or Equivalent Storage Tanks Atmospheric - Applicable Storage Tank Codes Applicable Storage Tank Codes APl-650, AWWA.0100 or ANSI B Storage Tan ks such a, APl-650, A.WWA.D100 or such as APl-650 AWWAD100 or 96.1 or Equivalent ANSI B 96.1 with NOT ANSI B 96.1 with NOT Examination Examination |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Piping ANSI B.31.7, Class 1. ANSI 8 31.7, Clins II. ANSI 8 31.7, Class Ill. ANSI 8 31. 1.0 or Equivale-nt See Footnote (3) See Footnote (3) See footnote (3) |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Instrumentation Associated with Other Systems 7.6 Required for Safety Spent fuel pooling cooling system P R NA 2 IEEE-279 I Y Fuel handling area ventilation isolation system P R NA 2 IEEE-279 I Y Control room panels P CS NA 2 IEEE-279 I Y Local instrument racks associated with safety related equipment P ALL NA 2 IEEE-279 I Y Instrumentation Associated with Systems Not Required 7.7 for Safety Seismic Instrumentation P ALL NA Other NA I Y Area radiation monitoring P ALL NA Other NA NA N Leak Detection Instrumentation Temperature elements GE C,R,T 2 IEEE-323 I Y 39 Differential temperature switch GE C,R 2 IEEE-323 I Y 39 Differential flow indicator GE CS 2 IEEE-323 I Y 39 Pressure switch GE C,R 2 IEEE-323 I Y 39 Differential pressure indicator switch GE CS 2 IEEE-323 I Y 39 Differential flow summer GE CS 2 IEEE-323 I Y 39 Process Radiation Monitors Electrical modules, main steam line and reactor building ventilation monitor GE R NA 2 IEEE-323 I Y Cable, main steam line and reactor building ventilation monitors P R NA 2 IEEE-279/323/383 NA Y 15 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 24 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Pumps and Draft A.SME Code for Pumps and Ofaft ASME Code for Pumps and Draft ASME Code for Pumps and Valve! - ANSI S 3 t.1.0 or Equivalent Valves Valves Class I. Valves Class II. Valves Class tu. Pump -Draft ASME Code for Pumps See Footnote (1) & (4) See Footnote (1) & (4) See Footnote 14) Valves Class Ill or Equivalent |
|
| |
|
| ==SUMMARY==
| | (1 l All Pf@SSUre-t"etaining cast parts afe radiographed (or ultr.MOnically ~ted to equivalent standards). Where size or configuration does not permit eff PCtive volumetric examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance sl.lndards are al IE'ast equivalent to those specified in the applicabfe class In the code. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (2! 1968 Edition including Addenda through Summer 1970. |
| Comments
| |
| -Section -
| |
| Supply -Location- -
| |
| Classification Class Codes and Standards Category Requirement (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| ELECTRIC SYSTEMS 8 Engineered Safety Features AC Equipment 4.16 kV switchgear 8.3 P,GH R,G,EG NA 2 IEEE-308/323/344 I Y 480 V load centers P,GH R,EG NA 2 IEEE-308/323/344 I Y 480 V motor control centers P,GH R,G,EG NA 2 IEEE-308/323/344 I Y Engineered Safety Features DC Equipment 8.3 125 V and 250 V station batteries and racks, battery chargers P,GH CS,EG NA 2 IEEE-308/323/344 I Y 125 V switchgear and distribution panels P,GH CS,EG NA 2 IEEE-308/323/344 I Y 120 V Vital AC System Equipment 8.3 Static inverters P CS NA 2 IEEE-308/323/344 NA Y 120 V distribution panels P CS,R,EG NA 2 IEEE-308/323/344 I Y Electric Cables for ESF Equipment 8.3 5 kV power cables P ALL NA 2 IEEE-323/383 NA Y 15 600 V power cables P ALL NA 2 IEEE-323/383 NA Y 15 Control and instrumentation cables P ALL NA 2 IEEE-323/383 NA Y 15 Miscellaneous Electrical 8 Primary containment building electrical penetration assemblies P C NA 2 IEEE-317/344/383 I Y Conduit supports, safety related P ALL NA 2 IEEE-344 I Y 15 Tray supports, safety related P ALL NA 2 IEEE-344 I Y 15 Emergency lighting systems P ALL NA 2 IEEE-344 I Y 74 Emergency communications systems P ALL NA Other NONE NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 25 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (31 1969 Edition and Addenda. |
|
| |
|
| ==SUMMARY==
| | (4! NOYffl1ber 1968 Edition and March 1970 Addenda. |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Rev. 46, 06/93 SSES-FSAR Table Rev. 52 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * AUXILIARY SYSTEMS 9.3.1 Compressed Air and Instrument Gas Systems Compressors P,PL T,R,I,RW NA Other NONE NA N Pressure Vessels, for safety related equipment P C,R C 3 III-3 I Y Pressure vessels, not for safety related equipment P,PL ALL D Other VIII-1 NA N Piping and valves forming part of containment boundary P C,R B 2 III-2 I Y Piping and valves, safety related P C,R C 3 III-3 I Y Piping and valves, other P ALL D Other B31.1.0 NA N Nitrogen storage bottles P R NA Other DOT I N 64 Piping and supports - Diesel Generator E Building GH EG D Other B31.1 I N 49 Sampling Systems 9.3.2 Sample coolers P, PL R,T,RW D Other VIII-1 NA N TEMA C Piping and valves on III-1 systems P C A 1 III-1 I Y 10 Piping and valves on III-2 systems P R B 2 III-2 I Y 10 Piping and valves on III-3 systems P R C 3 III-3 NA Y 68 Piping and valves, other systems P R,T,RW D Other B31.1.0 NA N 10 Piping and valves, containment penetration, isolation P C A 1 III-1 I Y 10 Fire Protection System 9.5.1 Tanks P O D Other API-650/D100 NA N Pumps, piping and water system components P ALL NA Other NFPA/NEPIA NA N Gas system components (CO and Halon 1301) P CS NA Other NFPA/NEPIA NA N Fire and smoke detection and alarm system P ALL NA Other NFPA/NEPIA NA N Piping and supports - Diesel Generator E Building GH EG NA Other NFPA/NEPIA I N 49 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 26 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | TABLE 3.2-3 |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| | OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971 |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | CODE CLASSIFICATIONS |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * General External Hydrogen System Vessels P T D Other VIII-1 NA N Piping P T D Other B31.1.0 NA N Valves P T D Other B31.1.0 NA N Nitrogen System Vessels P O D Other VIII-1 NA N Piping P R,O,RW D Other B31.1.0 NA N Valves P O D Other B31.1.0 NA N Reactor Building Chilled Water System 9.2.12.2 Chillers P R D Other X/B9.1 NA N Chilled Water Heat Exchangers P R D Other VIII/ TEMA C NA N Pumps P R D Other VIII/ Hyd.I NA N 24 Piping P R D Other B31.1 NA N Valves P R B 2 III-2 I Y Isolation, Chilled Water to Primary Containment Remainder P R D Other B31.1 NA N Turbine Building Chilled Water System 9.2.12.3 Chillers P T D Other X/B9.1 NA N Chilled Water Heat Exchangers P T D Other VIII/TEMA C NA N Pumps P T D Other VIII/ Hyd.I NA N 24 Piping P T D Other B31.1 NA N Valves P T D Other B31.1 NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 27 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | COMPONENT GROUP A(1) GROUP B(2) GROUP C(3) GROUP D(4) |
|
| |
|
| ==SUMMARY==
| | Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code, Section III, Vessel Code, Section III, Vessel Code, Section III, Vessel Code, Section VIII, Nuclear Power Plant Nuclear Power Plant Nuclear Power Plant Division 1 Components - CLASS 1 Components - CLASS 2 Components - CLASS 3 |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Piping As above(5)(12)(14)(15)(17)(20) As above(6)(11)(14)(18)(20) As above (7)(14)(19)(20) ANSI B31.1 Power Piping(20) |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Radwaste Building Chilled Water System 9.2.12.4 Chillers P RW D Other X/B9.1 NA N Chilled Water Heat Exchangers P RW D Other VIII/TEMA C NA N Pumps P RW D Other VIII/Hyd.I NA N 24 Piping P RW D Other B31.1 NA N Valves P RW D Other B31.1 NA N Control Structure Chilled Water System 9.2.12.1 Centrifugal Water Chillers - (Except Condenser) P CS D 3 VIII I Y Centrifugal Water Chillers - Condenser P CS C 3 III-3 I Y Heat exchangers P CS D 3 VIII-1/TEMA C I Y Pumps P CS D 3 VIII-1/L Hyd.I I Y Motors P CS NA 3 IEEE-323/344 I Y Piping P CS D 3 B31.1 I Y Valves P CS D 3 B31.1 I Y Equipment and Floor Drains 9.3.3 Piping, radioactive P ALL D Other B31.1.0 NA N Piping, nonradioactive P ALL D Other B31.1.0 NA N Piping & valves, containment penetrating isolation P R,C B 2 III-2 I Y Piping and supports in Diesel Generator E Building -
| |
| nonradioactive GH EG NA Other B31.1 I N 49 Demineralized Water Makeup System 9.2.9 Tanks P CW D Other VIII-1 NA N Pumps P CW D Other B31.1.0/Hyd.I NA N 24 Motors P CW NA Other NEMA MG1 NA N Piping and Valves P ALL D Other B31.1.0 NA N Piping and supports - Diesel Generator E Building GH EG D Other B31.1 I N 49 FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 28 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | Pipe Supports As above As above(11)(13) As above(11)(13) ANSI B31.1 |
|
| |
|
| ==SUMMARY==
| | Pumps As above As above As above Manufacturers Standards |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | Valves As above As above As above ANSI B31.1 |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Buildings Reactor Building P R B 2 ACI/AISC I Y Pressure resistant doors P R B 2 ASTM/AWS NA Y AISC Watertight door P R B 2 ASTM/AWS NA Y R.B. Equipment door P R B 2 ASTM/AWS NA Y Primary Containment P C B 2 ACI/AISC/III I Y 27,30 Access hatches/locks/doors P C B 2 III-MC I Y Liner plate P C B 2 III-MC I Y Penetration assemblies P C B 2 III-MC I Y 29 Vacuum relief valves P C B 2 III-2 I Y Downcomers P C B 2 III-2 I Y 44 Downcomer Bracing P C B 2 AISC I Y Diesel Generator A-D Building P G NA 2 ACI/AISC I Y Control structure P CS NA 2 ACI/AISC I Y Radwaste and offgas building P RW NA Other ACI/AISC NA N 22 Turbine building P T NA Other ACI/AISC NA N 21 Administration Building P 0 NA Other ACI/AISC NA N Circulating water pump house P 0 NA Other ACI/AISC NA N ESSW pumphouse P 0 NA 3 ACI/AISC I Y Low Level Radwaste Holding Facility P 0 NA Other ACI/AISC /UBC NA N Diesel Generator E Building GH EG NA 2 ACI/AISC I Y FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 29 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | 0-15 psig --- As above(8) As above(8) AP-620 or ASME Boiler and Storage Tanks Pressure Vessel Code Section VIII, Division 1 |
|
| |
|
| ==SUMMARY==
| | Atmospheric --- As above(8) As above(8)(9)(10) API-650, AWWA D 100, Storage Tanks ANSI B 96.1, or ASME Boiler and Pressure Vessel Code Section VIII, Division 1 |
|
| |
|
| Source Quality Quality FSAR Of Group Safety Principal Construction Seismic Assurance Principal Components (34*)
| | (1)(2)(3)Components ordered after July 1, 1971 comply with the Codes and Standards in effect at the date of award of the order, except t hat Group A, B and C components ordered between July 1, 1971 and July 1, 1972 also comply with the following paragraphs of the ASME Boiler and Pressure Vessel Code, Section III, Winter, 1971 Addenda as applicable: (1) NB-2510, NB-2541, NB-2553, NB-2561, (2) NC-2510, NC-2571, (3) ND-2510, ND-2571. |
| Section Supply Location Classification Class Codes and Standards Category Requirement Comments (1)* (2)* (3)* (4)* (5)* (6)* (7)*
| |
| * Structures Roof Scuppers and Parapet Openings P R,CS,G NA 2 ACI/AISC NA Y Spray pond & Emergency Spillway P O NA 3 ACI I Y Condensate storage tank P O D Other D100 NA N Spent fuel pool, Rxwell,Dryer-Sep.Pool&Cask Pit P R NA 2 ACI/AISC I Y Spent fuel pool liner P R NA 2 ACI/AISC I Y Refueling water storage tank P O D Other D100 NA N Pipe Whip Restraints P R,C NA 3 AISC I Y Missile Barriers for safety related equipment P C,R,CS, NA Other ACI/AISC I Y SW,G Biological shielding within Primary containment, Reactor Building and Control Building P C,R,CS NA Other ACI/AISC I Y 42 Safety related masonry walls P R,G,CS NA Other ACI/UBC I Y New Fuel Storage Vault P R NA 2 ACI/AISC I Y Post Accident Monitoring 7.6 SRV position indication system P R NA 2 344 I Y Noble gas effluent radiological monitor PL T NA NA ANSI N13.1 NA N Continuous samples of plant effluents for radioactive iodine
| |
| & particulates PL T NA NA ANSI N13.1 NA N Containment hi-range radiation monitor P R NA 2 323/344 I Y Containment pressure monitor P R NA 2 323/344 I Y Containment Suppression pool water level instr. P R NA 2 323/344 I Y Containment H2/O2 monitor system P R NA 2 323/344 I Y 70 Hydrogen Water Chemistry System 9.5.9 Tanks NA O NA NA VIII NA N 67 Gas System Components NA O, T NA NA B31.1 NA N Piping NA O, T NA NA B31.1 NA N Passive Zinc Injection System 9.5.10 Vessel NA T NA NA VIII-1 NA N Piping and valves NA T NA NA B31.1 NA N FSAR Rev. 71
| |
| * Refer to the general notes at the end of this table. Page 30 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (4) Certain portions of the radwaste systems meet the additional requirements of Quality Group D (Augmented) as defined in NRC Branch Technical Position ETSB 11-1, Parts B.IV and B.VI. |
| | I |
|
| |
|
| ==SUMMARY==
| | (5)(6)(7) For installation of ASME items, ASME Section III, 1971 Edition with Addenda through the Winter of 1972 shall apply. ASME mater ial shall meet the requirements of ASME Section II, 1971 Edition th rough the Winter 1972 Addenda or any later Edition or Addenda. Any additional ASME Section III material require ments of Subsection 2000, 1971 Edition through the Winter 1972 Addenda, shall apply. For postweld heat treatment, Paragraphs NB-4600, NC-4600 and ND-4600 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used. |
|
| |
|
| General Notes and Comments
| | For the installation of attachments to piping systems after te sting, paragraphs NB-4436, NC-4436, and ND-4436 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used. |
| : 1) GE = General Electric GEH = General Electric - Hitachi PL = Pennsylvania Power & Light P = Bechtel as agents for Pennsylvania Power & Light GH = Gibbs and Hill (Architect/Engineer) and Dravo Constructors, Inc. as agents for Pennsylvania Power & Light AREVA = AREVA NP, INC. (for reload fuel) Formerly Framatome ANP, formally SPC)
| |
| TNW = Transnucléaire West NA = Not Applicable, see comments HI = Holtec International
| |
| : 2) Location C Part of or within primary containment R Reactor Building T Turbine Building CS Control Structure RW Radwaste and Offgas Building G Diesel Generator 'A - D' Building FSAR Rev. 71 Page 31 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | For attachments to piping systems, Paragraphs NB-4433, NC-4433 and ND-4433 of ASME Section III, 1977 Edition, Summer 1979 Addenda are used. |
|
| |
|
| ==SUMMARY==
| | For Code Nameplates, Stamping, and Data Reports, paragraphs NCA-8210, NCA-8220, NCA-8230, NCA-8300, NCA-8414, NCA-8415, NCA-8416, NCA-8417, NCA-8418, and NCA-8420 of ASME Section III, 1977 Edition, Winter 1977 Addenda are used. |
|
| |
|
| EG Diesel Generator E' Building I Intake Structure A Administration Building CW Circulating Water Pumphouse SW Engineering Safeguards Service Water (ESSW) Pumphouse CA Chlorine and Acid Storage Building ISFSI Independent Spent Fuel Storage Installation O Outdoors, Onsite
| | FSAR Rev. 65 Page 1 of 2 SSES-FSAR Table Rev. 52 |
| : 3) A,B,C,D - Quality group classification as defined in Regulatory Guide 1.26. The equipment shall be constructed in accordance with codes listed in Tables 3.2-2, 3.2-3, and 3.2-4.
| |
| NA - Not applicable to quality group classification
| |
| : 4) 1,2,3, other = safety classes defined in ANSI-N212 and Section 3.2.3.
| |
| NA - Not applicable to safety classification
| |
| : 5) Where shown this supplements information in Tables 3.2/2, 3.2/3, and 3.2/4. Notations for principle construction codes:
| |
| I ASME Boiler and Pressure Vessel Code, Section I III 1,2,3, NA, NF, NG, MC = ASME Boiler and Pressure Vessel Code Section III, Class 1,2,3 or MC, or subsection NA, NF or NG FSAR Rev. 71 Page 32 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | TABLE 3.2-3 (Continued) |
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| ==SUMMARY== | | ==SUMMARY== |
| | OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971 |
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| VIII-1 ASME Boiler and Pressure Vessel Code, Section VIII, Div. 1 NP&V-II ASME Nuclear Pressure & Valve Code, Class II API-650 American Petroleum Institute, Welded Steel Tanks for Oil Storage API-620 American Petroleum Institute, Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage Tanks B9.1 ANSI B9.1, Safety Code for Mechanical Refrigeration B31.1.0 ANSI B31.1.0, Code for Pressure Piping SMACNA Sheet Metal & Air Conditioning Contractors National Assoc., Inc.
| | (8) Orders for Nuclear Storage Tanks were placed after December 31, 1971. |
| HEI Heat Exchange Institute TEMA C Tubular Exchanger Manufacturers Assoc., Class C HYD.I Hydraulic Institute AISC American Institute of Steel Construction AISI American Iron and Steel Institute, "Specification for the Design of Coldformed Steel Structural Members",
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| 1968, "Design of Light Gage Cold-Formed Stainless Steel Structural Members", 1968 ACI American Concrete Institute AMCA AMCA 210 "Test Codes for Air Moving Devices" AMCA 211 A "AMCA Certified Ratings Program for Air Performance" AWS D1.1 American Welding Society, Structural Welding Code FSAR Rev. 71 Page 33 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (9) Atmospheric Storage Tanks fabricated to Group C requirements may be used in a Group D or Group D (Augmented) system. |
|
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|
| ==SUMMARY==
| | (10) The Diesel E Fuel Oil Storage Tank Complies with ASME B&PV Code Section III, 1971 Edition, Winter 1972 Addenda. The A-D Die sel Generator Fuel Oil Storage Tanks comply with the ASME Boiler and Pressure Vessel Code, Section III, 1974 Edition, Winter 1975 A ddenda as applicable. |
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| AWWA American Water Works Association CS-8T American Association for Contamination Control, AACC CS-8T, "Tentative Standard for High-efficiency Gas Phase Adsorber Cells" July, 1972 DEMA Diesel Engine Manufacturer Association, "Standard Practices for Stationary Diesel and Gas Engines", 1971 D100 American Waterworks Association, AWWA-D100 "Standard for Steel Tanks Standpipes, Reservoirs and Elevated Tanks for Water Storage" NEC National Electrical Code NEMA National Electrical Manufacturer's Association NEMA MG1 National Electrical Manufacturers' Association, NEMA-MG-1, 1971 "Motors and Generators" NEMA SM22 National Electrical Manufacturers' Association, NEMA-SM-22, 1970, "Single Stage Steam Turbine for Mechanical Drive Service" IEEE-279 IEEE-279, Criteria for Protection Systems for Nuclear Power Generating Stations - 1971.
| | (11) Control Rod Drive Hydraulic System (CRD) piping and supports are constructed in accordance with ASME Section III, 1974 Edition with Addenda through Winter 1975 except as permitted by NA-1140(f) of ASME III as follows. Materials conform with ASME Section III, 1974 Edition, with Addenda through Winter 1975, or any later Edition of Addenda. ASME Section III, 1977 Edition, with Addenda through Winter 1977, |
| IEEE-308 IEEE-308, Standard Criteria for Class IE Electric Systems for Nuclear Power Generating Stations 1974 IEEE-317 IEEE-317, Standard for Electrical Penetration Assemblies in Containment Structures for Nuclear Fueled Power Generating Stations - 1972 IEEE-323 IEEE-323, General Guide for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations - 1974 IEEE-344 IEEE-344, Guide for Seismic Qualification of Class IE Electric Equipment for Nuclear Power Generating Stations - 1971 (1975 version used for the Diesel Generator E' Facility)
| | Subsection NF, Paragraph NF-2610, shall apply to piping system support. |
| FSAR Rev. 71 Page 34 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (12) 1 and smaller Nuclear Class 1 Piping is designed in accordance with the rules for Nuclear Class 2 piping per ASME Section III, 1974 Edition, Summer 1975 Addenda, Paragraph NB3630. |
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| ==SUMMARY==
| | (13) Allowable stresses for pipe supports for Nuclear Class 1, 2 and 3 piping shall be in accordance with ANSI Power Piping Code B3 1.1, 1973. |
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| IEEE-383 Type Test of Class IE Electrical Cables, Field Splices, and Connections for Nuclear Power Generating Stations-1975 IEEE-387 IEEE-387, Criteria for Diesel Generator Units applied as Standby Power Supplies for Nuclear Power Generating Stations - 1972 HSI-306 Health and Safety Information, USAEC, Revised Minimal Specification for the High Efficiency Particulate Air Filter. Issue No. 306 NFPA National Fire Protection Association NEPIA Nuclear Energy Property Insurance Association ARI Air Conditioning and Refrigeration Institute DOT Department of Transportation - Title 49, Section 178.37, Specification 3AA D1.1 See AWS-D1.1 above UBC Uniform Building Code NA None Applicable x Manufacturer's Standards AA Aluminum Association Standard for Aluminum Structures
| | (14) For the design of ASME flanges, ASME Section III, 1977 Edition with addenda through summer 1979 is used. |
| : 6) I - The equipment shall be constructed in accordance with the seismic requirements for the Safe Shutdown Earthquake, as described in Section 3.7.
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| NA - The seismic requirements for the Safe Shutdown Earthquake are not applicable to the equipment or structure.
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| FSAR Rev. 71 Page 35 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (15) For the design of Nuclear Class 1, 1 branch connections, ASME Section III, 1977 Edit ion with Addenda through Summer 1979 is used. |
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| ==SUMMARY==
| | (16) Code case N316, approved for use at Susquehanna SES by the NRC on 2/17/82, is used in the Bechtel design of small pipe and CRD small pipe. |
| : 7) Y - Requires compliance with the requirements of 10CFR50, Appendix B in accordance with the quality assurance program described in Chapter 17.
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| N - Not within the scope of 10CFR50, Appendix B.
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| : 8) This note has been intentionally left blank.
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| : 9) The following qualification shall be met with respect to the certification requirements:
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| : 1. The manufacturer of the turbine stop valves, turbine control valves, turbine bypass valves, and main steam leads from turbine control valve to HP turbine casing shall use quality control procedures equivalent to those defined in General Electric Publication GEZ/4982A, "General Electric Large Steam Turbine-Generator Quality Control Program".
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| : 2. A certification shall be obtained from the manufacturer of these valves and steam leads that the quality control program so defined has been accomplished.
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| : 10) 1. Instrument and sampling piping from the point where they connect to the process boundary and through the process shutoff (root) valve(s), isolation valve(s), and excess flow check valve, when provided, will be of the same classification as the system to which they connect.
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| : 2. See Figure 3.2-2 for instrument line classifications.
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| : 3. Other instrument lines:
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| a) Those connected to special equipment or Group D system pressure boundaries and utilized to actuate safety systems will be Group C from the system pressure boundary through the process shutoff valve(s) to the sensing instrumentation.
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| b) Those connected to Group B and Group C systems and not utilized to actuate safety systems will be of Group D classification except for those Group C systems by GE utilizing capillary (filled and sealed) instrument lines.
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| c) Those connected to Group D systems and not utilized to actuate safety systems will be of Group D classification.
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| FSAR Rev. 71 Page 36 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (17) For the evaluation of Nuclear Class 1 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1977 edition with addenda through summer of 1979 may be applied. |
|
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| ==SUMMARY==
| | (18) For the evaluation of Nuclear Class 2 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1980 edition with addenda through winter of 1981 may be applied. |
| : 4. For sample lines connected to the Reactor Recirculation System, the sample line shall be Group A through the penetration to the outboard containment isolation valve and Group D from the isolation valve to the shutoff valve outside the sample station.
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| : 11) The HPCI and RCIC turbines do not fall within the applicable design codes. To ensure that the turbine is fabricated to the standards commensurate with their safety and performance requirements, General Electric has established specific design requirements for this component.
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| : 12) The hydraulic control unit (HCU) is a General Electric factory assembled, engineered module of valves, tubing, piping, and stored water which controls a single control rod drive by the application of precisely timed sequences of pressures and flows to accomplish slow insertion or withdrawal of the control rods for power control, while providing rapid insertion for reactor scram.
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| Although the hydraulic control unit is field installed and connected to process piping, many of its internal parts differ markedly from process piping components because of the more complex functions they must provide. Thus, although the codes and standards invoked by the Group A, B, C, and D pressure integrity quality levels clearly apply at all levels to the interfaces between the HCU and the connecting conventional piping components (eg, pipe nipples, fittings, simple hand valves, etc.), it is considered that they do not apply to the specialty parts (eg, solenoid valves, pneumatic components and instruments).
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| The design and construction specifications for the HCU do invoke such codes and standards as can be reasonably applied to individual parts in developing required quality levels, but these codes and standards are supplemented with additional requirements for these parts and for the remaining parts and details. For example, (1) all welds are LP inspected, (2) all socket welds are inspected for gap between pipe and socket bottom, (3) all welding is performed by qualified welders, (4) all work is done per written procedures.
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| The following examples are typical of the problems associated with codes designed to control field assembled components when applied to the design and production of factory fabricated specialty components:
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| : 1. The HCU nitrogen gas bottle is a punch forging which is mechanically joined to the accumulator. It stores the energy required to scram a drive at low vessel pressures. It has been code stamped since its introduction in 1966, although its size exempts it from mandatory stamping. It is constructed of a material listed by ASME B&PV Code Section VIII which was selected for its strength and formability.
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| FSAR Rev. 71 Page 37 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (19) For the evaluation of Nuclear Class 3 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1983 edition with addenda through summer of 1984 may be applied. |
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| ==SUMMARY==
| | (20) For the evaluation of ASME piping components or ANSI piping components which are analyzed for Seismic Category I requirements, Code Case N-411 may be applied for Snubber Elimination or other piping modifications/evaluations. |
| : 2. The scram accumulator is joined to the HCU by a split flange joint chosen for its compact design to facilitate both assembly and maintenance. Both the design and construction conform to ANSI B31.1.0 Power Piping Code. This joint, which requires a design pressure of 1750 psig, has been proof tested to 10,000 psi.
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| : 3. The accumulator nitrogen shutoff valve is a 6,000 psi cartridge valve whose copper alloy material is listed by ASME B&PV Code Section VIII. The valve was chosen for this service partly because it is qualified by the U.S. Navy for submarine service.
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| : 4. The directional control valves are solenoid pilot operated valves which are subplate mounted on the HCU. The valve has a body specially designed for the HCU, but the operating parts are identical to a commercial valve with a proven history of satisfactory service. The pressure containing parts are stainless steel alloys chosen for service, fabrication and magnetic properties. The manufacturer cannot substitute a code material for that used for the solenoid core tube.
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| The foregoing examples are not meant to justify one pressure integrity quality level or another, but to demonstrate the codes and standards invoked by those quality levels are not strictly applicable to special equipment and part designs.
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| Group D Classification is generally applicable, supplemented by the QC techniques described above. Thus, the Hydraulic Control Unit shall be classified as "Special Equipment".
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| : 13) This Note Has Been Deleted.
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| : 14) This Note Has Been Deleted.
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| : 15) The trays and supports for safety related cables meet Seismic Category I and 10CFR50, Appendix B requirements, except in the turbine building. All Class IE and affiliated circuits, including RPS circuits located in a non-Seismic Category I structure (i.e. Turbine Building) are contained within Class IE, Seismic Category I raceways although they are supported from a non-Seismic Category I structure. (See Subsection 3.7b.2.8 for seismic information about the turbine building).
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| : 16) AEC Regulatory Guide 1.52, June 1973, suggests various industry standards and codes for this equipment. These references were used for system design, with exceptions as noted in section.
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| : 17) AMCA Publication 211A, "AMCA Certified Ratings Program for Air Performance" or AMCA Standard 210, "Test Codes for Air Moving Devices" can be used for blower design purposes.
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| FSAR Rev. 71 Page 38 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | FSAR Rev. 65 Page 2 of 2 SSES-FSAR |
|
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|
| ==SUMMARY==
| | TABLE 3.2-4 CODE GROUP DESIGNATIONS FOR MECHANICAL COMPONENTS SUPPLIED BY THE NSSS VENDOR -INDUSTRY CODES AND STANDARDS |
| : 18) This section of steam piping was seismically analyzed to ensure that it will not fail under loadings normally associated with an SSE.
| | {SEE NOTE a) |
| : 19) All or part of this component is constructed to a more stringent code or standard than indicated.
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| : 20) The MSS from its outer isolation valve up to and including the turbine stop valve and all branch lines 2-1/2 in. in diameter and larger, up to and including the first valve (including their restraints) shall be designed by the use of an appropriate dynamic seismic-system analysis to withstand the Operating Bases Earthquake (OBE) and Safe Shutdown Earthquake design loads in combination with other appropriate loads, within the limits specified for Class 2 pipe in the ASME, Section III Code. The mathematical model for the dynamic seismic analyses of the MSS and branch line piping shall include the turbine stop valves and piping beyond the stop valves including the piping to the turbine casing. The dynamic input loads for design of the MSS shall be derived from a time history model analysis (or an equivalent method) of the reactor and applicable portions of the turbine building. An elastic multi-degree-of-freedom system analysis shall be used to determine the input to the MSS. The stress allowable and associated deformation limits for piping shall be in accordance with the ASME Section III Class 2 requirements for the OBE and SSE loading combinations. The MSS supporting structures (those portions of the turbine building) shall be such that the MSS and its supports can maintain their integrity.
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| : 21) The power conversion system structures may be constructed in accordance with applicable codes for steam power plants.
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| Those portions of the turbine building interacting with the main steam lines and branch lines are analyzed to show that system integrity is maintained for the main steam lines and branch lines during the SSE.
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| : 22) The lower quality group classification, associated construction codes and seismic category are appropriate for this system as a result of analysis per regulatory guides 1.26 and 1.29. The loss of effluent from system components was analyzed to demonstrate that the site boundary dose would not exceed .5 Rem. The classifications indicated in the table are considered justified for the aforementioned doses.
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| : 23) These components and associated supporting structures must be designed to retain structural integrity during and after the SSE but do not have to retain operability for protection of public safety. The basic requirement is prevention of structural collapse and damage to equipment and structures required for protection of the public safety and health.
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| FSAR Rev. 71 Page 39 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | A A 1 ASME III, 1 ASHE Ill, 1 NA & NB Subsections TEHA C NA & NB Subsection TEHA C note (d) e 8*,C 2,MC* ASHE 1H, 8,. C ASHE III, 2 & HC*, |
| | ANSI B3U II NA & NC Subsections NP & VC, NA & NE Subsections TEMA C TANKS TEHA C TANKS NA, NC Note(d) |
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|
| ==SUMMARY==
| | C 3 ASME VIII, Div. l ASME III, 3 ANSI B31.7, NP & VC, IIJ IlI TEMA C NA & ND Subsections TANKS NA, ND TEHA C TANKS Note (d) |
| : 24) There is no established standard for commercial pumps. ASME Section VIII, Division 1 and ANSI B31.1.0 Power Piping represent related, available standards which, while intended for other applications, are used for guidance and recommendations in determining quality group D pump allowable stresses, steel casting quality factors, wall thicknesses, materials compatibility and specifications, temperature pressure environment restrictions, fittings, flanges, gaskets, and bolting, installation procedures, etc.
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| : 25) This Note Has Been Deleted.
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| : 26) The shell side of the nonregenerative heat exchanger was constructed in accordance with ASME Section VIII, Division I.
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| The regenerative and nonregenerative heat exchangers were also constructed to TEMA Class R requirements.
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| : 27) The containment spray ring header and connecting piping extending from the containment isolation valve meets all of the requirements of Group B except that hydrostatic testing is not required.
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| : 28) The HPCI and RCIC turbine exhaust lines extending from the containment isolating valve to the suppression pool meets all of the requirements of Group B except that hydrostatic testing of this portion of the piping is not required.
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| : 29) Piping which penetrates the containment, thus acting as an extension of the containment pressure boundary meets the requirements of Group B or higher. This requirement extends from the first pipe weld on the inside of the penetration to and involving the first isolation valve outside the containment.
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| : 30) Reinforced concrete primary containment, including drywell head, hatches, vent pipes, penetrations and spare penetrations are in accordance with Pennsylvania Special Certification. Personnel locks are in accordance with ASME Code Section III, Subsection NE, 1971 Edition, up to and including Addenda of Summer, 1972.
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| : 31) Systems and components so designated conform to Quality Group D (Augmented) as defined in NRC Branch Technical Position ETSB 11-1 (Rev. 1) Parts B. IV and B.VI. The Gaseous Radwaste System also conforms to the seismic requirements defined in NRC BTP ETSB-11-1 (Rev. 1) Part B. II. a (3).
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| FSAR Rev. 71 Page 40 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | D ASME VIII, Div. 1 ASME VIII, Div. 1 ANSI 831.1.0 ANSI 831.1.0 TEMA C TANKS (b) TEHA C TANKS (b) |
| | Note (cl Hate (c) |
| | * Hetal concrete containment vessels under ASME containment vessel (as applicable) Section and extens1ons III, Divisions 2, at which time the requirements of of containment only. Future addenda will include this division shall also be 111et. |
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|
| ==SUMMARY==
| | NOTES: |
| : 32) The feedwater lines from the reactor vessel through the third isolation valve are part of the reactor coolant pressure boundary. | |
| The classification of the feedwater line from the reactor vessel through the second isolation valve is Group A. The classification of the feedwater line from the second isolation valve through the third valve is Group B. These classifications are in accordance with Regulatory Guide 1.26 Revision 3, February 1976. Beyond the third valve the classification is Group D.
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| : 33) 1. The main steam leads from the turbine control valve to the turbine casing meets all of the requirements of Group D plus the addition of the following requirements:
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| : a. All longitudinal and circumferential butt weld joints are radiographed (or ultrasonically tested to equivalent standards). Where size or configuration does not permit effective volumetric examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance standards are at least equivalent to those specified in ANSI B31.1.0 Power Piping Code.
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| : b. All fillet and socket welds are examined by either magnetic particle or liquid penetrant methods. All structural attachment welds to pressure retaining materials are examined by either magnetic particle or liquid penetrant methods. Examination procedures and acceptance standards are at least equivalent to those specified in ANSI B31.1.0 Power Piping Code.
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| : c. All inspection records are maintained for the life of the plant. These records include data pertaining to qualification of inspection personnel, examination procedures, and examination results.
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| OR
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| : 2. The manufacturer of the main leads utilized quality control procedures equivalent to those defined for main steam leads in the General Electric Publication GEZ-4982, "General Electric Large Steam Turbine-Generator Quality Control Program".
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| A certification has been obtained from the manufacturer of the main steam leads that the quality control so defined has been accomplished.
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| : 34) This Note Has Been Deleted.
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| FSAR Rev. 71 Page 41 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (a) Wtth options and additions as necessary for service conditions and environmental requirements. |
| | (b) Class D tanks shall be designed, constructed, and tested to meet the intent of AP[ Standards 620/650, AWA Standard DlOO, or ANSI 896. 1 Standard for Aluminum Tanks. |
| | (c) For pumps classified Group O and operating above 150 psi or 212"F, ASHE Section VIII, Div. 1 shall be used as a guide in calculating the wall thickness for pressure retaining parts and In siling the cover bolting. For pumps operating below 150 psi and 212°F, manufacturer's standard pump for service Intended may be used. |
| | (d) For pumps classified A, B, or C applicable Subsections NB, NC, or NO respectively In Pressure Vessel Code, Section Ill shall be used as a guide In calculating the thickness of pressure ASHE Boiler and retaining portions of the pump and In sizing cover bolting, |
|
| |
|
| ==SUMMARY==
| | Rev. 48, 12/94 SSES-FSAR |
| : 35) The control rod drive insert and withdraw lines from the drive flange, up to and including the first valve on the hydraulic control unit shall be Safety Class 2.
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| : 36) These Notes Have Been Deleted.
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| : 37) This Note Has Been Deleted.
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| : 38) The turbine does not fall within the applicable design codes. To ensure that the turbine is fabricated to the standards commensurate with their safety and performance requirements, General Electric has established specific design requirements for this component which are as follows:
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| : a. All welding shall be qualified in accordance with Section IX, ASME Boiler and Pressure Vessel Code,
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| : b. All pressure-containing castings and fabrications shall be hydrotested in 1.5 X design pressure,
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| : c. All high-pressure castings shall be radiographed according to:
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| ASTM E-94 E-142 maximum feasible volume E-71, 186 or 280 Severity level 3
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| : d. As-cast surfaces shall be magnetic particle or liquid penetrant tested according to ASME, Section III, Paragraph N-232.4 or N-323.3,
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| : e. Wheel and shaft forgings shall be ultrasonically tested according to ASTM A-388,
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| : f. Butt-welds shall be radiographed according to ASME, Section III, Paragraph N624, and magnetic particle or liquid penetrant tested according to ASME Section III, Paragraph N626 or N627 respectively,
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| : g. Notification to be made on major repairs, and records maintained thereof, and
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| : h. Record system and traceability according to ASME Boiler and Pressure Code Section III, Appendix IX, Paragraph IX 225.
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| FSAR Rev. 71 Page 42 of 47 | |
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | TABLE 3.2-5 |
|
| |
|
| ==SUMMARY== | | ==SUMMARY== |
| : 39) These safety grade instruments provide signals for alarms and/or isolation in the following areas and are collected into this table in one area for ease of identification. Systems: Nuclear Boiler; RHR; RCIC; HPCI; RWCU.
| | OF SAFETY CLASS DESIGN REQUIREMENTS (MINIMUM) |
| : 40) This note has been intentionally left blank.
| | |
| : 41) Sample piping and isolation valves are quality group B. Because the analyzers are isolated from containment atmosphere on accident conditions, the piping in the analyzers is quality group D. Isolation is manually removed to allow monitoring.
| | .. 3 Other 2:. |
| : 42) Reactor shield wall concrete is a non-structural element (see subsection 3.8.3.1.3) and is therefore non-Category I. Shield wall concrete, because of concrete placement, is non-safety related.
| | Quality Group A B C D Cl ass i fi cat i on< 1 > |
| : 43) Code Case 1481-1 has been used because the design temperature of the piping involved is greater than 700°F. ASME Sec.
| | Quality Assurance B B B N/A Reoui rement<i!> |
| III Appendix Table 1-7.2 only gives allowable stress data up to 700°F. The use of this code case allows stress analysis to be done using stress values in accordance with stress tables of ASME Sec. VIII Division I.
| | Seismic Categor_v<3 > I I I N/A |
| : 44) ASME Boiler and Pressure Vessel Code, Division 1 Section III Subsection NC has been used for design and fabrication of the downcomers. | |
| : 45) Shipping casks will not be bought. They will be rented from the shipper.
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| : 46) Portions of embedded fuel pool piping are B31.1.
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| : 47) Seismically qualified for operating basis earthquakes.
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| : 48) The main steam line plugs are supplied by GE-Hitachi and have integral installation tools. The plugs are designed to withstand a design pressure of 60 psig from the steam line side and 16 psig from the vessel side. The plugs also have cable lanyards designed to prevent a dropped plug from reaching the upper core support plate during installation or removal of the plugs. The main steam line plugs are considered as safety-related components and the cable and installation tool are classified as non-quality.
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| : 49) All non-safety related piping inside the diesel generator E building has been seismically supported to satisfy Seismic Category 1 requirements in order to eliminate potential safety impact item concerns.
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| FSAR Rev. 71 Page 43 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | (1) The equipment shall be constructed in accordance with the indicated code group listed in Table 3.2-1 and defined in Tables 3.2-2, 3.2-3, and 3.2-4. |
|
| |
|
| ==SUMMARY==
| | (Z) B - The equipment shall be constructed in accordance with the quality assurance requirements of IOCFR50, Appendix B. |
| : 50) Table notations do not reflect seismic island design. For a further description on seismic island reference FSAR Subsection 6.2.3.2.3.1.
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| : 51) The Unit #1 offgas recombiner condenser is a dual code vessel. The shell is ASME Section VIII and the bonnet, tubes, and tube sheet are Section III. Section III is in excess of ESTB11-1 requirement but is remaining as Section III due to the inability of the shell supplier to re-stamp the entire condenser as Section VIII.
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| : 52) The Reactor and Turbine Building Closed Cooling Water System Heat Exchangers are presented separately.
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| : 53) For the strongback/carousel with integral nut-rack, compliance with the requirements of 10CFR50 Appendix B, (refer to column "Quality Assurance Requirements" and Note 7) is required only for the strongback components which are load-bearing during the RPV head lift. All other components are not within the scope of 10CFR50 Appendix B.
| |
| : 54) The diesel generator jacket water coolers (OE507B and OE507D) utilize an ASME Section VIII replacement tube bundle in accordance with the guidance of NRC Generic Letter 89-09.
| |
| : 55) The following manually operated valves provide a fillable volume for use of the RHRFPC mode.
| |
| The following manually operated valves, which are in the seismically analyzed sections of pipe, require a capability to be closed following a seismic event. These valves have been analyzed to demonstrate that they will be capable of closure following a seismic event:
| |
| Spent Fuel Pool to 153018A/B (253018A/B), Fuel Pool Gate Drain to 153038 (253038), and Reactor Well Diffuser to 15303OA/B (25303OA/B).
| |
| The following manually operated valves, which are in seismically analyzed sections of pipe, have a post seismic event function to remain in the closed position:
| |
| Reactor Well Drain to 153031 (253031), Reactor Well Drain to 153032 (253032), Reactor Well Drain to 153062 (253062),
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| Dryer Separator Pool Drain to 153040 (253040), Dryer Separator Pool Drain to 153041 (253041), Cask Pit Gate Drain to 153050 (2503050), Cask Pit Drain to 153054 (253054), Cask Pit Drain to 053084 & 253800, and Cask Pit Diffuser to 053025.
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| FSAR Rev. 71 Page 44 of 47
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| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | N/A - The equipment shall be constructed in accordance with the quality assurance requirements consistent with accepted practice for steam power plants. |
|
| |
|
| ==SUMMARY==
| | (3) I - The equipment for these safety classes shall be constructed in earthquake as described in Section 3.7. accordance with the seismic requirements for the safe shutdown |
| : 56) The portions of piping between the surge tank up to and including Valves HV15308 (25308), 153076 (253076), and 153064A/B (253064A/B) have been analyzed to show that they will remain intact following a seismic event. These valves have been analyzed to demonstrate that they will be capable of closure (or remaining closed) following a seismic event.
| |
| Closure of these valves is necessary to provide a fillable volume for use of the RHRFPC mode. The Skimmer Surge Tank Drain Line Valves, 153065A (253065A), are normally closed and assumed to remain closed during a seismic event.
| |
| : 57) Refuel Floor Wetlift System: The Main Steam Line (MSL) Plugs (Disk Spring Model) are supplied by Preferred Engineering.
| |
| The MSL Plugs are designed to withstand a design pressure of 50 psig. The MSL Plugs Restraint Ring supplied by Preferred Engineering provides a mechanical means to prevent ejection of the MSL Plugs while moving fuel during 45.4 psig Local Leak Rate Test (LLRT) of Main Steam Isolation Valve (MSIV) and during 22.5 psig back pressurization LLRT of MSIV.
| |
| : 58) Qualified for Safe Shutdown Earthquake (SSE).
| |
| : 59) Refuel Floor Wetlift System: The Watertight Hook Box is supplied by Preferred Engineering for use with the Dryer and Separator Sling.
| |
| : 60) Refuel Floor Wetlift System: The Rigid Pole Handling System is supplied by ABB Combustion Engineering for use on the Unit 1 or 2 Refueling Platforms.
| |
| : 61) ASME Section III - NB-3674 Design of Pipe Supporting Elements states that supporting elements, including hangers, anchors, and sliding components shall be designed in accordance with NF-3600. (Pending completion of Subsection NF, supporting elements shall be designed in accordance with the requirements of ANSI B31.7-1969).
| |
| ANSI B31.7 and MSS-SP-58 (included by reference in ANSI B31.7) were the principal design codes for the GE portion of the suspension system.
| |
| : 62) The NUHOMS Horizontal Storage Modules and Dry Shielded Canisters and the Holtec Multi-Purpose Canisters and HI-STORM FW overpacks are designed in accordance with 10CFR72. These components are designated as "Important to Safety".
| |
| : 63) The Dry Shielded Canister (DSC) is designed to meet the intent of ASME Section III, Subsection NB and the DSC Basket is designed to meet the intent of the ASME Section III, Subsections NF and NG, however the DSC is not a code vessel.
| |
| Utilization of this ASME criterion meets or exceeds the requirements of 10CFR72.
| |
| FSAR Rev. 71 Page 45 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | N/A - The seismic requirements for the safe shutdown earthquake are not applicable to the equipment of this classification. |
|
| |
|
| ==SUMMARY==
| | Rev. 48, 12/94 Security-Related Information Figure Withheld Under 10 CFR 2.390 |
| : 64) Bottles conform to Department of Transportation (DOT) Standards, Title 49, Section 178.37, Specification 3AA. These bottles and associated connection assemblies are not available as Seismic Category I components. However, the bottles are mounted in Seismic Category I racks and are connected to Seismic Category I gas distribution piping.
| |
| : 65) Seismic Category I and Quality Assurance Requirement Y applies to the safety related subsystems (Motors, Fans, Cooling Coils, Ductwork and Dampers) of Drywell Unit Coolers 1V414A/B, 1V416A/B and the Recirculation Fans 1V418A/B. The Seismic Category for all other subsystems of Drywell Unit Coolers is safety impact type. The Quality Assurance requirements for all other subsystems of Drywell Unit Coolers is N.
| |
| : 66) The SLC System Storage Tanks were purchased before Article NC-3800 on atmospheric tanks was included in the ASME Section III, Class 2 code. The tanks were designed and fabricated to API-650 and supplemental ASME Section III, Class C testing and examination requirements and therefore, meet Quality Group B requirements.
| |
| : 67) Hyrodgen Water Chemistry System: The hydrogen and oxygen storage tanks and associated equipment are located south of the Unit 2 turbine building, outside of the plant security boundary. The storage facility is owned, operated and maintained by a commercial gas supply vendor.
| |
| : 68) ASME Section III, Class 3 sample piping consists of those sample lines connected to the RWCU and FPCC Systems. These portions of the RWCU and FPCC Systems are design and constructed as ASME Section III, Class 3, yet are not Seismic Category I.
| |
| : 69) This section does not apply to the H2O2 Analyzers. See Post Accident Monitoring for the design criteria for the H2O2 Analyzers.
| |
| : 70) The design of the H2O2 Analyzer closed system outside primary containment is in accordance with the design requirements for such systems specified in USNRC Standard Review Plan 6.2.4 (September 1975), Containment Isolation Provisions, paragraph II.3.e., except as follows. The boundary valves between the H2O2 Analyzer and Post Accident Sampling System (i.e.,SV-1(2)2361, SV-1(2)2365, SV-1(2)2366, SV-1(2)2368, & SV-1(2)2369) are not electrical Class 1E. See Figure 3.2-2, requirements for instruments which are open to containment and form a containment pressure boundary for additional guidance regarding piping/tubing classification.
| |
| : 71) The Jet Pump Plugs are supplied by Preferred Engineering. The Jet Pump Plugs are designed to withstand a design pressure of 100 psi.
| |
| FSAR Rev. 71 Page 46 of 47
| |
|
| |
|
| SSES-FSAR Table Rev 77 TABLE 3.2-1 SSES DESIGN CRITERIA
| | SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT |
|
| |
|
| ==SUMMARY==
| | CODE CLASSIFICATION OF PIPING AND VALVES |
| : 72) The referenced military standards (MIL-F-51068C and MIL-F-51079A) have been deleted, but represent acceptable standards for installed (or previously purchased) HEPA filters. New HEPA filters will meet the standards presented in ASME AG-1-1997.
| |
| : 73) The Service Platform is not used and has been eliminated.
| |
| : 74) 8-hour battery powered emergency lighting units are seismically mounted for II/I concerns. Units are not qualified as functional through a seismic event.
| |
| FSAR Rev. 71 Page 47 of 47
| |
|
| |
|
| SSES-FSAR TABLE l.2-2
| | FIGURE 3.2-1 Restricted Orifice Adapter Process or Excess Flow Pipe Check Valve (Note 1) (See Note 3) Instrument, Instrument |
|
| |
|
| ==SUMMARY==
| | Panel, Instrument Valve Root Valve ASME Section I I I Class 2 Class 1 (See Note 4) |
| Of CODES AND STANDARDS FOR COMPONENTS Of WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE (ORDERED PRIOR TO JULY 1, 1971 WITH THE EXCEPTfONS OF THOSE COMPONENTS LOCATED INSIDE THE RCPB, ANO THE REACTOR PRESSURE VESSEL)
| | Class 2 Class 3 INSTRUMENTS REQUIRED (See Note 2) TO OPERATE SAFETY SYSTEMS Class 3 Class 3 (See Note 2) |
| CODE ClASSIFICATIONS COMPONENT CROUP A CROUP B CROUPC GROUP 0 Pressure Vessels ASME Soifer and Pressure Vessel ASME Boiler and Pressure Ve5sel ASME Boiler and Pressure Vessel ASME Boiler and Pressure Vessel Code, Section 111, Class A.. Code, s<<tion 111, Class C. Code, Section VIII, Division 1 Code, Section VIII, Division 1 or See Footnote (2) See Footnote (2) Equivalent 0-15 Psig Storage Tanks
| |
| - APl-620 with NOT Examination A.Pl-620 with NOT Examination APl-620 or Equivalent Atmospheric Storage Tan ks
| |
| - Applicable Storage Tank Codes such a, APl-650, A.WWA.D100 or Applicable Storage Tank Codes such as APl-650 AWWAD100 or APl-650, AWWA.0100 or ANSI B 96.1 or Equivalent ANSI B 96.1 with NOT ANSI B 96.1 with NOT Examination Examination Piping ANSI B .31.7, Class 1. ANSI 8 31.7, Clins II. ANSI 8 31.7, Class Ill. ANSI 8 31 .1.0 or Equivale-nt See Footnote (3) See Footnote (3) See footnote (3)
| |
| Pumps and Draft A.SME Code for Pumps and Ofaft ASME Code for Pumps and Draft ASME Code for Pumps and Valve! - ANSI S 3 t.1 .0 or Equivalent Valves Valves Class I. Valves Class II. Valves Class tu. Pump - Draft ASME Code for Pumps See Footnote (1) & (4) See Footnote (1) & (4) See Footnote 14) Valves Class Ill or Equivalent (1 l All Pf@SSUre-t"etaining cast parts afe radiographed (or ultr.MOnically ~ted to equivalent standards). Where size or configuration does not permit effPCtive volumetric examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance sl.lndards are al IE'ast equivalent to those specified in the applicabfe class In the code.
| |
| (2! 1968 Edition including Addenda through Summer 1970.
| |
| (31 1969 Edition and Addenda.
| |
| (4! NOYffl1ber 1968 Edition and March 1970 Addenda.
| |
| Rev. 46, 06/93
| |
|
| |
|
| SSES-FSAR Table Rev. 52 TABLE 3.2-3
| | Class Class 2 |
|
| |
|
| ==SUMMARY==
| | Class 2 ANSI B31.1 (Except for Note 2) |
| OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971 CODE CLASSIFICATIONS (1) (2) (3) (4)
| | Class 3 ANSI B31.1 NON-SAFETY INSTRUMENTS REQUIRED TO MAINTAIN A PRESSURE BOUNDARY |
| COMPONENT GROUP A GROUP B GROUP C GROUP D Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code, Section III, Vessel Code, Section III, Vessel Code, Section III, Vessel Code, Section VIII, Nuclear Power Plant Nuclear Power Plant Nuclear Power Plant Division 1 Components - CLASS 1 Components - CLASS 2 Components - CLASS 3 (5)(12)(14)(15)(17)(20) (6)(11)(14)(18)(20) (7)(14)(19)(20)
| |
| Piping As above As above As above ANSI B31.1 Power (20)
| |
| Piping (11)(13) (11)(13)
| |
| Pipe Supports As above As above As above ANSI B31.1 Pumps As above As above As above Manufacturers Standards Valves As above As above As above ANSI B31.1 (8) (8) 0-15 psig --- As above As above AP-620 or ASME Boiler and Storage Tanks Pressure Vessel Code Section VIII, Division 1 (8) (8)(9)(10)
| |
| Atmospheric --- As above As above API-650, AWWA D 100, Storage Tanks ANSI B 96.1, or ASME Boiler and Pressure Vessel Code Section VIII, Division 1
| |
| (1)(2)(3)
| |
| Components ordered after July 1, 1971 comply with the Codes and Standards in effect at the date of award of the order, except that Group A, B and C components ordered between July 1, 1971 and July 1, 1972 also comply with the following paragraphs of the ASME Boiler and Pressure Vessel Code, Section III, Winter, 1971 Addenda as applicable: (1) NB-2510, NB-2541, NB-2553, NB-2561, (2) NC-2510, NC-2571, (3) ND-2510, ND-2571.
| |
| (4)
| |
| Certain portions of the radwaste systems meet the additional requirements of Quality Group D (Augmented) as defined in NRC Branch (5)(6)(7)
| |
| Technical Position ETSB 11-1, Parts B.IV and B.VI.
| |
| I For installation of ASME items, ASME Section III, 1971 Edition with Addenda through the Winter of 1972 shall apply. ASME material shall meet the requirements of ASME Section II, 1971 Edition through the Winter 1972 Addenda or any later Edition or Addenda. Any additional ASME Section III material requirements of Subsection 2000, 1971 Edition through the Winter 1972 Addenda, shall apply. For postweld heat treatment, Paragraphs NB-4600, NC-4600 and ND-4600 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
| |
| For the installation of attachments to piping systems after testing, paragraphs NB-4436, NC-4436, and ND-4436 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
| |
| For attachments to piping systems, Paragraphs NB-4433, NC-4433 and ND-4433 of ASME Section III, 1977 Edition, Summer 1979 Addenda are used.
| |
| For Code Nameplates, Stamping, and Data Reports, paragraphs NCA-8210, NCA-8220, NCA-8230, NCA-8300, NCA-8414, NCA-8415, NCA-8416, NCA-8417, NCA-8418, and NCA-8420 of ASME Section III, 1977 Edition, Winter 1977 Addenda are used.
| |
| FSAR Rev. 65 Page 1 of 2
| |
|
| |
|
| SSES-FSAR Table Rev. 52 TABLE 3.2-3 (Continued)
| | ASME I I I CL. 1,2,3 ANSI B31.1 NON-SAFETY |
|
| |
|
| ==SUMMARY==
| | Other Then Section I I I INSTRUMENTS NOT Process Pipe Classes ANSI B31.1 REQUIRED TO MAINTAIN A Excess Flow Check I Instrument PRESSURE BOUNDARY Containment alve(See Note 5) INSTRUMENTS WHICH Penetration--...---... Class 2 Class 2 ARE OPEN TO CONTAINMENT AND FORM Root Valve CONTAINMENT PRESSURE BOUNDARY Piping Instrument or Instrument Panel Notes : 1) Class for instrument lines from pipe to root valve and adaper is same as process pipe class. |
| OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971 (8)
| | : 2) Class 2 shall be required on lines that can contain reactor coolant or are radiation Class V and are outside contaiment. |
| Orders for Nuclear Storage Tanks were placed after December 31, 1971.
| | : 3) A reducing adapter at the root valve serves as a restriction orifice. |
| (9)
| | : 4) Most GE shutoff instrument valves are B31.1 not Class 2. |
| Atmospheric Storage Tanks fabricated to Group C requirements may be used in a Group D or Group D (Augmented) system.
| | : 5) Any automatic valve equivalent to an excess flow check valve may be used as an isolation valve for this type of line. |
| (10)
| |
| The Diesel E Fuel Oil Storage Tank Complies with ASME B&PV Code Section III, 1971 Edition, Winter 1972 Addenda. The A-D Diesel Generator Fuel Oil Storage Tanks comply with the ASME Boiler and Pressure Vessel Code, Section III, 1974 Edition, Winter 1975 Addenda as applicable.
| |
| (11)
| |
| Control Rod Drive Hydraulic System (CRD) piping and supports are constructed in accordance with ASME Section III, 1974 Edition with Addenda through Winter 1975 except as permitted by NA-1140(f) of ASME III as follows. Materials conform with ASME Section III, 1974 Edition, with Addenda through Winter 1975, or any later Edition of Addenda. ASME Section III, 1977 Edition, with Addenda through Winter 1977, Subsection NF, Paragraph NF-2610, shall apply to piping system support.
| |
| (12) 1 and smaller Nuclear Class 1 Piping is designed in accordance with the rules for Nuclear Class 2 piping per ASME Section III, 1974 Edition, Summer 1975 Addenda, Paragraph NB3630.
| |
| (13)
| |
| Allowable stresses for pipe supports for Nuclear Class 1, 2 and 3 piping shall be in accordance with ANSI Power Piping Code B31.1, 1973.
| |
| (14)
| |
| For the design of ASME flanges, ASME Section III, 1977 Edition with addenda through summer 1979 is used.
| |
| (15)
| |
| For the design of Nuclear Class 1, 1 branch connections, ASME Section III, 1977 Edition with Addenda through Summer 1979 is used.
| |
| (16)
| |
| Code case N316, approved for use at Susquehanna SES by the NRC on 2/17/82, is used in the Bechtel design of small pipe and CRD small pipe.
| |
| (17)
| |
| For the evaluation of Nuclear Class 1 piping components for snubber elimination or other piping modifications, ASME Section III, 1977 edition with addenda through summer of 1979 may be applied.
| |
| (18)
| |
| For the evaluation of Nuclear Class 2 piping components for snubber elimination or other piping modifications, ASME Section III, 1980 edition with addenda through winter of 1981 may be applied.
| |
| (19)
| |
| For the evaluation of Nuclear Class 3 piping components for snubber elimination or other piping modifications, ASME Section III, 1983 edition with addenda through summer of 1984 may be applied.
| |
| (20)
| |
| For the evaluation of ASME piping components or ANSI piping components which are analyzed for Seismic Category I requirements, Code Case N-411 may be applied for Snubber Elimination or other piping modifications/evaluations.
| |
| FSAR Rev. 65 Page 2 of 2
| |
|
| |
|
| SSES-FSAR TABLE 3.2-4 CODE GROUP DESIGNATIONS - INDUSTRY CODES AND STANDARDS FOR MECHANICAL COMPONENTS SUPPLIED BY THE NSSS VENDOR
| | FSAR REV.65 |
| {SEE NOTE a)
| |
| A A 1 ASME III, 1 ASHE Ill, 1 NA &NB Subsections TEHA C NA &NB Subsection TEHA C note (d) e 8*,C 2,MC* ASHE 1H, 8,. C ASHE III, 2 &HC*,
| |
| ANSI B3U II NA & NC Subsections NP &VC, NA &NE Subsections TEMA C TANKS TEHA C TANKS NA, NC Note(d)
| |
| C 3 ASME VIII, Div. l ASME III, 3 ANSI B31.7, IlI NA & ND Subsections NP & VC, IIJ TEMA C TANKS NA, ND TEHA C TANKS Note (d)
| |
| D ASME VIII, Div. 1 ASME VIII, Div. 1 ANSI 831.1.0 ANSI 831.1.0 TEMA C TANKS (b) TEHA C TANKS (b)
| |
| Note (cl Hate (c)
| |
| * Hetal containment vessel (as applicable) and extens1ons of containment only . Future addenda will include concrete containment vessels under ASME Section III, Divisions 2, at which time the requirements of this division shall also be 111et.
| |
| NOTES:
| |
| (a) Wtth options and additions as necessary for service conditions and environmental requirements.
| |
| (b) Class D tanks shall be designed, constructed, and tested to meet the intent of AP[ Standards 620/650, AWA Standard DlOO, or ANSI 896 . 1 Standard for Aluminum Tanks.
| |
| (c) For pumps classified Group O and operating above 150 psi or 212"F, ASHE Section VIII, Div . 1 shall be used as a guide in calculating the wall thickness for pressure retaining parts and In siling the cover bolting. For pumps operating below 150 psi and 212°F, manufacturer's standard pump for service Intended may be used.
| |
| (d) For pumps classified A, B, or C applicable Subsections NB, NC, or NO respectively In ASHE Boiler and Pressure Vessel Code, Section Ill shall be used as a guide In calculating the thickness of pressure retaining portions of the pump and In sizing cover bolting, Rev. 48, 12/94
| |
|
| |
|
| SSES-FSAR TABLE 3.2-5
| | SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT |
|
| |
|
| ==SUMMARY==
| | MINIMUM INSTRUMENT LINE CLASSFICATIONS |
| OF SAFETY CLASS DESIGN REQUIREMENTS (MINIMUM) 2: . 3 Other Quality Group A B C D Cl ass i fi cat i on< 1 >
| |
| Quality Assurance B B B N/A Reoui rement<i!>
| |
| Seismic Categor_v< 3> I I I N/A (1)
| |
| The equipment shall be constructed in accordance with the indicated code group listed in Table 3.2-1 and defined in Tables 3.2-2, 3.2-3, and 3.2-4.
| |
| (Z)
| |
| B - The equipment shall be constructed in accordance with the quality assurance requirements of IOCFR50, Appendix B.
| |
| N/A - The equipment shall be constructed in accordance with the quality assurance requirements consistent with accepted practice for steam power plants.
| |
| (3)
| |
| I - The equipment for these safety classes shall be constructed in accordance with the seismic requirements for the safe shutdown earthquake as described in Section 3.7.
| |
| N/A - The seismic requirements for the safe shutdown earthquake are not applicable to the equipment of this classification.
| |
| Rev. 48, 12/94
| |
|
| |
|
| Security-Related Information Figure Withheld Under 10 CFR 2.390 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT CODE CLASSIFICATION OF PIPING AND VALVES FIGURE 3.2-1
| | FIGURE 3.2-2, Rev. 48 |
|
| |
|
| Restricted Orifice Adapter Process or Excess Flow Pipe Check Valve (Note 1) (See Note 3)
| | Auto-Cad Figure Fsar 3_2_2.dwg}} |
| Instrument, Instrument Panel, Instrument Valve Root Valve ASME Section I I I Class 2 Class 1 (See Note 4)
| |
| INSTRUMENTS REQUIRED Class 2 Class 3 TO OPERATE SAFETY (See Note 2) SYSTEMS Class 3 Class 3 (See Note 2)
| |
| Class Class 2 Class 2 ANSI B31.1 (Except for Note 2)
| |
| Class 3 ANSI B31.1 NON-SAFETY INSTRUMENTS REQUIRED TO MAINTAIN A PRESSURE BOUNDARY ASME I I I CL. 1,2,3 ANSI B31.1 NON-SAFETY INSTRUMENTS NOT Other Then Section I I I REQUIRED Process Pipe Classes ANSI B31.1 TO MAINTAIN A Containment Excess Flow Check alve(See Note 5)
| |
| I Instrument PRESSURE BOUNDARY INSTRUMENTS WHICH Penetration--...---... Class 2 Class 2 ARE OPEN TO CONTAINMENT AND FORM CONTAINMENT PRESSURE Root Valve BOUNDARY Piping Instrument or Instrument Panel Notes: 1) Class for instrument lines from pipe to root valve and adaper is same as process pipe class .
| |
| : 2) Class 2 shall be required on lines that can contain reactor coolant or are radiation Class V and are outside contaiment.
| |
| : 3) A reducing adapter at the root valve serves as a restriction orifice.
| |
| : 4) Most GE shutoff instrument valves are B31 .1 not Class 2.
| |
| : 5) Any automatic valve equivalent to an excess flow check valve may be used as an isolation valve for this type of line.
| |
| FSAR REV.65 SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT MINIMUM INSTRUMENT LINE CLASSFICATIONS FIGURE 3.2-2, Rev. 48 Auto-Cad Figure Fsar 3_2_2.dwg}}
| |
|
|---|
Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23291A4242023-10-24024 October 2023
1 to Updated Final Safety Analysis Report, Chapter 7, Section 7.6, All Other Instrumentation Systems Required for Safety
ML23292A2052023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions 021.01 Through 021.88
PLA-8081, 1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.212023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 121.1 Through 121.21
ML23292A2242023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 032.1 Through 032.103
ML23292A2232023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 331.1 Through 331.19
ML23292A2212023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Response 260.1
ML23292A2202023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 441.1 Through 441.15
ML23292A2172023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 410.1 Through 410.13
ML23292A2162023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 040.1 Through 40.99
ML23292A2142023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 005.1 Through 005.6
ML23292A2132023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 362.1 Through 362.25
ML23292A2092023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 421.1 Through 421.42
ML23292A2082023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 422.1 Through 422.4
ML23292A2062023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 372.1 Through 372.28
ML23292A1692023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 15, Section 15.3, Decrease in Reactor Coolant System Flow Rate
ML23292A2022023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Response 112.1 Through 112.10
ML23292A2012023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.2, Proposed Final Technical Specifications
ML23291A1132023-10-12012 October 2023
Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report
ML23292A1982023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 17, Section 17.2, Quality Assurance During the Operations Phase
ML23292A1922023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 232.1 Through 232.4
ML23292A1912023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 110.1 Through 110.57
ML23292A1892023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 18, Section 18.2, Response to Requirements in NUREG 0694
ML23292A1872023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.3, Technical Requirements Manuals
ML23292A1752023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15B, Accident Dose Model Descriptions
ML23292A1742023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 10, Section 10.3, Main Steam Supply System
ML23292A1722023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.7, Independent Dry Fuel Storage
ML23292A1712023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.2, Liquid Waste Management Systems
ML23292A1672023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 9, Section 9.5, Other Auxiliary Systems
ML23292A2072023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions 230.1 Through 230.8
ML23292A1732023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 9, Appendix 9A, Analysis for Non-Seismic Spent Fuel Pool Cooling Systems
ML23292A2002023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 18, Responses to TMI Related Requirements
ML23292A2102023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions 313.1 Through 313.9
ML23292A1652023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 11, Section 11.4, Solid Waste Management System
ML23292A1682023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 9, Section 9.3, Process Auxiliaries
ML23292A2192023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 231.1 Through 231.5
ML23292A2282023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Question and Response 440.1
ML23292A2042023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 130.1 Through 130.28
ML23292A2182023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 1, Questions 010.1 Through 010.26
ML23292A1862023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 18, Section 18.1, Response to Requirements in NUREG-0737
ML23292A1962023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions 123.1 Through 123.9
ML23292A1702023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 15, Appendix 15D, Susquehanna Steam Electric Station Unit 2 Final Safety Analysis Report Cycle Specific Data
ML23292A1852023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 442.1 Through 442.3
ML23292A2152023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 423.1 Through 423.58
ML23292A2272023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Figures Referenced in the FSAR Are Withheld Under 10 CFR 2.390
ML23292A2262023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Chapter 16, Section 16.1, Preliminary Technical Specifications
ML23292A2032023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 211.1 Through 211.296
ML23292A1942023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Response 361.1 Through 361.5-1
ML23292A2122023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 222.1 Through 222.2
ML23292A2112023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions and Responses 400.1
ML23292A2222023-10-12012 October 2023
1 to Updated Final Safety Analysis Report, Questions 321.1 Through 321.7
2023-10-24
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Text
SSES-FSAR Text Rev. 56
3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS
Certain structures, components, and systems of the nuclear plant are considered important to safety because they perform safety actions required to avoid or mitigate the consequences of abnormal operational transients or accidents. The purpose of this section is to classify structures, components, and systems, according to the importance of the safety function they perform. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when required.
3.2.1 Seismic Classification
General Design Criterion 2 of Appendix A to 10CFR50 and Appendix A to 10CFR100 require that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes without loss of capability to perform their safety function. NRC Regulatory Guide 1.29 (Rev. 2, 2/76) provides additional guidance and defines Seismic Category I structures, components, and systems as those necessary to assure:
(1) The integrity of the reactor coolant pressure boundary
(2) The capability to shut down the reactor and maintain it in a safe condition, or
(3) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR 50.67.
Plant structures, systems, and components, including their foundations and supports, designed to remain functional in the event of a Safe Shutdown Earthquake are designated as Seismic Category I, as indicated in Table 3.2-1. Class 1E electric equipment is Seismic Category I equipment.
Seismic classification of systems instrumentation is discussed in Chapter 7.
All Seismic Category I structures, systems, and components are analyzed under the loading conditions of the SSE and OBE. Since the two earthquakes vary in intensity, the design of Seismic Category I structures, components, equipment, and systems to resist each earthquake and other loads will be based on levels of material stress or load factors, whichever is applicable, and will yield margins of safety appropriate for each earthquake. The margin of safety provided for Safety Class structures, components, equipment, and systems for the SSE will be sufficiently large to assure that their design functions are not jeopardized.
Seismic Category I structures are sufficiently isolated or protected from other structures to ensure that their integrity is maintained at all times.
Components (and their supporting structures) which are not Seismic Category I and whose collapse could result in loss of required function through impact with or flooding of Seismic Category I structures, equipment, or systems required after a safe shutdown earthquake, are analytically checked to confirm their integrity against collapse when subjected to seismic loading resulting from the safe shutdown earthquake.
FSAR Rev. 68 3.2-1 SSES-FSAR Text Rev. 56
The Operating Basis Earthquake as defined in 10 CFR 100, Appendix A, is not incorporated as a part of the seismic classification scheme.
The seismic classification indicated in Table 3.2-1 meets the requirements of NRC Regulatory Guide 1.29 except as otherwise noted in the table. Where only portions of systems are identified as Seismic Category I on this table, the boundaries of the Seismic Category I portions of the system are shown on the piping and instrument diagrams in appropriate sections of this report.
3.2.2 System Quality Group Classifications
System quality group classifications as defined in NRC Regulatory Guide 1.26 have been determined for each water, steam or radioactive waste containing component of those applicable fluid systems relied upon to:
(1) prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary,
(2) permit shutdown of the reactor and maintain it in the safe shutdown conditions, and
(3) contain radioactive material.
A tabulation of quality group classification for each component so defined is shown in Table 3.2-1 under the heading, "Quality Group Classification." Figure 3.2-1 is a diagram which depicts the relative locations of these components along with their quality group classification. Interfaces between components of different classifications are indicated on the system piping and instrumentation diagrams which are found in the pertinent section of the FSAR.
System Quality Group Classifications and design and fabrication requirements as indicated in Tables 3.2-1, 3.2-2, 3.2-3, and 3.2-4 meet the requirements of Regulatory Guide 1.26 (Rev. 3, 2/76) except as noted.
3.2.2.1 Quality Group D (Augmented)
Certain portions of the radwaste system meet the additional requirements of Quality Group D (Augmented) as defined in the NRC Branch Technical Position ETSB 11-1 (Rev. 1), parts B.IV and B.VI. Portions of the radwaste system meeting the requirements of Quality Group D (Augmented) may be determined from notes on the appropriate figures in Chapter 11.
3.2.3 System Safety Classifications
Structures, systems, and components are classified as Safety Class l, Safety Class 2, Safety Class 3, or Other in accordance with the importance to nuclear safety. Equipment is assigned a specific safety class, recognizing that components within a system may be of differing safety importance. A single system may thus have components in more than one safety class.
FSAR Rev. 68 3.2-2 SSES-FSAR Text Rev. 56
The safety classes are defined in this section and examples of their broad application are given.
Because of specific design considerations, these general definitions are subject to interpretation and exceptions. Table 3.2-1 provides a summary of the safety classes for the principal structures, systems, and components of the plant.
Design requirements for components of safety classes are also delineated in this section. Where possible, reference is made to accepted industry codes and standards which define design requirements commensurate with the safety function(s) to be performed. In cases where industry codes and standards have no specific design requirements, the locations of the appropriate subsections that summarize the requirements to be implemented in the design are indicated.
3.2.3.1 Safety Class 1
3.2.3.1.1 Definition of Safety Class 1
Safety Class 1, SC-1, applies to components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal makeup system.
3.2.3.2 Safety Class 2
3.2.3.2.1 Definition of Safety Class 2
Safety Class 2, SC-2, applies to those structures, systems, and components, other than service water systems, that are not Safety Class 1 but are necessary to accomplish the safety functions of:
(1) inserting negative reactivity to shut down the reactor,
(2) preventing rapid insertion of positive reactivity,
(3) maintaining core geometry appropriate to all plant process conditions,
(4) providing emergency core cooling,
(5) providing and maintaining containment,
(6) removing residual heat from the reactor and reactor core, and
(7) storing spent fuel.
Safety Class 2 includes the following:
(1) Reactor protection system and Alternate Rod Injection system.
(2) Those components of the control rod system which are necessary to render the reactor subcritical.
(3) Systems or components which restrict the rate of insertion of positive reactivity.
FSAR Rev. 68 3.2-3 SSES-FSAR Text Rev. 56
(4) The assembly of components of the reactor core which maintain core geometry including the fuel assemblies, core support structure, and core grid plate, as examples.
(5) Other components within the reactor vessel such as jet pumps, core shroud, and core spray components which are necessary to accomplish the safety function of emergency core cooling.
(6) Emergency core cooling systems.
(7) Primary containment.
(8) Reactor building (secondary containment)
(9) Post-accident containment heat removal systems.
(10) Initiating systems required to accomplish safety functions, including emergency core cooling initiating system and containment isolation initiating system.
(11) At least one of the systems which recirculates reactor coolant to remove decay heat when the reactor is pressurized and the system to remove decay heat when the reactor is not pressurized.
(12) Spent fuel storage racks and spent fuel pool.
(13) Electrical and instrument auxiliaries necessary to operation of the above.
Structures, systems, and components in Safety Class 2 are listed in Table 3.2-1.
3.2.3.3 Safety Class 3
3.2.3.3.1 Definition of Safety Class 3
Safety Class 3, SC-3, applies to those structures, systems, and components that are not Safety Class 1 or Safety Class 2, but
(1) Whose function is to process radioactive wastes and whose failure would result in release to the environment of gas, liquid, or solids resulting in a single-event whole body dose to a person at the site boundary greater than 500 mrem.
(2) Which provide or support any safety system function. Safety Class 3 includes the following:
- a. Service water systems required for the purpose of:
- 1. Removal of decay heat from the reactor
- 2. Emergency core cooling
- 3. Post-accident heat removal from the suppression pool
FSAR Rev. 68 3.2-4 SSES-FSAR Text Rev. 56
- 4. Providing cooling water needed for the functioning of emergency systems.
- b. Fuel supply for the onsite emergency electrical system.
- c. Emergency equipment area cooling.
- d. Compressed gas or hydraulic systems required to support control or operation of safety systems.
- e. Electrical and instrumentation auxiliaries necessary for operation of the above.
3.2.3.4 Other Structures, Systems, and Components
3.2.3.4.1 Definition of Other Structures, Systems, and Components
A boiling water reactor has a number of structures, systems, and components in the power conversion or other portions of the facility which have no direct safety function but which may be connected to or influenced by the equipment within the Safety Classes defined above. Such structures, systems, and components are designated as "other."
3.2.3.4.2 Design Requirements for Other Structures, Systems, and Components
The design requirements for equipment classified as "other" are specified by the designer with appropriate consideration of the intended service of the equipment and expected plant and environmental conditions under which it will operate. Where possible, design requirements are based on applicable industry codes and standards. Where these are not available, the designer utilizes accepted industry or engineering practice.
3.2.4 Quality Assurance
Structures, systems, and components whose safety functions require conformance to the quality assurance requirement of 10CFR50, Appendix B, are summarized in Table 3.2-1 under the heading, "Quality Assurance Requirements." The Operational Quality Assurance Program is described in Chapter 17.
3.2.5 Correlation of Safety Classes with Industry Codes
The design of plant equipment will be commensurate with the safety importance of the equipment.
Hence, the various safety classes have a gradation of design requirements. The correlation of safety classes with other design requirements are summarized in Table 3.2-5.
FSAR Rev. 68 3.2-5
SSES-FSAR TABLE l.2-2
SUMMARY
Of CODES AND STANDARDS FOR COMPONENTS Of WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE (ORDERED PRIOR TO JULY 1, 1971 WITH THE EXCEPTfONS OF THOSE COMPONENTS LOCATED INSIDE THE RCPB, ANO THE REACTOR PRESSURE VESSEL)
CODE ClASSIFICA TIONS
COMPONENT CROUP A CROUP B CROUPC GROUP 0
Pressure Vessels ASME Soifer and Pressure Vessel ASME Boiler and Pressure Ve5sel ASME Boiler and Pressure Vessel ASME Boiler and Pressure Vessel Code, Section 111, Class A.. Code, s<<tion 111, Class C. Code,Section VIII, Division 1 Code,Section VIII, Division 1 or See Footnote (2) See Footnote (2) Equivalent
0-15 Psig - APl-620 with NOT Examination A.Pl-620 with NOT Examination APl-620 or Equivalent Storage Tanks Atmospheric - Applicable Storage Tank Codes Applicable Storage Tank Codes APl-650, AWWA.0100 or ANSI B Storage Tan ks such a, APl-650, A.WWA.D100 or such as APl-650 AWWAD100 or 96.1 or Equivalent ANSI B 96.1 with NOT ANSI B 96.1 with NOT Examination Examination
Piping ANSI B.31.7, Class 1. ANSI 8 31.7, Clins II. ANSI 8 31.7, Class Ill. ANSI 8 31. 1.0 or Equivale-nt See Footnote (3) See Footnote (3) See footnote (3)
Pumps and Draft A.SME Code for Pumps and Ofaft ASME Code for Pumps and Draft ASME Code for Pumps and Valve! - ANSI S 3 t.1.0 or Equivalent Valves Valves Class I. Valves Class II. Valves Class tu. Pump -Draft ASME Code for Pumps See Footnote (1) & (4) See Footnote (1) & (4) See Footnote 14) Valves Class Ill or Equivalent
(1 l All Pf@SSUre-t"etaining cast parts afe radiographed (or ultr.MOnically ~ted to equivalent standards). Where size or configuration does not permit eff PCtive volumetric examination, magnetic particle or liquid penetrant examination may be substituted. Examination procedures and acceptance sl.lndards are al IE'ast equivalent to those specified in the applicabfe class In the code.
(2! 1968 Edition including Addenda through Summer 1970.
(31 1969 Edition and Addenda.
(4! NOYffl1ber 1968 Edition and March 1970 Addenda.
Rev. 46, 06/93 SSES-FSAR Table Rev. 52
TABLE 3.2-3
SUMMARY
OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971
CODE CLASSIFICATIONS
COMPONENT GROUP A(1) GROUP B(2) GROUP C(3) GROUP D(4)
Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code,Section III, Vessel Code,Section III, Vessel Code,Section III, Vessel Code,Section VIII, Nuclear Power Plant Nuclear Power Plant Nuclear Power Plant Division 1 Components - CLASS 1 Components - CLASS 2 Components - CLASS 3
Piping As above(5)(12)(14)(15)(17)(20) As above(6)(11)(14)(18)(20) As above (7)(14)(19)(20) ANSI B31.1 Power Piping(20)
Pipe Supports As above As above(11)(13) As above(11)(13) ANSI B31.1
Pumps As above As above As above Manufacturers Standards
Valves As above As above As above ANSI B31.1
0-15 psig --- As above(8) As above(8) AP-620 or ASME Boiler and Storage Tanks Pressure Vessel Code Section VIII, Division 1
Atmospheric --- As above(8) As above(8)(9)(10) API-650, AWWA D 100, Storage Tanks ANSI B 96.1, or ASME Boiler and Pressure Vessel Code Section VIII, Division 1
(1)(2)(3)Components ordered after July 1, 1971 comply with the Codes and Standards in effect at the date of award of the order, except t hat Group A, B and C components ordered between July 1, 1971 and July 1, 1972 also comply with the following paragraphs of the ASME Boiler and Pressure Vessel Code,Section III, Winter, 1971 Addenda as applicable: (1) NB-2510, NB-2541, NB-2553, NB-2561, (2) NC-2510, NC-2571, (3) ND-2510, ND-2571.
(4) Certain portions of the radwaste systems meet the additional requirements of Quality Group D (Augmented) as defined in NRC Branch Technical Position ETSB 11-1, Parts B.IV and B.VI.
I
(5)(6)(7) For installation of ASME items, ASME Section III, 1971 Edition with Addenda through the Winter of 1972 shall apply. ASME mater ial shall meet the requirements of ASME Section II, 1971 Edition th rough the Winter 1972 Addenda or any later Edition or Addenda. Any additional ASME Section III material require ments of Subsection 2000, 1971 Edition through the Winter 1972 Addenda, shall apply. For postweld heat treatment, Paragraphs NB-4600, NC-4600 and ND-4600 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
For the installation of attachments to piping systems after te sting, paragraphs NB-4436, NC-4436, and ND-4436 of ASME Section III, 1974 Edition, Summer 1976 Addenda are used.
For attachments to piping systems, Paragraphs NB-4433, NC-4433 and ND-4433 of ASME Section III, 1977 Edition, Summer 1979 Addenda are used.
For Code Nameplates, Stamping, and Data Reports, paragraphs NCA-8210, NCA-8220, NCA-8230, NCA-8300, NCA-8414, NCA-8415, NCA-8416, NCA-8417, NCA-8418, and NCA-8420 of ASME Section III, 1977 Edition, Winter 1977 Addenda are used.
FSAR Rev. 65 Page 1 of 2 SSES-FSAR Table Rev. 52
TABLE 3.2-3 (Continued)
SUMMARY
OF CODES AND STANDARDS FOR COMPONENTS OF WATER-COOLED NUCLEAR POWER UNITS SUPPLIED BY AE ORDERED AFTER JULY 1, 1971
(8) Orders for Nuclear Storage Tanks were placed after December 31, 1971.
(9) Atmospheric Storage Tanks fabricated to Group C requirements may be used in a Group D or Group D (Augmented) system.
(10) The Diesel E Fuel Oil Storage Tank Complies with ASME B&PV Code Section III, 1971 Edition, Winter 1972 Addenda. The A-D Die sel Generator Fuel Oil Storage Tanks comply with the ASME Boiler and Pressure Vessel Code,Section III, 1974 Edition, Winter 1975 A ddenda as applicable.
(11) Control Rod Drive Hydraulic System (CRD) piping and supports are constructed in accordance with ASME Section III, 1974 Edition with Addenda through Winter 1975 except as permitted by NA-1140(f) of ASME III as follows. Materials conform with ASME Section III, 1974 Edition, with Addenda through Winter 1975, or any later Edition of Addenda. ASME Section III, 1977 Edition, with Addenda through Winter 1977,
Subsection NF, Paragraph NF-2610, shall apply to piping system support.
(12) 1 and smaller Nuclear Class 1 Piping is designed in accordance with the rules for Nuclear Class 2 piping per ASME Section III, 1974 Edition, Summer 1975 Addenda, Paragraph NB3630.
(13) Allowable stresses for pipe supports for Nuclear Class 1, 2 and 3 piping shall be in accordance with ANSI Power Piping Code B3 1.1, 1973.
(14) For the design of ASME flanges, ASME Section III, 1977 Edition with addenda through summer 1979 is used.
(15) For the design of Nuclear Class 1, 1 branch connections, ASME Section III, 1977 Edit ion with Addenda through Summer 1979 is used.
(16) Code case N316, approved for use at Susquehanna SES by the NRC on 2/17/82, is used in the Bechtel design of small pipe and CRD small pipe.
(17) For the evaluation of Nuclear Class 1 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1977 edition with addenda through summer of 1979 may be applied.
(18) For the evaluation of Nuclear Class 2 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1980 edition with addenda through winter of 1981 may be applied.
(19) For the evaluation of Nuclear Class 3 piping components for s nubber elimination or other piping modifications, ASME Section II I, 1983 edition with addenda through summer of 1984 may be applied.
(20) For the evaluation of ASME piping components or ANSI piping components which are analyzed for Seismic Category I requirements, Code Case N-411 may be applied for Snubber Elimination or other piping modifications/evaluations.
FSAR Rev. 65 Page 2 of 2 SSES-FSAR
TABLE 3.2-4 CODE GROUP DESIGNATIONS FOR MECHANICAL COMPONENTS SUPPLIED BY THE NSSS VENDOR -INDUSTRY CODES AND STANDARDS
{SEE NOTE a)
A A 1 ASME III, 1 ASHE Ill, 1 NA & NB Subsections TEHA C NA & NB Subsection TEHA C note (d) e 8*,C 2,MC* ASHE 1H, 8,. C ASHE III, 2 & HC*,
ANSI B3U II NA & NC Subsections NP & VC, NA & NE Subsections TEMA C TANKS TEHA C TANKS NA, NC Note(d)
C 3 ASME VIII, Div. l ASME III, 3 ANSI B31.7, NP & VC, IIJ IlI TEMA C NA & ND Subsections TANKS NA, ND TEHA C TANKS Note (d)
D ASME VIII, Div. 1 ASME VIII, Div. 1 ANSI 831.1.0 ANSI 831.1.0 TEMA C TANKS (b) TEHA C TANKS (b)
Note (cl Hate (c)
- Hetal concrete containment vessels under ASME containment vessel (as applicable) Section and extens1ons III, Divisions 2, at which time the requirements of of containment only. Future addenda will include this division shall also be 111et.
NOTES:
(a) Wtth options and additions as necessary for service conditions and environmental requirements.
(b) Class D tanks shall be designed, constructed, and tested to meet the intent of AP[ Standards 620/650, AWA Standard DlOO, or ANSI 896. 1 Standard for Aluminum Tanks.
(c) For pumps classified Group O and operating above 150 psi or 212"F, ASHE Section VIII, Div. 1 shall be used as a guide in calculating the wall thickness for pressure retaining parts and In siling the cover bolting. For pumps operating below 150 psi and 212°F, manufacturer's standard pump for service Intended may be used.
(d) For pumps classified A, B, or C applicable Subsections NB, NC, or NO respectively In Pressure Vessel Code, Section Ill shall be used as a guide In calculating the thickness of pressure ASHE Boiler and retaining portions of the pump and In sizing cover bolting,
Rev. 48, 12/94 SSES-FSAR
TABLE 3.2-5
SUMMARY
OF SAFETY CLASS DESIGN REQUIREMENTS (MINIMUM)
.. 3 Other 2:.
Quality Group A B C D Cl ass i fi cat i on< 1 >
Quality Assurance B B B N/A Reoui rement<i!>
Seismic Categor_v<3 > I I I N/A
(1) The equipment shall be constructed in accordance with the indicated code group listed in Table 3.2-1 and defined in Tables 3.2-2, 3.2-3, and 3.2-4.
(Z) B - The equipment shall be constructed in accordance with the quality assurance requirements of IOCFR50, Appendix B.
N/A - The equipment shall be constructed in accordance with the quality assurance requirements consistent with accepted practice for steam power plants.
(3) I - The equipment for these safety classes shall be constructed in earthquake as described in Section 3.7. accordance with the seismic requirements for the safe shutdown
N/A - The seismic requirements for the safe shutdown earthquake are not applicable to the equipment of this classification.
Rev. 48, 12/94 Security-Related Information Figure Withheld Under 10 CFR 2.390
SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT
CODE CLASSIFICATION OF PIPING AND VALVES
FIGURE 3.2-1 Restricted Orifice Adapter Process or Excess Flow Pipe Check Valve (Note 1) (See Note 3) Instrument, Instrument
Panel, Instrument Valve Root Valve ASME Section I I I Class 2 Class 1 (See Note 4)
Class 2 Class 3 INSTRUMENTS REQUIRED (See Note 2) TO OPERATE SAFETY SYSTEMS Class 3 Class 3 (See Note 2)
Class Class 2
Class 2 ANSI B31.1 (Except for Note 2)
Class 3 ANSI B31.1 NON-SAFETY INSTRUMENTS REQUIRED TO MAINTAIN A PRESSURE BOUNDARY
ASME I I I CL. 1,2,3 ANSI B31.1 NON-SAFETY
Other Then Section I I I INSTRUMENTS NOT Process Pipe Classes ANSI B31.1 REQUIRED TO MAINTAIN A Excess Flow Check I Instrument PRESSURE BOUNDARY Containment alve(See Note 5) INSTRUMENTS WHICH Penetration--...---... Class 2 Class 2 ARE OPEN TO CONTAINMENT AND FORM Root Valve CONTAINMENT PRESSURE BOUNDARY Piping Instrument or Instrument Panel Notes : 1) Class for instrument lines from pipe to root valve and adaper is same as process pipe class.
- 2) Class 2 shall be required on lines that can contain reactor coolant or are radiation Class V and are outside contaiment.
- 3) A reducing adapter at the root valve serves as a restriction orifice.
- 4) Most GE shutoff instrument valves are B31.1 not Class 2.
- 5) Any automatic valve equivalent to an excess flow check valve may be used as an isolation valve for this type of line.
FSAR REV.65
SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 & 2 FINAL SAFETY ANALYSIS REPORT
MINIMUM INSTRUMENT LINE CLASSFICATIONS
FIGURE 3.2-2, Rev. 48
Auto-Cad Figure Fsar 3_2_2.dwg
